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Gunji, Satoshi; Araki, Shohei; Watanabe, Tomoaki; Fernex, F.*; Leclaire, N.*; Bardelay, A.*; Suyama, Kenya
Proceedings of 12th International Conference on Nuclear Criticality Safety (ICNC2023) (Internet), 9 Pages, 2023/10
Institut de radioprotection et de sret nuclaire (IRSN) and Japan Atomic Energy Agency (JAEA) have a long-standing partnership in the field of criticality safety. In this collaboration, IRSN and JAEA are planning a joint experiment using the new STACY critical assembly, modified by JAEA. In order to compare the codes (MVP3, MORET6, etc.) and nuclear data (JENDL and JEFF) used by both institutes in the planning of the STACY experiment, benchmark calculations of the Apparatus B and TCA, which are critical assemblies once owned by both institutes, benchmarks from the ICSBEP handbook and the computational model of the new STACY were performed. Including the new STACY calculation model, the calculations include several different neutron moderation conditions and critical water heights. There were slight systematic differences in the calculation results, which may have originated from the processing and/or format of the nuclear data libraries. However, it was found that the calculated results, including the new codes and the new nuclear data, are in good agreement with the experimental values. Therefore, there are no issues to use them for the design of experiments for the new STACY. Furthermore, the impact of the new TSL data included in JENDL-5 on the effective multiplication factor was investigated. Experimental validation for them will be completed by critical experiments of the new STACY by both institutes.
Laird, J. S.; Hirao, Toshio; Onoda, Shinobu*; Kamiya, Tomihiro
Nuclear Instruments and Methods in Physics Research B, 219-220, p.1015 - 1021, 2004/06
Times Cited Count:7 Percentile:45.03(Instruments & Instrumentation)no abstracts in English
Sakurai, Kiyoshi; Nojiri, Ichiro*
JAERI-Conf 2003-019, p.855 - 857, 2003/10
This paper provides overview of sub-criticality safety analysis seminar (July 2000-July 2003, JAERI, total 40 engineers from universities, research institutes and enterprises) for nuclear fuel cycle facility with the Monte Carlo method in Japan. MCNP-4C2 system (MS-DOS version) was installed in each note-type personal computer. Fundamental theory of reactor physics and Monte Carlo simulation including MCNP-4C manual was lectured. Effective neutron multiplication factor and neutron spectrum were calculated for JCO deposit tank, JNC uranium solution storage tank, JNC plutonium solution storage tank and JAERI TCA core. In the seminar, methodology of safety management for nuclear fuel cycle facility was discussed in order to prevent criticality accident.
Laird, J. S.; Hirao, Toshio; Onoda, Shinobu; Kamiya, Tomihiro
Proceedings of 3rd IEEE/LEOS International Conference on Numerical Simulation of Semiconductor Optoelectronic Devices (NUSOD '03), 2 Pages, 2003/10
no abstracts in English
Cao, X.; Suzaki, Takenori; Kugo, Teruhiko; Mori, Takamasa
JAERI-Tech 2003-069, 36 Pages, 2003/08
From the viewpoint of nuclear criticality safety of fuel rod storage and transport, a series of critical experiments concerning effects of water hole size, water gap width, water-to-fuel volume ratio and non-uniform arrangement of water moderator have been performed at the Tank-type Critical Assembly (TCA) of Japan Atomic Energy Research Institute. In the present study, the effects of volume fraction and non-uniform arrangement of water moderator on reactivity are evaluated by the water level worth method and analyzed by the SRAC code. Error sources of experiments and calculations are discussed, especially for an energy group model. The calculation results of diffusion model with 17-group model show good agreement with the experiment results within a few dozen cents.
Ide, Hiroshi; Matsui, Yoshinori; Nagao, Yoshiharu; Komori, Yoshihiro; Itabashi, Yukio; Tsuji, Hirokazu; Tsukada, Takashi; Nagata, Nobuaki*; Dozaki, Koji*; Takiguchi, Hideki*
Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 7 Pages, 2003/04
The advanced water chemistry controlled irradiation research device has been developed in JAERI to perform irradiation tests for research on IASCC. The irradiation device consists of the SATCAP (Saturated Temperature Capsule) inserted into the JMTR core and the water control unit installed out-of-core. Regarding the SATCAP, thermohydraulic design of the SATCAP was performed aiming at controlling the specimen temperature with high accuracy and increasing water flow velocity on the specimen surface to improve the controllability of water chemistry. As a result of irradiation test using the new type SATCAP, each specimen temperature and water chemistry were able to be controlled as designed.
