Neutron to start the chain reaction

AI Thread Summary
The discussion centers on the source of neutrons needed to initiate a chain reaction in nuclear reactors. It highlights that while uranium can spontaneously fission and release neutrons, reactors typically require a startup neutron source for monitoring and control, especially when sub-critical. Commonly used sources include Sb-124-Be, which generates neutrons through photoneutron reactions. The conversation also notes that after several operational cycles, reactors may achieve a 'sourceless' startup due to accumulated transuranics. Ultimately, the presence of neutrons is essential for achieving and maintaining criticality in nuclear systems.
sstone
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Hello,

I can't find :confused: where do we get the starting neutron(s) for the chain reaction in the reactor. I'm aware that then the splitted atom emits enough(in fact even too much?) neutrons to selfsustain the reaction, which are then slowed down to be able to split uranium and so on.

So where do one get the triggering neutron, to start the chain reaction?

Thanks.
 
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There is a small probability that the Uranium nucleus can spotantiously fission, this releases neutrons. So uranium triggers its own chain reaction.

In nuclear weapons there is a source of neutrons included to trigger the reaction, something like a beryllium and polonium mix. When beryllium gets hit by alpha particles from the polonium it emits neutrons. This to ensure that there is indeed enough neutrons around exactly when needed.
 
sstone said:
Hello,

I can't find :confused: where do we get the starting neutron(s) for the chain reaction in the reactor. I'm aware that then the splitted atom emits enough(in fact even too much?) neutrons to selfsustain the reaction, which are then slowed down to be able to split uranium and so on.

So where do one get the triggering neutron, to start the chain reaction?

Nuclear reactors contain special 'startup' sources to provide sufficient neutron activity, so that the activity in the core can be monitored. Otherwise, one would approach criticality without sufficient knowledge of knowing how close one is. The objective is to maintain control of the reactor.

While the (alpha, Be) sources are possible, e.g. Po-Be, Ra-Be or Pu-Be, they are not typically used. Rather the startup sources use Sb124-Be, which is a photoneutron source in which a high energy gamma photon knocks out a neutron from Be-9, which becomes Be-8, which promptly decomposes to 2 alpha particles. Sb-124 (which is formed from neutron absorption (activation) by Sb-123) emits a 1.6 MeV gamma.

See pages 37 & 38 of this document - http://lrs.web.psi.ch/educational/courses/2006_EPFL_DOCTORAL_PSI_COURSE/week3/Week_3_Lecture_5.pdf

Once the reactor has completed a few cycles of operation, it might have sufficient transuranics in the twice burned fuel to enable a 'sourceless' startup. Otherwise, the source stay in the reactor where they are reactivated by the neutron flux.
 
Astronuc said:
Nuclear reactors contain special 'startup' sources to provide sufficient neutron activity, so that the activity in the core can be monitored. Otherwise, one would approach criticality without sufficient knowledge of knowing how close one is. The objective is to maintain control of the reactor.

While the (alpha, Be) sources are possible, e.g. Po-Be, Ra-Be or Pu-Be, they are not typically used. Rather the startup sources use Sb124-Be, which is a photoneutron source in which a high energy gamma photon knocks out a neutron from Be-9, which becomes Be-8, which promptly decomposes to 2 alpha particles. Sb-124 (which is formed from neutron absorption (activation) by Sb-123) emits a 1.6 MeV gamma.

See pages 37 & 38 of this document - http://lrs.web.psi.ch/educational/courses/2006_EPFL_DOCTORAL_PSI_COURSE/week3/Week_3_Lecture_5.pdf

Once the reactor has completed a few cycles of operation, it might have sufficient transuranics in the twice burned fuel to enable a 'sourceless' startup. Otherwise, the source stay in the reactor where they are reactivated by the neutron flux.

Thanks for that information. It never occurred to me that a reactor needs a startup source aswell.:blushing:
 
Azael said:
Thanks for that information. It never occurred to me that a reactor needs a startup source aswell.:blushing:
Azael,

Actually after the reactor has been run; you don't even "need" the startup source, since
there will be enough radionuclides present as a result of fission that can provide the
initial neutrons.

However, as a matter of a condition on the operating license; the operator is required to
have a startup source in the core when it is sub-critical in any case. The instrumentation
for monitoring the core and its criticality are based on detecting neutrons.

Although with a fresh core, there are probably enough stray neutrons around to start the
reaction; you can't count on that. So the operator is required to have a source in the
reactor when it is subcritical, as Astronuc points out; so that one can monitor the
condition of the core.

Dr. Gregory Greenman
Physicist
 
Thank you all for the info.
 
Further to the point that a extraneous neutron source is not always required, consider the natural fission reactor that is believed to have existed at Oklo, Africa a couple of billion years ago.
 
curie said:
Further to the point that a extraneous neutron source is not always required, consider the natural fission reactor that is believed to have existed at Oklo, Africa a couple of billion years ago.
This is true. It depends on kinf and size, which in part determines keff. Composition and homogeneity are also factors.
 
curie said:
Further to the point that a extraneous neutron source is not always required, consider the natural fission reactor that is believed to have existed at Oklo, Africa a couple of billion years ago.
curie,

Without the neutron source; the Oklo could have just sat there in a critical state; but with
no neutrons in it. However, given that there are extraneous neutrons; it is only a matter
of time before one finds its way to the reactor, and we get a self-sustaining chain reaction.

But there DOES need to be an initial neutron - provided by cosmic rays, radioactive decay...
whatever.

In a manufactured reactor, that has been operating for even a short period of time; the
neutrons to restart the reactor can come from the fission products; some of which are
neutron emitters.

For a brand-new manufactured reactor; then you need a source. You don't want to be
trying to take the reactor critical and not have any neutrons in it. The instrumentation
as to the criticality of the reactor responds to neutrons. You can put the reactor into
a critical state - or even a super-critical state - without neutrons; and without those
neutrons, you wouldn't know that you had reached the critical or super-critical state.

That's why reactor operators are REQUIRED to have a source in the reactor at low
power and sub-critical conditions.

Dr. Gregory Greenman
Physicist
 
  • #10
Morbius said:
ou can put the reactor into
a critical state - or even a super-critical state - without neutrons; and without those
neutrons, you wouldn't know that you had reached the critical or super-critical state.

What the...?

That would be akin to suggesting that I could start-up, run, and accelerate an internal combustion engine without fuel.

No neutrons, no criticality. No criticality, no super-criticality.

Morbius said:
That's why reactor operators are REQUIRED to have a source in the reactor at low
power and sub-critical conditions.

Dr. Gregory Greenman
Physicist

I'm not sure who you're generalizing this to, but operating power reactors that aren't brand new most certainly do not have this requirement. There is more than enough neutron activity coming from the spent fuel going through multiple cycles for the nuclear instrumentation to pick up.
 
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  • #11
Emfuser said:
What the...?

That would be akin to suggesting that I could start-up, run, and accelerate an internal combustion engine without fuel.

No neutrons, no criticality. No criticality, no super-criticality.

I think Mobius is talking about the reactor being critical as in its size is big enough to sustain a reaction if there are neutrons. For example, 10 kg of Pu is supercritical, but not much will happen until there are incident neutrons.
 
  • #12
Emfuser said:
What the...?

That would be akin to suggesting that I could start-up, run, and accelerate an internal combustion engine without fuel.

No neutrons, no criticality. No criticality, no super-criticality.
Emfuser,

Then you don't understand the concept of "criticality".

The car is NOT a critical system - the analogy doesn't hold.

Criticality is a property of the geometry and the materials; NOT the neutrons.

Theoretically, you could have a system that is "critical" even when neutrons
are not present.

[ A critical system will be "steady-state" only if the neutron distribution that is
present is the fundamental eigenfunction of the critical system. ]

You can assemble a system that is super-critical; even without neutrons.

That's why nuclear weapons have "initiators":

http://en.wikipedia.org/wiki/Nuclear_weapon_design#Neutron_trigger_.2F_initiator

The nuclear weapon has a device to put neutrons into the system; in case there aren't
any there to start the reaction when the device assembles. You wouldn't call an
assembled nuclear weapon "sub-critical" would you?

Of course not! You can assemble a system that is critical, or even super-critical; but
nothing will happen if there are no neutrons present.

That's because the concept of "criticality" is NOT a property of the neutron population;
it is a property of the materials and the geometry that they are in. Criticality tells you
what the system would do if neutrons are present; whether or not those neutrons are
actually present.

