Shinya Miyahara

Profile Information

Affiliation: Japan Atomic Energy Agency
: 産学連携コーディネータ, 国立研究開発法人日本原子力研究開発機構

Degree: 工学博士(茨城大学)

J-GLOBAL ID: 200901080663057270
researchmap Member ID: 5000101315

Committee Memberships

Nov, 2006 - Present

Reviewer of Nuclear Technology, American Nuclear Society
May, 2014 - Apr, 2018

標準委員会システム安全専門部会委員, 日本原子力学会
Oct, 2006 - Mar, 2010

「シビアアクシデント時の格納容器内の現実的ソースターム評価」特別専門委員会委員, 日本原子力学会

Papers

Development and validation of analysis code for spallation products behavior in LBE coolant system of ADS comparing with the distribution data in MEGAPIE spallation target

Shinya Miyahara, Yuji Arita, Keita Nakano, Fujio Maekawa, Toshinobu Sasa, Hironari Obayashi, Hayanori Takei

Nuclear Engineering and Design, 403, Mar, 2023
300

ANALYTICAL STUDY ON REMOVAL MECHANISMS OF CESIUM AEROSOL FROM A NOBLE GAS BUBBLE RISING THROUGH LIQUID SODIUM POOL

Shinya Miyahara, Munemichi Kawaguchi, Seino Hiroshi

Proceedings of the 2020 28th Conference on Nuclear Engineering Joint with the ASME 2020 Power Conference, (ICONE28-POWER2020-16208), Aug, 2020 Peer-reviewedLead author
A Study on Sodium–Concrete Reaction in Presence of Internal Heating

Munemichi Kawaguchi, Shinya Miyahara, Masayoshi Uno

Journal of Nuclear Engineering and Radiation Science, 6(2) 021305-1-021305-9, Feb, 2020 Peer-reviewedInvited
346

The analytical study of inventories and physicochemical configuration of spallation products produced in Lead-Bismuth Eutectic of Accelerator Driven System

Shinya MIYAHARA, Naoya ODAIRA, Yuji ARITA, Fujio MAEKAWA, Hiroki MATSUDA, Toshinobu SASA, Shin-ichiro MEIGO

Nuclear Engineering and Design, 352 110192, Sep, 2019 Peer-reviewed
201

Visualizing an ignition process of hydrogen jets containing sodium mist by high-speed imaging

Daisuke Doi, Hiroshi Seino, Shinya Miyahara, Masayoshi Uno

Journal of Nuclear Science and Technology, 56(6) 521-532, Jun 3, 2019 Peer-reviewedCorresponding author
Melting behavior and thermal conductivity of solid sodium-concrete reaction product

Munemichi Kawaguchi, Miyahara Shinya, Uno Masayoshi

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 56(6) 513-520, Jun 3, 2019 Peer-reviewed
A study on self-terminating behavior of sodium-concrete reaction (2)

Munemichi Kawaguchi, Shinya Miyahara, Masayoshi Uno

Journal of Nuclear Science and Technology, 55(8) 874-884, Aug 3, 2018 Peer-reviewed
229

Discussion about sodium-concrete reaction in presence of internal heater

Kawaguchi, Munemichi, Miyahara, Shinya, Uno, Masayoshi

Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), (82233) 8, Jul, 2018 Peer-reviewed
Thermophysical properties of sodium-concrete reaction products

Kawaguchi, Munemichi, Miyahara, Shinya, Uno, Masayoshi

Netsu Sokutei, 45(1) 2-8, Jan, 2018 Peer-reviewed
A study on self-terminating behavior of sodium-concrete reaction

Munemichi Kawaguchi, Daisuke Doi, Hiroshi Seino, Shinya Miyahara

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 53(12) 2098-2107, 2016 Peer-reviewed
297

Development of fast reactor containment safety analysis code, CONTAIN-LMR, 1; Outline of development project

Miyahara, Shinya, Seino, Hiroshi, Ohno, Shuji, Konishi, Kensuke

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), (1586) 5, May, 2015 Peer-reviewed
292

Development of fast reactor containment safety analysis code, CONTAIN-LMR, 3; Improvement of sodium-concrete reaction model

Kawaguchi, Munemichi, Doi, Daisuke, Seino, Hiroshi, Miyahara, Shinya

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), (1588) 6, May, 2015 Peer-reviewed
268

Combustion characteristics of generating hydrogen during sodium-concrete reaction

Seino, Hiroshi, Ohno, Shuji, Yamamoto, Ikuo, Miyahara, Shinya

Proceedings of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8) (USB Flash Drive), (N8P1031) 10, Dec, 2012 Peer-reviewed
245

Simulation of radioactive corrosion product in primary cooling system of Japanese sodium-cooled fast breeder reactor

Matsuo, Yoichiro, Miyahara, Shinya, Izumi, Yoshinobu

Journal of Power and Energy Systems (Internet), 6(1) 6-17, Mar, 2012 Peer-reviewed
70

