Akikazu Kurihara - My portal

Profile Information

Affiliation: Japan Atomic Energy Agency

J-GLOBAL ID: 202101003926492074
researchmap Member ID: R000017481

Papers

Transient behavior of multi-dimensional core cooling by D-DHX in sodium-cooled fast reactors

Ezure Toshiki, Akimoto Yuta, Onojima Takamitsu, Kurihara Akikazu, Tanaka Masaaki

Proceedings of 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) (Internet), 3652-3662, Aug, 2023 Peer-reviewed
Study on performance evaluation of self-actuated shutdown system for sodium-cooled fast reactor; Investigation on flow field around curie point electromagnet

Aizawa Kosuke, Hiyama Tomoyuki, Kobayashi Jun, Kurihara Akikazu

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 6, May, 2023 Peer-reviewed
Study on uncertainty evaluation methodology for decay heat removal experiment in sodium experimental facility

Akimoto Yuta, Ezure Toshiki, Onojima Takamitsu, Kurihara Akikazu

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 9, May, 2023 Peer-reviewed
Investigation on natural circulation behavior for decay heat removal in reactor vessel of sodium-cooled fast reactor under severe accident condition, 1; Effect of decay-heat conditions on natural circulation behavior under dipped-type DHX operation conditions

Tsuji Mitsuyo, Aizawa Kosuke, Kobayashi Jun, Kurihara Akikazu

Proceedings of 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12) (Internet), 6, Oct, 2022 Peer-reviewed
Investigation on natural circulation behavior for decay heat removal in reactor vessel of sodium-cooled fast reactor under severe accident condition, 2; Transient behavior under operations of multiple decay heat removal systems

Aizawa Kosuke, Tsuji Mitsuyo, Kobayashi Jun, Kurihara Akikazu

Proceedings of 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12) (Internet), 7, Oct, 2022 Peer-reviewed
Sodium-cooled Fast Reactors

Ohshima Hiroyuki, Morishita Masaki*, Aizawa Kosuke, Ando Masanori, Ashida Takashi, Chikazawa Yoshitaka, Doda Norihiro, Enuma Yasuhiro, Ezure Toshiki, Fukano Yoshitaka …

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631, Jul, 2022 Peer-reviewed
Investigation on natural circulation for decay heat removal in reactor vessel of sodium-cooled fast reactor

Aizawa Kosuke, Tsuji Mitsuyo, Kobayashi Jun, Kurihara Akikazu, Miyake Yasuhiro*, Nakane Shigeru*, Ishida Katsuji*

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet), 10, Apr, 2022 Peer-reviewed
Water experiments on thermal striping phenomena at the core outlet of an advanced sodium-cooled fast reactor, 2; Proposal of countermeasures to mitigate temperature fluctuations around radial blanket fuel assemblies

Kobayashi Jun, Aizawa Kosuke, Ezure Toshiki, Kurihara Akikazu, Tanaka Masaaki

Hozengaku, 20(3) 97-101, Oct, 2021 Peer-reviewed
Water experiments on thermal striping phenomena at the core outlet of an advanced sodium-cooled fast reactor, 1; Proposal of countermeasures to mitigate temperature fluctuations around control rods

Kobayashi Jun, Aizawa Kosuke, Ezure Toshiki, Kurihara Akikazu, Tanaka Masaaki

Hozengaku, 20(3) 89-96, Oct, 2021 Peer-reviewed
Droplet-entrainment phenomena affected by interfacial behavior of a high-speed gas jet into a liquid pool

Saito Masafumi*, Kaneko Akiko*, Abe Yutaka*, Uchibori Akihiro, Kurihara Akikazu, Takata Takashi*, Ohshima Hiroyuki

Proceedings of 28th International Conference on Nuclear Engineering (ICONE 28) (Internet), 7, Aug, 2021 Peer-reviewed
Experimental study on aerosol transport behavior in multiple cells with expandable connecting pipe for safety assessment of sodium-cooled fast reactors

Umeda Ryota, Kondo Toshiki, Kikuchi Shin, Kurihara Akikazu

Proceedings of 28th International Conference on Nuclear Engineering (ICONE 28) (Internet), 9, Aug, 2021 Peer-reviewed
Droplet entrainment by high-speed gas jet into a liquid pool

Sugimoto Taro*, Kaneko Akiko*, Abe Yutaka*, Uchibori Akihiro, Kurihara Akikazu, Takata Takashi, Ohshima Hiroyuki

Nuclear Engineering and Design, 380 111306\_1-111306\_11, Aug, 2021 Peer-reviewed
Experiments of self-wastage phenomena elucidation in steam generator tube of sodium-cooled fast reactor