The word "critical" comes from mathematics. If the eigenvalue of the transport equation
for the system is exactly unity; mathematically the system is "critical". Note that the
solution of the transport equation is only dependent on the materials and geometry;
NOT the neutron population. In fact, it CAN'T be - because the eigenvalue system is
singular - being both linear and homegeneous - any constant multiple of a solution is also
a solution; including a multiple of zero. The criticality doesn't depend on the neutron
population.

The "reactivity" on the other hand, DOES depend on the neutron population. A system
could be exactly critical; but with a neutron population that isn't the fundamental
eigenfunction. Such a system would not be steady-state; the reactivity would be a
finite non-zero value until the system evolved into one where the neutron population
is the fundamental eigenfunction.

It's really the matematical system that is "critical"; and that just depends on materials
and geometry, and NOT the neutrons.

Dr. Gregory Greenman
Physicist
 
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  • #13
Good lord... why is it always the book-bound guys that come up with this stuff? If you want to talk in the purely theoretical realm, then by all means, feel free to talk right out of a reactor dynamics book all day. However if you want to talk about the world of operating power reactors (which you did), then I suggest you step away from the chalkboard and try not using the most mathematically bound definition of criticality that you can find in place of the concept of a critical mass or critical geometry.

I passed all my reactor theory & neutron transport classes without problem. I understand full well what you're talking about, and then some. However I, just like every other nuclear professional who isn't holed up in a university, office, or other paper-bound world, recognize that the zero solution is always immediately discarded as trivial and that nobody ever talks about criticality exclusively in terms of critical geometry. It's always in the context of neutron population and 'k'.

That's why this statement:
Morbius said:
That's why reactor operators are REQUIRED to have a source in the reactor at low
power and sub-critical conditions.
... is false. The zero solution to the transport equation means nothing to us.

I'm sorry if this seems a bit curt, but in the world of operating power reactors, or any related work or study function, critical is not taken in the literal (but wondefully and uselessly abstract) mathematical definition. In the working nuclear world, critical has EVERYTHING to do with your neutron population and how it behaves. The reactor is real, the mathematical model is not. One is reality, the other abstractly attempts to model it.
 
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  • #14
Emfuser said:
Good lord... why is it always the book-bound guys that come up with this stuff? If you want to talk in the purely theoretical realm, then by all means, feel free to talk right out of a reactor dynamics book all day. However if you want to talk about the world of operating power reactors (which you did), then I suggest you step away from the chalkboard and try not using the most mathematically bound definition of criticality that you can find in place of the concept of a critical mass or critical geometry.

I passed all my reactor theory & neutron transport classes without problem. I understand full well what you're talking about, and then some. However I, just like every other nuclear professional who isn't holed up in a university, office, or other paper-bound world, recognize that the zero solution is always immediately discarded as trivial and that nobody ever talks about criticality exclusively in terms of critical geometry. It's always in the context of neutron population and 'k'.

That's why this statement:

... is false. The zero solution to the transport equation means nothing to us.

I'm sorry if this seems a bit curt, but in the world of operating power reactors, or any related work or study function, critical is not taken in the literal (but wondefully and uselessly abstract) mathematical definition. In the working nuclear world, critical has EVERYTHING to do with your neutron population and how it behaves. The reactor is real, the mathematical model is not. One is reality, the other abstractly attempts to model it.

if i may: LOL...are you serious? is speaking about nuclear physics in mathematical terms silly?

Homer Simpson works at a power plant too...i think that you are way over your head in debating Morbius on these kinds of issues - why don't you search the PF archives...
 
  • #15
Emfuser said:
Good lord... why is it always the book-bound guys that come up with this stuff? If you want to talk in the purely theoretical realm, then by all means, feel free to talk right out of a reactor dynamics book all day. However if you want to talk about the world of operating power reactors (which you did), then I suggest you step away from the chalkboard and try not using the most mathematically bound definition of criticality that you can find in place of the concept of a critical mass or critical geometry.\
Emfuser,

The use of the word "critical" comes from the mathematics. It is YOU that is using it
in a non-standard fashion

I passed all my reactor theory & neutron transport classes without problem.

You may have passed; but this is one part of transport theory that you have
WRONG!

I understand full well what you're talking about, and then some.

Asserting facts not in evidence. I see no evidence of "..and then some".

However I, just like every other nuclear professional who isn't holed up in a university, office, or other paper-bound world, recognize that the zero solution is always immediately discarded as trivial and that nobody ever talks about criticality exclusively in terms of critical geometry. It's always in the context of neutron population and 'k'.

Yes - 'k"! What is "k". It is an eigenvalue of the transport equation. [There are
others.] The existence and value of "k" exists INDEPENDENT of the value of the eigenfunction;
whether that eigenfunction is the trivial zero, or a non-zero eigenfunction.

Look at any expression for "k". Do you see anything that has to do with neutrons like a
flux? No - you will see only material and geometric properties.
That's why this statement:

... is false. The zero solution to the transport equation means nothing to us.

I'm sorry if this seems a bit curt, but in the world of operating power reactors, or any related work or study function, critical is not taken in the literal (but wondefully and uselessly abstract) mathematical definition. In the working nuclear world, critical has EVERYTHING to do with your neutron population and how it behaves. The reactor is real, the mathematical model is not. One is reality, the other abstractly attempts to model it.

The above shows that you really DON'T understand some very important features about
the operation of a nuclear reactor. I would defy you to calculate reactor transients,
and do reactor "noise" analysis with your concept of what criticality is.

It is actually VERY IMPORTANT to the transport computer codes that are used in the
design and safety analysis of the reactor. You wouldn't know about that - because all
that work and analyis is done BEFORE you get your hands on the reactor.

Your concept of "reality" being divorced from the mathematics; what I call the
"seat of the pants" reality is really quite limiting. Without the mathematics, which you
seem to disdain; the reactors wouldn't work as well or as safe as they do.

The term "criticality" comes from the mathematics. The concept of "k" is an
eigenvalue; which comes from the mathematics.

It is the mathematics that keeps us well grounded in the physics; NOT the "seat of the
pants" understanding.

You might find it illuminating to consider the problem I posed in my previous post.
Let's consider the detonation of "Little Boy". The fissile material in Little Boy has
assembled, but the initiators haven't fired yet. Let's suppose additionally that there
were no stray neutrons around.

Little Boy has assembled its mass of U-235; but for an extremely brief period of time,
there are no neutrons present, as of yet. Consider:

Is Little Boy critical?

What is "k" of Little Boy? Does it exist? If so; can you say something about its value?

Or consider the following. I have an EXACTLY critical reactor with the fundamental
mode flux therein. I send a pulse of neutrons into the reactor.

Have I changed the criticality of the reactor by adding the neutron pulse?

Have I changed "k" for the reactor by adding the neutron pulse?

Have I changed the reactivity of the reactor by adding the neutron pulse?

Dr. Gregory Greenman
Physicist
 
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  • #16
quetzalcoatl9 said:
Homer Simpson works at a power plant too...i think that you are way over your head in debating Morbius on these kinds of issues - why don't you search the PF archives...
quetzalcoatl9,

Yes - it was nuclear power plant operators like "Homer Simpson" working
at Three Mile Island Unit 2 that needlessly plunged the nuclear industry
into a tail-spin for more than a quarter century; because they didn't
understand the physics of a reactor as well as they thought they did.

That was the subject of a pevious discussion here, not long ago.

It's like the old adage from the aerospace industry; "Planes are designed
by people with PhD degrees, built by people with Master degrees..."

There's a REASON they have the PhDs design the planes.

Dr. Gregory Greenman
Physicist
 
  • #17
Morbius said:
curie,
Without the neutron source; the Oklo could have just sat there in a critical state; but with
no neutrons in it. However, given that there are extraneous neutrons; it is only a matter
of time before one finds its way to the reactor, and we get a self-sustaining chain reaction.

But there DOES need to be an initial neutron - provided by cosmic rays, radioactive decay...

I was going to say I meant source in the "conventional sense" of a neutron source, but that is actually incorrect & lazy. I still don't think the initial neutron would have to literally be a neutron external to the assembly. Could it have been the initial neutron was from a spontaneous fission (SF) inside the assembly that happened to "get lucky" at a time when the reflecting & moderating properties of the assembly were also just right? If so, then your inclusion of radioactive decay as a source of initial neutron could be said to include SF.

Btw, I would be interested to read your input on the questions you posed on the example scenarios.
 
  • #18
curie said:
Btw, I would be interested to read your input on the questions you posed on the example scenarios.
curie,

I'll give Emfuser a chance to answer.

If not - then I will give a full explanation to each of those questions.

Dr. Gregory Greenman
Physicist
 
  • #19
quetzalcoatl9 said:
if i may: LOL...are you serious? is speaking about nuclear physics in mathematical terms silly?