DEVELOPMENT OF EVALUATION METHODS FOR THE TRANSFER BEHAVIOR OF CORROSION PRODUCT IN THE PRIMARY COOLING SYSTEM OF FAST BREEDER REACTOR

Youichirou Matuo, Shinya Miyahara

PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 1, (54505) 359-366, 2012 Peer-reviewed
323

The dependence of equilibrium partition coefficient of cesium and iodine between sodium pool and the inert cover gas on the concentration in the pool

Shinya Miyahara, Masahiro Nishimura, Toshio Nakagiri

NUCLEAR ENGINEERING AND DESIGN, 241(12) 4731-4736, Dec, 2011 Peer-reviewed
239

Predictive analysis of the radiation exposure for the primary cooling system of the rated power operation of MONJU

Matsuo, Yoichiro, Hasegawa, Masanori, Maegawa, Yoshiharu, Miyahara, Shinya

Hoken Butsuri, 46(4) 304-313, Dec, 2011 Peer-reviewed
205

Proposed method of the modeling and simulation of corrosion product behavior in the primary cooling system of fast breeder reactors

Matsuo, Yoichiro, Miyahara, Shinya, Izumi, Yoshinobu

Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), (43502) 8, May, 2011 Peer-reviewed
126

Experimental investigation of reaction behavior between carbon dioxide and liquid sodium

Shinya Miyahara, Hiroyasu Ishikawa, Yoshio Yoshizawa

NUCLEAR ENGINEERING AND DESIGN, 241(5) 1319-1328, May, 2011 Peer-reviewed
Reactive wetting of metallic plated steels by liquid sodium

Munemichi Kawaguchi, Akihiro Tagawa, Shinya Miyahara

Journal of Nuclear Science and Technology, 48(4) 499-503, Apr, 2011 Peer-reviewed

Misc.

Thermodynamic stability of volatile radionuclides in cladding failure accident of sodium-cooled fast reactor

山本郁夫, 河口宗道, 宮原信哉, 宇埜正美

日本原子力学会春の年会予稿集(CD-ROM), 2022, 2022
A Study on Removal Mechanisms of Cesium Aerosol from Noble Gas Bubble in Sodium Pool (3) Measurement for Decontamination Factors of Bubbling in Water Simulation Test

鯉江竜輔, 河口宗道, 宮原信哉, 宇埜正美, 清野裕

日本原子力学会春の年会予稿集(CD-ROM), 2022, 2022
A study on removal mechanisms of cesium aerosol from noble gas in sodium pool (2) Comparison of water simulation test results with calculation results of AESOP code

宮原信哉, 河口宗道, 清野裕, 厚見拓大, 宇埜正美

日本原子力学会秋の大会予稿集(CD-ROM), 2021, 2021
A study on removal mechanisms of cesium aerosol from noble gas bubble in sodium pool (1) Water simulation test for bubble rising behavior

河口宗道, 宮原信哉, 清野裕, 厚見拓大, 宇埜正美

日本原子力学会秋の大会予稿集(CD-ROM), 2021, 2021
ADSにおける鉛ビスマス中の核破砕生成物の物理化学形態に関する研究(2)核破砕生成物の物理化学形態に関する熱力学的検討

宮原信哉, 大平直也, 有田裕二, 佐々敏信, 前川藤夫, 松田洋樹, 明午伸一郎

日本原子力学会秋の大会予稿集(CD-ROM), 2018, 2018
E204 Experimental Study on Sodium-Concrete Reaction Mechanism in a Sodium-cooled Fast Reactor

KIKUCHI Shin, SEINO Hiroshi, MIYAHARA Shinya, KONISHI Kensuke

National Symposium on Power and Energy Systems, 2013(18) 389-390, Jun 19, 2013
Sodium fire test at broad ranges of temperature and oxygen concentrations, 4; Low temperature sodium spray tests (Translated document)

Kawata Koji, Matsuki Takuo, MIYAHARA Shinya

JAEA-Review 2011-046, 1-42, Feb, 2012 Peer-reviewed
Experimental investigation of fission products release from irradiated FBR MOX fuel

Ohno, Shuji, Sato, Isamu, Nakagiri, Toshio, HIROSAWA, Takashi, Miyahara, Shinya, Namekawa, Takashi

JAERI-Review-2004-021, 199-208, Oct, 2004
Sodium Leak and Fire Control in Fast Breeder Reactors

MIYAHARA Shinya, OHNO Shuji, ISHIKAWA Hiroyasu, DODA Norihiro

Journal of the Combustion Society of Japan, 45(133) 141-151, Aug 31, 2003
None

Kondo, Satoru

Nippon Genshiryoku Gakkai-Shi, 38(2) 109-112, 1996 Peer-reviewed

Presentations

108

Analytical study on removal mechanisms of cesium aerosol from noble gas bubble in sodium pool (2) Effects of particle size distribution and coagulation in aerosols

Shinya Miyahara

Sep 18, 2020
137

Analytical study on removal mechanisms of cesium aerosol from noble gas bubble in sodium pool

