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 -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.

Nuclear design of the high-temperature engineering test reactor (HTTR)

Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao; Maruyama, So; Fujimoto, Nozomu; Takeda, Takeshi

Nuclear Science and Engineering, 122, p.212 - 228, 1996/00

https://doi.org/10.13182/NSE96-A24156

no abstracts in English

Analysis of control rod reactivity worths for AVR power plant at cold and hot conditions

Yamashita, Kiyonobu; Murata, Isao; Shindo, Ryuichi; *; H.Werner*

Journal of Nuclear Science and Technology, 31(5), p.470 - 478, 1994/05

https://doi.org/10.3327/jnst.31.470

no abstracts in English

Analysis of overall temperature coefficient of reactivity of the VHTRC-1 core with a nuclear design code system for the High-Temperature Engineering Test Reactor

Yamashita, Kiyonobu; Murata, Isao; Shindo, Ryuichi

Nuclear Science and Engineering, 110, p.177 - 185, 1992/02

https://doi.org/10.13182/NSE92-A23887

no abstracts in English

Analysis of SHE critical experiments by neutronic design codes for experimental very high temperature reactor

; ; ; *

Journal of Nuclear Science and Technology, 22(5), p.358 - 370, 1985/05

https://doi.org/10.3327/jnst.22.358

no abstracts in English

Analysis of Reactivity Worths of Burnable Poison Rods in SHE-14 - Accuracy Investigation of VHTR Nuclear Design Methods (5) -

; *; ;

JAERI-M 9956, 23 Pages, 1982/03

JAERI-M-9956.pdf:0.81MB

no abstracts in English

Analysis of Prompt Neutron Decay Constants of Critical and Control Rod Inserted States of SHE-14 -Accuracy Investigation of VHTR Nuclear Design Methods (3)-

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JAERI-M 9942, 60 Pages, 1982/02

JAERI-M-9942.pdf:1.87MB

no abstracts in English

An Analysis of Copper Activation Reaction Rate Distribution of SHE-8 - Accuracy Investigation of VHTR Nuclear Design Method (4) -

; ; ;

JAERI-M 9912, 21 Pages, 1982/01

JAERI-M-9912.pdf:0.76MB

no abstracts in English