Homer Simpson works at a power plant too...i think that you are way over your head in debating Morbius on these kinds of issues - why don't you search the PF archives...

Not really

Morbius is the typical paper-bound scientist. Completely stuck in a paper world with a very narrow, rigid view of things. He reminds me of my neutronics teacher who was a physics guy. There's no hate, just an amusement at the unnecessary rigidity when talking specifically about actual nuclear power plant operations.

Just to clarify what I am and what I do, I'm a reactor engineer with experience as an operator. I actually work at a nuclear power plant, participate in the design of cores, participate in and supervise plant startups, and regularly write power transient plans. I'm not exactly talking out of my behind here.

So to us, it's fine and dandy that, in the world of universities, research labs, and the rest of the paper bound world, the single word "critical" is used broadly to incorporate what the functional nuclear power world calls "critical mass" and "critical geometry." Yes, we all understand the theoretical basis for these things because we went to school and learned them and apply said education every day in our work.

Even the companies that write the codes, like Westinghouse, Areva, GE, and some now gone or absorbed, older vendors, don't ever use criticality in the fashion that Morbius is so stuck on. We always specify "critical mass" or "critical geometry" if you want to talk about those specific aspects of core design. In the world of nuclear power, which I have restricted my comments to, criticality is always in terms of neutron population.

To talk about who is using what terminology in a "non-standard" fashion is needless. To a physicist, it's purely in the mathematics. They will use "critical" in the abstract mathematical sense, which considers only the mathematical model. In the functional nuclear power world, "critical" is always in regards to actual neutron population behavior.

This statement
Morbius said:
The above shows that you really DON'T understand some very important features about
the operation of a nuclear reactor. I would defy you to calculate reactor transients,
and do reactor "noise" analysis with your concept of what criticality is.
... is laughable. I understand it just fine. I just happen to be in the position of having to deal with the reality of nuclear power operations, rather than just spouting theory and mathematics at people.

Maybe if I go to the nearest nuclear engineering grad program, and get my PhD, my true-to-life experiences will stop meaning anything? Maybe it has to be a physics PhD...
 
  • #20
Morbius said:
It's like the old adage from the aerospace industry; "Planes are designed by people with PhD degrees, built by people with Master degrees..."

Morbius,

I couldn't agree more.

As someone currently doing their PhD dissertation in theoretical chemistry, I know what you mean. I worked in industry for several years before going to grad school, so I am well familar with the false assumptions behind the attitude that Emfuser is espousing. I've even been referred to once as "too academic", as if that were an insult :smile:

Despite being a "paper-bound scientist" I have managed to design a few systems at my computer-bound desk that have worked out just fine in the non-paper-bound "real world" (as if the entire theoretical physics established by humanity were somehow "not real") :rolleyes: My experimental collaborators seem happy enough at these abstract, and hence clearly false, results. :-p
 
  • #21
Emfuser said:
Maybe if I go to the nearest nuclear engineering grad program, and get my PhD, my true-to-life experiences will stop meaning anything? Maybe it has to be a physics PhD...

No, your experiences of course mean a great deal and there is no substitute for that. But you may also realize that folks who have a PhD in physics have worked very hard to understand their subject matter extremely well.

It was the endeavors of academic physicists that resulted in the development of nuclear science (over 90% of all cutting edge science is still done at universities and government labs) - in a setting of peer review, not supply and demand. Do you respect that even a tiny bit?
 
  • #22
quetzalcoatl9 said:
Morbius,

I couldn't agree more.

As someone currently doing their PhD dissertation in theoretical chemistry, I know what you mean. I worked in industry for several years before going to grad school, so I am well familar with the false assumptions behind the attitude that Emfuser is espousing. I've even been referred to once as "too academic", as if that were an insult :smile:

Despite being a "paper-bound scientist" I have managed to design a few systems at my computer-bound desk that have worked out just fine in the non-paper-bound "real world" (as if the entire theoretical physics established by humanity were somehow "not real") :rolleyes: My experimental collaborators seem happy enough at these abstract, and hence clearly false, results. :-p

I believe you misinterpret my words.

I have a real problem with people stuck in the theoretical world who go around beating people over the head with their degrees. I have an even bigger problem with the people who not only beat people over the head with their degrees, but they do so to those who are actually knee deep in the applied world, and not sitting at a desk or in a lab.

It is pretentiousness such as what I see in this thread that causes the very disrespect that you describe. The failure of high-horse-riding scientists to acknowledge the realities of how something is actually done vs. the conceptual world is the very reason that the idea of being "too academic" exists. Any engineer recognizes full well the value of the theory and methodology we are taught, but it's not until you take that engineer, slap a hardhat and some PCs on him, and drag him into containment while we're offline does he or she gain the understanding of what is actually going on when you have to take those ideas you came up with on paper, and try to fit them with reality.

Thus, I will reiterate that I do not come into this thread with any agenda to disrespect, but I have little tolerance for people who don't actually do the job I do, telling other readers that I have a gross misunderstanding of the concepts at hand while simultaneously making needlessly obnoxious comments about academic degrees, and figuratively thumping their chests, with authority.

That turbine sitting a few hundred feet away from me is still spinning. That reactor is critical. No, we don't have any silly requirement about having a neutron source in the core all the time.

Now, can we agree to acknowledge that there are two schools of equally valuable thought here? One is the purely theoretical, one is applied. They each have their own nuances, and it would probably be a good idea for those involved in each to be representing their respective schools of thought, without one trying to put on the hat of the other, and speak for them.

Is such a suggestion agreeable to you academic folks? You can talk in the realm of theory all you want, but instead of trying to stifle and browbeat people who come from the applied side, actually consider their viewpoints.

:)
 
  • #23
Emfuser said:
Not really

Morbius is the typical paper-bound scientist.

WRONG! I have worked on design and design methods for REAL devices; real
nuclear reactors, and other real nuclear systems.

These reactors and systems have been BUILT and TESTED!

NO - you can't paint me as someone who is in an ivory tower somewhere.

My experience is AT LEAST as "real" as yours!

Just to clarify what I am and what I do, I'm a reactor engineer with experience as an operator. I actually work at a nuclear power plant, participate in the design of cores, participate in and supervise plant startups, and regularly write power transient plans. I'm not exactly talking out of my behind here.

Could have fooled me!

So to us, it's fine and dandy that, in the world of universities, research labs, and the rest of the paper bound world, the single word "critical" is used broadly to incorporate what the functional nuclear power world calls "critical mass" and "critical geometry." Yes, we all understand the theoretical basis for these things because we went to school and learned them and apply said education every day in our work.

Even the companies that write the codes, like Westinghouse, Areva, GE, and some now gone or absorbed, older vendors, don't ever use criticality in the fashion that Morbius is so stuck on.

WRONG! My thesis supervisor was the late Prof. Allan F. Henry - who used to be
the head of codes and methods development at Westinghouse. Prof. Henry was a
stickler for the proper use of these terms. In his textbook, which is one of the seminal
texts in nuclear reactor theory; Prof Henry made a point of the fact that "critical" is a
property of the geometry and materials, and does NOT mean neutrons!

We always specify "critical mass" or "critical geometry" if you want to talk about those specific aspects of core design. In the world of nuclear power, which I have restricted my comments to, criticality is always in terms of neutron population.

And you are WRONG! It is those "in the industry" that have BASTARDIZED the term;
and use it incorrectly.

I note that you sidestepped my challenge to answer the questions I posed in my last
post. It would have been illustrative for you to have attempted them.

However, let's consider a super-critical assembly - like the example I gave of the
core of Little Boy before it exploded. Let's assume that we have this assembly sitting
there without any neutrons present.

Now suppose I introduce a single neutron heading into the assembly. [ This is the type
of problem nuclear weapons designers have to consider.] The interactions of neutrons
with the material is stochastic - that is it is probabilistic - NOT deterministic. There is
a finite probability that the neutron thus introduced will be absorbed without starting a
chain reaction. That's because the radiative capture cross-section of the Uranium is
finite.

All we can say is that there is a certain probability that the neutron so introduced will
lead to a chain reaction - it is not guaranteed. So how do we determine that probability?

That probability is a VERY REAL physical property of the assembled nuclear system.

It turns out - that the probability is a function of the "k"; or "criticality" of the assembled
system - something Emfuser claims doesn't exist because there are no neutrons.

There's a whole inter-related body of physics and knowledge here that requires that
"k" and "criticality" exist as a function of the geometry and materials independent of
whether there are neutrons present or not.

Emfuser, you are analogous to the child that is playing a toy piano wherein all the black
keys are just painted on. The only notes you have at your disposal are those in the key
of C-Major. The problem is you don't see any use for the other notes.