MIYAHARA Shinya

Sep 11, 2019
Research on physicochemical composition of spallation products in lead-bismuth eutectic in ADS, 2; Thermodynamic study of physicochemical composition of spallation products

Miyahara, Shinya, Ohdaira, Naoya, Arita, Yuji, Sasa, Toshinobu, Maekawa, Fujio, Matsuda, Hiroki, Meigo, Shinichiro

日本原子力学会2018年秋の大会, Sep, 2018
Research on physicochemical composition of spallation products in lead-bismuth eutectic in ADS, 1; Estimation of inventories of spallation products

Maekawa, Fujio, Matsuda, Hiroki, Meigo, Shinichiro, Sasa, Toshinobu, Miyahara, Shinya, Arita, Yuji, Ohdaira, Naoya

日本原子力学会2018年秋の大会, Sep, 2018
Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 20; Summary of sodium-concrete reaction experiments

Kawaguchi, Munemichi, Miyahara, Shinya, Uno, Masayoshi

日本原子力学会2017年秋の大会, Sep, 2017
Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 22; Chemical reaction analysis of the hydrogen combustion by sodium vapor/mist ignition

Doi, Daisuke, Ito, Kei, Seino, Hiroshi, Miyahara, Shinya, Uno, Masayoshi

日本原子力学会2017年秋の大会, Sep, 2017
Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 16; Ignition study on various gas concentration of hydrogen jet containing sodium vapor/mist

Doi, Daisuke, Ito, Kei, Seino, Hiroshi, Miyahara, Shinya, Uno, Masayoshi

日本原子力学会2017年春の年会, Mar, 2017
Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 14; Self-terminating behavior of Na-concrete reaction

Kawaguchi, Munemichi, Miyahara, Shinya, Uno, Masayoshi

日本原子力学会2017年春の年会, Mar, 2017
Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 13; Simulation of Na-concrete reaction process

Kawaguchi, Munemichi, Miyahara, Shinya, Uno, Masayoshi

日本原子力学会2016年秋の大会, Sep, 2016
Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 8; Estimation of phase equilibrium state of fuel debris under sodium by thermodynamic calculation

Yamamoto, Ikuo, Uno, Masayoshi, Miyahara, Shinya, Kawaguchi, Munemichi

日本原子力学会2016年春の年会, Mar, 2016
Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 7; Calculation of sodium-concrete reaction with phase-field method

Kawaguchi, Munemichi, Miyahara, Shinya, Uno, Masayoshi

日本原子力学会2016年春の年会, Mar, 2016
A Study on a microscopic state of Na-concrete reaction products

Kawaguchi, Munemichi, Miyahara, Shinya, Uno, Masayoshi

化学工学会第47回秋季大会, Sep, 2015
Development of fast reactor containment safety analysis code, CONTAIN-LMR, 1; Outline of development project

Miyahara, Shinya, Seino, Hiroshi, Ohno, Shuji, Konishi, Kensuke

日本原子力学会2015年春の年会, Mar, 2015
Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 4; Study on hydrogen combustion behavior in sodium aerosol containing atmosphere

Doi, Daisuke, Ito, Kei, Seino, Hiroshi, Miyahara, Shinya, Uno, Masayoshi

日本原子力学会2015年春の年会, Mar, 2015
Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor, 3; Corium/sodium-concrete interaction behavior

Kawaguchi, Munemichi, Uno, Masayoshi, Konishi, Kensuke, Yamamoto, Ikuo, Miyahara, Shinya

日本原子力学会2015年春の年会, Mar, 2015
Study on sodium-concrete reaction

Kawaguchi, Munemichi, Doi, Daisuke, Masuyama, Daisuke, Seino, Hiroshi, Konishi, Kensuke, Miyahara, Shinya

日本原子力学会2014年秋の大会, Sep, 2014
Experimental study on sodium-concrete reaction mechanism in a sodium-cooled fast reactor

Kikuchi, Shin, Seino, Hiroshi, Miyahara, Shinya, Konishi, Kensuke

日本機械学会第18回動力・エネルギー技術シンポジウム, Jun, 2013
Calculation of radioactive corrosion product transfer in primary systems of prototype fast breeder reactor MONJU, 2; Introduction of the particulate CP transport model

Matsuo, Yoichiro, Miyahara, Shinya, Izumi, Yoshinobu

日本原子力学会2011年春の年会, Mar, 2011
Development of CONTAIN/LMR code for LMFBR's ex-vessel phenomena; Improvement and validation of sodium-concrete reaction model

Seino, Hiroshi, Ohno, Shuji, Miyahara, Shinya, Izumi, Keitaro, Yamamoto, Ikuo

日本原子力学会2011年春の年会, Mar, 2011
Calculation of radioactive corrosion product transfer in primary systems of prototype fast breeder reactor MONJU

Matsuo, Yoichiro, Hasegawa, Masanori, Maegawa, Yoshiharu, Miyahara, Shinya

日本原子力学会2010年秋の大会, Sep, 2010

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