Doctor of Engineering, University of Fukui, Mar. 2017

Aerosol

Nuclear safety

Source term

Melted oxide

Phase-field method

Chemical analysis

Thermophysical property

Metal

Optical property

Severe accident

Fast reactor

Sodium

Energy Engineering, Nuclear engineering, Aerosol

Energy Engineering, Nuclear engineering, Source term

Energy Engineering, Nuclear engineering, シビアアクシデント

Energy Engineering, Nuclear engineering, 無機材料

Energy Engineering, Nuclear engineering, Alkali metal

Energy Engineering, Nuclear engineering, Sodium-cooled fast reactor

Bachelor's degree program, School of Engineering

Master's degree program, Graduate School of Engineering

Doctoral (PhD) degree program, Graduate School of Engineering

Mar. 2023, Faculty of Engineering, Hokkaido University, 令和4年度大学院工学研究院若手教員奨励賞
Munemichi Kawaguchi

Dec. 2019, Kansaigenishiryoku-kondankai, Best presentation
Thermophysical properties of sodium-concrete reaction products in severe accident of sodium-cooled fast reactor
munemichi kawaguchi

Oct. 2018, 日本原子力機構, 理事長表彰
河口宗道

Feb. 2013, 日本原子力学会関西支部賞, 奨励賞
河口宗道

Dec. 2009, 日本原子力機構, 理事長表彰
河口宗道

Initial aerosolization of deposited powder particles through upward flow
Munemichi Kawaguchi; Kotaro Miwa; Kazuhiro Sawa
Annals of Nuclear Energy, 238, 112564, Dec. 2026, [Peer-reviewed], [Lead author]
English, Scientific journal

Semi-mechanistic modeling of moisture release from heated concrete for safety design under sodium fire accident conditions
Ryogo Okamoto; Munemichi Kawaguchi
Nuclear Engineering and Design, 458, 115138, 115138, Elsevier BV, Nov. 2026, [Peer-reviewed], [Last author, Corresponding author]
English, Scientific journal

A review of sodium-concrete reactions in sodium-cooled fast reactors: Experimental findings and containment failure implications
Munemichi Kawaguchi
Progress in Nuclear Energy, 197, 106405, Jul. 2026, [Peer-reviewed], [Lead author, Last author, Corresponding author]
English, Scientific journal

Experimental Evaluation of Cesium Removal from Contaminated Concrete by Preheating and Attrition Treatment
Munemichi Kawaguchi; Keigo Sokugawa; Kazuhiro Sawa
Nuclear Engineering and Technology, 58, 11, 104517, 104517, Elsevier BV, Jun. 2026, [Peer-reviewed], [Lead author]
English, Scientific journal, 50393471

Development of methods to model the uncertainty distribution of seismically induced joint failure probability for seismic probabilistic risk assessment
Shota Soga; Eishiro Higo; Sunghyon Jang; Munemichi Kawaguchi; Hiromichi Miura
Journal of Nuclear Science and Technology, Informa UK Limited, 27 Apr. 2026, [Peer-reviewed]
English

Development of Single-Bubble Model for Removal of Soluble Gas, CO2, and I2 During Pool Scrubbing
Munemichi Kawaguchi; Shun Wakabayashi; Kazuhiro Sawa
Nuclear Technology, 1, 14, 13 Apr. 2026, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal

Development of High-Performance Molten-Salt Thermal Energy Storage Systems
Munemichi Kawaguchi; Yifan Jiang
Proceedings of international conference on power engineering -2026, 1, 4, 11 Apr. 2026, [Peer-reviewed], [Lead author, Corresponding author]
English, International conference proceedings

A novel kinetic model for dissolution and precipitation of oxide on stainless-steel surface in stagnant liquid sodium
Munemichi Kawaguchi; Asuka Ikeda; Jun-ichi Saito
Annals of Nuclear Energy, 226, 111880, 111880, Elsevier BV, Feb. 2026, [Peer-reviewed]
English, Scientific journal

Mechanisms of Dissolution-governed Wetting in the Liquid Na/au-coated Substrate System: A Scaling Approach Based on Competing Transport Time Scales
Munemichi Kawaguchi; Masanari Namie; Asuka Ikeda; Jun-ichi Saito
2026

