Abstract
A new fuel modeling capability, CTFFuel, is developed from the subchannel code, CTF. This code is a standalone interface to the CTF fuel rod models, allowing for fuel rod simulations to be run independently from the fluid. This paper provides an overview of the code with a case study on the thermal conductivity degradation of LWR fuels to demonstrate its capabilities. The modeling of fuel thermal conductivity degradation in the code is improved through the addition of new modeling options to account for the irradiation effects via globally defined parameters. After the initial implementation, a variety of order-of-accuracy tests and code comparisons are performed to test software quality. A controlled analysis is allowed by CTFFuel to verify the numerical scheme of CTF's conduction solution and to benchmark its fuel temperature predictions against FRAPCON-4.0's. Overall, the software quality and verification procedure ensures that the new model is coded correctly, that it properly interacts with the rest of the code.
Original language | English |
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Pages (from-to) | 248-258 |
Number of pages | 11 |
Journal | Nuclear Engineering and Design |
Volume | 341 |
DOIs | |
State | Published - Jan 2019 |
Funding
This research is supported by and performed in conjunction with the Consortium for Advanced Simulation of Light Water Reactors ( http://www.casl.gov ), an Energy Innovation Hub http://www.energy.gov/hubs ) for Modeling and Simulation of Nuclear Reactors under US Department of Energy Contract No. DE-AC05-00OR22725.
Funders | Funder number |
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Consortium for Advanced Simulation of Light Water Reactors | |
Modeling and Simulation of Nuclear Reactors | |
US Department of Energy |
Keywords
- CTF
- CTFFuel
- SQA
- Thermal conductivity degradation
- Verification