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Journal Articles

Event sequence assessment of deep snow in sodium-cooled fast reactor based on continuous Markov Chain Monte Carlo method with plant dynamics analysis

Takata, Takashi; Azuma, Emiko*

Journal of Nuclear Science and Technology, 53(11), p.1749 - 1757, 2016/11

 Times Cited Count:1 Percentile:14.27(Nuclear Science & Technology)

Margin assessment of a nuclear power plant against external hazards is one of the most important issues after Fukushima Dai-ichi Nuclear Power Plant Accident. In this paper, a new approach has been developed to assess the plant status during external hazards and countermeasures against them in operation quantitatively and stochastically. A Continuous Markov chain Monte Carlo (CMMC) method is applied and coupled with a plant dynamics analysis. In the CMMC method, a subsequence plant status is determined by the latest state (Markov chain) and the status is evaluated from the plant dynamics analysis. A failure or success of safety function of plant component is also evaluated stochastically based on a latest state of plant or hazard. A numerical investigation of plant dynamics analysis against a snow hazard is also carried out in a loop type sodium cooled fast reactor so as to assess the margin against the hazard.

Journal Articles

Analysis of natural circulation tests in the experimental fast reactor JOYO

Nabeshima, Kunihiko; Doda, Norihiro; Ohshima, Hiroyuki; Mori, Takero; Ohira, Hiroaki; Iwasaki, Takashi*

Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.1041 - 1049, 2015/08

Natural circulation is one of the most important mechanisms to remove decay heat in the sodium cooled fast reactors from the viewpoint of passive safety. On the other hand, it is difficult to evaluate plant dynamics accurately under low flow natural circulation condition. In this study, Super-COPD has been validated through the application to the analysis of natural circulation tests in the experimental fast reactor JOYO. Almost all plant components in JOYO including four air-coolers were modeled in Super COPD. Furthermore, the full scale modeling of fuel subassembly was also adopted in this analysis. The natural circulation test after reactor scram from 100 MW full power at JOYO was selected and simulated by Super-COPD. The transient behaviors predicted by Super-COPD showed good agreement with the experimental data.

Journal Articles

Development of plant dynamics analytical code named Conan-GTHTR for the Gas Turbine High Temperature Gas-cooled Reactor, 1; Code validation by Use of the experimental data of HTTR

Takamatsu, Kuniyoshi; Katanishi, Shoji; Nakagawa, Shigeaki; Kunitomi, Kazuhiko

Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(1), p.76 - 87, 2004/03

The Gas Turbine High Temperature Reactor 300 (GTHTR300) composed of an inherent safe 600MWt reactor and a closed gas turbine power conversion system is a high efficient and economically competitive HTGR to be deployed in 2010s. To analyze the plant dynamics and the thermal hydraulics of the GTHTR300, a new analytical code (Conan-GTHTR) based on 'RELAP5/MOD3' has been developed and applied to heat transfer calculations of the High Temperature Engineering Test Reactor (HTTR) for its verification. The results proved that the new code was available for transient simulations in Higt Temperature Gas-Cooled Reactor systems.

JAEA Reports

Analytical evaluation on loss of off-site electric power simulation of the High Temperature Engineering Test Reactor

Takeda, Takeshi; Nakagawa, Shigeaki; Tachibana, Yukio; Takada, Eiji*; Kunitomi, Kazuhiko

JAERI-Research 2000-016, p.80 - 0, 2000/03

JAERI-Research-2000-016.pdf:2.72MB

no abstracts in English

JAEA Reports

Development of analytical code 'ACCORD' for incore and plant dynamics of high temperature gas-cooled reactor

Takeda, Takeshi; Tachibana, Yukio; Kunitomi, Kazuhiko; Itakura, Hirofumi*

JAERI-Data/Code 96-032, 147 Pages, 1996/11

JAERI-Data-Code-96-032.pdf:4.58MB

no abstracts in English

Journal Articles

Noise source analysis of nuclear ship Mutsu plant using multivariate autoregressive model

Hayashi, Koji; Shimazaki, Junya; Shinohara, Yoshikuni*

SMORN-VII,Symp. on Nuclear Reactor Surveillance and Diagnostics,Vol. 1, 0, P. 3_5, 1995/00

no abstracts in English

JAEA Reports

7 (Records 1-7 displayed on this page)
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