Well - there is a WHOLE WORLD of music and music theory beyond the key of C-Major.

There's the key of D, E,...as well as the existence of "minor keys", and "diminished keys"
... ALL of which you see no use for because you are only familar with the notes in the
key of C-Major.

Then you would have the audacity to tell Mozart that he doesn't need any notes beyond
those of C-Major; when Mozart has actually composed symphonies, that you HAVEN'T!

... is laughable. I understand it just fine.

You keep proving that you DON'T understand just fine.

I just happen to be in the position of having to deal with the reality of nuclear power operations, rather than just spouting theory and mathematics at people.

I doubt that you have done say a reactor noise analysis? Have you ACTUALLY done
reactor noise analysis?

OK - you're a startup engineer. Did you DESIGN the reactor?

A friend of mine was a startup engineer. I'm familiar with the job. You've essentially
been given the reactor - you DIDN'T design it. You didn't deal with all the physics that
require the mathematics and concepts that I'm talking about.

Maybe if I go to the nearest nuclear engineering grad program, and get my PhD, my true-to-life experiences will stop meaning anything? Maybe it has to be a physics PhD...

If you do go study at a nuclear engineering grad program; you would find out that
"criticality" is a property of the geometry and materials.

Dr. Gregory Greenman
Physicist
 
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  • #24
curie said:
Btw, I would be interested to read your input on the questions you posed on the example scenarios.
curie,

Since Emfuser took a pass at answering the questions i posed; I'll do so for you.

In regards to the core of the Little Boy device sitting there without any neutrons:

Is Little Boy critical? Yes - in fact the assembled Little Boy core is super-critical.
Even though there are no neutrons, the "k" of Little Boy is defined; and it is greater than
unity. The "k" and the "criticality" are properties of the geometry and materials;
irrespective of whether there are neutrons in the device at the time.

As I explained in my previous response to Emfuser, one of the physical properties
of the super-critical assembly is the probability that a neutron introduced at a given
position, with a given energy, and going in a given direction will lead to a chain reaction,
as opposed to immediately being absorbed, or having the chain reaction start and then
die out. It turns out that the probability that the neutron will cause a runaway chain
reaction is a function of the "k" the assembly [ in addition to the properties of the added
neutron].

Under Emfuser's understanding [ or in actuality lack thereof ]; there would be no "k"
defined because his "understanding" requires neutrons to be present. The super-critical
Little Boy assembly has a physical property every bit as REAL as any other physical
property - namely this probability - but we can't characterize it without the value of "k".

Evidently Emfuser is also ignorant of the concept of "neutron importance". You need
the concept of neutron importance when you define reactivity. Neutron importance
will properly account for the fact that a given number of neutron introduced into the
core will have differing effects on the reactivity based on the position, energy, and
direction of the incident neutrons.

The neutron importance is the solution to the adjoint transport equation. However,
unlike the forward transport equation which solves for a physical quantity - namely
the distribution of neutrons in phase space - there are no "adjoint neutrons". So
Emfuser would contend that it isn't "real".

As another analogy, consider the suspension system on your car. This suspension
system can either be underdamped, overdamped, or "critically damped". [ If your
"shocks" are worn - it will be underdamped. ] This property of the car's suspension
system EXISTS and is WELL DEFINED - independent of whether the suspension
system is actually moving at the time. The car's suspension is either underdamped,
overdamped, or critically dampded; even if it is not moving. Likewise, a reactor is
sub-critical, super-critical, or exactly critical; independent of whether there are actually
neutrons in the reactor multiplying or attenuating.

Emfuser knows only basic Reactor Theory 101. Fortunately, I would assume the
people that actually designed the reactor he works on have a more comprehensive
knowledge of Nuclear Reactor Theory.

The question about putting a pulse into an exactly critical reactor:

Putting a pulse of neutrons into the reactor DOESN'T CHANGE the criticality.

Likewise, putting a pulse of neutrons in the reactor DOESN'T CHANGE the "k" of the
reacor. [ Assuming no heating that would alter the material properties. There will be
an insignificant amount of heating - depending on the magnitude of the pulse ].

The reactivity is different. The reactivity DOES DEPEND on the distribution of neutrons
in the reactor.

Before the pulse. the exactly critical reactor had a reactivity of ZERO. The reactivity
vanishes because the geometry and materials are in an exactly critical configuration,
AND I also premised the question with the fact that the neutron population present was
the fundamental mode. Under those conditions, the reactivity vanishes identically.

However, when I add the pulse of neutrons; I'm augmenting the neutron population with
a bunch of neutrons that are NOT in the same distribution as the fundamental mode.

With the addition of this neutron pulse; the reactor will go through a transient on its way
to a new steady-state. During this transition the reactivity is NOT ZERO!

When the reactor reaches a new steady state with an increased neutron population; that
new population will be a multiple of the fundamental mode; so that the neutron population
is once again in the fundamental mode and the reactivity vanishes exactly.

[This is all modulo the assumption of constant material properties; i.e. insignificant heating
or the assumption that the cooling system removes any excess heat ]

This is EXACTLY the type of questions one would expect in a graduate program in
nuclear engineering; in a reactor theory or transport theory course.

Dr. Gregory Greenman
Physicist
 
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  • #25
i have a copy of Arfken's "mathematical methods for physicist" from a grad course i took.

in one chapter it gives what is called the neutron diffusion equation as:

-D \grad^2 \phi(r) + k^2 D \phi(r) = Q \delta(r)

where \phi(r) is the neutron flux, Q\delta(r) is the source, k and D are constants (I assume D is the diffusion constant).

(the solution involves Fourier transforming, solving, then back-transforming).

i am curious, is the "k" in this expression the same "k" that you guys are talking about? (i know virtually nothing about nuclear science).
 
  • #26
Then, can you define "k" for anything? The entire earth, for example?

quetzalcoatl9, that form is different from what I remember. I think that k2 is a coefficent of absorption, but don't quote me. :wink:
 
  • #27
quetzalcoatl9 said:
i have a copy of Arfken's "mathematical methods for physicist" from a grad course i took.

in one chapter it gives what is called the neutron diffusion equation as:

-D \grad^2 \phi(r) + k^2 D \phi(r) = Q \delta(r)

where \phi(r) is the neutron flux, Q\delta(r) is the source, k and D are constants (I assume D is the diffusion constant).

(the solution involves Fourier transforming, solving, then back-transforming).

i am curious, is the "k" in this expression the same "k" that you guys are talking about? (i know virtually nothing about nuclear science).
quetzalcoatl9,

Afraid not.

-D \grad^2 \phi(r) + \Sigma_a \phi(r) = {1 \over k} \Sigma_f \phi(r)

The above is a zero-scattering version of the diffusion equation. [ The "sigma a" term
means absorption. If there were scattering, this would be replaced by the total
cross-section and there would be an in-scattering term on the right ] The scattering
just complicates things - so for illustration - let's assume zero scatter.

The term with sigma_f on the right is the fission source.

The inverse "k" multiplier is a way to make the equation "artificially critical".

What we have here is a time-independent form of the diffusion equation. If a system
is really sub-critical, or super-critical; it is not time independent. The neutron flux should
either be falling off for a sub-critical system; or soaring up for a super-critical system.

An equation implies equality or balance. If the system is sub-critical, then destruction
exceeds production. If the system is super-critical, then production exceeds destruction.
So there's no equality, and no equation without a time-dependent derivative term.

However, you can make the system balance artificially by dividing the fission source
on the right hand side by "k". If production is too large; bring it down by dividing by
a "k" greater than 1. If destruction exceeds production; artificially increase the fission
source on the right by dividing by a "k" less than 1 to achieve balance.

Thus you get k > 1 for a super-critical system, and k < 1 for a subcritical system. If the
system is exactly critical - then k = 1.

That's the "k" that we are talking about. It's a eigenvalue of the equation; or equivalently
its inverse is the actual eigenvalue. Note that the equation is homogeneous. That is
you can put all the terms involving phi and its derivatives on one side and the right hand
side will then be zero.

If the equation were non-singular there would be exactly one solution. Well since the
equation is linear and homogeneous; there is an easily seen solution - phi = 0.

Well phi = 0; meaning no neutrons is not what you want for an operating power reactor.

So for particular values of the eigenvalue 1/k; you can make the above equation singular.
That means there will be multiple solutions. With multiple solutions, you can have both
the trivial solution phi = 0; and some more interesting solutions. In fact, you get
INFINITELY many solutions, because if phi is a solution, then any constant multiple of
phi is a solution.

