Výsledky vyhledávání - "Yukiharu Ohga"

Evaluation Tests of Event Identification Method Using Neural Network at Kashiwazaki Kariwa Nuclear Power Station Unit No.4

Autor: Naoshi Tanikawa, Shinobu Shiratori, Takaharu Fukuzaki, Toshiyuki Wada, Yoshiyuki Takano, Yukiharu Ohga, Setsuo Arita

Publikováno v: Journal of Nuclear Science and Technology. 33:439-447

An event identification method using a neural network has been evaluated in an on-line environment during the plant startup test at Unit No.4 Plant in the Kashiwazaki Kariwa Nuclear Power Station. In the method, the neural network identifies the even

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::30398dc91a8dc16a4eee65ed984e489b
https://doi.org/10.1080/18811248.1996.9731930

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Thermal Hydraulic Test of Advanced Fuel Bundle With Spectral Shift Rod (SSR) for BWR: Steady State and Transient Test Results and Analysis

Autor: Yukiharu Ohga, Kazuaki Kitou, Masao Chaki, Takeshi Makigami, Kondo Takao

Publikováno v: Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries.

Japanese national project of next generation light water reactor (LWR) development started in 2008. Under this project, spectral shift rod (SSR) is being developed. SSR, which replaces conventional water rod (WR) of boiling water reactor (BWR) fuel b

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::4d5e04640e512cdc137737d611a0ba98
https://doi.org/10.1115/icone20-power2012-54469

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Abnormal Event Identification in Nuclear Power Plants Using a Neural Network and Knowledge Processing

Autor: Hiroshi Seki, Yukiharu Ohga

Publikováno v: Nuclear Technology. 101:159-167

The combination of a neural network and knowledge processing have been used to identify abnormal events that cause a reactor to scram in a nuclear power plant. The neural network recognizes the abnormal event from the change pattern of analog data fo

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::17217d93f2fbb39131857e7f1ce275f9
https://doi.org/10.13182/nt93-a34777

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Thermal Hydraulic Test of Advanced BWR Fuel Bundle With Spectral Shift Rod (SSR): Overview and Pre-Test Analysis by TRACG Code

Autor: Yukiharu Ohga, Masao Chaki, Moriyasu Abe, Kondo Takao

Publikováno v: 18th International Conference on Nuclear Engineering: Volume 6.

Japanese national project of next generation light water reactor (LWR) development started in 2008. As one of its development items, the thermal-hydraulic test of spectral shift rod (SSR) is planned. A new component called SSR, which replaces convent

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::61096b1f9c8622da8191e71eb46949b3
https://doi.org/10.1115/icone18-29967

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