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Journal Articles

Whole core analysis of BEAVRS benchmark for hot zero power condition using MVP3 with JENDL-5

Suzuki, Motomu*; Nagaya, Yasunobu

Journal of Nuclear Science and Technology, 61(2), p.177 - 191, 2024/02

https://doi.org/10.1080/00223131.2023.2279299

Times Cited Count：2 Percentile：25.62(Nuclear Science & Technology)

With the release of the latest Japanese evaluated nuclear data library JENDL-5, the prediction accuracy of JENDL-5 for neutronics parameters of the BEAVRS benchmark for the hot zero power condition was evaluated in this study. The criticality, control rod bank worth (CRW), isothermal temperature coefficient (ITC), and in-core detector signals were calculated and compared with the measured data for evaluation. For the criticality, the calculation-to-experimental (C/E) values varied between 1.0001 and 1.0045. Sensitivity analysis by replacing cross section data from the JENDL-4.0u1 with JENDL-5 revealed that H, $^{235}$ U, $^{238}$ U, and $^{16}$ O significantly affected the criticality. The individual CRW agreed within 50 pcm, and total CRW also agreed within 100 pcm from the measured values. The ITC results calculated with a temperature deviation of 5.56 K case were negatively overestimated comparing with the measured values; whereas those of with 2.78 K were improved and agree with the measured values within a standard deviation. The axial detector signals indicated a maximum relative error of 4.46% and the root mean squared error (RMSE) of 2.13%. The differences between the previous version of JENDL-4.0u1 and JENDL-5 were also investigated.

Journal Articles

Tritium release from neutron-irradiated LiO; Transport in porous sintered pellets

Tanifuji, Takaaki*; Yamaki, Daiju; Jitsukawa, Shiro

Fusion Engineering and Design, 81(1-7), p.595 - 600, 2006/02

https://doi.org/10.1016/j.fusengdes.2005.10.011

Times Cited Count：3 Percentile：23.55(Nuclear Science & Technology)

The tritium release behavior from Li $_{2}$ O sintered pellets is observed by isothemal heating tests. (1) For 81%TD,The rate determining process is controlled by Kohlrauch strecthed exponential form. Tritium trapped in irradiation defects released with recovering the defects by isothermal heating. (2) For 88%TD, tritium release behavior is controlled by Avrami law (exponent n=0.5). The rate determining process is the connected micro-pore migration process.