That corresponds to the fact that in a reactor, if phi is the solution; then a constant
multiple is also a solution - corresponding to a power level that is that same constant
multiplied by the power for your original solution. It means a critical reactor can be
run up or down to whatever power you want, as long as you can hold the material and
geometric properties constant.

Dr. Gregory Greenman
Physicist
 
  • #28
So if I am understanding this correctly, forcing the equation to be excatly critical makes it time independent? That sounds a little too easy, isn't it just ignoring the actual situation?
 
  • #29
theCandyman said:
So if I am understanding this correctly, forcing the equation to be excatly critical makes it time independent? That sounds a little too easy, isn't it just ignoring the actual situation?
Candyman,

No - because what you ultimately WANT is a time-independent equation.

What you ultimately want for your reactor is for it to sit there at a steady-state power level
and just turn out energy.

So in effect - you postulate the end solution that you want - one that is "stationary" - that
is time-independent.

As I stated above; you can only get that if you make the equation "singular".

The system will only be singular for some special choices of the cross-sections and
geometry.

That is - if you are designing your reactor - you adjust the design of the system
so that you eventually get a stationary system with k = 1 ; i.e. the system is exactly
critical.

Now in actual fact; because we don't know cross-sections exactly, and some other factors
it turns out that the system may actually go critical at some different, non-unity value of
"k". Therefore, "k" also provides a systematic way to deal with the errors in your nuclear
data.

If the reactor actually goes critical with k = 1.002; because of small errors in your data;
then the next reactor you design; you shoot for k = 1.002 instead of exactly k = 1.

Dr. Gregory Greenman
Physicist
 
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  • #30
i see.

does one go about solving this equation iteratively (much like a self-consistent field equation - i assume the actually boundary conditions can be complicated) as opposed to an exact matrix inversion?
 
  • #31
I don't think so. I had to use this equation some in my fundamentals class. The one we used was time independent and for monoenergetic neutrons. It didn't strike me as anything difficult, but I never REALLY understood what it was I was looking at after getting the answer.

As for the boundary conditions, it depends on the geometry. If I remember correctly, sphereical geometry was the easiest with which to deal.
 
  • #32
Thanks for the enlightenment on your questions Morbius - gets the old grey matter churning!

I must say I have never had an appreciation of the concept of k, criticality, etc in the purely mathematically derived sense, although talking around the subject here I can see it. I have some brief reactor theory academic training & interact with masters students study reactor engineering & I am confident that none of these students over the last couple of years will have a clue about this level of the theory. But on the other side, the practical side, they can be equally clueless, not having done any lab work since their first undergraduate year, eg no obvious appreciation of the basic concept as to why one would take more than one reading of a varying parameter & compute an average, not being able to interpret a log scale to take a reading from a chart, etc

Onwards from student level, I don't think it is necessarily a problem - broadly speaking there are & always will be operational types & more theoretical types of person as demanded by the world beyond the teaching stage. Ultimately the most theorectical & academic mathematically-based understanding is the highest form and will always be "correct", correct meaning adhering to the most accepted advanced theory. In other different (& thus it could be said lower) levels of understanding, some concepts may be "understood in a different way" & are actually incorrect, but nevertheless they are generally adequate for the model they are applied to, eg having a full understanding of reactor physics theory as opposed to having a more operationally-based grasp. The fullest level of understanding will always work downwards, ie it can be applied to all models & situations, but if you are looking upwards from a different level of understanding, this can result in a problem. I see this often at plant nuclear/reactor safety meetings, where the committee is a mix of both types of people. Ideally it should work collaboratively as a team, getting the best out of all but all too often it ends up in academic vs operational type debates, sometimes this results in hopelessly over-complex & impracticable measures being imposed with little or no operational benefit. On no account though, should disrespect for any viewpoints be allowed to cloud the issues - this is the science & technology field, not politics! So back to increasing our understanding, where it is helpful to discuss not only the "purist" understanding but how it can be understood where it applies in the more operational setting.
 
  • #33
quetzalcoatl9 said:
i see.

does one go about solving this equation iteratively (much like a self-consistent field equation - i assume the actually boundary conditions can be complicated) as opposed to an exact matrix inversion?
quetzalcoatl9,

Yes - the solution is solved iteratively.

It actually requires a "nested iteration" - there's an "inner iteration" and an "outer iteration".

When you solve the equation, you start out not knowing either the flux, phi; nor the
eigenvalue "k" that you are trying to solve for.

Therefore, there is an "outer iteration" that converges on the eigenvalue "k". That
iteration takes the form, typically as a "power iteration"; which you can look up in any
text on iterative methods.

Within each outer iteration, the value of "k" is fixed; but you still have an iterative problem
solving for the value of the neutron flux as a function of space and energy.

As for boundary conditions; "vacuum" boundary conditions are the norm. That is at
the edge of your problem - at the reactor boundary, or beyond the shield if that is included
[ which it should be because it can scatter neutrons back to the reactor ]; you impose
a boundary condition that says there are no incoming neutrons.

Dr. Gregory Greenman
Physicist
 
  • #34
curie said:
Ultimately the most theorectical & academic mathematically-based understanding is the highest form and will always be "correct", correct meaning adhering to the most accepted advanced theory. In other different (& thus it could be said lower) levels of understanding, some concepts may be "understood in a different way" & are actually incorrect, but nevertheless they are generally adequate for the model they are applied to, eg having a full understanding of reactor physics theory as opposed to having a more operationally-based grasp. The fullest level of understanding will always work downwards, ie it can be applied to all models & situations, but if you are looking upwards from a different level of understanding, this can result in a problem.
curie,

I agree with your summary above. The fullest and most complete understanding is the
scientific and mathematical understanding. I also see that one can have a "working
understanding" that serves a more limited purpose. That, I believe; is where Emfuser
is.

That's why I analogized his understanding to a musician that only plays in the key of
C-Major. You can make a lot of music in the key of C-Major, and if that's what you
play in; fine, so be it.

However, it is limiting. There's a whole body of music and music theory that goes
beyond the key of C-Major. So Emfuser tellinig me that a device can't be super-critical
unless it has neutrons in it; is like a "musician" telling a composer that there's no note
between "F" and "G". The composer counters with, of course there is; "F#".

Then the "musician" comes back and says that "in the real world" nobody uses "F#".
That's just something to write on the chalkboard. Nobody out making music and selling
records uses "F#".

Obviously, there's a very good use for "F#", and all the other notes that are not in the
key of C-Major.

If this were a forum about Music; one wouldn't want the contention to stand unchallenged
that there was no need for "F#" and the other notes beyond the key of C-Major.

I think one's understanding should be grounded in a complete understanding of the
subject. I hear too many engineers that just "plug and chug"; they plug values into some
formula they learned in school, without an understanding of what the formula really means.

There are many cases where someone used the wrong formula; or forget that the formula
is an approximation and forget under what conditions the approximation is valid.

I recall NASA had some trouble a while back where they lost [ crashed ] a mission
because someone used an approximation that wasn't valid. I would sure hate to have
something like that happen in the nuclear field.

Dr. Gregory Greenman
Physicist
 
  • #35
Morbius said:
It actually requires a "nested iteration" - there's an "inner iteration" and an "outer iteration".

When you solve the equation, you start out not knowing either the flux, phi; nor the
eigenvalue "k" that you are trying to solve for.

Isn't flux a given measurement?
 
  • #36
theCandyman said:
Isn't flux a given measurement?

What is the definition of flux? The number of neutrons passing through a unit area per unit time (n/cm2s), and it can vary between 0 (never negative) and whatever value can be achieved in a transient before the fuel and reactor geometry become disrupted.

At zero power, the neutron flux is due to whatever spontaeous fissions of certain transuranics and the few fissions they induce, which could be on the order of 10,000 - 100,000 n/cm2s, as compared to full power where the flux is on the order of 1013 n/cm2s.

The objective in having a startup source is to provide the neutron detectors with a strong enough signal to monitor the criticality of the core. In subcritical configuration, the neutron activity is a function of the source strength. When a reactor has gone through some cycles, and some of the fuel has achieved some reasonable level of burnup to where there is sufficient transuranics, a sourceless startup might be possible. If a reactor has incore detectors (IIRC all commercial plants were built initally with ex-core detectors), it is more likely that one could do a sourceless startup.

As for targeting particular eigenvalues, one can only expect the same eigenvalue in a subsequent startup if all initial conditions are the same, i.e. the core configuration is more or less in equilibrium, which means the same core average burnup (efpd), same power history, same burnup distribution, same feed batch size and enrichment, same burnable absorber content and distribution, same temperature spatial distribution. In reality, this never never happens.

