RELAP fuel rod-coolant response modeling

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Discussion Overview

The discussion revolves around the modeling of heat transfer between a fuel rod and coolant in the context of RELAP simulations. Participants are exploring the concept of the direct moderator heating multiplier and its significance in reactor types, specifically Pressurized Water Reactors (PWR) and CANDU reactors.

Discussion Character

  • Exploratory
  • Technical explanation

Main Points Raised

  • One participant seeks clarification on the direct moderator heating multiplier and its value in RELAP simulations.
  • Another participant suggests that the multiplier represents the fraction of heat delivered directly to the coolant from neutrons and gamma rays, indicating it is generally a constant dependent on reactor type.
  • For PWRs, a value of 97.4% is proposed for the fraction of heat generated in the fuel, implying a 2.6% contribution from the moderator.
  • A further contribution notes that for CANDU reactors, a value of 92.5% is typically used for heat-to-fuel, suggesting a lower efficiency compared to PWRs, potentially due to a higher fuel ratio in LWRs.

Areas of Agreement / Disagreement

Participants present differing values for the direct moderator heating multiplier based on reactor type, indicating a lack of consensus on a single value applicable across all contexts.

Contextual Notes

The discussion does not clarify the assumptions behind the proposed values or the specific conditions under which they apply, leaving some uncertainty regarding their general applicability.

Vnt666Skr
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Hi,
I am a beginner with the use of relap. So this might be a bit silly. I am studying the heat transfer between a fuel rod and a single channel of coolant. One of the inputs for the heat structure is the direct moderator heating multiplier. What is that and how do I find its value?

Thanks. Any help or advice will be greatly appreciated.
 
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I presume that is the fraction of heat delivered directly to the coolant, i.e. from neutrons and gamma rays. This is generally a constant only dependent on reactor type. For PWR's we use 97.4% for fraction of heat generated in the fuel (moderator would thus be 2.6%).
 
Thanks QuantumPion ! :)
 
QuantumPion said:
I presume that is the fraction of heat delivered directly to the coolant, i.e. from neutrons and gamma rays. This is generally a constant only dependent on reactor type. For PWR's we use 97.4% for fraction of heat generated in the fuel (moderator would thus be 2.6%).

I know for CANDU's we normally use a value of 92.5% heat-to-fuel/energy released. It is interesting that it is so much lower than PWR's. Presumably this is because LWRs have a higher ratio of fuel in the core.
 

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