Which is more efficient: Nuclear Q

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Discussion Overview

The discussion revolves around the efficiency of nuclear power systems, specifically comparing enriched uranium with light water reactors to unenriched uranium with heavy water reactors. Participants explore the definitions of efficiency in terms of material and energy usage for maximum energy output, while also considering various operational factors and reactor designs.

Discussion Character

  • Debate/contested
  • Technical explanation
  • Conceptual clarification

Main Points Raised

  • Some participants argue that efficiency depends on factors such as enrichment levels, burnup rates, and thermal-to-electrical conversion efficiency.
  • Others suggest that the question is ill-posed, as reactor output is limited by cooling systems rather than fuel type.
  • There is a discussion on the physical size of reactors, with enriched uranium reactors potentially being smaller due to higher U-235 concentration.
  • Some participants propose that the problem should be constrained to specific reactor designs and operational parameters, such as a 1000 MWe output and equilibrium cycles.
  • Concerns are raised about the costs associated with fuel production, including enrichment and heavy water separation, as well as backend costs.
  • Some participants express opinions on the safety and reliability of light water reactors compared to other designs, while others challenge these views, suggesting that newer reactor types may not be as safe as claimed.
  • There is a mention of the potential for higher fuel burnup in CANDU reactors due to online refueling, though this is contested.

Areas of Agreement / Disagreement

Participants do not reach a consensus on the efficiency of the two reactor types, with multiple competing views and unresolved questions regarding definitions of efficiency, safety, and operational limits.

Contextual Notes

Participants note that the discussion is complicated by the need for precise definitions of efficiency and the various operational constraints that affect reactor performance. The comparison of costs and energy output is also acknowledged as a complex issue influenced by multiple factors.

K.J.Healey
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Which is more efficient, nuclear power using enriched uranium and light water or unenriched uranium and heavy water?

and by efficient I mean uses the least materials and energy for maximum energy output.

And I'm only asking out of pure curiosity.
 
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The answer will depend upon the LWR enrichment, and the average burnups achieved by both fuels, and the thermal-to-electrical conversion efficiency (which is temperature dependent) of the power generation system.

I'll have to get back on this, since it requires some calcs.
 
Healey01 said:
Which is more efficient, nuclear power using enriched uranium and light water or unenriched uranium and heavy water?

and by efficient I mean uses the least materials and energy for maximum energy output.

And I'm only asking out of pure curiosity.
Healey,

I'm afraid your question is ill-posed.

In regard to your definition of efficiency being with respect to "maximum energy output";
you have to realize that one you get the reactor critical - you can operate it at ANY
power level you desire. The energy output of a reactor is limited by its cooling
system, and not by the fuel it uses and the enrichment thereof.

One could ask the question as to which reactor type uses the least amount of
material to achieve criticality; but even here one has to be specific - least amount of
what material? Total Uranium? Total U-235?

Because the concentration of U-235 is higher for a reactor using enriched uranium;
the core of an enriched uranium reactor can be made physically smaller than that
for an unenriched uranium reactor. However, the fuel is seldom the sole limiting factor
in the design of the reactor core. Cooling consideration play a much bigger part.

If a country has access to enriched uranium fuel, they usually opt for enriched uranium
reactors, while others like Canada, forego enrichment and use unenriched uranium in
their heavy water moderated CANDU reactors.

Both reactors work equally well as heat sources to drive a steam cycle power plant.

Dr. Gregory Greenman
Physicist
 
In regard to your definition of efficiency being with respect to "maximum energy output";
you have to realize that one you get the reactor critical - you can operate it at ANY
power level you desire.

??

This statement is hyperbole, yes? It implies infinite energies. If this statement were litereally true as stated, one power plant of arbitrarily small size could power the whole world without operating at its maximum capcity.

I think the OP was asking which type of reactor produces the most power for the least overall cost investment of energy & fuel.
 
This statement is hyperbole, yes? It implies infinite energies.

There is a practical limit (not a theoretical one) in that at some point the reactor would explode or meltdown.
 
LURCH said:
??

This statement is hyperbole, yes? It implies infinite energies. If this statement were litereally true as stated, one power plant of arbitrarily small size could power the whole world without operating at its maximum capcity.

Not hyperbole. It doesn't imply infinite energy - but infinite power. The transport
equation is linear and homogeneous; thus for any solution, any arbitrary multiple of
that solution is also a solution. If there were no feedbacks, the reactor could put out
infinite power.

The practical limit is if the same material were put into a weapon configuration, not a
reactor configuration; how much energy would be delivered then.

I think the OP was asking which type of reactor produces the most power for the least overall cost investment of energy & fuel.

That's the question I'm saying doesn't make sense. For a given investment of
energy and fuel, you can get the reactor critical - thus it produces energy. If the
cooling system can handle it - this same reactor can operate at whatever power
level your cooling system can handle.

In practice, the power level of the reactor is not limited by the fuel; it is limited by
your capacity to get the heat energy generated out of the core.