As for reactor design, in a sense doing a core design is much like reactor design, but with many parameters already determined, e.g. the number of assemblies and their geometry (lattice), coolant temperature, control element configuration. Some of the key variables in a core design include energy, batch size, enrichment and distribution, and burnable absorber (either discrete or integral) and distribution. A core designer however does not go back and re-write the physics of the lattice code (CASMO, Phoenix, WIMS, TGBLA) or core simulator (SIMULATE, ANC, Panther, POLCA, MIRCOBURN, PANACEA).

Even today, the nuclear physics codes are still tweaked, particularly with respect to handling the presence of burnable absorber adjacent to guide tubes and water rods where the moderation is more significant.

Presently, ANL is conducting a program - National Numerical Reactor - which uses multigroup transport theory to do a core simulation. This has been coupled with a sophisticated CFD code which calculates the coolant properties, which then provides the input for the moderation of the core.
 
  • #37
so let me see if i got this right..(bear with me, as I'm just a lowly chemist :) )

1) Without the ability to detect the neutron current density, operators would essentially have no idea what is going on in the reactor. Other detection means, such as coolant temperature, gamma radiation, etc. are all indirect methods and are insufficient to completely guarantee safe startup of the core.

2) Neutron detection, like any detection means, may have significant error in detecting weak signals (I assume that He-3 is used in detection, like in INS studies?)

3) New reactors need startup sources to initiate fission. Older reactor components, having been irradiated and are currently in some decay process, can become natural neutron emitters and hence it may be possible to startup the fission cycle without a startup source.

4) HOWEVER...these natural emitters in the core emit low levels of neutrons and so the neutron detectors may be partial "blind" as to the true neutron flux in the reactor - and so a critical (or worse, supercritical) configuration can be achieved, at least momentarily (until the neutron flux starts to rapidly shoot up, i presume). The operator is going completely on "faith" at this point.

In analogy, if I have a gas oven i may a) start up a pilot flame (neutrons) and b) turn on the gas (fission fuel) in order to get more flame (neutrons). That would be safe operation. Alternatively, I could just turn on the gas and then light the flame. But since I really have no way of detecting the gas, it could be possible that the entire room has filled with gas prior to ignition, at which point the room+gas non-equilibrium state will proceed to follow the potential energy surface down to a new energy minimum

5) Therefore, startup of an older reactor without an ignition source puts the general public at risk needlessly.

Since it seems operators are willing to startup with such risk, I assume changing out the source must be a hassle?
 
  • #38
Remember, the initial question was reactor startup, and startup of the first core (all fresh fuel) definitely requires a source of neutrons other than those from fission. That source is placed in the reactor in order to induce a 'detectable' signal so that the state of the core IS known.

See slide 32 of
http://www.energy.kth.se/courses/4A1627/Material2005/PhysicsPart/05%20Reactor%20Kinetics%20and%20Operation%20Rev%200.pdf

See also -

When a reactor is started up with unirradiated fuel, or on those occasions when the reactor is restarted following a long shutdown period, the source neutron population will be very low. In some reactors, the neutron population is frequently low enough that it cannot be detected by the nuclear instrumentation during the approach to criticality. Installed neutron sources, such as those discussed in Module 2, are frequently used to provide a safe, easily monitored reactor startup. The neutron source, together with the subcritical multiplication process, provides a sufficiently large neutron population to allow monitoring by the nuclear instruments throughout the startup procedure. Without the installed source, it may be possible to withdraw the control rods to the point of criticality, and then continue withdrawal without detecting criticality because the reactor goes critical below the indicating range. Continued withdrawal of control rods at this point could cause reactor power to rise at an uncontrollable rate before neutron level first becomes visible on the nuclear instruments.
http://www.hss.energy.gov/NuclearSafety/techstds/standard/hdbk1019/h1019v2.pdf - page 116 of 128
See also - http://www.hss.energy.gov/NuclearSafety/techstds/standard/hdbk1019/h1019v1.pdf

12.2.1.2.9.1 Reactor Startup Source
The reactor startup source is shipped to the site in a special cask designed with shielding. The source is transferred under water while in the cask and loaded into beryllium containers. This is then loaded into the reactor while remaining under water. The source remains within the reactor for its lifetime. Thus, no unique shielding requirements are required after reactor operation.
Lungmen PSAR, Chapter 12

Neutron detectors work on the basis of activation (not with He-3, but something like Rh or Co) or fission (e.g. fission detectors). See page 76 of -

http://www.hss.energy.gov/NuclearSafety/techstds/standard/hdbk1013/h1013v2.pdf

Startup sources usually stay in the reactor, unless the operating utility applies for a licensing amendment to remove them and do a sourceless startup.

3) . . . Older reactor components, having been irradiated and are currently in some decay process, can become natural neutron emitters . . .
'Older reactor components' should be changed to 'older fuel' or 'irradiated fuel', or 'high burnup fuel', which is typically loaded toward the periphery of the core. In a PWR, the startup sources are placed in assemblies toward the core periphery and near the ex-core detectors.

Some (many or most ?) plants employ in-core detectors in addition to ex-core detectors. I would imagine that this would facilitate sourceless startups.

4) HOWEVER...these natural emitters in the core emit low levels of neutrons and so the neutron detectors may be partial "blind" as to the true neutron flux in the reactor - and so a critical (or worse, supercritical) configuration can be achieved, at least momentarily (until the neutron flux starts to rapidly shoot up, i presume). The operator is going completely on "faith" at this point.
NO! A fresh core has no transuranics, unless it is loaded with MOX (with Pu isotopes). After one cycle of operation, part of the core is replaced with fresh fuel, with the one-cycle (once-burned) fuel returned. After the second cycle, another batch of fresh fuel is added, with the remainder being a mix of once- and twice burned (one and two cycles of operation) being coresident. The burnup is still too low to be effective for use of ex-core detection.

Older reactors might have some high burnup assemblies with sufficient spontaneous fissions to permit a sourceless startup. In that case, the spontaneous fisson rate must provide comparable strength to that of the startup source.

5) Therefore, startup of an older reactor without an ignition source puts the general public at risk needlessly.
Operators follow procedures designed to prevent putting the public at risk! Failure to follow procedure can lead to discharge, and if deliberate, will lead to arrest.

As for whether or not sourceless startups have been performed, perhaps Emfuser knows, or I could check with reactor engineers whom I know.
 
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  • #39
Morbius said:
WRONG! I have worked on design and design methods for REAL devices; real
nuclear reactors, and other real nuclear systems.

These reactors and systems have been BUILT and TESTED!

NO - you can't paint me as someone who is in an ivory tower somewhere.

My experience is AT LEAST as "real" as yours!

For somebody claiming not to be in an ivory tower somewhere, you most certainly talk like you are in one. The fact still remains that I work in nuclear power, you work in research. I work on reactor engineering and core design at a nuclear power plant, you work at a lab. I have tried to make it abundantly obvious that, while we share some similar nuclear background, that we operate in different working worlds

Morbius said:
WRONG! My thesis supervisor was the late Prof. Allan F. Henry - who used to be
the head of codes and methods development at Westinghouse. Prof. Henry was a
stickler for the proper use of these terms. In his textbook, which is one of the seminal
texts in nuclear reactor theory; Prof Henry made a point of the fact that "critical" is a
property of the geometry and materials, and does NOT mean neutrons!

And you are WRONG! It is those "in the industry" that have BASTARDIZED the term;
and use it incorrectly.

Do you have a key on your keyboard, or perhaps a keyboard shortcut that generates the string "WRONG!"? You seem to enjoy condescending just a wee bit.

It must drive you absolutely bonkers that the industry, and even some nuke engineering textbooks use "critical geometry" and "critical mass". No matter how much you want to stonewall and beat on a strawman, a rose, by any name, is still a rose. Like it or not, we're talking about the same thing, just from different perspectives. Just because we use different language does not make it "WRONG!", as you so put, just different. The entirity of the rest of your post continues to beat on the "Emfuser doesn't understand, because he doesn't use "criticality" the same way that I do!" strawman.

No matter how much you talk down my different colloquial language about criticality, it doesn't mean it's "WRONG!". I'm sorry that it's so bothersome to you. We're actually talking about the same thing.

Morbius said:
I note that you sidestepped my challenge to answer the questions I posed in my last
post. It would have been illustrative for you to have attempted them.

Sorry, but I did not have the time last Thursday. Your questions are nuke engineering 101 style questions. I can answer them if you want, but you might blow a gasket when I use "critical mass" & "critical geometry", followed by usage of "critical" in terms of neutron population change. :smile:

Morbius said:
Now suppose I introduce a single neutron heading into the assembly. [ This is the type
of problem nuclear weapons designers have to consider.] The interactions of neutrons
with the material is stochastic - that is it is probabilistic - NOT deterministic. There is
a finite probability that the neutron thus introduced will be absorbed without starting a
chain reaction. That's because the radiative capture cross-section of the Uranium is
finite.

