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Yanagisawa, Hiroshi; Motome, Yuiko
JAEA-Research 2025-010, 197 Pages, 2025/11
JAEA-Research-2025-010.pdf:3.5MB
For understandings of nuclear criticality risks of TRIGA fuel rods and review of safety measures for handling them, nuclear criticality characteristics for infinite and finite heterogeneous lattice systems composed of the NSRR fuel rods were re-evaluated with the use of a detailed computational model for the fuel rod. The MVP version 3 code was used with the JENDL libraries including the latest version, JENDL-5, for the re-evaluation. As the criticality characteristics, variations of neutron multiplication factors of the infinite and water-reflected finite systems were examined in detail with parameters of the lattice pitch and density of moderator water. From the results of the re-evaluated criticality characteristics, the minimum critical number of fuel rods for the water-reflected hexagonal shaped lattice system was obtained to be 46.8 
0.2 using the JENDL-5 library. Moreover, the attainability of criticality without the water as moderator and reflector was examined because the zirconium hydride moderator and graphite reflector are equipped with the TRIGA fuel rod. It was found that the criticality is possible to be attained by 115.7 0.6 of the number of fuel rods, which is the smaller number of fuel rods than loaded in the NSRR standard core, even though no water exists.
Teshigawara, Makoto; Ikeda, Yujiro; Oi, Motoki; Harada, Masahide; Takada, Hiroshi; Kakishiro, Masanori*; Noguchi, Gaku*; Shimada, Tsubasa*; Seita, Kyoichi*; Murashima, Daisuke*; et al.
Nuclear Materials and Energy (Internet), 14, p.14 - 21, 2018/01
Times Cited Count：1 Percentile：8.97(Nuclear Science & Technology)We developed an Au-In-Cd (AuIC) decoupler material to reduce induced radioactivity instead of Ag-In-Cd one, which has a cut off energy of 1eV. In order to implement it into an actual moderator-reflector assembly, a number of critical engineering issues need to be resolved with regard to large-sized bonding between AuIC and A5083 alloys by the hot isostatic pressing process. We investigated this process in terms of the surface conditions, sizes, and heat capacities of large AuIC alloys. We also show a successful implementation of an AuIC decoupler into a reflector assembly, resulting in a remarkable reduction of radioactivity by AuIC compared to AIC without sacrificing neutronic performance.
Akimoto, Hajime; Sugawara, Takanori
JAEA-Data/Code 2016-008, 87 Pages, 2016/09
JAEA-Data-Code-2016-008.pdf:15.62MB
Thermal hydraulic behavior in a lead-bismuth cooled accelerator driven system (ADS) is analyzed under normal operation condition. Input data for the ADS version of J-TRAC code have been constructed to integrate the conceptual design. The core part of the ADS is modeled in detail to evaluate the core radial power profile effect on the core cooling. As the result of the analyses, the followings are found; (1) Both maximum clad temperature and fuel temperature are below the design limits. (2) The radial power profile has little effect on the coolant flow distribution among fuel assemblies. (3) The radial power profile has little effect on the heat transfer coefficients along fuel rods. (4) The thermal hydraulic behaviors along four steam generators are identical. The thermal hydraulic behaviors along two pumps are also identical. A fast running input data is developed by the simplification of the detailed input data based on the findings mentioned above.
Takeda, Takeshi; Onuki, Akira*; Kanamori, Daisuke*; Otsu, Iwao
Science and Technology of Nuclear Installations, 2016, p.7481793_1 - 7481793_15, 2016/00
Times Cited Count：2 Percentile：16.40(Nuclear Science & Technology)Akimoto, Hajime
JAEA-Data/Code 2014-031, 75 Pages, 2015/03
JAEA-Data-Code-2014-031.pdf:37.23MB
A thermal-hydraulic analysis code for transmutation system with lead-bismuth cooled accelerator-driven system (ADS) has been developed using the Japanese-version of Transient Reactor Analysis Code (J-TRAC) as the framework to apply the design studies of ADS. To identify the required capabilities of the thermal-hydraulic analysis code for ADS, previous thermal-hydraulic analyses of light water reactors, sodium-cooled fast reactor and ADS have been surveyed. To make up for insufficient capabilities of the J-TRAC code as a thermal-hydraulic analysis code of ADS, physical properties of lead-bismuth eutectic (LBE), argon gas and nitride nuclear fuel were implemented to the J-TRAC code. It was confirmed that the implemented capabilities worked as expected through verification calculations on (1) single-phase LBE flow, (2) heat transfer in a fuel assembly, and (3) heat transfer in a steam generator.