Umeda Ryota, Shimoyama Kazuhito, Kurihara Akikazu

Nihon Genshiryoku Gakkai Wabun Rombunshi, 19(4) 234-244, Dec, 2020 Peer-reviewed
Study on cooling process in a reactor vessel of sodium-cooled fast reactor under severe accident; Velocity measurement experiments simulating operation of decay heat removal systems

Tsuji Mitsuyo, Aizawa Kosuke, Kobayashi Jun, Kurihara Akikazu, Miyake Yasuhiro*

Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 5, Aug, 2020 Peer-reviewed
Investigation on velocity distribution in the subchannels of pin bundle with wrapping wire; Evaluation of Reynolds number dependence in 3-pin bundle

Aizawa Kosuke, Hiyama Tomoyuki, Nishimura Masahiro, Kurihara Akikazu, Ishida Katsuji*

Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 8, Aug, 2020 Peer-reviewed
Effects of temperature fluctuation on PIV measurement of natural circulation flow field

Tsuji Mitsuyo, Aizawa Kosuke, Kobayashi Jun, Kurihara Akikazu, Miyake Yasuhiro*

Proceedings of 14th International Symposium on Advanced Science and Technology in Experimental Mechanics (14th ISEM'19) (USB Flash Drive), 4, Nov, 2019 Peer-reviewed
Study on multi-dimensional core cooling behavior of sodium-cooled fast reactors under DRACS operating conditions

Ezure Toshiki, Onojima Takamitsu, Tanaka Masaaki, Kobayashi Jun, Kurihara Akikazu, Kameyama Yuri*

Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) (USB Flash Drive), 3355-3363, Aug, 2019 Peer-reviewed
Improvement of steam generator tube failure propagation analysis code LEAP for evaluation of overheating rupture

Uchibori Akihiro, Yanagisawa Hideki*, Takata Takashi, Kurihara Akikazu, Hamada Hirotsugu, Ohshima Hiroyuki

Journal of Nuclear Science and Technology, 56(2) 201-209, Feb, 2019 Peer-reviewed
Measurement of Velocity Field in Five Jets Water Test (FIWAT) for thermal striping in sodium-cooled fast reactor

Aizawa Kosuke, Kobayashi Jun, Tanaka Masaaki, Kurihara Akikazu, Ishida Katsuji*, Nagasawa Kazuyoshi*

Proceedings of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11) (Internet), 10, Nov, 2018 Peer-reviewed
Evaluation of target-wastage in consideration of sodium-water reaction environment formed on the periphery of an adjacent tube in steam generator of sodium-cooled fast reactor

Kurihara Akikazu, Umeda Ryota, Shimoyama Kazuhito, Kikuchi Shin

Nihon Kikai Gakkai Rombunshu (Internet), 84(859) 17-00382\_1-17-00382\_11, Mar, 2018 Peer-reviewed

Misc.

Experimental study on prevention of high cycle thermal fatigue at the core outlet of advanced sodium-cooled fast reactor; Characteristics of temperature fluctuations and countermeasures to mitigate temperature fluctuations at a bottom of upper internal structure

Kobayashi Jun, Aizawa Kosuke, Ezure Toshiki, Nagasawa Kazuyoshi*, Kurihara Akikazu, Tanaka Masaaki

JAEA-Research 2022-009, 125, Jan, 2023
Experimental study on velocity distribution in the subchannels of a fuel pin bundle with wrapping wire; Evaluation of the characteristics of flow field in 3-pin bundle

Hiyama Tomoyuki, Aizawa Kosuke, Nishimura Masahiro, Kurihara Akikazu

JAEA-Research 2021-009, 29, Nov, 2021
Development of experimental database for decay heat removal system of sodium-cooled fast reactor; Uncertainty evaluation of temperature measurement data in PLANDTL-2 experiment

Akimoto Yuta, Ezure Toshiki, Onojima Takamitsu, Kurihara Akikazu

Dai-25-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 5, Jul, 2021
Material test data of SUS316 and SUS321, 1

Hashidate Ryuta, Kato Shoichi, Kurihara Akikazu

JAEA-Data/Code 2019-005, 117, Jul, 2019
Phenomenon elucidation experiment for target wastage caused in steam generator of sodium-cooled fast reactor; Corrosion experiment in flowing high-temperature sodium hydroxide environment

Umeda Ryota, Shimoyama Kazuhito, Kurihara Akikazu

JAEA-Technology 2017-018, 70, Aug, 2017
Development of LEAP-III code for evaluation of long-time event progress under tube failure accident in steam generators

Uchibori Akihiro, Yanagisawa Hideki*, Takata Takashi, Kurihara Akikazu, Hamada Hirotsugu, Ohshima Hiroyuki