All we can say is that there is a certain probability that the neutron so introduced will
lead to a chain reaction - it is not guaranteed. So how do we determine that probability?

That probability is a VERY REAL physical property of the assembled nuclear system.

It turns out - that the probability is a function of the "k"; or "criticality" of the assembled
system - something Emfuser claims doesn't exist because there are no neutrons.

There's a whole inter-related body of physics and knowledge here that requires that
"k" and "criticality" exist as a function of the geometry and materials independent of
whether there are neutrons present or not.

Emfuser, you are analogous to the child that is playing a toy piano wherein all the black
keys are just painted on. The only notes you have at your disposal are those in the key
of C-Major. The problem is you don't see any use for the other notes.

Well - there is a WHOLE WORLD of music and music theory beyond the key of C-Major.

There's the key of D, E,...as well as the existence of "minor keys", and "diminished keys"
... ALL of which you see no use for because you are only familar with the notes in the
key of C-Major.

Then you would have the audacity to tell Mozart that he doesn't need any notes beyond
those of C-Major; when Mozart has actually composed symphonies, that you HAVEN'T!

*yawn*
How's that ivory tower? :smile:

This is much more analagous to me speaking Italian while you speak Latin. Sure, I learned to speak Latin. I understand it and recognize that it's still spoken by some, and has its uses, but I'm speaking Italian.

Morbius said:
I doubt that you have done say a reactor noise analysis? Have you ACTUALLY done
reactor noise analysis?

We usually don't do them unless we have reason to. It's a collaborative between nuclear design and analysis (my group) and the reactor internals system engineeer.

Morbius said:
OK - you're a startup engineer. Did you DESIGN the reactor?

A friend of mine was a startup engineer. I'm familiar with the job. You've essentially
been given the reactor - you DIDN'T design it. You didn't deal with all the physics that
require the mathematics and concepts that I'm talking about.

No, I'm not just a startup engineer. That's just a portion of my job. Yes, I participate in the core design we do every cycle.

Morbius said:
If you do go study at a nuclear engineering grad program; you would find out that
"criticality" is a property of the geometry and materials.

Well... critical mass & critical geometry sure are fun, aren't they? I'm quite amused that the commercial operating usage of "critical" bothers you so much. :wink:

You still sure that I don't know what I'm talking about over here? Like I said before, that reactor is good and hot, sitting at a nice effective critical state. That turbine is still spinning, those electrons are still moving. I guess I'm not as "WRONG!" as you say I am, regardless of how much furious howling you want to do over what is little more than different perspectives.

Oh and no, we still don't require a source on hand at all times for subcritical operation. :wink:
 
  • #40
Astronuc said:
Remember, the initial question was reactor startup, and startup of the first core (all fresh fuel) definitely requires a source of neutrons other than those from fission. That source is placed in the reactor in order to induce a 'detectable' signal so that the state of the core IS known.

Correct

Only on that first core, of completely fresh Uranium, do we need a source for startup. After all, we're not going critical without any neutrons. (waits for Morbius to come in fuming over my language :biggrin: )

Astronuc said:
Startup sources usually stay in the reactor, unless the operating utility applies for a licensing amendment to remove them and do a sourceless startup.

We can yank them after the first cycle, but they usually sit there until the utility wants to analyze to remove them. They are an insert for the fuel assemblies, and quite easily removed. The burnt fuel from the cycle provides ample neutrons for subsequent startups.

Astronuc said:
Some (many or most ?) plants employ in-core detectors in addition to ex-core detectors. I would imagine that this would facilitate sourceless startups.

We all have incores. Whether or not they are fixed or movable will vary by NSSS design. They have no use as sources during startups. They are used to determine core behavior during power ascension and periodically at power.

Astronuc said:
Older reactors might have some high burnup assemblies with sufficient spontaneous fissions to permit a sourceless startup. In that case, the spontaneous fisson rate must provide comparable strength to that of the startup source.

One, two cycles at the most before sources can be pulled.

Astronuc said:
Operators follow procedures designed to prevent putting the public at risk! Failure to follow procedure can lead to discharge, and if deliberate, will lead to arrest.

As for whether or not sourceless startups have been performed, perhaps Emfuser knows, or I could check with reactor engineers whom I know.

Failure to follow a procedure carries a penalty range anywhere from reprimand to termination or even legal action by the NRC. That's right.

Startups without secondary sources are quite the norm. :smile:
 
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  • #41
quetzalcoatl9 said:
In analogy, if I have a gas oven i may a) start up a pilot flame (neutrons) and b) turn on the gas (fission fuel) in order to get more flame (neutrons). That would be safe operation. Alternatively, I could just turn on the gas and then light the flame. But since I really have no way of detecting the gas, it could be possible that the entire room has filled with gas prior to ignition, at which point the room+gas non-equilibrium state will proceed to follow the potential energy surface down to a new energy minimum

Be careful with your analogies. They might be declared as "WRONG!", and you'll be sent to nuclear jail! No lay person or passerby should be able to understand this stuff!

 
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  • #42
Emfuser said:
For somebody claiming not to be in an ivory tower somewhere, you most certainly talk like you are in one. The fact still remains that I work in nuclear power, you work in research. I work on reactor engineering and core design at a nuclear power plant, you work at a lab.
Emfuser,

I may work at a lab - but it is a lab that does "real world" design and engineering - not
the "ivory tower" type of analysis that you ineptly tried to paint my work as being.

It must drive you absolutely bonkers that the industry, and even some nuke engineering textbooks use "critical geometry" and "critical mass".

Again you are confusing terms. One can have a "critical mass" in a system, and not
have the system be "critical". You are being sloppy in your terminology.

"Critical Mass" and "Criticality" are NOT synonomous!

For example, does a nuclear weapon contain therein a "critical mass" of special nuclear material? YES.
Does it contain a "super-critical mass" of special nuclear material? YES.
Is the warhead, as it is sitting on the missile inside the submarine "critical", or "super-critical"? NO - it is sub-critical.
It has a"super-critical mass" of material; however, it is "sub-critical".

The terms "critical mass" and "critical" are NOT synonomous!

No matter how much you want to stonewall and beat on a strawman, a rose, by any name, is still a rose. Like it or not, we're talking about the same thing, just from different perspectives. Just because we use different language does not make it "WRONG!", as you so put, just different. The entirity of the rest of your post continues to beat on the "Emfuser doesn't understand, because he doesn't use "criticality" the same way that I do!" strawman.

No - it isn't a strawman. For the designs we do at the lab - we operate in the super-critical
realm. As I stated in my previous posts; there are VERY REAL physical properties of a
super-critical assembly that doesn't contain neutrons - for example the probability distribution
that a neutron injected at a give position, with a given energy, and in a given direction;
will produce a chain reaction. That property is a function of the criticality of the
super-critical system.

However, YOU claim that super-criticality doesn't exist for such a system unless it has
neutrons in it. If that were the case, then the above property would be undefined. But
it IS defined - because super-criticality and "k" are properties of the system - NOT
properties of the neutrons.

The best analogy is the underdamped / overdamped / critically damped car suspension.
That is a property of the SUSPENSION and its spring constants, viscous damping
coefficients, and masses - NOT the motion of the car. The property exists even if the
suspension isn't moving.

No matter how much you talk down my different colloquial language about criticality, it doesn't mean it's "WRONG!". I'm sorry that it's so bothersome to you. We're actually talking about the same thing.

No - there's a fundamental difference. You think that the criticality and the eigenvalue
are properties of the neutron distribution - and not the geometry and materials and that
is just plain "WRONG". If you were to do graduate study in nuclear engineering - and
you said the things you said on this board, your professors would tell you that you are
"WRONG".

Perhaps you could address the concept of "neutron importance". Do you need to have
neutrons in the reactor for the neutron importance distribution to exist?

Sorry, but I did not have the time last Thursday. Your questions are nuke engineering 101 style questions.

Yes - they were that type of questions - and you would have FLUNKED based on your
previous and current statements.

We usually don't do them unless we have reason to. It's a collaborative between nuclear design and analysis (my group) and the reactor internals system engineeer.

So how do you do such an analysis with a flawed concept of criticality.

No, I'm not just a startup engineer. That's just a portion of my job. Yes, I participate in the core design we do every cycle.

Just as long as someone with a better understanding of the job checks your work; I'll
have to be OK with that.
Well... critical mass & critical geometry sure are fun, aren't they? I'm quite amused that the commercial operating usage of "critical" bothers you so much. :wink:

I just surprised that you would haven't been better trained.

