山野秀将 (Hidemasa Yamano) - マイポータル

基本情報

所属: 国立研究開発法人日本原子力研究開発機構高速炉・新型炉研究開発部門

J-GLOBAL ID: 201801007320859274
researchmap会員ID: B000304699

研究分野

エネルギー / 原子力工学 /

論文

Normal spectral emissivity, specific heat capacity, and thermal conductivity of type 316 austenitic stainless steel containing up to 10 mass% B4C in a liquid state

Hiroyuki Fukuyama, Hideo Higashi, Hidemasa Yamano

Journal of Nuclear Materials 568 153865-153865 2022年9月
Effect of B4C addition on the solidus and liquidus temperatures, density and surface tension of type 316 austenitic stainless steel in the liquid state

Hiroyuki Fukuyama, Hideo Higashi, Hidemasa Yamano

Journal of Nuclear Materials 554 153100-153100 2021年10月
Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors: (1) project overview

Hidemasa Yamano, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama, Hiroyuki Fukuyama, Hideo Higashi, Tsuyoshi Nishi, Hiromichi Ohta, Xiaoxing Liu, Koji Morita, Kinya Nakamura, Hirokazu Ohta, Masahiro Furuya

GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water Reactor Fuel Performance Conference 418-427 2020年
Thermophysical Properties of Molten Stainless Steel Containing 5 mass % B4C

Hiroyuki Fukuyama, Hideo Higashi, Hidemasa Yamano

Nuclear Technology 205 1154-1163 2019年9月査読有り
Development of probabilistic risk assessment methodology against volcanic eruption for sodium-cooled fast reactors

Hidemasa Yamano, Hiroyuki Nishino, Kenichi Kurisaka, Takahiro Yamamoto

ASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part B: Mechanical Engineering 4(3) 2018年9月1日査読有り
Development of a probabilistic risk assessment methodology against a combination hazard of strong wind and rainfall for sodium-cooled fast reactors

Yamano Hidemasa, Nishino Hiroyuki, Kurisaka Kenichi

MECHANICAL ENGINEERING JOURNAL 5(4) 2018年査読有り
Development of probabilistic risk assessment methodology of decay heat removal function against combination hazards of strong wind and rainfall for sodium-cooled fast reactors

Hidemasa Yamano, Hiroyuki Nishino, Kenichi Kurisaka

International Conference on Nuclear Engineering, Proceedings, ICONE 4 2017年査読有り
Development of probabilistic risk assessment methodology of decay heat removal function against combination hazard of low temperature and snow for sodium-cooled fast reactors

Hiroyuki Nishino, Hidemasa Yamano, Kenichi Kurisaka

International Conference on Nuclear Engineering, Proceedings, ICONE 4 2017年査読有り
Development of probabilistic risk assessment methodology of decay heat removal function against combination hazard of low temperature and snow for sodium-cooled fast reactors

Hiroyuki Nishino, Hidemasa Yamano, Kenichi Kurisaka

International Conference on Nuclear Engineering, Proceedings, ICONE 4(4) 2017年査読有り
Characteristics of flow field and pressure fluctuation in complex turbulent flow in the third elbow of a triple elbow piping with small curvature radius in three-dimensional layout

Shinji Ebara, Hiroyuki Takamura, Hidetoshi Hashizume, Hidemasa Yamano

INTERNATIONAL JOURNAL OF HYDROGEN ENERGY 41(17) 7139-7145 2016年5月査読有り
低温と積雪の重畳事象に対する確率論的リスク評価手法の開発

西野裕之, 山野秀将, 栗坂健一

日本機械学会論文集 2016年
Influence of Piping Layout upon the characteristics of flow separation and pressure fluctuation in the primary cold-leg of sodium cooled fast reactor

Jun Mizutani, Shinji Ebara, Hidetoshi Hashizume, Hidemasa Yamano

10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety 2014年12月14日査読有り
Unsteady wall pressure characteristics of a 90 degree elbow in high Reynolds numbers

岩本幸治

Journal of Fluid Science and Technology 9(3) 14-00047 2014年9月査読有り
DEVELOPMENT OF PROPOSED GUIDELINE OF FLOW-INDUCED VIBRATION EVALUATION FOR HOT-LEG PIPING IN A SODIUM-COOLED FAST REACTOR

Takaaki Sakai, Hidemasa Yamano, Masaaki Tanaka, Ayako Ono, Hiroyuki Ohshima, Tetsuya Kaneko, Kazuo Hirota, Hiromi Sago, Yang Xu, Yukiharu Iwamoto, Shinji Ebara, Takahiro Murakami, Takashi Nishihara, Akira Yamaguchi, Tomomichi Nakamura

Proceedings of The 15th International Topical Meeting on Nuclear Reactor Thermalhydraulics NURETH15-042 2013年5月査読有り
JSFRの安全設計検討のための外部事象の条件設定

山野秀将, 久保重信, 西野裕之, 堺公明, 谷明洋

日本原子力学会年会・大会予稿集 2013s 336 2013年
EFFECTS OF SEPARATION VORTICES ON PRESSURE FLUCTUATION OF COMPLEX TURBULENT FLOW IN A DUAL ELBOW WITH SMALL CURVATURE RADIUS IN A THREE-DIMENSIONAL LAYOUT

Shinji Ebara, Hiroaki Konno, Hidetoshi Hashizume, Tetsuya Kaneko, Hidemasa Yamano

Proceedings of the Eighth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety N8P1048 2012年12月査読有り
Unsteady Flow Characteristics in a 90 Degree Elbow Affected by Developed, Undeveloped and Swirling Inflow Conditions

Yukiharu IWAMOTO, Manabu KONDO, Hirotaka MINAMIURA, Masaaki TANAKA, Hidemasa YAMANO

