Design flaw in Canadian Maple Reactor

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Discussion Overview

The discussion revolves around the design flaws in the Canadian Maple reactors, specifically Maple1 and Maple2, focusing on the positive power coefficient of reactivity that was discovered during commissioning. Participants explore the implications of this issue, questioning why it cannot be resolved and discussing potential design and simulation shortcomings.

Discussion Character

  • Debate/contested
  • Technical explanation
  • Exploratory

Main Points Raised

  • Some participants express confusion about why the positive power coefficient of reactivity was not identified during design simulations, questioning the assumptions made regarding environmental conditions.
  • There is mention of the reactor's intended negative power coefficient of reactivity of –0.12 mk/MW, contrasted with the measured +0.28 mk/MW, leading to discussions about the implications of these values.
  • Participants speculate on the potential use of different neutronics/core simulators and cross-section libraries that may have contributed to faulty predictions in moderation or resonance absorption.
  • Some suggest that redesigning the fuel composition could address the issues, with specific mention of using burnable absorbers or changing fuel types to improve the Doppler coefficient.
  • There is a claim that the reactors were scaled up from a smaller design, with references to historical examples like the Soviet RBMK reactors, raising concerns about the integrity of the design process.
  • Participants discuss the need for a coupled physics simulation code to accurately model the behavior of the heavy water moderator under varying conditions, emphasizing the importance of accurate thermal-hydraulics calculations.
  • Concerns are raised about potential miscommunications or oversights in the design process that could have led to significant errors, drawing parallels to other historical engineering failures.

Areas of Agreement / Disagreement

Participants generally express uncertainty and concern regarding the design flaws and the inability to resolve them, with multiple competing views on the causes and potential solutions remaining unresolved.

Contextual Notes

Limitations include unresolved assumptions about the design process, the adequacy of simulation methods, and the specific characteristics of the reactor's fuel and moderator. The discussion reflects a complex interplay of technical considerations that are not fully settled.

Andrew Mason
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I am trying to figure out why the design problem with the Maple1 and Maple 2 reactors cannot be fixed. This http://www.theglobeandmail.com/servlet/story/RTGAM.20080516.wnuclear17/BNStory/National explains the decision to end the projects.

These reactors have been built. During commissioning, they became aware of the problem with a positive power coefficient of reactivity, which means that reactor power output increases with temperature. Obviously that has to be corrected. But why would it present such an insoluble problem that the reactors must be scrapped?

AM
 
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I don't understand this. How come that was not noticed upon design simulation ??
 
vanesch said:
I don't understand this. How come that was not noticed upon design simulation ??
That appears to be a $592 million question.

It was designed to have a negative power coefficient of reactivity of –0.12 mk/MW. But in operation it was measured at +0.28 mk/MW. The units are some kind of measure of the increase in ratio of neutrons produced to neutrons used per MW increase in power output.

AM
 
vanesch said:
I don't understand this. How come that was not noticed upon design simulation ??
That's the question. It depends on what assumption are made particularly with respect environmental (boundary) conditions.

I wonder what neutronics/core simulator was used in the design process, and what cross-section library, and how it was collapsed.

Perhaps the methods lead to faulty predictions in moderation or resonance absorption (Doppler coefficient), which ostensibly could be fixed with an appropriate burnable absorber or fuel composition.

28-06-2006 - INVAP to perform nuclear calculations for Canadian company
http://www.invap.net/news/novedades-e.php?id=20060628192056

An article on the design of Maple and the fuel. Ostensibly, they could redesign the fuel.
http://anes.fiu.edu/Pro/s4ma1.pdf
 
Last edited:
I heard somewhere that to save on design effort they essentially just scaled up a previous smaller fully engineered design. I'm not too sure how true that is.
 
Homer Simpson said:
I heard somewhere that to save on design effort they essentially just scaled up a previous smaller fully engineered design. I'm not too sure how true that is.
Homer,

Of course that's what the Soviets did when they built the RBMK reactors like those at Chernobyl.

The Soviet RBMK reactor is a smaller Soviet nuclear weapons material production reactor scaled
up by a factor of 2. The mistake the Soviets made was not redesigning the fuel to go along with
the reduced neutron leakage afforded by the larger RBMK.

The Soviet RBMK thus had the wrong feedback characteristics; which led to the infamous accident.
If they have a reactor that has the wrong feedback characteristics; it's best not to pursue startup
unless the problems are corrected. Perhaps the mistakes in the design are too integral to the design
that they can't be fixed without essentially scrapping the original design.

This means that they really don't have a good model for their design simuation. Somebody made a
BIG MISTAKE somewhere - be it in processing the nuclear data, the transport simulation software;
the design calculations...who knows where the error is - but evidently the error is large.

I hope someone follows up on this; I'd be curious as to what part of the design process was faulty.

Dr. Gregory Greenman
Physicist
 
Astronuc said:
Perhaps the methods lead to faulty predictions in moderation or resonance absorption (Doppler coefficient), which ostensibly could be fixed with an appropriate burnable absorber or fuel composition.
I was thinking more about this aspect. Could it be in the design phase, they made assumptions about the moderator (heavy water) and it's decrease in density if the temperature changed, whereas the reactor is a pool type so like the Trigas, convection will allow for a flow of moderator which will have a lower temperature than in a static case.

Or, they could improve the Doppler coefficient by changing out the U-silicide fuel with UO2, which has lower thermal conductivity, so the fuel runs hotter and that would produce more negative reactivity at a given power level.
 
Astronuc said:
I was thinking more about this aspect. Could it be in the design phase, they made assumptions about the moderator (heavy water) and it's decrease in density if the temperature changed, whereas the reactor is a pool type so like the Trigas, convection will allow for a flow of moderator which will have a lower temperature than in a static case.
Astronuc,

One would hope that they have a "coupled physics" simulation code; neutron transport coupled with
a thermal-hydraulics response solver. That way they don't have to "assume" anything about the density
or temperature of the heavy water moderator. The thermal-hydraulics code will calculate that for them.

Dr. Gregory Greenman
Physicist
 
Homer Simpson said:
I heard somewhere that to save on design effort they essentially just scaled up a previous smaller fully engineered design. I'm not too sure how true that is.

Ooopsa ! That's centimeter, not inches ! :biggrin:
 
  • #10
vanesch said:
Ooopsa ! That's centimeter, not inches
vanesch,

You mean remeniscient of the miscommunication between NASA and Lockheed on the
Mars Orbiter mission due to a confusion over whether the units were metric or English:

http://www.cnn.com/TECH/space/9909/30/mars.metric/

Dr. Gregory Greenman
Physicist
 
  • #11
Morbius said:
Astronuc,

One would hope that they have a "coupled physics" simulation code; neutron transport coupled with
a thermal-hydraulics response solver. That way they don't have to "assume" anything about the density
or temperature of the heavy water moderator. The thermal-hydraulics code will calculate that for them.

Dr. Gregory Greenman
Physicist
One would hope. But then in this day and age, I've seen some rather unbelieveable practices or mind-bogglingly stupid assumptions, which left me wondering 'what were they thinking?' The miscommunication between NASA and Lockheed - and no one bother to check the interface to assure consistency in the calcs - is a striking example.

It would seem pretty easy to figure out what's wrong with the initial design and develop a remedy. Afterall, TRIGA fuel was redesigned from HEU to LEU, but still had to meet all the same tech specs. It should be a simple proposition to modify the driver fuel.
 

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