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Featured researches published by Kazutaka Ohashi.


Nuclear Technology | 2008

A STUDY OF AIR INGRESS AND ITS PREVENTION IN HTGR

Xing L. Yan; Tetsuaki Takeda; Tetsuo Nishihara; Kazutaka Ohashi; Kazuhiko Kunitomi; Nobumasa Tsuji

Abstract A rupture of the primary piping in the helium-cooled and graphite-moderated high-temperature gas-cooled reactor (HTGR) represents a design-basis event that should not result in significant safety consequences. In such a loss-of-coolant event, the reactor would be shut down inherently, and the decay heat would be removed passively with the ultimate reactor temperature rise being less than the design limit. Still, an important concern for reactor safety continues to be graphite oxidation damage to the fuel and core should a major air ingress take place through the breached primary pressure boundary. Two major cases of air ingress are studied. The first case results from the rupture of a control rod or refuel access standpipe atop the reactor pressure vessel (RPV). To rule out the possibility of such a standpipe rupture, a design change is proposed in the vessel top structure. The feasibility of the modified vessel local structure is evaluated. The second case of air ingress results from the rupture of one or more main coolant pipes on the lower body of the RPV. Experiment and analysis are performed to understand the multiphased air ingress phenomena in the depressurized reactor. Accordingly, a new passive mechanism of sustained counter air diffusion is proposed and shown to be effective in preventing major air ingress through natural circulation in the reactor. The results of the present study are expected to enhance the HTGR safety and economics.


ASME Turbo Expo 2002: Power for Land, Sea, and Air | 2002

Design and Economics of the HTGR-GT Power Plant by JAERI

Yasushi Muto; Shintaro Ishiyama; Shusaku Shiozawa; Masanori Tanihira; Yasuyuki Miyoshi; Kazutaka Ohashi

This paper describes the conceptual design and cost estimation of a 600MW(t) HTGR-GT power plant, which has been completed in the framework of the HTGR-GT feasibility study project in the duration of FY 1996 to FY 2000. The project is assigned to JAERI by the Ministry of Education, Culture, Sports, Science and Technology (MEXT) (former Science and Technology Agency) in Japan. The inlet and outlet gas temperatures in the reactor are 460°C and 850°C, respectively. Helium gas pressure is 6MPa. The gas turbine system type is an intercooled recuperative direct cycle. Designs of reactor and gas turbine are presented. The main feature of the plant is a relatively large 600 MW(t) HTGR, horizontal single shaft helium turbine and divided power conversion vessel, that is, a turbomachine vessel and heat exchanger one. Their main specifications and drawings are presented. As a result of cost estimation, an economically attractive construction cost and a power generation cost have been obtained.© 2002 ASME


Atomic Energy Society of Japan | 2007

Fundamental Philosophy on the Safety Design of the HTTR-IS Hydrogen Production System

Kazutaka Ohashi; Tetsuo Nishihara; Kazuhiko Kunitomi


Nuclear Engineering and Design | 2014

Study of the applicability of CFD calculation for HTTR reactor

Nobumasa Tsuji; Masaaki Nakano; Eiji Takada; Kazumi Tokuhara; Kazutaka Ohashi; Futoshi Okamoto; Yujiro Tazawa; Yoshitomo Inaba; Yukio Tachibana


Archive | 2006

Nuclear power generation system adaptable to load fluctuations

Kazuhiko Kunitomi; Kazutaka Ohashi; Yan Xing; シンヤン; 一彦 國富; 一孝 大橋


Atomic Energy Society of Japan | 2008

Conceptual Core Design Study of the Very High Temperature Gas-Cooled Reactor (VHTR) Upgrading the Core Performance by Using Multihole-Type Fuel

Kazutaka Ohashi; Tetsuo Nishihara; Kazuhiko Kunitomi; Masaaki Nakano; Yujiro Tazawa; Futoshi Okamoto


Nuclear Engineering and Design | 2014

Core design and safety analyses of 600 MWt, 950 °C high temperature gas-cooled reactor

Masaaki Nakano; Eiji Takada; Nobumasa Tsuji; Kazumi Tokuhara; Kazutaka Ohashi; Futoshi Okamoto; Yujiro Tazawa; Yukio Tachibana


Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues | 2017

Development of Security and Safety Fuel for Pu-Burner HTGR: Part 3 — Preliminary Reactor Safety Analyses Under Depressurization Accidents

Masaaki Nakano; Kazutaka Ohashi; Koji Okamoto


Atomic Energy Society of Japan | 2017

Safety design issues to meet the safety requirements

Kazutaka Ohashi


The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 | 2015

ICONE23-1203 Development of seismic analysis model for HTGR core on commercial FEM code

Nobumasa Tsuji; Kazutaka Ohashi

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Futoshi Okamoto

Japan Atomic Energy Research Institute

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Kazuhiko Kunitomi

Japan Atomic Energy Agency

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Eiji Takada

Japan Atomic Energy Research Institute

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Tetsuo Nishihara

Japan Atomic Energy Agency

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Yujiro Tazawa

Japan Atomic Energy Agency

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Yukio Tachibana

Japan Atomic Energy Agency

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Masanori Tanihira

Mitsubishi Heavy Industries

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Yasushi Muto

Japan Atomic Energy Research Institute

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