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Dive into the research topics where Hirohide Oikawa is active.

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Featured researches published by Hirohide Oikawa.


Journal of Nuclear Science and Technology | 1991

Development of Evaluation Code for Long-Term Cooling of Containment with Passive Safety Feature.

Junichiro Otonari; Kenji Arai; Hideo Nagasaka; Hirohide Oikawa

Simplified BWRs are characterized as an adoption of a passive ECCS and a passive containment cooling system (PCCS). While a passive ECCS has a short term core cooling function, a PCCS has a long-term decay heat removal function. As a PCCS, several concepts, differing in cooling location and method employed, have been considered. From the containment thermal- hydraulic response analysis viewpoint, simplified BWRs are essentially different from the current BWRs. For evaluating and comparing the performance of several PCCSs over full break spectra, the new containment safety evaluation code TOSPAC was developed as a preliminary design tool for PCCS. This paper summarizes the thermal-hydraulic modelings of the TOSPAC code and the validity evaluation of the TOSPAC code, compared with TRAC-BF1 calculation. From the validity evaluation concerning a main steam line break (MSLB) accident analysis for an isolation condenser (I/C) as a PCCS, it was found that the TOSPAC calculation result shows reasonable agreement ...


10th International Conference on Nuclear Engineering, Volume 2 | 2002

Numerical Analysis of Catalytic Recombiner Performance Considering a 3-Dimensional Gas Flow

Mika Tahara; Hirohide Oikawa; Kenji Arai

Metal-water reaction and radiolysis of water generate hydrogen during a severe accident in a light water reactor. To prevent hydrogen combustion, a flammability gas control system (FCS) is installed in reactor containment. Most of the current FCS combine hydrogen with oxygen by heating and employ active devices to maintain the gas flow through the FCS. Recently a catalytic recombiner has been developed as passive FCS. The catalytic recombiner performs its function passively and has the advantages of the robustness during an accident, easy maintenance and low cost compared with the current active FCS. The hydrogen depletion rate of the catalytic recombiner is affected by the local thermal hydraulic conditions during an accident. To evaluate hydrogen depletion by the catalytic recombiner considering these phenomena in the containment, a 3-dimensional fluid dynamics analysis is useful. A theoretical catalytic recombiner model has been developed in which the flammable gas depletion rate is estimated accounting for the gas transfer rate in porous catalyst material. The model has been incorporated with a thermal hydraulic model for the fluid dynamics in a containment that has been developed using a 3-dimensional CFD code STRA-CD. This catalytic recombiner model has been confirmed using a catalytic recombiner performance test that was carried out in the Battelle Model Containment (BMC). Further verification of the analysis model has been conducted using the test data described in NUREG/CR-6580 which addressed the wall effect on the catalytic recombiner performance. The predicted performance of the catalytic recombiner shows a good agreement with the test data, and especially the parameters effects on the recombiner performance is well described, which include the effects of the containment wall, gas flow rate to the catalytic recombiner and gas concentration distribution in the containment.Copyright


Archive | 2011

PRESSURIZED WATER REACTOR PLANT

Takashi Sato; Kazunori Hashimoto; Hirohide Oikawa; Yasunobu Fujiki; Makoto Akinaga; Hisaki Sato


Nuclear Engineering and Design | 2004

Basic concept of a near future BWR

Takashi Sato; Hirohide Oikawa; Hitoshi Muta; Yutaka Sosa


Archive | 2010

BOILING WATER NUCLEAR REACTOR AND EMERGENCY CORE COOLING SYSTEM OF THE SAME

Yoshihiro Kojima; Takashi Sato; Hirohide Oikawa


Archive | 2007

Core catcher and its manufacturing method, and reactor container and its modifying method

Takashi Sato; Ryoichi Hamazaki; Mika Tahara; Yoshihiro Kojima; Hirohide Oikawa; Tomohisa Kurita; Seiichi Yokobori; Yuka Suzuki


Archive | 2002

INSTALLATION AND METHOD FOR COOLING REACTOR CONTAINMENT VESSEL

Ryoichi Hamazaki; Yoshihiro Kojima; Hirohide Oikawa; 弘秀 及川; 良洋 小島; 亮一 濱崎


Archive | 1997

Nuclear power generating facility

Yoshihisa Akata; Toshihiro Funabashi; M. Goto; Setsurou Itou; Yutaka Kawamura; Hiroshi Machiba; Takuya Miyagawa; Hirohide Oikawa; Takashi Saito; Takehiko Saito; Takashi Sato; 説朗 伊藤; 崇 佐藤; 弘秀 及川; 卓也 宮川; 浩 待場; 政志 後藤; 健彦 斉藤; 隆 斎藤; 豊 河村; 俊博 船橋; 喜央 赤田


Archive | 2008

NUCLEAR POWER PLANT OF PRESSURIZED WATER TYPE

Makoto Akinaga; Yasunobu Fujiki; Kazunori Hashimoto; Hirohide Oikawa; Hisaki Sato; Takashi Sato; 寿樹 佐藤; 崇 佐藤; 弘秀 及川; 和典 橋本; 誠 秋永; 保伸 藤木


Archive | 1999

Emergency core cooling system and its water intake equipment

Akira Murase; Hitoshi Muta; Hirohide Oikawa; Takashi Sato; Yuji Yamamoto; 崇 佐藤; 弘秀 及川; 雄司 山本; 昭 村瀬; 仁 牟田

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Hideo Nakamura

Japan Atomic Energy Research Institute

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