Experimental study of AESOP code for aerosol removal behavior from a rising gas bubble in water pool and parametric study for application to sodium pool system
Shinya Miyahara; Ryusuke Koie; Masayoshi Uno; Munemichi Kawaguchi; Rika Sato; Hiroshi Seino
Nuclear Engineering and Design, 446, 114523, 114523, Jan. 2026, [Peer-reviewed]
English, Scientific journal

An analytical comparison of the multivariate normal model and the Reed–McCann procedure
Shota Soga; Eishiro Higo; Sunghyon Jang; Munemichi Kawaguchi; Hiromichi Miura
Reliability Engineering & System Safety, 265, 111518, 111518, Elsevier BV, Jan. 2026, [Peer-reviewed]
English, Scientific journal

Applicability of Butler Model for Estimation of Surface Tension in Liquid Na-K-Cs Alloys
Munemichi Kawaguchi
Nuclear Technology, 212, 6, 1579, 1594, Informa UK Limited, 11 Jun. 2025, [Peer-reviewed], [Lead author]
English, Scientific journal

Phase-field simulation of vapor pressure for micropore formation in pseudo-binary system, B2O3–UO2
Munemichi Kawaguchi; Sota Hamajima; Masayoshi Uno
Journal of the Ceramic Society of Japan, 132, 5, 214, 221, Ceramic Society of Japan, 01 May 2024, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal

Prediction for crystal growth rates in borides under supercooled temperature conditions
Munemichi Kawaguchi; Masayoshi Uno
Journal of the Ceramic Society of Japan, 131, 10, 802, 807, Ceramic Society of Japan, 01 Oct. 2023, [Peer-reviewed], [Lead author]
English, Scientific journal

Estimation Method for Residual Sodium Amount on Unloaded Dummy Fuel Assembly
Munemichi Kawaguchi; Yasushi Hirakawa; Yusuke Sugita; Yutaka Yamaguchi
Nuclear Technology, 210, 1, 55, 71, Informa UK Limited, 28 Jun. 2023, [Peer-reviewed]
English, Scientific journal

Phase-field simulation on micropore formation mechanisms in pseudo binary system, B2O3-UO2: Comparison of monotectic reaction model
Munemichi Kawaguchi; Sota Hamajima; Masayoshi Uno; Sunghyon Jang; Kazuhiro Sawa
Proceedings of the 2023 30th International Conference on Nuclear Engineering (ICONE30), ICONE30-1061, 1, 7, May 2023, [Peer-reviewed], [Lead author]
English, International conference proceedings

Phase-Field Modeling of Crystal Growth on the Surface and in the Volume of Na2O–2CaO–3SiO2 Glass under Periodic Temperature Conditions
Munemichi Kawaguchi; Masayoshi Uno
ACS Omega, 8, 3, 3329, 3338, 24 Jan. 2023, [Peer-reviewed], [Lead author]
English, Scientific journal

Thermodynamic Stability of Volatile Radionuclides in Cladding Failure Accident of Sodium-cooled Fast Reactor
YAMAMOTO Ikuo; KAWAGUCHI Munemichi; MIYAHARA Shinya; UNO Masayoshi
Transactions of the Atomic Energy Society of Japan, 22, 1, 1, 11, Atomic Energy Society of Japan, Jan. 2023, [Peer-reviewed]
Japanese, Scientific journal, Thermodynamic calculation of volatile radionuclides such as Cs, I and Te in a cladding failure accident of a sodium-cooled fast reactor has been conducted for the evaluation of an in-vessel source term. Important chemical reactions and chemical forms such as Cs, Cs₂, Te, CsI, Cs₂I₂, Cs₂Te, CsNa, NaI, Na₂I₂, Cs₂Te, Na₂Te, AgTe and Cs₂MoO₄ were suggested by the results of interaction among fuel, fission products, a cladding tube and Na coolant at high reduction rates inside the fast reactor vessel. As the cladding failure accident proceeds, it was confirmed that 15% and 60% of Cs was in gas phase at 1,155 K and 5.7 MPa and at 1,670 K and 10.5 MPa, respectively. 58% and 66% of Cs was in the gas phase at 1,155 K and 1,670 K at 0.1 MPa owing to cladding failure. Under Na mixing conditions, almost 100% of Cs became gas. Furthermore, we confirmed the same behavior as in light water reactors, that is, the release of Cs is suppressed at high pressures, but we observed that Cs rarely oxidizes and that the amount of Cs released increases with Na mixing in the fast reactor., 12133761

