Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Sono, Hiroki; Yanagisawa, Hiroshi*; Miyoshi, Yoshinori
JAERI-Tech 2003-096, 84 Pages, 2004/01
Prior to the supercritical experiments using a water-reflected core of the TRACY Facility, neutronic characteristics regarding criticality and reactivity of the core system were evaluated. In the analyses, a continuous energy Monte Carlo code, MVP, and a two-dimensional transport code, TWOTRAN, were used together with a nuclear data library, JENDL-3.3. By comparison to the characteristics in the former-used bare core system of TRACY, the water reflector was estimated not to change the kinetic parameter and to reduce the critical solution level by 
20 %, the temperature coefficient of reactivity by 610 %, and the void coefficient of reactivity by 18 %, respectively. According to the Nordheim-Fuchs model, the first peak power during a power excursion was evaluated to be 15 % smaller than that in the bare system under the same conditions of fuel and reactivity insertion. The influence of the void feedback effect of reactivity, which is left out of consideration in the model, on the power characteristics will be evaluated from the results of the experiments.
Takamatsu, Kuniyoshi; Shimakawa, Satoshi; Nojiri, Naoki; Fujimoto, Nozomu
JAERI-Tech 2003-081, 49 Pages, 2003/10
In the case of evaluations for the highest temperature of the fuels in the HTTR, it is very important to expect the power density distributions accurately; therefore, it is necessary to improve the analytical model with the neutron diffusion and the burn-up theory. The power density distributions are analyzed in terms of two models, the one mixing the fuels and the burnable poisons homogeneously and the other modeling them heterogeneously. Moreover these analytical power density distributions are compared wtih the ones derived from the gross 
-ray measurements and the Monte Carlo calculational code with continuous energy. As a result the homogeneous mixed model isn't enough to expect the power density distributions of the core in the axial direction; on the other hand, the heterogeneous model improves the accuracy.
*; *; *; *; *; *; Harada, Hiro; ; Kume, Etsuo;
JAERI-Data/Code 97-055, 161 Pages, 1998/01
JAERI-Data-Code-97-055.pdf:4.57MB
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
Miyoshi, Yoshinori; ; Tonoike, Kotaro; Izawa, Naoki; Sugikawa, Susumu; Okazaki, Shuji
Nuclear Technology, 118(1), p.69 - 82, 1997/04
Times Cited Count：13 Percentile：70.37(Nuclear Science & Technology)no abstracts in English
Sakurai, Kiyoshi; Yamamoto, Toshihiro
Journal of Nuclear Science and Technology, 34(2), p.202 - 210, 1997/02
Times Cited Count：3 Percentile：30.37(Nuclear Science & Technology)no abstracts in English
; Sakamoto, Yukio
Journal of Nuclear Science and Technology, 30(9), p.926 - 945, 1993/09
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Masukawa, Fumihiro; ; Inoue, Osamu*; Hara, Toshiharu*
JAERI-M 93-024, 31 Pages, 1993/02
no abstracts in English
JAERI-M 91-108, 25 Pages, 1991/07
no abstracts in English
Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Maruyama, So; *
JAERI-M 89-118, 67 Pages, 1989/09
no abstracts in English
;
JAERI-M 82-199, 40 Pages, 1982/12
no abstracts in English
; *; ;
JAERI-M 9956, 23 Pages, 1982/03
no abstracts in English
; *; ;
JAERI-M 9942, 60 Pages, 1982/02
no abstracts in English
; ; ;
JAERI-M 9911, 32 Pages, 1982/02
no abstracts in English
; ; ;
JAERI-M 9912, 21 Pages, 1982/01
no abstracts in English
; *
JAERI-M 8019, 68 Pages, 1978/12
no abstracts in English
;
JAERI-M 7799, 53 Pages, 1978/08
no abstracts in English
