Compilation of the data book on light water reactor benchmark to develop the next version of JENDL; Utilization of criticality data in ICSBEP and IRPhEP open databases

Reactor Integral Test Working Group, JENDL Committee

JAEA-Data/Code 2017-006, 152 Pages, 2017/05

JAEA-Data-Code-2017-006.pdf:13.46MB
JAEA-Data-Code-2017-006(errata).pdf:0.07MB
JAEA-Data-Code-2017-006-appendix1(CD-ROM).zip:115.88MB
JAEA-Data-Code-2017-006-appendix2(CD-ROM).zip:110.88MB

A benchmark database which is devoted to the evaluation of the future JENDL against the criticality of light water reactors was prepared, where the ICSBEP and IRPhEP handbooks by OECD/NEA were utilized effectively. Specific features of this report can be described as follows: (1) The recommendation for benchmarking is based on careful reviewing for the document and related information. Validity of the original benchmark evaluation is carefully checked, and numerical results obtained with JENDL-4.0 are considered. (2) Heterogeneity effect of PuO particles dispersed in fuel medium is consistently quantified for the MOX fuel-loaded experimental data. This precise evaluation is realized by the newly developed finite fuel pin bundle model with the Monte Carlo neutron transport code. (3) Sensitivity analysis is conducted in order to specify nuclear data whose difference between recent nuclear data libraries significantly affects the critical parameter calculation.