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Araki, Shohei; Gunji, Satoshi; Tonoike, Kotaro; Kobayashi, Fuyumi; Izawa, Kazuhiko; Ogawa, Kazuhiko
Proceedings of European Research Reactor Conference 2020 (RRFM 2020) (Internet), 7 Pages, 2020/10
Critical experiments of thermal neutron system are still expected to be playing an important role for wide technical issues. The Japan Atomic Energy Agency (JAEA) is renovating the Static Experimental Critical Facility (STACY) to maintain the experimental capability. The new STACY is designed as a general-purpose criticality facility. Its core mainly consists of low enriched UO
fuel rods, grid plates, and light water moderator. The first experiment campaign in the new STACY aims to obtain criticality characteristics of fuel debris, which will be used in validation of criticality analysis methods. The designs of the experimental core configurations are in progress.
Tsujimoto, Kazufumi; Sasa, Toshinobu; Nishihara, Kenji; Oigawa, Hiroyuki; Takano, Hideki*
Proceedings of International Conference on Physics of Fuel Cycles and Advanced Nuclear Systems; Global Developments (PHYSOR 2004) (CD-ROM), 8 Pages, 2004/04
The Japan Atomic Energy Research Institute (JAERI) is developing an Accelerator Driven System (ADS) for transmutation of nuclear waste such as minor actinide (MA) and long-lived fission product (LLFP). To study and evaluate the feasibility of ADS by physical and engineering viewpoints, the Transmutation Experimental Facility (TEF) is proposed under a framework of J-PARC (Japan Proton Accelerator Research Complex) project. The TEF consists of two facilities named as Transmutation Physics Experimental Facility (TEF-P) and ADS Target Test Facility (TEF-T). The TEF-P consists of a zero-power critical assembly which is operated with a low power proton beam to research the reactor physics and the controllability of ADS. The TEF-T is a facility for material irradiation and partial mockup of beam window which can accept a maximum 600MeV-200kW proton beam into the Pb-Bi eutectic target. The purposes, experimental items and the specifications of the facilities are described.
; Numata, Kazuyuki*; ; *; Oigawa, Hiroyuki*
JNC TY9400 2000-006, 162 Pages, 2000/04
JNC-TY9400-2000-006.pdf:4.57MB
no abstracts in English
Yamamoto, Toshihiro; Miyoshi, Yoshinori
Journal of Nuclear Science and Technology, 36(11), p.1069 - 1075, 1999/11
Times Cited Count：2 Percentile：21.18(Nuclear Science & Technology)no abstracts in English
Hunter
JNC TN9400 99-049, 74 Pages, 1999/04
This document describes a series of calculations that were carried out to model various measurements from the BFS-58-1-I1 experiment. BFS-58-1-I1 was a mock-up of a uranium-free, Pu burning core at BFS-2, a Russian critical assembly operated by IPPE. The experiment measured values of keff, Na void reactivity worth, material sample reactivity worths and reaction rate ratios. The experiments were modelled using a number of different methods. Basic nuclear data was taken from JENDL-3.2, in either 70 or 18 groups. Cross-section data for the various material regions of the assembly were calculated by either SLAROM or CASUP; the heterogeneous structure of the core regions was modelled in these calculations, with 3 different options considered for representing the (essentially 2d) geometry of the assembly components in a 1D cell model. Whole reactor calculations of flux and keff were done using both a diffusion model (CITATION) and a transport model (TWOTRAN2), both using an RZ geometry. Reactivity worths were calculated both directly from differences in keff values and by using the exact perturbation calculations of PERKY and SN-PERT (for CITATION and TWOTRAN2, respectively). Initial calculations included a number of inaccuracies in the assembly representation, a result of communication difficulties between JNC and IPPE; these errors were removed for the final calculations that are presented. Calculations for the experiments have also been carried out in Russia (IPPE) and France (CEA) as part of an international comparison exercise, some of those results are also presented here. The calculated value of keff was 1.1%
k/k higher than the measured value, Na void worth C/E values were 
1.06; these results were considered to be reasonable. (Discrepancies in certain Na void values were probably due to experimental causes, though the efect should be investigated in any future experiments.) several sample worth values were small compared with calculational uncertaint
Suzaki, Takenori; Horiki, Oichiro*
Nihon Genshiryoku Gakkai-Shi, 40(4), p.257 - 259, 1998/00
no abstracts in English
*; *; *; Horiki, Oichiro*; Suzaki, Takenori
JAERI-Review 97-014, 43 Pages, 1997/10
no abstracts in English
*
PNC TN9450 96-052, 694 Pages, 1996/10
The present report compiles the experimental data of JUPITER Phase-II, which was a joint research program between U.S. DOE and PNC of Japan, using the ZPPR facility, which stands for Zero Power Physics Reactor at ANL-Idaho in l982 to l984. The JUPITER-II experiment was a series of critical experiments for conventional radial heterogeneous cores of 650 MWe class LMFBR, including six experimental cores. The nuclear characteristics recorded here include criticality, control rod reactivity, reaction rate distribution, sodium void reactivity, sample reactivity, Doppler reactivity and gamma heating. The present work is a part of efforts to develop a standard data base for LMFBR core nuclear design at PNC. The detail of experimental data is thoroughly recorded here so as to re-analyze these experiments in future. In addition, these experimental data are installed in the computer system at OEC for convenience of analytical code input.
Tsujino, Takeshi; Takeshita, Isao; ; Nomura, Masayuki; *
Proc. of the 8th Pacific Basin Nuclear Conf., p.9-E-1 - 9-E-6, 1992/00
no abstracts in English
Takeda, Toshikazu*; Unesaki, Hironobu*; Nakano, Makoto*; Arakawa, Yasushi*; Sakuma, Hiroomi*; Kurisaka, Kenichi*; Ito, Noboru*; Oe, Takashi*; Yamaguchi, Yoshiharu*
PNC TJ2605 87-001, 204 Pages, 1987/03
no abstracts in English
; Miyoshi, Yoshinori
Journal of Nuclear Science and Technology, 23(9), p.840 - 842, 1986/00
Times Cited Count：2 Percentile：42.61(Nuclear Science & Technology)no abstracts in English
; ; ; ;
JAERI-M 9147, 46 Pages, 1980/11
no abstracts in English
JAERI-M 7844, 218 Pages, 1978/10
no abstracts in English
; ; Nakagawa, Masayuki; ; Katsuragi, Satoru
JAERI 1255, 200 Pages, 1978/03
no abstracts in English
JAERI-M 7135, 30 Pages, 1977/06
no abstracts in English
; ; Makino, Akihiro; Murano, Toru*; Wakabayashi, Hiroaki*; Yoshii, Koji*
PNC TN841 77-06, 76 Pages, 1976/03
no abstracts in English
