Hidemasa Yamano

发表

Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III: Theoretical modeling and basic verification

Ryo Akasaka, Koji Morita, Tatsuya Matsumoto, 2003 .

Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III: Extended verification using multi-bubble condensation experiment

Ryo Akasaka, Koji Morita, Tatsuya Matsumoto, 2003 .

Safety design approach for external events in Japan sodium-cooled fast reactor

Hidemasa Yamano, Shigenobu Kubo, A. Tani, 2012 .

ICONE19-43712 STUDY ON FLOW INDUCED VIBRATION EVALUATION FOR A LARGE SCALE JSFR PIPING : (3) PRESSURE FLUCTUATION CHARACTERISTICS IN 1/3 SCALE HOT-LEG PIPING EXPERIMENTS UNDER DEFLECTED INFLOW CONDITIONS DUE TO UIS STRUCTURES

Hidemasa Yamano, Tadashi Shiraishi, Yang Xu, 2011 .

Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazard of Low Temperature and Snow for Sodium-Cooled Fast Reactors

Kenichi Kurisaka, Hidemasa Yamano, Hiroyuki Nishino, 2017 .

Dynamic behavior of a solid particle bed in a liquid pool: SIMMER-III code verification

Ping Liu, Koji Morita, Tatsuya Matsumoto, 2007 .

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

Yasushi Okano, Hidemasa Yamano, 2017 .

Development of technical basis in the initiating and transition phases of unprotected events for Level-2 PSA methodology in sodium-cooled fast reactors

Yoshiharu Tobita, Hidemasa Yamano, Ikken Sato, 2012 .

S054093 Evaluation for Flow-Induced Vibration of a Primary Circuit Hot-Leg Piping in a Sodium-Cooled Fast Reactor : (3) Evaluation Method for Random Vibration Based on PSD and Correlation Length of Pressure Fluctuation

Tetsuya Kaneko, Hidemasa Yamano, Hiromi Sago, 2011 .

Development of Probabilistic Risk Assessment Methodology Against Volcanic Eruption for Sodium-Cooled Fast Reactors

Kenichi Kurisaka, Hidemasa Yamano, Hiroyuki Nishino, 2018 .

Recent Knowledge From an Experimental Investigation on Self-Leveling Behavior of Debris Bed

Koji Morita, Yuya Nakamura, Tatsuya Matsumoto, 2013 .

Development of a three-dimensional CDA analysis code: SIMMER-IV and its first application to reactor case

Yoshiharu Tobita, Hidemasa Yamano, Ikken Sato, 2008 .

ICONE23-1009 DEVELOPMENT OF RISK ASSESSMENT METHODOLOGY OF DECAY HEAT REMOVAL FUNCTION AGAINST EXTERNAL HAZARDS FOR SODIUM-COOLED FAST REACTORS : (3) NUMERICAL SIMULATIONS OF FOREST FIRE SPREAD AND SMOKE TRANSPORT AS AN EXTERNAL HAZARD ASSESSMENT METHODOLOGY DEVELOPMENT

Yasushi Okano, Hidemasa Yamano, 2015 .

Development of level-1 PSA method applicable to Japan Sodium-cooled Fast Reactor

Kenichi Kurisaka, Akira Yamaguchi, Hidemasa Yamano, 2014 .

ICONE19-43710 STUDY ON FLOW INDUCED VIBRATION EVALUATION FOR A LARGE SCALE JSFR PIPING : (2) VIBRATION ANALYSIS IN 1/3 SCALE HOT-LEG PIPING EXPERIMENTS UNDER SWIRL INFLOW CONDITIONS

Hidemasa Yamano, Hiromi Sago, Kazuo Hirota, 2011 .

S054095 Evaluation for Flow-Induced Vibration of a Primary Circuit Hot-Leg Piping in a Sodium-Cooled Fast Reactor (5) Study on Mechanism of Pressure Fluctuation at Elbow based on LES result

Hidemasa Yamano, Yuzuru Eguchi, Takahiro Murakami, 2011 .

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

Kenichi Kurisaka, Yasushi Okano, Hidemasa Yamano, 2016 .

Detailed analyses of key phenomena in core disruptive accidents of sodium-cooled fast reactors by the COMPASS code

Yuichi Yamamoto, Seiichi Koshizuka, Koji Morita, 2011 .

A three-dimensional neutronics-thermohydraulics simulation of core disruptive accident in sodium-cooled fast reactor

Yoshiharu Tobita, Hidemasa Yamano, Satoshi Fujita, 2009 .

ICONE15-10462 SIMMER-III : A COUPLED NEUTRONICS-THERMOHYDRAULICS COMPUTER CODE FOR SAFETY ANALYSIS

Satoshi Fujita, Werner Maschek, Satoshi Fujita, 2007 .

