Critical Benchmark Validation of the Core Physics Multigroup Cross-Section Library TPEX.
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| Title: | Critical Benchmark Validation of the Core Physics Multigroup Cross-Section Library TPEX. |
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| Authors: | Chen, Ying1 (AUTHOR), Wu, Haicheng1,2 (AUTHOR), Wen, Lili1,3 (AUTHOR) wenlili@ciae.ac.cn, Xiao, Yue1 (AUTHOR), Zhang, Jinchao2 (AUTHOR), Zhang, Qian3 (AUTHOR), Wu, Xiaofei1 (AUTHOR), Zhang, Huanyu1 (AUTHOR) |
| Source: | Energies (19961073). May2026, Vol. 19 Issue 9, p2143. 20p. |
| Subject Terms: | *Pressurized water reactors, *Model validation, *Nuclear reactors, *Reactivity (Chemistry) |
| Abstract: | Core physics multigroup cross-section libraries provide essential cross-section and burnup data for reactor neutron physics calculations, serving as a fundamental prerequisite for reactor physics analysis. The China Nuclear Data Center has developed the TPEX multigroup cross-section library for pressurized water reactors (PWRs) based on the Chinese Evaluated Nuclear Data Library CENDL-3.2. A systematic critical benchmark validation of the newly developed TPEX library has been performed. To verify its applicability and accuracy, the validation has been conducted against 131 critical benchmark experiments from the International Criticality Safety Benchmark Evaluation Project (ICSBEP 2006) and the WIMS-D library update project. The calculated effective multiplication factors (k e f f) are compared with the experimental values, results from equivalent multigroup libraries, and reference solutions from Monte Carlo code. The results indicate that the absolute average deviations between the calculated k e f f values using the TPEX library and the experimental measurements are 280 pcm for the uranium solution experiments, 410 pcm for the plutonium solution experiments, 10 pcm for the uranium metal lattice experiments, 20 pcm for the uranium dioxide lattice experiments, 22 pcm for the MOX fuel lattice experiments, and 150 pcm for the LCT001 uranium oxide assembly experiments. Accordingly, the TPEX library demonstrates excellent performance in reactivity predictions for PWRs. [ABSTRACT FROM AUTHOR] |
| Database: | Energy & Power Source |
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