Journal
NUCLEAR ENGINEERING AND TECHNOLOGY
Volume 53, Issue 6, Pages 1893-1908Publisher
KOREAN NUCLEAR SOC
DOI: 10.1016/j.net.2020.12.001
Keywords
Burn-up module; Oxide nuclear fuels; Fuel performance code; SCIANTIX; Helium production
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Funding
- Euratom research and training programme [754329]
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This study presents a burn-up module to calculate helium production in fast reactor fuels, verified by comparing with high-fidelity calculations and another module.
In light of the importance of helium production in influencing the behaviour of fast reactor fuels, in this work we present a burn-up module with the objective to calculate the production of helium in both in-pile and out-of-pile conditions tracking the evolution of 23 alpha-decaying actinides. This burn-up module relies on average microscopic cross-section look-up tables generated via SERPENT high-fidelity calculations and involves the solution of the system of Bateman equations for the selected set of actinide nuclides. The results of the burn-up module are verified in terms of evolution of actinide and helium concentrations by comparing them with the high-fidelity ones from SERPENT, considering two representative test cases of (U,Pu)O-2 fuel in fast reactor conditions. In addition, a code-to-code comparison is made with the independent state-of-the-art module TUBRNP (implemented in the TRANSURANUS fuel performance code) for the same test cases. The herein presented burn-up module is available in the SCIANTIX code, designed for coupling with fuel performance codes. (C) 2020 Korean Nuclear Society, Published by Elsevier Korea LLC.
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