A study on removal mechanisms of cesium aerosol from noble gas bubble in sodium pool (III) Measurement of decontamination factors in water simulation test
Rsuke Koie; Munemichi Kawaguchi; Shinya Miyahara; Masayoshi Uno; Hiroshi Seino
Proceedings of the 2022 29th International Conference on Nuclear Engineering (ICONE29), ICONE29-94057, 1, 4, Aug. 2022, [Peer-reviewed]
English, International conference proceedings

Phase-field mobility for crystal growth rates in undercooled silicates, SiO2 and GeO2 liquids
Munemichi Kawaguchi; Masayoshi Uno
Journal of Crystal Growth, 126590, 126590, Elsevier BV, Feb. 2022, [Peer-reviewed], [Lead author]
English, Scientific journal

Analytical study on removal mechanisms of cesium aerosol from a noble gas bubble rising through liquid sodium pool (II) Effects of particle size distribution and agglomeration in aerosols
Shinya Miyahara; Munemichi Kawaguchi; Hiroshi Seino; Takuto Atsumi; Masayoshi Uno
The Proceedings of the 28th International Conference on Nuclear Engineering (ICONE28), ICONE28-63286, 1, 6, Aug. 2021, [Peer-reviewed]
English, International conference proceedings

Phase-field model for recrystallization of impurities in sodium coolant
Munemichi Kawaguchi
The Proceedings of the 28th International Conference on Nuclear Engineering (ICONE28), ICONE28-65721, 1, 5, Aug. 2021, [Peer-reviewed], [Lead author]
English, International conference proceedings

Kinetic and Fourier Transform Infrared Studies on the Thermal Decomposition of Sodium Hydride
Munemichi Kawaguchi
The Journal of Physical Chemistry C, 125, 22, 11813, 11819, American Chemical Society ({ACS}), 10 Jun. 2021, [Peer-reviewed], [Lead author]
English, Scientific journal

Phase-field model for crystallization in alkali disilicate glasses: Li₂O–2SiO₂, Na₂O–2SiO₂ and K₂O–2SiO₂
Munemichi KAWAGUCHI; Masayoshi UNO
Journal of the Ceramic Society of Japan, 128, 10, 832, 838, Ceramic Society of Japan, 01 Oct. 2020, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal, 12133761

Analytical study on removal mechanisms of cesium aerosol from a noble gas bubble rising through liquid sodium pool
Shinya Miyahara; Munemichi Kawaguchi; Hiroshi Seino
The Proceedings of the International Conference on Nuclear Engineering (ICONE28), ICONE28-POWER2020-16208, 1, 6, Aug. 2020, [Peer-reviewed]
English, International conference proceedings

Measurement of thermal decomposition temperature and rate of sodium hydride
Munemichi Kawaguchi
The Proceedings of the International Conference on Nuclear Engineering (ICONE28), ICONE28-POWER2020-16423, 1, 6, Aug. 2020, [Peer-reviewed], [Lead author]
English, International conference proceedings

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-reviewed], [Invited], [Lead author]
English, Scientific journal

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, 03 Jun. 2019, [Peer-reviewed], [Lead author]
English, Scientific journal

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, 03 Aug. 2018, [Peer-reviewed], [Lead author]
English, Scientific journal

Thermophysical Properties of Sodium-Concrete Reaction Products
河口 宗道; 宮原 信哉; 宇埜 正美
熱測定 = Calorimetry and thermal analysis, 45, 1, 2, 8, 日本熱測定学会, Jan. 2018, [Peer-reviewed], [Lead author]
Japanese, Scientific journal

Discussion about sodium-concrete reaction in presence of internal heater
Munemichi Kawaguchi; Shinya Miyahara; Masayoshi Uno
PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 4, 2018, [Peer-reviewed], [Lead author]
English, International conference proceedings, 12133761

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], [Lead author]
English, Scientific journal