Dr. Gregory Greenman
Physicist
 
It would be useful to constrain the problem to say a 1000 MWe and an equilibrium cycle for the respective plants. Then it is a matter of energy production per unit mass of fuel and the cost associated with producing and utilizing the fuel. Enriched fuel has the cost of enrichment and U-ore compared to using natural uranium. But then one has to look at the burnup (energy produced per unit mass, e.g. GWd/tU, or MWh/kgU). CANDUs use less ore input per unit mass, but they also have lower burnups, so they might use 5 or 6 times the mass of fuel.
 
Astronuc said:
It would be useful to constrain the problem to say a 1000 MWe and an equilibrium cycle for the respective plants.
Astronuc,

Exactly. That's why I said the problem as originally stated is ill-posed; it is under
constrained in its definition.

Then it is a matter of energy production per unit mass of fuel and the cost associated with producing and utilizing the fuel. Enriched fuel has the cost of enrichment and U-ore compared to using natural uranium. But then one has to look at the burnup (energy produced per unit mass, e.g. GWd/tU, or MWh/kgU). CANDUs use less ore input per unit mass, but they also have lower burnups, so they might use 5 or 6 times the mass of fuel.

One also has the cost of the isotopic separation for making the heavy water.
Although not as difficult, nor energy intensivie as enriching uranium; it still
represents a significant factor.

In the end, the decision seems to hinge on whether a country has access to
enrichment technology. If a country has enrichment technology, or can purchase
fuel from a country that does have enrichment technology; then light water reactors
are usually used.

Canada on the other hand, does not have enrichment technology, but does seek to
be self-sufficient in their nuclear fuel supply. Hence, they developed / use the
CANDU system.

Dr. Gregory Greenman
Physicist
 
Morbius said:
One also has the cost of the isotopic separation for making the heavy water. Although not as difficult, nor energy intensive as enriching uranium; it still represents a significant factor.
Yep, that's another part of the problem. Then one also has to consider the backend costs, which historically are one of the biggest unknowns.

If we stick to mass of ore/fuel and energy required for enrichment and heavy water, then we'd have the simplest comparison. Trying to determine actual costs is much more difficult, especially when one figures in discount rate and currency conversion rates.
 
  • #10
Generally speaking, light water reactors are safer, more reliable and easier to maintain, IMO. Albeit I think both designs are obsolete. PBR's and fast gas reactors will, again IMO, be the wave of the future. The safety factor alone is overwhelmingly attractive.
 
  • #11
Chronos said:
PBR's and fast gas reactors will, again IMO, be the wave of the future. The safety factor alone is overwhelmingly attractive.
Chronos,

The gas-cooled fast reactor [GCFR ] is probably one of the LEAST forgiving in terms of
safety.

One has the high power density that is the hallmark of a fast reactor, coupled with the
low thermal inertial [ heat capacity ] of a gas-cooled reactor. One needs a lot of good
engineering to resolve those problems.

At this stage of the game; I wouldn't say that any reactor types are "obsolete" or that
any other design is "overwhelmingly attractive".

Dr. Gregory Greenman
Physicist
 
  • #12
Outside of +ve void co-eff. I don't think there is much argument to say that light water is safer than CANDU.

As far as fuel burnup is concerned, I could be wrong but I thought that the CANDU online refuelling made it so that we had higher fuel burnup, since we never run with extra poison due to a new fresh fuel load. I guess this is likely offset due to the lower Bundle Power of the natural Uranium. That said, I would assume Maximum bundle power in a PWR must be about the same since it is center line melting and dryout that are the limiting factors. I guess the enriched bundle could just stay incore for more days.

Any comments??
 
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  • #13
LURCH said:
??

This statement is hyperbole, yes? It implies infinite energies. If this statement were litereally true as stated, one power plant of arbitrarily small size could power the whole world without operating at its maximum capcity.
LURCH,

It's not hyperbole at all - it is simply the physics and mathematics of neutron transport.

By what "logic" did you conclude that the multiplicative indetermism of the power
necessarily implies "infinite energy"? Power is the derivative of the energy with
respect to time. An infinite derivative DOES NOT imply an infinite value of the function.

Take for instance, an electrical "square wave" - a voltage that jumps from 0 to 1 then
back down to zero, then later jumps back up to 1...

Although one can't make a perfect square wave in practice; an "ideal" square wave
has the voltage jump from 0 to 1 instantaneously. The value of the derivative is
INFINITE.

Using your flawed reasoning; one would conclude that the infinite derivative would
result in an infinite value of the voltage. But that isn't true. The voltage stays finite.

The neutron transport equation is linear and homogeneous. IF, and that is a big IF;
one is able to cool the reactor adequately - one can take the energy out as fast as
one likes.

That does NOT imply infinite energy. The total amount of energy in the finite mass of
fuel is FINITE.

This is essentially what allows nuclear weapons to work. There is a finite amount of
energy; even a nuclear weapon is not an infinite source of energy; and that energy
can be produced in a very small amount of time. However, that time is finite; so the
power of a nuclear weapon is not infinite.

However, the mathematics and physics allows energy to be released at very fast rates.
We are limited in how fast we can extract that energy by limits on how well we can
cool the system or hold it together if we don't adequately cool it.

Dr. Gregory Greenman
Physicist
 

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