You still sure that I don't know what I'm talking about over here? Like I said before, that reactor is good and hot, sitting at a nice effective critical state. That turbine is still spinning, those electrons are still moving. I guess I'm not as "WRONG!" as you say I am, regardless of how much furious howling you want to do over what is little more than different perspectives.

In the limit of the reactor being critical and full of neutrons; then your definition of criticality
works.

However, if you consider a super-critical system without neutrons - like an assembled
nuclear weapon - then you are WRONG - because your definitions require neutrons, and
the concepts and properties exist independent of the presence of neutrons.

How would you characterize an assembly - like the assembled core of "Little Boy" that
I used as an example before - without neutrons. Is that core "super-critical" even though
it doesn't have neutrons in it? If not "super-critical", then is it "sub-critical" or "critical".

Here is a physically realistic system - not some "chalk board" hypothetical system; but
a REAL system that existed. You tell me, in your vernacular; is the case of the assembled
Little Boy before neutrons are present - "sub-critical", "critical", or "super-critical"?

Dr. Gregory Greenman
Physicist
 
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  • #43
Emfuser said:
Only on that first core, of completely fresh Uranium, do we need a source for startup. After all, we're not going critical without any neutrons. (waits for Morbius to come in fuming over my language
Emfuser,

The WHOLE REASON for having that source is that YOU CAN go critical without any
neutrons.

It is possible to take the reactor into the critical or even super-critical regime without
neutrons. However, if you don't have any neutrons in the system; then your instrumentation
doesn't indicate that you are in the critical or super-critical regime.

Without an indication by the instuments - you could keep pulling rods when the system
was already super-critical. Then some cosmic rays generate a burst of neutrons for you,
and you have suddenly gone from a super-critical reactor without neutrons to a
super-critical reactor with neutrons that are rapidly proliferating.

It is exactly THAT scenario that the presence of the source is meant to forestall.

It is this very scenario that we are trying to prevent - a super-critical reactor without
neutrons - because the instrumentation relies on neutrons, you don't know it.

Dr Gregory Greenman
Physicist
 
  • #44
Morbius said:
It is this very scenario that we are trying to prevent - a super-critical reactor without
neutrons - because the instrumentation relies on neutrons, you don't know it.

wait...so was my understanding that - startup without a source is dangerous - actually correct or not?

Morbius, is sourceless startup in an older reactor ok?
 
  • #45
quetzalcoatl9 said:
wait...so was my understanding that - startup without a source is dangerous - actually correct or not?

Morbius, is sourceless startup in an older reactor ok?

quetzalcoatl9,

Yes - in an older reactor - or more precisely a reactor with "old" fuel; then you don't need
a source because of the presence of fission products that provide a background source
of neutrons.

What you are trying to prevent is the case where there are no fission products present to
provide a source of neutrons; and there is no neutron source to provide the neutrons.

In other words, you have a reactor; but no neutrons running around in it. The problem is
that all the instrumentation for the reactor runs off neutron detectors. If there are no
neutrons to detect; then you don't get any readings on your instruments; regardless of
what the state of the reactor is.

In this case, your instruments would just read ZERO. However, if you are pulling control
rods at the time; you can take the reactor into a critical or super-critical state while the
instruments still read ZERO.

So with the instruments reading ZERO all the time; you don't know when you crossed the
threshhold into having a critical or super-critical reactor. You don't know when to stop
pulling rods.

You can essentially get the reactor into a state that is very super-critical; but without the
neutrons. However, should a "stray" neutron - like those produced by cosmic ray events
or whatever - comes across this very super-critical reactor, you've now suddenly got a
super-critical reactor with neutrons in it that are multiplying rapidly and producing energy.

This sudden unexpected production of energy could be a problem; and be unsafe.

The reactor became "unsafe" when it transitioned into a state where it could support a
self-sustaining, or self-multiplying chain reaction - i.e. became "critical" or "super-critical"
and not when the neutrons showed up.

That's the essence of my disagreement with Emfuser; the reactor became "critical" or
"super-critical" when the conditions for a self-sustaining or self-multiplying chain reaction
were created - NOT when the neutrons "took advantage" of the configuration.

Nuclear engineers define "criticality" and "super-criticality" to be a property of the
materials and geometry of the reactor, bomb, or whatever - NOT a function of the
neutrons. "Criticality" or "super-criticality" tells you what the neutrons would do;
whether or not they are actually present.

So in the example above; the reactor became "unsafe" when it became "critical" or
"super-critical". The consequences of that "unsafe" condition are only realized when
the neutrons show up.

Dr. Gregory Greenman
Physicist
 
  • #46
thank you, i think i get it.

the definition of criticality seems logical to me.
 
  • #47
Morbius said:
Emfuser,

The WHOLE REASON for having that source is that YOU CAN go critical without any
neutrons.

It is possible to take the reactor into the critical or even super-critical regime without
neutrons. However, if you don't have any neutrons in the system; then your instrumentation
doesn't indicate that you are in the critical or super-critical regime.

Without an indication by the instuments - you could keep pulling rods when the system
was already super-critical. Then some cosmic rays generate a burst of neutrons for you,
and you have suddenly gone from a super-critical reactor without neutrons to a
super-critical reactor with neutrons that are rapidly proliferating.

It is exactly THAT scenario that the presence of the source is meant to forestall.

It is this very scenario that we are trying to prevent - a super-critical reactor without
neutrons - because the instrumentation relies on neutrons, you don't know it.

Dr Gregory Greenman
Physicist

(sorry for my long absence from the thread)

We are most definitely in agreement there. For that fresh new core, you absolutely need a source to go critical. I look forward to doing startups on new cores in the future, as new plants go online.
 
  • #48
That was awesome! I've got to visit back here more often.

I'm definitely glad the pilot doesn't design the jets we fly on, and I'm sure as hell glad the Phd that designed them doesn't pilot them.

I'm betting the pilots have a lot of "who's the friggin newfie idiot that designed this piece of crap" comments and I'm sure that the designers scoff when (insert Morbius TMI operator slam here) pilot error brings their planes down.

Keep up the entertaining threads!
 
  • #49
Homer Simpson said:
(insert Morbius TMI operator slam here)
Homer,

My slam / opinion of the operators of TMI comes from attending a seminar by
Prof. Kemeny who led the commission to investigate TMI.

Prof Kemeny stated that the operators of TMI didn't take into consideration the
equation of state of the water coolant. Prof Kemeny stated that when he visited the
TMI control room, he asked for a "steam table" - a book that gives the equation of state
of water - i.e. at what pressures/temperatures is the water a liquid, and when is it a gas;
and the dividing line between them - the saturation line.

It took the TMI operators about a half-hour to find a steam table. This is something they
should have had available right at hand. What good is it for the operator to know the
pressure and temperature of the water coolant if the operator doesn't know where those
conditions are on the water phase diagram? THAT'S what's important - how far is the
PWR in this case to boiling conditions that you want to prevent?

The accident at TMI was reversible, and could have been forestalled; up to the time the
operators made an irreversible error. The operators noted that the main coolant pumps
were vibrating. The reason the pumps were vibrating is that the coolant conditions in the
reactor were at saturation - the coolant was boiling. The pumps were vibrating because
they were pumping a two-phase mixture of liquid water and steam.

The operators were unaware of that - because they had not consulted a steam table to
ascertain the thermodynamic condition of the water coolant. They decided to shutdown
the pumps to avoid damaging them. THAT was when they lost the core!

Perhaps if the operators had asked themselves under what conditions the pumps would
vibrate like that; perhaps they would not have made an irreversible error. It would be
better to risk damage to the pumps; than to let the core melt.

The operators at TMI basically just reacted to circumstances; and never "got out ahead"
of the accident progression. The philosophy of the NRC in the past was that all one had
to do was to present the information to the operators, and the operators would take care
of the situation.

That's no longer the case. The operators are now more limited in what they can / can not
do. The accident at TMI is analogous to what in the aerospace industry is called CFT -
Controlled Flight into Terrain; which means the plane is always under the pilot's control
as he flies it into the ground.

Dr. Gregory Greenman
Physicist
 
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  • #50
In fairness to the operators, there were major issues with the utility and vendor management. As a results of the TMI incident, staff was enhanced with several folk, including the shift technical advisor (STA) who understood core neutronic and thermal hydraulics. In addition, operators were give much more extensive training and with better simulators, especially in the areas of dealing with fault modes and accidents.

Interface between vendor (supplier of the NSSS) and utility engineering and operations was improved, and the industry was forced to be more 'proactive'.

Complacency is still an issue, not only with nuclear, but any technology based industry.
 
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