S054092 Evaluation for Flow-Induced Vibration of a Primary Circuit Hot-Leg Piping in a Sodium-Cooled Fast Reactor (2) Flow Pattern and Pressure Fluctuation Characteristics on the 1/3 Scale Hot-leg Piping Experiments

Hidemasa Yamano, Tadashi Shiraishi, Yang Xu, 2011 .

SIMMER-III Code Assessment for Material Expansion Dynamics During Core Disruptive Accidents in Sodium-Cooled Fast Reactors

Yoshiharu Tobita, Hidemasa Yamano, 2014 .

S054091 Evaluation for Flow-Induced Vibration of a Primary Circuit Hot-Leg Piping in a Sodium-Cooled Fast Reactor (1) : Approach to the Evaluation Methodology Development

Tetsuya Kaneko, Hidemasa Yamano, Hiromi Sago, 2011 .

A finite element LES for high-Re flow in a short-elbow pipe with undisturbed inlet velocity

Hidemasa Yamano, Yuzuru Eguchi, Takahiro Murakami, 2011 .

Safety Design and Evaluation in a Large-Scale Japan Sodium-Cooled Fast Reactor

Kenichi Kurisaka, Tohru Suzuki, Hidemasa Yamano, 2012 .

U-RANS Simulation of Single Elbow Pipe Flow Experiments Simulating JSFR Hot-Leg Piping

Hidemasa Yamano, Yukiharu Iwamoto, Masaaki Tanaka, 2015 .

S054094 Evaluation of Flow-Induced Vibration of a Primary Circuit Hot-Leg Piping in a Sodium-Cooled Fast Reactor (4) : LDV Flow Measurement in a 1/10-scale Hot-Log Piping Test Facility

Hidemasa Yamano, Kazunori Yasuda, Shota Ogawa, 2011 .

Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazards of Strong Wind and Rainfall for Sodium-Cooled Fast Reactors

Kenichi Kurisaka, Hidemasa Yamano, Hiroyuki Nishino, 2017 .

A methodological study on extending an empirical model to predict self-leveling behavior of debris beds with non-spherical particles

Koji Morita, Yuya Nakamura, Tatsuya Matsumoto, 2013 .

Numerical simulation of the self-leveling phenomenon by modified SIMMER-III

Koji Morita, Tatsuya Matsumoto, Tohru Suzuki, 2012 .

Characteristics of self-leveling behavior of debris beds in a series of experiments

Koji Morita, Yuya Nakamura, Tatsuya Matsumoto, 2013 .

ICONE19-43594 Conceptual Design Study for the Demonstration Reactor of JSFR : (3) Safety Design and Evaluation

Hidemasa Yamano, Shigenobu Kubo, Yoshio Shimakawa, 2011 .

Study on Event Progression in PLOHS for JSFR:(2) Numerical simulation of Melt-down behavior in PLOHS

Tohru Suzuki, Yoshiharu Tobita, Hidemasa Yamano, 2012 .

ICONE23-1112 DEVELOPMENT OF RISK ASSESSMENT METHODOLOGY OF DECAY HEAT REMOVAL FUNCTION AGAINST EXTERNAL HAZARDS FOR SODIUM-COOLED FAST REACTORS : (2) PROBABILISTIC RISK ASSESSMENT METHODOLOGY AGAINST STRONG WIND

Kenichi Kurisaka, Hidemasa Yamano, Hiroyuki Nishino, 2015 .

Next Generation Safety Analysis Methods for SFRs—(6) SCARABEE BE+3 Analysis With SIMMER-III and COMPASS Codes Featuring Duct-Wall Failure

Yuichi Yamamoto, Seiichi Koshizuka, Yoshiharu Tobita, 2009 .

Experimental study and empirical model development for self-leveling behavior of debris bed using gas-injection

Koji Morita, Yuya Nakamura, Tatsuya Matsumoto, 2014 .

Pressure Measurement Test of Single Elbow Simulating Na Cooled Fast Reactor Cold-Leg Piping

Hidemasa Yamano, Hidetoshi Hashizume, Tsukasa Sato, 2010 .

B123 Study on the influence of piping layout upon flow separation characteristic in the downstream of a elbow in the primary cold-leg of sodium cooled fast reactor

Hidemasa Yamano, Hidetoshi Hashizume, Jun Mizutani, 2014 .

The SIMMER safety code system and its validation efforts for fast reactor application

Satoshi Fujita, Giacomino Bandini, Werner Maschek, 2008 .

Experimental analyses by SIMMER-III on duct-wall failure and fuel discharge/relocation behavior

Yoshiharu Tobita, Hidemasa Yamano, 2014 .

Development of severe accident evaluation technology (Level 2 PSA) for sodium-cooled fast reactors (1) overview of evaluation methodology development

Ryodai Nakai, Kenji Kamiyama, Tohru Suzuki, 2009 .

R&D of the Next Generation Safety Analysis Methods for Fast Reactors With New Computational Science and Technology: 4 — Experimental Analyses by SIMMER-III for the Integral Verification of COMPASS

Yoshiharu Tobita, Hidemasa Yamano, 2008 .