JAEA-Research 2017-007, 61, Jul, 2017
Rapid heating rupture experiment using the high chromium steel tubes

Umeda Ryota, Kurihara Akikazu, Shimoyama Kazuhito

JAEA-Technology 2016-030, 50, Dec, 2016
Development of experimental method for self-wastage behavior in sodium-water reaction; Development of test rig (SWAT-2R) and study for experimental procedure

Abe Yuta, Shimoyama Kazuhito, Kurihara Akikazu

JAEA-Technology 2014-026, 40, Jul, 2014
Heat transfer characteristics inside an adjacent tube thermally-affected by sodium-water reaction in steam generator of sodium-cooled commercial fast reactor

Kurihara Akikazu, Umeda Ryota, Yanagisawa Hideki*, Ohshima Hiroyuki

Dai-16-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, 9-10, Jun, 2011
Thermal analysis experiment for elucidating sodium-water chemical reaction mechanism in steam generator of sodium-cooled fast reactor

Kikuchi Shin, Kurihara Akikazu, Ohshima Hiroyuki

Dai-16-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, 15-16, Jun, 2011
Construction of interfacial area concentration model for sodium-water reaction

Yoshikawa Ryuji, Ohshima Hiroyuki, Hamada Hirotsugu, Kurihara Akikazu, Uchibori Akihiro

JAEA-Research 2008-055, 24, Jun, 2008
Thermal-Hydraulic Characteristics of Sodium-Water Reaction Jet; Effect of Cover Gas Pressure on Temperature Distribution

Futagami Satoshi, Kurihara Akikazu, Yatabe Toshio

JNC TN9400 2005-042, 82, Aug, 2005
Quasi-Steady Pressure Analysis in Intermediate Water Leak Rate with SWAC-13 Module in SWACS code; Validation of Sodium-Water reaction test (SWAT-3 Run-13)

Ono Isao*, Kurihara Akikazu

JNC TN9400 2005-047, 98, Aug, 2005
Study of thermal influence on tubes due to sodium-water reactions in LMFBR steam generator

Hamada Hirotsugu, Kurihara Akikazu, Nishimura Masahiro

Proceedings of 12th International Conference on Nuclear Engineering (ICONE-12) (CD-ROM), Jan, 2004
Heat Transfer Characteristics of High-Temperature Liquid Metal Two-Phase Jet Accompanied by Reaction Heating

Hamada Hirotsugu, Kurihara Akikazu

Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(1) 44-50, Jan, 2004
Test results of Run-1 and Run-2 in Steam Generator Safety Test Facility (SWAT-3)

Kurihara Akikazu, Yatabe Toshio, Hiroi Hiroshi, Tanabe Hiromi

JNC TN9400 2003-060, 236, Jul, 2003
Development of Blow Down Model for the LEAP Code; Validation by Data of Sodium-Water Reaction Tests

Jitsu Koji, Ono Isao*, Kawada Koji, Kurihara Akikazu, Yatabe Toshio

JNC TN9400 2003-062, 84, Jun, 2003
Development of tube rupture evaluation code for FBR steam generator (II); Modification of heat transfer model in sodium side

Hamada Hirotsugu, Kurihara Akikazu

JNC TN9400 2003-031, 96, May, 2003
Sodium-water reaction test to confirm thermal influence on heat transfer tubes

Nishimura Masahiro, Shimoyama Kazuhito, Kurihara Akikazu, Seino Hiroshi

JNC TN9400 2003-014, 167, Mar, 2003
The Burst Behavior of the Heat Transfer Tube under an Internal Pressure Load with Extraordinarily High Temperature Condition

Hamada Hirotsugu, Kurihara Akikazu

Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(1) 32-38, Jan, 2003

Presentations

117

Study on performance evaluation of Self-Actuated Shutdown System (SASS) in sodium-cooled fast reactor, 2; Flow field measurement around a temperature sensing alloy

Yamasaki Ryota, Aizawa Kosuke, Kobayashi Jun, Kurihara Akikazu

日本原子力学会2023年秋の大会
PLANDTL-2 experiment for evaluation of decay heat removal in sodium-cooled fast reactors; Effect of inter-subassembly gap flow under interruption of flow through fuel assemblies

Ezure Toshiki, Akimoto Yuta, Tsuji Mitsuyo, Kurihara Akikazu, Tanaka Masaaki

日本原子力学会2023年春の年会
Validation of liquid droplet entrainment and transport model in sodium-water reaction analysis code, SERAPHIM

Uchibori Akihiro, Shiina Yoshimi*, Kurihara Akikazu, Okano Yasushi, Saito Masafumi*, Kaneko Akiko*, Abe Yutaka*

