RELAP fuel rod-coolant response modeling

AI Thread Summary
The discussion focuses on understanding the direct moderator heating multiplier in heat transfer between a fuel rod and coolant. This multiplier represents the fraction of heat delivered directly to the coolant from neutrons and gamma rays, typically a constant based on reactor type. For Pressurized Water Reactors (PWRs), the value is generally 97.4%, indicating that 2.6% of heat is attributed to the moderator. In contrast, CANDU reactors use a lower value of 92.5% for heat-to-fuel ratio, likely due to a higher fuel ratio in light water reactors (LWRs). This highlights the differences in heat transfer characteristics between various reactor designs.
Vnt666Skr
Messages
11
Reaction score
0
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.
 
Engineering news on Phys.org
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.
 
Hello everyone, I am currently working on a burnup calculation for a fuel assembly with repeated geometric structures using MCNP6. I have defined two materials (Material 1 and Material 2) which are actually the same material but located in different positions. However, after running the calculation with the BURN card, I am encountering an issue where all burnup information(power fraction(Initial input is 1,but output file is 0), burnup, mass, etc.) for Material 2 is zero, while Material 1...
Hi everyone, I'm a complete beginner with MCNP and trying to learn how to perform burnup calculations. Right now, I'm feeling a bit lost and not sure where to start. I found the OECD-NEA Burnup Credit Calculational Criticality Benchmark (Phase I-B) and was wondering if anyone has worked through this specific benchmark using MCNP6? If so, would you be willing to share your MCNP input file for it? Seeing an actual working example would be incredibly helpful for my learning. I'd be really...
Back
Top