Yoshizawa, Michio; Endo, Akira
JAERI-Conf 2003-002, 166 Pages, 2003/03
JAERI-Conf-2003-002.pdf:9.79MB
The present report is Proceedings of the Third Workshop on Dosimetry for External Radiations, held at the Tokai Research Establishment, Japan Atomic Energy Research Institute (JAERI), in November 28-29, 2002. The proceedings comprises 16 papers and a summary of general discussion. The Third Workshop, subtitled "On an opportunity of the completion of the facility of calibration standards for neutron at JAERI", focused on neutron dosimetry and included presentations on the status of international neutron standards, the development of calibration techniques of neutron dosimeters using accelerator neutron sources, and dosimetry for high-energy neutrons. The workshop identified the directions for the future research and development in this field.
Ikeda, Yujiro
Journal of Nuclear Science and Technology, 39(Suppl.2), p.13 - 18, 2002/08
no abstracts in English
Sakamoto, Yukio; Yamaguchi, Yasuhiro
JAERI-Tech 2001-042, 29 Pages, 2001/06
JAERI-Tech-2001-042.pdf:1.79MB
no abstracts in English
Tanaka, Susumu; Fukuda, Mitsuhiro; Nishimura, Koichi; Hosono, Masakazu; Watanabe, Hiromasa; Yamano, Naoki*
Journal of Nuclear Science and Technology, 37(Suppl.1), p.840 - 844, 2000/03
no abstracts in English
; Fukuda, Mitsuhiro; ; Watanabe, Hiromasa; Yamano, Naoki*
JAERI-Data/Code 97-019, 91 Pages, 1997/05
JAERI-Data-Code-97-019.pdf:2.58MB
no abstracts in English
Nakane, Yoshihiro; ; Sakamoto, Yukio; Yoshizawa, Nobuaki*; Nakao, Noriaki*; Ban, Shuichi*; Hirayama, Hideo*; ; Shin, Kazuo*; Nakamura, Takashi*
JAERI-Data/Code 96-029, 80 Pages, 1996/09
JAERI-Data-Code-96-029.pdf:2.34MB
no abstracts in English
; Sasa, Toshinobu; Takada, Hiroshi; Takizuka, Takakazu
Proc. of 2nd Int. Conf. on Accelerator-Driven Transmutation Technologies and Applications, 1, p.668 - 674, 1996/00
no abstracts in English
; Sakamoto, Yukio; Tanaka, Shunichi; ; Fukahori, Tokio; ; Sasamoto, Nobuo; Tanaka, Susumu; Nakamura, Takashi*; Shin, Kazuo*; et al.
JAERI-Data/Code 94-012, 90 Pages, 1994/09
JAERI-Data-Code-94-012.pdf:2.26MB
no abstracts in English
Dai-26-Kai Robutsuri Kaki Semina, Tekisuto; Shometsu Shori Kenkyu, 0, p.47 - 66, 1994/00
no abstracts in English
Sasamoto, Nobuo;
JAERI-M 90-229, 61 Pages, 1991/01
no abstracts in English
F.Serre*; Yonomoto, Taisuke; Kukita, Yutaka;
EUROTHERM Seminar,No. 16; Natural Circulation in Industrial Applications, p.103 - 110, 1990/10
no abstracts in English
;
JAERI 1308, 75 Pages, 1987/11
no abstracts in English
Nemoto, Toshiyuki; Tsunematsu, Toshihide
JAERI-M 87-062, 36 Pages, 1987/04
no abstracts in English
; Tsunematsu, Toshihide; ; Takeda, Tatsuoki
JAERI-M 83-085, 26 Pages, 1983/06
no abstracts in English
;
JAERI-M 82-106, 55 Pages, 1982/08
no abstracts in English