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

Kenichi Kurisaka, Yasushi Okano, Hidemasa Yamano, 2015 .

Next Generation Safety Analysis Methods for SFRs—(2) Experimental Analyses by SIMMER-III for the Integral Verification of the COMPASS Code on Fuel-Pin Disruption and Low-Energy Disrupted Core Motion

Yoshiharu Tobita, Hidemasa Yamano, 2009 .

Visualization Experiment of Complex Flow Fields in a Triple Elbow Piping System under Swirling Inflow Conditions

Hidemasa Yamano, Hidetoshi Hashizume, Jun Mizutani, 2016 .

ICONE19-43569 STUDY ON FLOW INDUCED VIBRATION EVALUATION FOR A LARGE SCALE JSFR PIPING : (4) UNSTEADY FLOW CHARACTERISTICS IN 1/10 SCALE HOT-LEG PIPING EXPERIMENTS UNDER UNDEVELOPED AND SWIRL INFLOW CONDITIONS

Manabu Kondo, Hidemasa Yamano, Kazunori Yasuda, 2011 .

Next Generation Safety Analysis Methods for SFRs—(3) Thermal Hydraulics Models of COMPASS Code and Experimental Analyses

Yuichi Yamamoto, Seiichi Koshizuka, Koji Morita, 2009 .

Evaluation of debris bed self-leveling behavior: A simple empirical approach and its validations

Tatsuya Matsumoto, Tohru Suzuki, Yoshiharu Tobita, 2014 .

Development of the evaluation methodology for the material relocation behavior in the core disruptive accident of sodium-cooled fast reactors

Tohru Suzuki, Yoshiharu Tobita, Hidemasa Yamano, 2016 .

Thermophysical Properties of Lead-Bismuth Eutectic Alloy in Reactor Safety Analyses

Werner Maschek, Yoshiharu Tobita, Hidemasa Yamano, 2006 .

Research and Development of Margin Assessment Methodology of Decay Heat Removal Function against External Hazards

Hidemasa Yamano, 2016 .

Safety Design Requirements for Safety Systems and Components of JSFR

Shoji Kotake, Hidemasa Yamano, Shigenobu Kubo, 2011 .

Development of flow-induced vibration evaluation methodology for large-diameter piping with elbow in Japan sodium-cooled fast reactor

Hidemasa Yamano, Hideki Kamide, Nobuyuki Kimura, 2011 .

Transient Heat Transfer Characteristics Between Molten Fuel and Steel with Steel Boiling in the CABRI-TPA2 Test

Yoshiharu Tobita, Hidemasa Yamano, Ikken Sato, 2009 .

Experimental Studies and Empirical Models for the Transient Self-Leveling Behavior in Debris Bed

Tatsuya Matsumoto, Kenji Fukuda, Tohru Suzuki, 2011 .

The Development of SIMMER-III, An Advanced Computer Program for LMFR Safety Analysis, and Its Application to Sodium Experiments

Werner Maschek, T. Cadiou, Sa. Kondo, 2006 .

The Development of SIMMER-III, An Advanced Computer Program for LMFR Safety Analysis, and Its Application to Sodium Experiments

Werner Maschek, T. Cadiou, Sa. Kondo, 2006 .

Technological Feasibility of Two-Loop Cooling System in JSFR

Kenichi Kurisaka, Hidemasa Yamano, Shigenobu Kubo, 2010 .

Analytical study on elimination of severe recriticalities in large scale LMFBRS with enhancement of fuel discharge

Yoshiharu Tobita, Hidemasa Yamano, Ikken Sato, 2008 .

Experimental Analyses by SIMMER-III on Molten Fuel Freezing and Boiling Pool Behavior

Yoshiharu Tobita, Hidemasa Yamano, 2009 .

First 3-D calculation of core disruptive accident in a large-scale sodium-cooled fast reactor

Werner Maschek, Satoshi Fujita, Yoshiharu Tobita, 2009 .

Experimental investigation on self-leveling behavior in debris beds

Tatsuya Matsumoto, Kenji Fukuda, Tohru Suzuki, 2011 .

Unsteady Elbow Pipe Flow to Develop a Flow-Induced Vibration Evaluation Methodology for Japan Sodium-Cooled Fast Reactor

Hidemasa Yamano, Hiromi Sago, Kazuhisa Yuki, 2011 .

Development of probabilistic risk assessment methodology against extreme snow for sodium-cooled fast reactor

Kenichi Kurisaka, Hidemasa Yamano, Hiroyuki Nishino, 2016 .

Experimental Analyses by SIMMER-III on Debris-Bed Coolability and Metallic Fuel Freezing Behavior

Yoshiharu Tobita, Hidemasa Yamano, 2011 .

Experimental investigation of bubbling in particle beds with high solid holdup

Tatsuya Matsumoto, Kenji Fukuda, Tohru Suzuki, 2011 .