@article{oai:repo.qst.go.jp:00047897,
 author = {太田, 雅之 and 佐藤, 聡 and 権, セロム and 落合, 謙太郎 and 今野, 力 and 太田 雅之 and 佐藤 聡 and 権 セロム and 落合 謙太郎},
 journal = {Fusion Engineering and Design},
 month = {Nov},
 note = {An integral experiment on molybdenum is performed with a DT neutron source at JAEA/FNS. A Mo assembly is covered with lithium oxide blocks in order to reduce background neutrons inside the assembly.Several reaction rates and fission rates are measured along the central axis inside the assembly and com-pared with calculated ones with the Monte Carlo transport code MCNP5-1.40 and recent nuclear data libraries of ENDF/B-VII.1, JENDL-4.0, and JEFF-3.2. The calculated results generally show underestimation.From our detailed analysis, it is concluded that the (n,2n) cross section data of all the Mo stable isotopes in JEFF-3.2 are more suitable than those in JENDL-4.0 and the (n,g) cross section data of 92Mo, 94Mo, 95Mo, 96Mo, 97Mo, and 100Mo in JENDL-4.0 are overestimated.},
 pages = {1644--1648},
 title = {Integral experiment on molybdenum with DT neutrons at JAEA/FNS},
 volume = {109/111},
 year = {2016}
}