Development of fast reactor containment safety analysis code, CONTAIN-LMR : (5) Improvement of debris-concrete interaction model
Hiroshi Seino; Munemichi Kawaguchi; Keitaro Izumi
The Proceedings of the International Conference on Nuclear Engineering (ICONE23), ICONE23-1683, 0, ICONE23-1, ICONE23-5, 一般社団法人日本機械学会, May 2015, [Peer-reviewed]
English, International conference proceedings, The CONTAIN-LMR code, which had been originally released from Sandia National Laboratories (SNL) in the U.S.A., has been developed in the Japan Atomic Energy Agency (JAEA) to evaluate ex-vessel severe accident progression in a liquid metal fast reactor (LMFR). As a part of several studies in JAEA, this paper mainly describes a state of the art of a debris-concrete interaction model. Since the debris-concrete interaction might be accompanied with concrete erosion, hydrogen generation and FP release etc., it is one of the most important phenomena in the ex-vessel accident. Stand-alone codes CORCON and VANESA, which were developed for the debris-concrete interaction calculation under a light water reactor (LWR) condition, have been incorporated into the CONTAIN-LMR code. Therefore, CORCON and VANESA have been improved to apply the LMFR condition in JAEA. Main topics of these works are followings; (1) addition of chemical reactions in the sodium pool, (2) consideration of heat conduction through the concrete, and (3) validation using SURC experimental data. As a result, improved CORCON and VANESA can represent the debris-concrete interaction behavior reasonably well.

Development of fast reactor containment safety analysis code, CONTAIN-LMR : (3) Improvement of sodium-concrete reaction model
Munemichi Kawaguchi; Daisuke Doi; Hiroshi Seino; Shinya Miyahara
The Proceedings of the International Conference on Nuclear Engineering (ICONE23), ICONE23-1588, 0, ICONE23-1, ICONE23-6, 一般社団法人日本機械学会, May 2015, [Peer-reviewed], [Lead author]
English, International conference proceedings, A computer code, CONTAIN-LMR, is an integrated analysis tool to predict the consequence of severe accident in a liquid metal fast reactor. Because a sodium-concrete reaction behavior is one of the most important phenomena in the accident, a Sodium-Limestone Concrete Ablation Model (SLAM) has been developed and installed into the original CONTAIN code at Sandia National Laboratories (SNL) in the U.S. The SLAM treats chemical reaction kinetics between the sodium and the concrete compositions mechanistically using a three-region model, containing a pool (sodium and reaction debris) region, a dry (boundary layer (B/L) and dehydrated concrete) region, and a wet (hydrated concrete) region, the application is limited to the reaction between sodium and limestone concrete. In order to apply SLAM to the reaction between sodium and siliceous concrete which is an ordinary structural concrete in Japan, the chemical reaction kinetics model has been improved to consider the new chemical reactions between sodium and silicon dioxide. The improved model was validated to analyze a series of sodium-concrete experiments which were conducted in Japan Atomic Energy Agency (JAEA). It has been found that relatively good agreement between calculation and experimental results is obtained and the CONTAIN-LMR code has been validated with regard to the sodium-concrete reaction phenomena.

Reactive wetting by liquid sodium on thin Au plating
Munemichi Kawaguchi; Hirotsugu Hamada
Journal of Nuclear Science and Technology, 51, 2, 201, 207, Feb. 2014, [Peer-reviewed], [Lead author]
English, Scientific journal

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], [Invited], [Lead author]
English, Scientific journal

The experimental study on wetting behaviour between liquid sodium and various plated stainless steel under low temperature condition
Munemichi Kawaguchi; Akihiro Tagawa; Shinya Miyahara; Shojiro Honda; Hajime Kiyokawa
Fast Reactors and Related Fuel Cycles: Challenges and Opportunities (FR09), 43106601, Dec. 2009, [Peer-reviewed], [Lead author]
English, International conference proceedings

Ce site substitution effect on the multipolar ordering in CeB6
M. Sera; M. Kawaguchi; S. Kishimoto; A. Kondo; H. Iwakubo; H. Tou; K. Umeo; F. Iga
Journal of magnetism and magnetic materials, 310, 2, E158, E159, Mar. 2007, [Peer-reviewed]
English, International conference proceedings

Sb NQR studies of ferromagnetism in YbxFe4Sb12 with x approximate to 0.89
Munemichi Kawaguchi; Hideki Tou; Masafumi Sera; Kenichi Kojima; Tsuyoshi Ikeno; Yosikazu Isikawa
Journal of the physical society of Japan, 75, 9, 093702-1, 093702-4, Sep. 2006, [Peer-reviewed], [Lead author]
English, Scientific journal

Competition between the Kondo effect and gap formed by the antiferromagnetic order in CexNd1-xB6
M. Kawaguchi; M.-S. Kim; H. Tou; M. Sera; F. Iga
Physica B Condensed Matter, 383, 1, 33, 34, Aug. 2006, [Peer-reviewed], [Lead author]
English, International conference proceedings

