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Fukushima, Masahiro; Goda, J.*; Oizumi, Akito; Bounds, J.*; Cutler, T.*; Grove, T.*; Hayes, D.*; Hutchinson, J.*; McKenzie, G.*; McSpaden, A.*; et al.
Nuclear Science and Engineering, 194(2), p.138 - 153, 2020/02
Times Cited Count:7 Percentile:61.94(Nuclear Science & Technology)To validate lead (Pb) nuclear cross sections, a series of integral experiments to measure lead void reactivity worth was conducted systematically in three fast spectra with different fuel compositions on the Comet critical assembly of the National Criticality Experiments Research Center. Previous experiments in a high-enriched uranium (HEU)/Pb and a low-enriched uranium (LEU)/Pb systems had been performed in 2016 and 2017, respectively. A follow-on experiment in a plutonium (Pu)/Pb system has been completed. The Pu/Pb system was constructed using lead plates and weapons grade plutonium plates that had been used in the Zero Power Physics Reactor (ZPPR) of Argonne National Laboratory until the 1990s. Furthermore, the HEU/Pb system was re-examined on the Comet critical assembly installed newly with a device that can guarantee the gap reproducibility with a higher accuracy and precision, and then the experimental data was re evaluated. Using the lead void reactivity worth measured in these three cores with different fuel compositions, the latest nuclear data libraries, JENDL 4.0 and ENDF/B VIII.0, were tested with the Monte Carlo calculation code MCNP version 6.1. As a result, the calculations by ENDF/B-VIII.0 were confirmed to agree with lead void reactivity worth measured in all the cores. It was furthermore found that the calculations by JENDL 4.0 overestimate by more than 20% for the Pu/Pb core while being in good agreements for the HEU/Pb and LEU/Pb cores.
Tabata, Toshio; Nagao, Yoshiharu; Komukai, Bunsaku; Naka, Michihiro; Takeda, Takashi*; Fujiki, Kazuo
JAERI-Tech 2002-100, 108 Pages, 2003/01
After the investigation of the new core arrangement for the JMTR reactor in order to enhance the fuel burn-up and consequently extend the operation period, the "improved LEU core" that utilized 2 additional fuel elements instead of formerly installed reflector elements, was adopted. This report describes the results of the thermal-hydraulic analysis of the improved LEU core as a part of safety analysis for the licensing. The analysis covers steady state, abnormal operational transients and accidents, which were described in the annexes of the licensing documents as design bases events. Calculation conditions for the computer codes were conservatively determined based on the neutronic analysis results and others. The results of the analysis, that revealed the safety criteria were satisfied on the fuel temperature, DNBR and primary coolant temperature, were used in the licensing. The operation license of the JMTR with the improved LEU core was granted in March 2001, and the reactor operation with new core started in November 2001 as 142nd operation cycle.
Yanagisawa, Kazuaki;
Journal of Nuclear Science and Technology, 32(10), p.981 - 988, 1995/10
Times Cited Count:1 Percentile:17.53(Nuclear Science & Technology)no abstracts in English
Yanagisawa, Kazuaki
JAERI-M 91-152, 195 Pages, 1991/10
no abstracts in English
Okuno, Hiroshi; Komuro, Yuichi
JAERI-M 90-058, 174 Pages, 1990/03
no abstracts in English
Yamane, Tsuyoshi; ; Akino, Fujiyoshi; Kaneko, Yoshihiko
Journal of Nuclear Science and Technology, 27(2), p.122 - 132, 1990/02
no abstracts in English
Yamamoto, Katsumune; ; ; Yokouchi, Iichiro; ;
Nihon Genshiryoku Gakkai-Shi, 28(5), p.425 - 427, 1986/00
Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)no abstracts in English
; ; ; ;
JAERI-M 85-047, 81 Pages, 1985/04
no abstracts in English
; ; ; ;
JAERI-M 8046, 181 Pages, 1979/02
no abstracts in English
; Akino, Fujiyoshi
Nihon Genshiryoku Gakkai-Shi, 21(11), p.876 - 890, 1979/00
Times Cited Count:1no abstracts in English