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Dive into the research topics where Yasushi Okano is active.

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Featured researches published by Yasushi Okano.


Journal of Nuclear Science and Technology | 2006

A Feasibility Study on a Small Sodium Cooled Reactor as a Diversified Power Source

Yoshitaka Chikazawa; Yasushi Okano; Toru Hori; Yoshiyuki Ohkubo; Yoshio Shimakawa; Toshihiko Tanaka

A conceptual design study of a small sized sodium cooled reactor with 165 MWe output with a metallic fuel, which aimed at the application for the diversified power supply has been carried out. A metal fuel core has been developed with 550°C core outlet temperature and 20 years core life time by utilizing the three zone core having different Zr contents in U-Pu-Zr of metal fuel. Major components in the nuclear steam supply system has been design and safety analyses has been performed to evaluate economical and safety potential of the concept. ATWS analyses show the passive safety feature of this concept adopting control rod driver-line (CRD) expansion reactivity and prolongation of electromagnetic pump (EMP) coastdown. Enhancing passive safety features, a improved upper inner structure enhancing CRD expansion and a reliable power source for EMP has been proposed. Though construction cost in first of a kind (FOAK) does not satisfy the economical goal, the present concept has potential for achieving the economical goal in Nth of a kind (NOAK) considering learning effect.


Journal of Nuclear Science and Technology | 2016

Hazard curve evaluation method development for a forest fire as an external hazard on nuclear power plants

Yasushi Okano; Hidemasa Yamano

A method to obtain a hazard curve of a forest fire was developed. The method has four steps: a logic tree formulation, a response surface evaluation, a Monte Carlo simulation, and an annual exceedance frequency calculation. The logic tree consists domains of “forest fire breakout and spread conditions”, “weather conditions”, “vegetation conditions”, and “forest fire simulation conditions.” Condition parameters of the logic boxes are static if stable during a forest fire or not sensitive to a forest fire intensity, and non-static parameters are variables whose frequency/probability is given based on existing databases or evaluations. Response surfaces of a reaction intensity and a fireline intensity were prepared by interpolating outputs from a number of forest fire propagation simulations by fire area simulator (FARSITE). The Monte Carlo simulation was performed where one sample represented a set of variable parameters of the logic boxes and a corresponding intensity was evaluated from the response surface. The hazard curve, i.e. an annual exceedance frequency of the intensity, was therefore calculated from the histogram of the Monte Carlo simulation outputs. The new method was applied to evaluate hazard curves of a reaction intensity and a fireline intensity for a typical location around a sodium-cooled fast reactor in Japan.


Archive | 2016

Development of Risk Assessment Methodology Against External Hazards for Sodium-Cooled Fast Reactors

Hidemasa Yamano; Hiroyuki Nishino; Yasushi Okano; Takahiro Yamamoto; Takashi Takata

In this study, hazard evaluation methodologies were developed for the decay heat removal of a typical sodium-cooled fast reactor in Japan against snow, tornado, wind, volcanic eruption, and forest fire. In addition, probabilistic risk assessment and margin assessment methodologies against snow were developed as well. Snow hazard curves were developed based on the Gumbel and Weibull distributions using historical records of the annual maximum values of snow depth and daily snowfall depth. Wind hazard curves were also evaluated using the maximum wind speed and instantaneous speed. The tornado hazard was evaluated by an excess probability for the wind speed based on the Weibull distribution multiplied by an annual probability of the tornado strike at a target plant. The volcanic eruption hazard was evaluated using geological data and tephra diffusion simulation which indicated tephra layer thickness and tephra diameter. The forest fire hazard was evaluated based on numerical simulation which contributed to creating a response surface of frontal fire intensity and Monte Carlo simulation for excess probability calculation. After developing an event tree and failure probabilities, the snow PRA showed the order of 10−7/year of core damage frequency. Event sequence assessment methodology was also developed based on plant dynamics analysis coupled with continuous Markov chain Monte Carlo method in order to apply to the event sequence against snow. Furthermore, this study developed the snow margin assessment methodology that the margin was regarded as the snowfall duration to the decay heat removal failure which was defined as when the snow removal speed was smaller than the snowfall speed.


Case Studies in Fire Safety | 2015

Forest fire propagation simulations for a risk assessment methodology development for a nuclear power plant

Yasushi Okano; Hidemasa Yamano


Mechanical Engineering Journal | 2016

Numerical simulations of forest fire propagation and smoke transport as an external hazard assessment methodology development for a nuclear power plant

Yasushi Okano; Hidemasa Yamano


Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management | 2018

Level 1 PRA for External Vessel Storage Tank of Japan Sodium-Cooled Fast Reactor in Scheduled Refueling

Hidemasa Yamano; Kenichi Naruto; Kenichi Kurisaka; Hiroyuki Nishino; Yasushi Okano


Mechanical Engineering Journal | 2017

Sensitivity study on forest fire breakout and propagation conditions for forest fire hazard curve evaluations

Yasushi Okano; Hidemasa Yamano


Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management | 2016

Development of Risk Assessment Methodology of Decay Heat Removal Function Against Natural External Hazards for Sodium-Cooled Fast Reactors: Project Overview and Volcanic PRA Methodology

Hidemasa Yamano; Hiroyuki Nishino; Kenichi Kurisaka; Yasushi Okano; Takaaki Sakai; Takahiro Yamamoto; Yoshihiro Ishizuka; Nobuo Geshi; Ryuta Furukawa; Futoshi Nanayama; Takashi Takata


Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management | 2016

Sensitivity Study on Forest Fire Breakout and Propagation Conditions for Forest Fire Hazard Curve Evaluations

Yasushi Okano; Hidemasa Yamano


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

ICONE23-1003 DEVELOPMENT OF RISK ASSESSMENT METHODOLOGY OF DECAY HEAT REMOVAL FUNCTION AGAINST EXTERNAL HAZARDS FOR SODIUM-COOLED FAST REACTORS : (1) PROJECT OVERVIEW AND MARGIN ASSESSMENT METHODOLOGY AGAINST SNOW

Hidemasa Yamano; Hiroyuki Nishino; Kenichi Kurisaka; Yasushi Okano; Takaaki Sakai; Takahiro Yamamoto; Yoshihiro Ishizuka; Nobuo Geshi; Ryuta Furukawa; Futoshi Nanayama

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Hidemasa Yamano

Japan Atomic Energy Agency

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Hiroyuki Nishino

Japan Atomic Energy Agency

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Kenichi Kurisaka

Japan Atomic Energy Agency

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Takahiro Yamamoto

National Institute of Advanced Industrial Science and Technology

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Futoshi Nanayama

National Institute of Advanced Industrial Science and Technology

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Nobuo Geshi

National Institute of Advanced Industrial Science and Technology

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Ryuta Furukawa

National Institute of Advanced Industrial Science and Technology

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Takaaki Sakai

Japan Atomic Energy Agency

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Yoshihiro Ishizuka

National Institute of Advanced Industrial Science and Technology

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