Study on Optical Properties of Metallic Sodium by Vacuum Ultra Violet in UVSOR (2)
M. Kawaguchi; J. Saito; H. Daido; T. Suemoto, UVSOR Activity Report 2019, III, 2, 85, 85, Nov. 2020, [Lead author]
English, Report research institution

Study on Optical Properties of Metallic Sodium by Vacuum Ultra Violet in UVSOR
M. Kawaguchi; J. Saito; H. Daido; T. Suemoto, UVSOR Activity Report 2018, III, 2, 89, 89, Apr. 2019, [Lead author]
English, Introduction research institution

Toward for improvement of sodium safety in a fast reactor
Munemichi Kawaguchi, Tsuruganoshiki, 114, 4, 4, Mar. 2017, [Invited], [Lead author]
Japanese, Introduction research institution

Study of the Impurity Effect on Wetting Property by Liquid Sodium
河口宗道, 日本原子力研究開発機構JAEA-Review(Web), 2012, 2013-035, 2-1 (WEB ONLY), 293, Dec. 2013, [Lead author]
ナトリウム中目視検査装置（USV）の高度化研究において、液体ナトリウムとUSVセンサとの濡れ性に課題があると考えている。高速炉内の液体ナトリウムには不純物が含まれるため、液体ナトリウムに不純物が含まれる場合の濡れ性の変化について考察を行ったので、報告するものである。, Atomic Energy Society of Japan, Japanese, Report research institution

Aiming at Improved Visualization Technology for Reactor Structures
Munemichi Kawaguchi, JAEA R&D Review 2013, 2, 36, 36, Nov. 2013, [Invited], [Lead author]
Japanese, Introduction research institution, 12133761

液体ナトリウムによる金属メッキ試験体の反応性濡れ
河口宗道, 日本原子力研究開発機構JAEA-Review(Web), 2012-039, 2-1 (WEB ONLY), Nov. 2012, [Lead author]
Japanese, Report research institution

原子力協定の下で高速炉協力を行うための要件とは 日本とカザフスタンの高速炉に関する取極を例に
河口宗道, ΑΤΟΜΟΣ, 53, 12, 841, 844, 01 Dec. 2011, [Lead author]
日本原子力学会, Japanese, Introduction scientific journal

Experimental study on aerosol decontamination factors of pool scrubbing
MIWA Kotaro; KAWAGUCHI Munemichi; SAWA Kazuhiro
The Proceedings of the National Symposium on Power and Energy Systems, 2025, The Japan Society of Mechanical Engineers, Japanese
2025 - 2025, In this study, the decontamination factor (DF) was measured using Cu aerosols (8.9 g/cm3) and Al aerosols (2.7 g/cm3) of different densities and the experimental values were compared with the calculated values using model equations. In the evaluation of DF with respect to water depth, C/E, the ratio of the calculated value to the experimental value, was lower than the experimental value for almost all water depths. In the evaluation of DF with respect to particle size, DF for Cu and Al generally showed the same trend. For particle sizes 0-0.3 μm, C/E exceeded 1 in many cases, and for particle sizes 0.3-2.0 μm, C/E was less than 0.7, indicating that the calculated model did not reflect well the increase in DF with increasing particle size.

Study on the Decontamination Factor Model of Gaseous Radioactive Substances in Pool Scrubbing: (Experiment of CO₂-pool scrubbing in NaOH solution)
KAWAGUCHI Munemichi; WAKABAYASHI Shun; SAWA Kazuhiro
The Proceedings of the National Symposium on Power and Energy Systems, 2025, The Japan Society of Mechanical Engineers, Japanese
2025 - 2025, Considering elaborate research on CO₂ transfer coefficients in NaOH aqueous, we conducted CO₂-pool scrubbing experiments and a simple calculation to confirm the accuracy of the calculation models. This experiment obtained quantitative data that the decontamination factor increased with the NaOH concentration. The simple calculation traced the experimental values by considering the decrease of the CO₂ bubble diameter with dissolution. In the next step, we plan to develop the calculation code that divides the NaOH concentration distribution along the pool depth for elaborate calculations.