Rahman, M.*; Suzaki, Takenori; Mori, Takamasa
JAERI-Research 2003-007, 68 Pages, 2003/03
no abstracts in English
Yamamoto, Toshihiro; Miyoshi, Yoshinori; Tonoike, Kotaro; Okamoto, Hajime*; Ida, Toshikazu*; Aoki, Shigeaki*
Journal of Nuclear Science and Technology, 40(2), p.77 - 83, 2003/02
Times Cited Count:8 Percentile:49.75(Nuclear Science & Technology)no abstracts in English
Sakurai, Takeshi; Okajima, Shigeaki
Proceedings of International Conference on the New Frontiers of Nuclear Technology; Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002) (CD-ROM), 12 Pages, 2002/10
The cross section adjustment method was applied to total delayed neutron yields of U, U and Pu of the JENDL-3.2 file by using experimental results of effective delayed neutron fraction at six cores built in two fast critical facilities of the MASURCA and FCA and a thermal critical facility of the TCA to improve these yields. The adjustment was carried out on the yields given at several incident neutron energy points in the file. Furthermore, to validate these adjusted delayed neutron yields, analyses were performed for the experiments at ZPR fast critical facility. These adjusted yields brought a reduction of uncertainty of calculated and an improvement in agreement of between experiment and calculation.
Yoshida, Tadashi*; Okajima, Shigeaki; Sakurai, Takeshi; Nakajima, Ken; Yamane, Tsuyoshi; Katakura, Junichi; Tahara, Yoshihisa*; Zukeran, Atsushi*; Oyamatsu, Kazuhiro*; Osawa, Takaaki*; et al.
Journal of Nuclear Science and Technology, 39(Suppl.2), p.136 - 139, 2002/08
no abstracts in English
Sakurai, Takeshi; Okajima, Shigeaki
Journal of Nuclear Science and Technology, 39(1), p.19 - 30, 2002/01
Times Cited Count:6 Percentile:39.30(Nuclear Science & Technology)The cross section adjustment method was applied to total delayed neutron yields of U, U and Pu of the JENDL-3.2 file by using experimental results of effective delayed neutron fraction at six cores built in two fast critical facilities of the MASURCA and FCA and a thermal critical facility of the TCA to improve these yields. The adjustment was carried out on the yields given at several incident neutron energy points in the file. After the adjustment, the yield of U was almost uniformly decreased by about 3% below 7 MeV. The yield of Pu was increased by 2.6% and that of U was decreased by 0.9% at the thermal energy point, while the change of yield was less than 0.3% at the other energy points for these nuclides. By using these adjusted yields, the uncertainty of calculated was reduced and the agreement of between experiment and calculation was improved.
Laird, J. S.; Hirao, Toshio; Onoda, Shinobu; Mori, Hidenobu; Ito, Hisayoshi
Proceedings of 6th European Conference on Radiation and its Effects on Components and System (RADECS 2001) (CD-ROM), 7 Pages, 2002/00
no abstracts in English
Research Group for Advanced Reactor System; Research Group for Reactor Physics; Research Group for Thermal and Fluid Engineering
JAERI-Research 2000-035, 316 Pages, 2000/09
no abstracts in English
Shimada, Shoichiro*; Akie, Hiroshi; Suzaki, Takenori; Okubo, Tsutomu; Usui, Shuji*; Shirakawa, Toshihisa*; Iwamura, Takamichi; Kugo, Teruhiko; Ishikawa, Nobuyuki
JAERI-Research 2000-026, 74 Pages, 2000/06
no abstracts in English
Suzaki, Takenori; Sakurai, Kiyoshi; Nakajima, Ken; Horiki, Oichiro*
Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 1, p.386 - 394, 1999/00
no abstracts in English
Matsui, Yoshinori; Niimi, Motoji; Hoshiya, Taiji; Tsukada, Takashi; Tsuji, Hirokazu
Journal of Nuclear Materials, 258-263, p.378 - 382, 1998/00
Times Cited Count:0 Percentile:0.01(Materials Science, Multidisciplinary)no abstracts in English
Sakurai, Kiyoshi; Yamamoto, Toshihiro; Arakawa, Takuya*;
Nihon Genshiryoku Gakkai-Shi, 40(5), p.380 - 386, 1998/00
Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)no abstracts in English
Suzaki, Takenori; Horiki, Oichiro*
Nihon Genshiryoku Gakkai-Shi, 40(4), p.257 - 259, 1998/00
no abstracts in English
; Nomura, Yasushi; Suyama, Kenya
Proc. of Int. Conf. on the Phys. of Nucl. Sci. and Technol., 1, p.742 - 748, 1998/00
no abstracts in English
Yamamoto, Toshihiro; Sakurai, Kiyoshi; Suzaki, Takenori; ; ; Horiki, Oichiro*
Journal of Nuclear Science and Technology, 34(12), p.1178 - 1184, 1997/12
Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)no abstracts in English