2024年度核データ研究会/Symposium on Nuclear Data 2024

Feedback on neutron capture cross-section of 133Cs from analysis of measured inventories of 133Cs and 134Cs of UO2 fuel irradiated in TMI Unit 1/TMI 1号炉において照射されたUO2燃料の133Cs及び134Csの核種組成測定値の解析から得られた133Csの中性子捕獲断面積の知見

14 Nov 2024, 16:00

2h

熊取交流センター　すまいるズ　煉瓦館

Poster presentation/ポスターセッション

Speaker

Toru/徹 Yamamoto/山本 ((Former affiliation) NRA/（前所属）原子力規制庁)

Description

Nuclide inventory calculations with MVP-BURN and JENDL-4.0 were performed for the twelve fuel samples taken from two 15×15 PWR fuel assemblies irradiated in Three Mile Island (TMI) Unit 1[1,2]. The calculated results of ${}^{134}$Cs for the one-cycle-irradiation fuel samples and those of ${}^{133}$Cs for the two-cycle-irradiation fuel samples were compared with the measured data. The averaged C/E-1s of ${}^{134}$Cs and ${}^{133}$Cs were −11.2% and 2.9%, respectively. They were similar to those with the previous studies. The C/E-1s were also compared with those with SCALE 5.1 (ENDF/B-V)[1] for ${}^{134}$Cs and those with SCALE 6.1.2 (ENDF/B-VII.0)[2] for ${}^{133}$Cs. The differences in the C/E-1s were mainly attributed to the differences in the neutron capture resonance integrals (RI$\gamma$s) of ${}^{133}$Cs in the nuclear data libraries. The C/E-1s of ${}^{133}$Cs and ${}^{134}$Cs in the present study both indicated that a larger RI$\gamma$ of ${}^{133}$Cs than that in JENDL-4.0 would bring the C/Es closer to 1.

References
[1] Radulescu G, Gauld IC, Ilas G. SCALE 5.1predictions of PWR spent nuclear fuel isotopic compositions. Oak Ridge (Tennessee): Oak Ridge National Laboratory; 2010. (ORNL/TM-2010/44).
[2] Gauld IC, Giaquinto JM, Delashmitt JS. Re-evaluation of spent nuclear fuel assay data for the Three Mile Island unit 1 reactor and application to code validation. Annals of Nuclear Energy. 2016 Jan; 87(2):267-281.