Experimental study on aerosol decontamination factors of pool scrubbing
三輪虹太朗; 河口宗道; 澤和弘
日本原子力学会春の年会予稿集(CD-ROM), 2025
2025 - 2025

Experimental and simulation studies on aerosolization using a dry dispersion method
河口宗道; 三輪虹太朗; 澤和弘
日本原子力学会春の年会予稿集(CD-ROM), 2025
2025 - 2025

Study on treatment method of radioactive concrete waste by heating and rubbing method
束河慶吾; 河口宗道; 澤和弘
日本原子力学会春の年会予稿集(CD-ROM), 2025
2025 - 2025

Study on aerosol generation and supply technology (1) Investigation of aerosol generation and supply technology with wet dispersion method
河口宗道; 甲斐康太朗; 澤和弘; 佐藤理花; 清野裕
日本原子力学会秋の大会予稿集(CD-ROM), 2024
2024 - 2024

Study on Aerosol Generation and Supply Technology (2) Performance confirmation on wet dispersion method using TiO₂ particles
甲斐康太郎; 河口宗道; 澤和弘; 佐藤理花; 清野裕
日本原子力学会秋の大会予稿集(CD-ROM), 2024
2024 - 2024

Study on Moisture Transfer in Heated Concrete
岡本凌吾; 河口宗道; 澤和弘
日本原子力学会秋の大会予稿集(CD-ROM), 2024
2024 - 2024

Study of treatment methods for radioactive contaminated concrete
河口宗道
日本原子力学会春の年会予稿集(CD-ROM), 2024
2024 - 2024

ベイズ推定を用いた多質点系構造物の地震損傷評価手法の開発
川又浩世; 張承賢; 河口宗道; 澤和弘
日本原子力学会 北海道支部 第40回研究発表会, 17 Feb. 2023, Japanese, Oral presentation

粒子法を用いたナトリウム冷却高速炉におけるナトリウム―水反応に起因する反応ジェット挙動の評価
東ヶ﨑駿; 張承賢; 河口宗道; 澤和弘
日本原子力学会 北海道支部 第40回研究発表会, 17 Feb. 2023, Japanese, Oral presentation

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
日本原子力学会和文論文誌(Web), 2023
2023 - 2023

Prediction of Pore Generation for Simulant B₂O₃-UO₂ Fuel Debris Using Multiphase-field Method
河口宗道; 河口宗道; 宇埜正美; JANG Sunghyon; 澤和弘
日本原子力学会秋の大会予稿集(CD-ROM), 2023
2023 - 2023

Evaluation of human error probability in cognitive and diagnostic tasks as a criterion for considering environmental effects
三輪虹太朗; 河口宗道; 澤和弘; JANG Sunghyon
日本原子力学会秋の大会予稿集(CD-ROM), 2023
2023 - 2023

Evaluation on Seismic damage Inference for mass-spring damper structure using Bayesian Theorem
川又浩世; JANG Sunhyon; 河口宗道; 澤和弘; 松中修平; 町田秀夫
日本原子力学会秋の大会予稿集(CD-ROM), 2023
2023 - 2023

A Multi-unit Risk Assessment Using time and spatial depedent Human Error Probability
JANG Sunghyon; 河口宗道; 澤和弘
日本原子力学会秋の大会予稿集(CD-ROM), 2023
2023 - 2023

Evaluation on Temperature of Reaction Jet caused by Sodium-water Reaction in Steam Generator of Sodium-Cooled Fast Reactor Using Particle Method
東ヶ崎駿; JANG Sunghyon; 河口宗道; 澤和弘; 小坂亘; 内堀昭寛; 岡野靖
日本原子力学会秋の大会予稿集(CD-ROM), 2023
2023 - 2023

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), Aug. 2022, English
Aug. 2022 - Aug. 2022

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, Atomic Energy Society of Japan, Japanese
2022 - 2022, 12133761

Sodium Discharge Test of Dummy Fuel Assembly
河口宗道; 平川康; 杉田裕亮; 山口裕
日本原子力学会春の年会予稿集(CD-ROM), 2022
2022 - 2022

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 - 2021

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 - 2021

A Study on Thermal Decomposition Behavior of Sodium Hydride with TG-DTA
河口宗道
日本原子力学会春の年会予稿集(CD-ROM), 2020
2020 - 2020

高速炉格納容器内事象解析コードCONTAIN‐LMRの開発 ナトリウム‐コンクリート反応解析モデルの検証
河口宗道; 山本郁夫; 清野裕
日本原子力学会春の年会予稿集(CD-ROM), 04 Mar. 2019, Japanese

