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ray measurements in a target room of several tens MeV Proton FacilityNakashima, Hiroshi; Masumura, Tomomi*; Tanaka, Susumu; Sakamoto, Yukio; Takada, Hiroshi; Tanaka, Shunichi; Nakane, Yoshihiro; Meigo, Shinichiro; Nakamura, Takashi*; Kurosawa, Tadahiro*; et al.
Journal of Nuclear Science and Technology, 37(Suppl.1), p.192 - 196, 2000/03
no abstracts in English
Nakashima, Hiroshi; Masumura, Tomomi*; Tanaka, Susumu; Sakamoto, Yukio; Tanaka, Shunichi; Nakane, Yoshihiro; Meigo, Shinichiro; Nakamura, Takashi*; Kurosawa, Tadahiro*; Hirayama, Hideo*; et al.
Journal of Nuclear Science and Technology, 37(Suppl.1), p.197 - 201, 2000/03
no abstracts in English
Mizuno, Masahiro*; Uto, Nariaki
JNC TN9400 98-007, 147 Pages, 1998/11
A design study of a new in-pile experimental reactor, SERAPH (Safety Engineering Reactor for Accident PHenomenology), for FBR safety research has progressed at JNC (Japan Nuclear Cycle Development Institute). SERAPH is intended for various in-pile experiments to be performed under steady state and various transient operation modes. Heavy water is selected as a coolant material for heat removal of the SERAPH driver core during the experiments. Control rods are needed to conduct the experiments, and a control rod with heavy water follower is considered as one of the promising ideas and is now under investigation. In this idea, care must be taken to avoid production of local power peaks which are caused by neutron moderation in the follower and may appear in the vicinity of the boundary between the control rod and its neighboring fuel subassembly, since deuterium has an excellently high moderation power. Therefore, preparation of some methods of evaluating power density distribution in detail is required for control rod design. This report describes preparation of a set of neutronic calculation methods to evaluate intra-subassembly power density distribution including local power peaks around a control rod. A two-dimensional S
transport calculation code TWOTRAN-II is selected as a tool for evaluating neutron transport phenomena near the control rod with no cares for statistical influence. A two-dimensional rectangular super-cell model, which is a physical model composed of a control rod and its surrounding fifteen fuel sub-assemblies, and a method to construct the super-cell model based on thirteen unit cells are created, considering neutron mean free path near a control rod. Two processing tools are newly developed to generate a material region map and mesh boundaries for an efficient super-cell construction procedure and to obtain pin-wise power densities based on calculated mesh-wise neutron flux data. The results in this report are expected to be ...
*; *; *; Suzaki, Takenori; Horiki, Oichiro*
JAERI-Review 96-010, 40 Pages, 1996/08
JAERI-Review-96-010.pdf:1.14MB
no abstracts in English
-HO latticesMiyoshi, Yoshinori; ; ; Hirose, Hideyuki;
Nuclear Technology, 103, p.380 - 391, 1993/09
Times Cited Count：3 Percentile：38.1(Nuclear Science & Technology)no abstracts in English
Sawada, Shusaku*; *; *
PNC TJ9124 91-002, 331 Pages, 1991/03
"HIBEACON", which is a three dimensional core deformation analysis code for the experimental fast reactor "JOYO", had been modified in order to expand the code's functions for planning a long-term operation and managing the operation of "JOYO", and to analyse the core deformation characteristics speedily and accurately. In this study, "HITETRAS", which is a code for calculating temperatures and fast neutron fluxes on wrapper tubes, has been modified in order for it to correspond with the modification of "HIBEACON". And, the core deformation analysis on "JOYO" MK-III has been performed with those modified codes. Results of this study are as follows: (1) Improvement of core deformation analysis code. (a) Modification of function of "HITETRAS" to output temperatures and neutron fluxes. The method to output wrapper tubes' temperatures and neutron fluxes has been modified corresponding to the modification of "HIBEACON". (b) Addition of ability to alter program size of "HITETRAS". An ability to alter the program size has been added to "HITETRAS" by using INCLUDE statement and PARAMETER statement of FORTRAN language. (c) Modification of "HIBEACON". Following modifications, which are required for analysis on "JOYO" MK-III, have been perfomed. (1) alteration of calculation method for gap clearance between wrapper tubes. (2) addition of function for outputting elements of free bowing deformation (3) addition of function for selecting items to be output on list (2) Core deformation analysis on "JOYO" MK-III. "JOYO" MK-III will have different core characteristics from MK-II because of its higer neutron flux feature, two core regions, wider irradiation space, and so on. So, the core deformation behavior of "JOYO" MK-III has been analysed with the modified codes above-mentioned, and it has been clarified that there is no problem on the core integrity of MK-III from the view point of the core deformation.
; *;
Nuclear Science and Engineering, 87, p.283 - 294, 1984/00
Times Cited Count：5 Percentile：51.32(Nuclear Science & Technology)no abstracts in English
Kawamura, Hiroshi; ; ; ;
JAERI-M 83-133, 27 Pages, 1983/08
no abstracts in English
Kawamura, Hiroshi; ; ;
JAERI-M 82-020, 16 Pages, 1982/03
no abstracts in English
O
-UO Fuel in LWRMatsuura, Shojiro; ; *; *; *
JAERI-M 9844, 122 Pages, 1981/12
no abstracts in English
O pellets; *; Tanifuji, Takaaki; ; ; ; ;
Journal of Nuclear Materials, 88(2-3), p.193 - 198, 1980/00
Times Cited Count：1 Percentile：22.79(Materials Science, Multidisciplinary)no abstracts in English
;
JAERI-M 6943, 169 Pages, 1977/03
no abstracts in English
JAERI-M 4870, 71 Pages, 1972/07
no abstracts in English
Genshiryoku Hatsuden, 2(3), P. 33, 1958/00
no abstracts in English
Maeda, Makoto; Komeda, Masao; Tobita, Hiroshi; Ozu, Akira; Kureta, Masatoshi
no journal, ,
JAEA has started to develop a technology which can be applicable to high radioactive special nuclear materials such as next-generation fuel cycle products. We have been developed Non-destructive assay system Active-N as a test equipment which utilizes D-T neutron generator. In a system for Differential Die-Away (DDA) method which is tested in Active-N, it is important to evaluate neutron flux to check the performance of the system. In this research, we have evaluated neutron flux in a system for Fast Neutron Direct Interrogation method which is a kind of DDA method by activation method and Monte Carlo simulation by using PHITS.
Nakagawa, Naoki*; Fujimoto, Nozomu*; Ho, H. Q.; Hamamoto, Shimpei; Nagasumi, Satoru; Ishitsuka, Etsuo
no journal, ,
no abstracts in English
Nakagawa, Naoki*; Fujimoto, Nozomu*; Ho, H. Q.; Hamamoto, Shimpei; Nagasumi, Satoru; Ishitsuka, Etsuo
no journal, ,
no abstracts in English
