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JAEA Reports

Evaluation of neutronic characteristics of TRACY water-reflected core system

Sono, Hiroki; Yanagisawa, Hiroshi*; Miyoshi, Yoshinori

JAERI-Tech 2003-096, 84 Pages, 2004/01

JAERI-Tech-2003-096.pdf:3.6MB

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 $$sim$$20 %, the temperature coefficient of reactivity by 6$$sim$$10 %, and the void coefficient of reactivity by $$sim$$18 %, respectively. According to the Nordheim-Fuchs model, the first peak power during a power excursion was evaluated to be $$sim$$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.

JAEA Reports

Evaluation for the models of neutron diffusion theory in terms of power density distributions of the HTTR

Takamatsu, Kuniyoshi; Shimakawa, Satoshi; Nojiri, Naoki; Fujimoto, Nozomu

JAERI-Tech 2003-081, 49 Pages, 2003/10

JAERI-Tech-2003-081.pdf:2.6MB

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 $$gamma$$-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.

JAEA Reports

Vectorization, parallelization and porting of nuclear codes on the VPP500 system, porting; Progress report fiscal 1996

*; *; *; *; *; *; 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

Journal Articles

Measurements and analyses of reactivity effect of fission product nuclides in epithermal energy range

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

Journal Articles

Critical experiments on 10% enriched uranyl nitrate solution using a 60-cm-diameter cylindrical core

Miyoshi, Yoshinori; ; Tonoike, Kotaro; Izawa, Naoki; Sugikawa, Susumu; Okazaki, Shuji

Nuclear Technology, 118(1), p.69 - 82, 1997/04

 Times Cited Count:12 Percentile:68.74(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Benchmark model of critical experiment at TCA for integral evaluation of fission product nuclide cross sections

Sakurai, Kiyoshi; Yamamoto, Toshihiro

Journal of Nuclear Science and Technology, 34(2), p.202 - 210, 1997/02

 Times Cited Count:2 Percentile:23.65(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Comparison between measured and design dose rate equivalents on board of nuclear ship Mutsu

; 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

JAEA Reports

Installation and execution of criticality and radiation shielding analysis codes on engineering work station

Masukawa, Fumihiro; ; Inoue, Osamu*; Hara, Toshiharu*

JAERI-M 93-024, 31 Pages, 1993/02

JAERI-M-93-024.pdf:0.84MB

no abstracts in English

JAEA Reports

Optimization of uranium isotope distribution and burnable poison of High temperature engineering test reactor(HTTR)

Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Maruyama, So; *

JAERI-M 89-118, 67 Pages, 1989/09

JAERI-M-89-118.pdf:1.65MB

no abstracts in English

JAEA Reports

Vector Processing of the Newtron Transport Codes

;

JAERI-M 82-199, 40 Pages, 1982/12

JAERI-M-82-199.pdf:0.94MB

no abstracts in English

JAEA Reports

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