ナトリウム冷却高速炉における格納容器破損防止対策の有効性評価技術の開発(20)ナトリウム‐コンクリート反応実験のまとめ
河口宗道; 宮原信哉; 宇埜正美
日本原子力学会秋の大会予稿集(CD-ROM), 29 Aug. 2017, Japanese

ナトリウム冷却高速炉における格納容器破損防止対策の有効性評価技術の開発(17)全体成果の概要
宇埜正美; 青柳光裕; 渡辺正; 山本郁夫; 河口宗道; 土井大輔; 伊藤啓; 伊藤啓; 矢田浩基; 安藤勝訓; 月森和之
日本原子力学会秋の大会予稿集(CD-ROM), 29 Aug. 2017, Japanese

ナトリウム冷却高速炉における格納容器破損防止対策の有効性評価技術の開発(14)Na‐コンクリート反応の自己終息挙動
河口宗道; 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), 09 Mar. 2017, Japanese

ナトリウム冷却高速炉における格納容器破損防止対策の有効性評価技術の開発(13)Na‐コンクリート反応過程のシミュレーション
河口宗道; 河口宗道; 宮原信哉; 宇埜正美
日本原子力学会秋の大会予稿集(CD-ROM), 26 Aug. 2016, Japanese

ナトリウム冷却高速炉における格納容器破損防止対策の有効性評価技術の開発(8)熱力学計算によるナトリウム存在下のデブリの相平衡状態の評価
山本郁夫; 宇埜正美; 宮原信哉; 河口宗道
日本原子力学会春の年会予稿集(CD-ROM), 16 Mar. 2016, Japanese

ナトリウム冷却高速炉における格納容器破損防止対策の有効性評価技術の開発(7)フェーズフィールド法によるナトリウムとコンクリートの反応解析
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), 16 Mar. 2016, Japanese

ナトリウム冷却高速炉における格納容器破損防止対策の有効性評価技術の開発(13)Na-コンクリート反応過程のシミュレーション
河口宗道; 河口宗道; 宮原信哉; 宇埜正美
日本原子力学会秋の大会予稿集(CD-ROM), 2016
2016 - 2016

Na‐コンクリート反応生成物の微視的状態に関する研究
河口宗道; 宮原信哉; 宇埜正美
化学工学会秋季大会研究発表講演要旨集(CD-ROM), 09 Sep. 2015, Japanese

高速炉格納容器内事象解析コードCONTAIN‐LMRの開発(3)デブリ関連計算モデルの開発及び妥当性確認
清野裕; 河口宗道; 泉啓太郎
日本原子力学会春の年会予稿集(CD-ROM), 05 Mar. 2015, Japanese

ナトリウム冷却高速炉における格納容器破損防止対策の有効性評価技術の開発(1)全体概要
宇埜正美; 大野修司; 河口宗道; 土井大輔; 月森和之
日本原子力学会春の年会予稿集(CD-ROM), 05 Mar. 2015, Japanese

ナトリウム冷却高速炉における格納容器破損防止対策の有効性評価技術の開発(3)炉心溶融物/ナトリウムとコンクリート構造物との反応挙動
河口宗道; 小西賢介; 宇埜正美; 山本郁夫; 宮原信哉
日本原子力学会春の年会予稿集(CD-ROM), 05 Mar. 2015, Japanese

Na‐コンクリート反応の研究
河口宗道; 土井大輔; 増山大輔; 清野裕; 小西賢介; 宮原信哉
日本原子力学会秋の大会予稿集(CD-ROM), 22 Aug. 2014, Japanese

液体金属ナトリウムによる金メッキの反応性濡れのシミュレーション
河口宗道; 浜田広次
日本原子力学会秋の大会予稿集(CD-ROM), 20 Aug. 2013, Japanese

Wetting of metallic plated stainless steels by liquid metal sodium
Kawaguchi, Munemichi; Hamada, Hirotsugu
日本原子力学会関西支部第8回若手研究者による研究発表会, Feb. 2013, Japanese
大阪, Since liquid sodium is used as a coolant of sodium-cooled fast breeder reactors, the optical visual inspection in the inner of the reactor is difficult. Then, Japan Atomic Energy Agency has developed the under sodium viewer (USV) for the purpose of visually inspecting, and it is important to understand the wetting mechanism between the liquid sodium and USV sensor surface. In order to improve the wettability, Au plating is used in the surface of USV sensor at the present. In this study, some various plating specimens including Au plating were manufactured, and their wettability by liquid sodium were measured experimentally. In the result, we confirmed that solubility of the plating is important parameter for the plating processing on the sodium wetting., [Domestic Conference]