Journal of Fluid Science and Technology 7(3) 315-328 2012年8月査読有り
Na冷却高速炉における大口径配管の流力振動評価に関する研究—(35) ホットレグ配管流力振動評価指針（案）の作成

山野秀将, 田中正暁, 金子哲也, 堺公明, 佐郷ひろみ, 廣田和生, 徐陽

日本原子力学会年会・大会予稿集 2012s 293-293 2012年
Na冷却高速炉における大口径配管の流力振動評価に関する研究:（39）コールドレグ1/7縮尺流動試験装置を用いた1段および2段エルボ管内流れPIV計測による複数エルボ効果の検証

高村宏行, 江原真司, 橋爪秀利, 山野秀将

日本原子力学会年会・大会予稿集 2012 265-265 2012年
高速炉の確率論的安全評価手法（レベル１PSA）の開発:(6) 自然循環崩壊熱除去機能の失敗確率評価手法

山野秀将, 堺公明, 栗坂健一

日本原子力学会年会・大会予稿集 2012 310-310 2012年

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MISC

120

Thermophysical properties of stainless steel containing 5mass%-b4c in the solid phase

Toshihide Takai, Tomohiro Fumkawa, Hidemasa Yamano

Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018 1007-1013 2018年1月1日
Thermophysical properties of molten stainless steel containing 5mass%-b<inf>4</inf>c

Hiroyuki Fukuyama, Hideo Higashi, Hidemasa Yamano

Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018 1014-1019 2018年1月1日
ナトリウム冷却高速炉の炉心損傷事故時の制御棒材の共晶溶融挙動に関する研究(1)プロジェクト全体概要

山野秀将, 高井俊秀, 古川智弘, 江村優軌, 倉田正輝, 東英生, 福山博之, 西剛史, 太田弘道, LIU Xiaoxing, 守田幸路, 古谷正裕

日本原子力学会秋の大会予稿集(CD-ROM) 2017 2017年
SAS4A analysis study on the initiating phase of atws events for generation-IV loop-type SFR

Ryuzaburo Kubota, Kazuya Koyama, Hiroyuki Moriwaki, Yumi Yamada, Yoshio Shimakawa, Suzuki Tohru, Kenichi Kawada, Shigenobu Kubo, Hidemasa Yamano

2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings 2017年1月1日
Safety evaluation of self actuated shutdown system for Gen-IV SFR

Hiroyuki Saito, Yumi Yamada, Kazuhiro Oyama, Shoko Matsunaga, Hidemasa Yamano, Shigenobu Kubo

2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings 2017年1月1日
Effect of deflected inflow on flows in a stronglycurved 90 degree elbow

Yukiharu Iwamoto, Ryo Kusuzaki, Motosuke Sogo, Kazunori Yasuda, Hidemasa Yamano, Masaaki Tanaka

International Journal of Fluid Machinery and Systems 10(1) 76-85 2017年1月1日
Hazard curve evaluation for forest fire smoke effects on air-cooling decay heat removal systems

Yasushi Okano, Hidemasa Yamano

International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017 2 1334-1342 2017年1月1日
Development of probabilistic risk assessment methodology against extreme snow for sodium-cooled fast reactor

Hidemasa Yamano, Hiroyuki Nishino, Kenichi Kurisaka

NUCLEAR ENGINEERING AND DESIGN 308 86-95 2016年11月
Development of the evaluation methodology for the material relocation behavior in the core disruptive accident of sodium-cooled fast reactors

Yoshiharu Tobita, Kenji Kamiyama, Hirotaka Tagami, Ken-ichi Matsuba, Tohru Suzuki, Mikio Isozaki, Hidemasa Yamano, Koji Morita, LianCheng Guo, Bin Zhang

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 53(5) 698-706 2016年5月
Flow-induced vibration evaluation of primary hot-leg piping in advanced loop-type sodium-cooled fast reactor for demonstration

Hidemasa Yamano, Yang Xu, Hiromi Sago, Kazuo Hirota, Takeo Baba

International Congress on Advances in Nuclear Power Plants, ICAPP 2016 2 1029-1038 2016年1月1日
SENSITIVITY STUDY ON FOREST FIRE BREAKOUT AND PROPAGATION CONDITIONS FOR FOREST FIRE HAZARD CURVE EVALUATIONS

Yasushi Okano, Hidemasa Yamano

PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 4 4 2016年
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

PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 4 111-121 2016年
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

PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 4 4 2016年
Hazard curve evaluation method development for a forest fire as an external hazard on nuclear power plants

Yasushi Okano, Hidemasa Yamano

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 53(8) 1224-1234 2016年
Forest fire propagation simulations for a risk assessment methodology development for a nuclear power plant

Yasushi Okano, Hidemasa Yamano

Case Studies in Fire Safety 4 1-10 2015年10月1日
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

International Conference on Nuclear Engineering, Proceedings, ICONE 2015-January 2015年1月1日
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, Takashi Takata, Emiko Azuma

International Conference on Nuclear Engineering, Proceedings, ICONE 2015-January 2015年1月1日
Development of a hazard curve evaluation method for a forest fire as an external hazard

Yasushi Okano, Hidemasa Yamano

International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2015 1 22-31 2015年1月1日
U-RANS simulation of single elbow pipe flow experiments simulating JSFR hot-leg piping

Hidemasa Yamano, Masaaki Tanaka, Yukiharu Iwamoto

ASME/JSME/KSME 2015 Joint Fluids Engineering Conference, AJKFluids 2015 1A 2015年
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

Hiroyuki Nishino, Kenichi Kurisaka, Hidemasa Yamano

International Conference on Nuclear Engineering, Proceedings, ICONE 2015-January 2015年1月1日

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山野秀将

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論文

MISC

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