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Sugimoto, Masayoshi; Kinsho, Michikazu; Kawai, Masayoshi*; M.Chernogubovsky*
Proc. of 11th Symp. on Accelerator Sci. and Technol., p.127 - 129, 1997/00
no abstracts in English
Sugimoto, Masayoshi; Kinsho, Michikazu; M.Chernogubovsky*; Kawai, Masayoshi*; *
Proc. of 22nd Linear Accelerator Meeting in Japan, p.101 - 103, 1997/00
no abstracts in English
*; Kawashima, Masatoshi*; *; Yamaoka, Mitsuaki*; Fujita, Reiko*
PNC TJ9164 96-008, 189 Pages, 1996/12
In the first reactor, sodium void reactivity and and sodium coolant temperature reavtivity are increased, and Doppler coefficient is decreased when MA is recycled. It is important to improve these reactivities in terms of safety features. In the study, Analysis was conducted of the effect on the sodium void reduction without deteriorating the core performance by mixing nuclides that give large absorption reactions in the higher energy region, where neutrons are increased at the neutron spectrum is hardened. Effect of higher Pu isotopes was also analyzed with parameters for improving Doppler coefficient. In the analysis of reduced sodium void reactivity core usig the threshold reaction, dominant energy region was identified for the sodium void reactivity by analyzing the core neutron spectra with parameters of MA mixing and core size. Furthermore, effect on reducing void reactivity was analyzed with parameters of inventory amounts and kinds of absorber nuclides. As a result, it was found that the sodium void reactivity of the MOX core with oxide-17 was about half of that of the core with natural oxide. In the analysis of reduced Doppler reactivity core, effect of improving the Doppler effect was analyzed for the nitride fuel core with higher Pu isotopes and resonance absorbers. Applicability and properties required for core analysis were also examined for candidates of base inert material, and the properties of fuel with those materials were preliminary surveyed. As a result, it was found that characteristics including Doppler coefficients can be improved with nuclides of structure material as metal form.
Kawai, Masayoshi*; Iijima, Shungo*; Nakagawa, Tsuneo; Nakajima, Yutaka; Sugi, Teruo; Watanabe, Takashi*; Matsunobu, Hiroyuki*; *; *
Journal of Nuclear Science and Technology, 29(3), p.195 - 213, 1992/03
no abstracts in English
Nakagawa, Tsuneo; Kawai, Masayoshi*; Iijima, Shungo*; Matsunobu, Hiroyuki*; Watanabe, Takashi*; Nakajima, Yutaka; Sugi, Teruo; *; *; *; et al.
Nuclear Data for Science and Technology, p.939 - 941, 1992/00
no abstracts in English
Asami, Tetsuo*; Iijima, Shungo*; ; Ihara, Hitoshi; Kawai, Masayoshi*; ; Komuro, Yuichi; Shibata, Keiichi; Takano, Hideki; *; et al.
Nihon Genshiryoku Gakkai-Shi, 31(11), p.1190 - 1217, 1989/11
no abstracts in English
*; *; *; Kawai, Masayoshi*; *; Yamaoka, Mitsuaki*; *; Seki, Yasushi
JAERI-M 88-251, 303 Pages, 1988/12
no abstracts in English
Tanaka, Shunichi; *; Hirayama, Hideo*; Ban, Shuichi*; Nakamura, Takashi*; Kosako, Toshiso*; *; *; *; Kawai, Masayoshi*; et al.
Applied Radiation and Isotopes, 39(2), p.241 - 252, 1988/00
no abstracts in English
Tanaka, Shunichi; Sakamoto, Yukio; Tanaka, Susumu; *; Hirayama, Hideo*; Ban, Shuichi*; Kosako, Toshiso*; *; *; Nakamura, Takashi*; et al.
Nihon Genshiryoku Gakkai-Shi, 30(5), p.385 - 393, 1988/00
no abstracts in English
*; Sasamoto, Nobuo; Mori, Seiji*; *; Kawai, Masayoshi*; *; Sakurai, Kiyoshi; Shin, Kazuo*; Sekimoto, Hiroshi*; Oyama, Yukio; et al.
JAERI-M 87-203, 230 Pages, 1987/12
no abstracts in English
*; ; ; *; *; *; *; *; *; *
JAERI-M 86-071, 67 Pages, 1986/05
no abstracts in English
*; ; ; *
Nuclear Science and Engineering, 94, p.24 - 35, 1986/00
Times Cited Count：236 Percentile：99.84(Nuclear Science & Technology)no abstracts in English
Kikuchi, Yasuyuki; Nakagawa, Tsuneo; Asami, Tetsuo; *; *; *
Journal of Nuclear Science and Technology, 22(8), p.593 - 603, 1985/00
Times Cited Count：13 Percentile：47.95(Nuclear Science & Technology)no abstracts in English
; *; ; ; *
JAERI-M 84-182, 107 Pages, 1984/10
no abstracts in English
; *; *; *; *; *; *; *; *; *; et al.
JAERI-M 83-225, 99 Pages, 1984/01
no abstracts in English
; ; *
Journal of Nuclear Science and Technology, 20(5), p.435 - 438, 1983/00
Times Cited Count：0 Percentile：0.29(Nuclear Science & Technology)no abstracts in English
Kawai, Masayoshi*; Hayashida, Yoshihisa*; Yamauchi, Michinori*; Uematsu, Mikio*; Sato, Yoshiaki*; Niidome, Jiro*; Nakai, Masaru*
PNC TJ201 82-03, 160 Pages, 1982/02
Analyses of JOYO shielding experimental data have been performed for the purpose of studying the shielding design technique of fast breeder reactor, confirming the shielding calculation procedure of prototype fast breeder reactor MONJU, and acquiring the data for the evaluation of the uncertainty shielding design. This paper describes the analyses for the effect of neutron streaming through the detector guide tube in the pedestal heavy concrete upon the experimental data, for the neutron streaming through the primary coolant and the argon cover gas pipe penetrations in the biological shield concrete and for the neutron behaviour in the primary pump room and in the intermediate heat exchanger room. The calculation was carried out by using the albedo monte carlo code morsealb with 21 neutron groups and p5anisotropic scattering cross section. The calculated results were compared with the shielding performance test data of JOYO. It was found that the present albedo monte carlo method predicted the therm
U,
U,
U,
Pu,
Pu,
Pu and PuNakagawa, Tsuneo; Kikuchi, Yasuyuki; *; *; *;
JAERI-M 9823, 62 Pages, 1981/11
no abstracts in English
Kikuchi, Yasuyuki; Nakagawa, Tsuneo; *; *; ; *
JAERI 1268, 142 Pages, 1981/02
no abstracts in English