Study of the inpurity effect on wetting property by liquid sodium
KAWAGUCHI Munemichi; HAMADA Hirotsugu
Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan, 03 Sep. 2012, Japanese
ナトリウム中目視検査装置（USV）の高度化研究において、液体ナトリウムとUSVセンサとの濡れ性に課題があると考えている。高速炉内の液体ナトリウムには不純物が含まれるため、液体ナトリウムに不純物が含まれる場合の濡れ性の変化について考察を行ったので、報告するものである。

高速炉の炉心損傷評価技術(レベル2PSA)の開発(13)格納容器内事象に関する評価手法の開発―ナトリウム‐コンクリート反応関連モデルの整備―
清野裕; 石川浩康; 大野修司; 河口宗道; 磯崎三喜男; 宮原信哉
日本原子力学会春の年会予稿集(CD-ROM), 09 Mar. 2010, Japanese

18pPSA-49
Araki R; Kawaguchi M; Kondo A; Tou H; Iga H; Sera M; Mignot J-M
Meeting Abstracts of the Physical Society of Japan, 2007, Japanese

28pUE-3 Ce main magnetic ordering phase in Ce_xNd_<1-x>B_6
Kawaguchi M; Tou H; Sera M; Iga H; Sakakibara T
Meeting Abstracts of the Physical Society of Japan, 2006, Japanese

27pTA-7 NQR/NMR Studies of magnetic ordered state in filled skutterudite, YbFe_4Sb_<12>
Kawaguchi M; TOU H; Sera M; Kojima K; Ikeno T; Ishikawa Y
Meeting Abstracts of the Physical Society of Japan, 2005, Japanese

21aYG-2 Competition between anisotropic gap coming from AF ordering and Kondo effect in Ce_xNd_<1-x>B_6
Kawaguchi M; Sera M; Kim M; Iga H
Meeting Abstracts of the Physical Society of Japan, 2005, Japanese

12aRC-2 Multipolar interactions on the IC-C phase transition in Ce_xPr_<1-x>B_6
Sera M; Kawaguchi M; Kishimoto S; Kondo A; Shimono Y; Tsugawa N; Kim Moo Sung; Tou H; Iga F
Meeting Abstracts of the Physical Society of Japan, 2004, Japanese

原子力システム安全工学特論, 2024年, 修士課程, 工学院

沸騰・二相流特論, 2024年, 修士課程, 工学院

沸騰・二相流特論, 2024年, 修士課程, 工学院

原子力・エネルギーシステム特論, 2024年, 修士課程, 工学院

原子力システム安全工学特論, 2024年, 博士後期課程, 工学院

沸騰・二相流特論, 2024年, 博士後期課程, 工学院

沸騰・二相流特論, 2024年, 博士後期課程, 工学院

原子力・エネルギーシステム特論, 2024年, 博士後期課程, 工学院

伝熱工学Ⅰ, 2024年, 学士課程, 工学部

安全工学, 2024年, 学士課程, 工学部

エネルギー工学概論, 2024年, 学士課程, 工学部

環境エネルギー工学, 2024年, 学士課程, 工学部

科学・技術の世界, 2024年, 学士課程, 全学教育

2025 - Present
日本機械学会

科研費
科学研究費
Apr. 2026 - Mar. 2029
河口宗道
日本学術振興会, 基盤C, 北海道大学, Principal investigator, 26K07382

オープン教材を活用した原子力規 制人材育成プログラム
原子力規制人材育成事業
2023 - 2027
千葉豪
北海道大学, Coinvestigator

放射性コンクリート廃棄物の減容を考慮した合理的処理・処分方法の検討
英知を結集した原子力科学技術・人材育成推進事業 課題解決型廃炉研究プログラム
2023 - 2026
小崎完
北海道大学、福井大学、電力中央研究所、日本原子力研究開発機構, Coinvestigator

Development of estimation technology for availability of measure for failure of containment vessel in sodium cooled fast reactor
原子力システム研究開発事業
Oct. 2013 - Mar. 2017
uno masayoshi
Japan science and technology agency, Competitive research funding