日本機械学会2022年度年次大会
Water experiments on thermal striping phenomena at the core outlet of an advanced sodium-cooled fast reactor; Simultaneous temperature measurement in the circumferential direction of around the flow hole of the core instrumentation support plate

Kobayashi Jun, Aizawa Kosuke, Ezure Toshiki, Kurihara Akikazu, Tanaka Masaaki

日本保全学会第18回学術講演会
Water experiments on thermal striping phenomena at the core outlet of an advanced sodium-cooled fast reactor

Kobayashi Jun, Aizawa Kosuke, Ezure Toshiki, Kurihara Akikazu, Tanaka Masaaki

日本保全学会第12回学会賞(論文賞)講演会
Effect of a high-speed gas jet behavior into a liquid pool on droplet entrainment phenomena

Saito Masafumi*, Kaneko Akiko*, Abe Yutaka*, Uchibori Akihiro, Kurihara Akikazu, Ohshima Hiroyuki

第66回理論応用力学講演会
PLANDTL-2 experiment for evaluation of decay heat removal in sodium-cooled fast reactors; Transient characteristics of core cooling behavior by dipped-type direct heat exchanger

Ezure Toshiki, Akimoto Yuta, Onojima Takamitsu, Kurihara Akikazu, Tanaka Masaaki

日本原子力学会2022年春の年会
Study on performance evaluation of self-actuated shutdown system for sodium-cooled fast reactor; Evaluation on flow field around temperature sensing part

Aizawa Kosuke, Hiyama Tomoyuki, Kobayashi Jun, Kurihara Akikazu

日本原子力学会2022年春の年会
Study on cooling process of decay heat removal systems in a reactor vessel of sodium-cooled fast reactor by scaled water experiments, 6; Thermal hydraulics behavior under operations of multiple decay heat removal systems

Tsuji Mitsuyo, Aizawa Kosuke, Kobayashi Jun, Kurihara Akikazu

日本原子力学会2022年春の年会
Evaluation of a high-speed gas jet behavior into a liquid pool and entrained droplets phenomena

Saito Masafumi*, Kaneko Akiko*, Uchibori Akihiro, Kurihara Akikazu, Takata Takashi*, Ohshima Hiroyuki

日本原子力学会2021年秋の大会
Study on performance evaluation of self-actuated shutdown system for sodium-cooled fast reactor; Measurement of flow field around temperature sensing part

Hiyama Tomoyuki, Aizawa Kosuke, Kobayashi Jun, Kurihara Akikazu, Nagasawa Kazuyoshi*, Onuma Hideyoshi*

日本原子力学会2021年秋の大会
Study on cooling process of decay heat removal systems in a reactor vessel of sodium-cooled fast reactor by scaled water experiments, 5; Transient behavior under operations of multiple decay heat removal systems

Aizawa Kosuke, Tsuji Mitsuyo, Kobayashi Jun, Kurihara Akikazu, Nakane Shigeru*, Onuma Hideyoshi*

日本原子力学会2021年秋の大会
Droplet entrainment phenomena affected by interfacial behavior of a high speed gas jet into a liquid pool

Saito Masafumi*, Kaneko Akiko*, Abe Yutaka*, Uchibori Akihiro, Kurihara Akikazu, Takata Takashi, Ohshima Hiroyuki

日本原子力学会2021年春の年会
Study on cooling process of decay heat removal systems in a reactor vessel of sodium-cooled fast reactor by scaled water experiments, 4; Effect of heat generation condition on natural convection flow field in reactor vessel

Tsuji Mitsuyo, Aizawa Kosuke, Kobayashi Jun, Kurihara Akikazu, Nakane Shigeru*, Ishida Katsuji*

日本原子力学会2021年春の年会
Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor, 20; Numerical simulation of experiment on aerosol transport behavior in multi-cell facility connected with horizontal or vertical pipe

Kikuchi Norihiro, Umeda Ryota, Kikuchi Shin, Kurihara Akikazu, Takata Takashi, Ohshima Hiroyuki

日本原子力学会2020年秋の大会
Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor, 19; Experimental study on aerosol transport behavior in multi-cell facility connected with horizontal or vertical pipe

Umeda Ryota, Kikuchi Norihiro, Kurihara Akikazu, Kikuchi Shin, Takata Takashi, Ohshima Hiroyuki

日本原子力学会2020年秋の大会
Visualization study on behavior of entrained droplets in a high-speed gas jet into a liquid pool

Saito Masafumi*, Kaneko Akiko*, Abe Yutaka*, Uchibori Akihiro, Kurihara Akikazu, Takata Takashi, Ohshima Hiroyuki

日本原子力学会2020年秋の大会
Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor, 18; Physical property measurement of reaction product aerosol at sodium oxygen reaction surface

Deguchi Yoshihiro*, Kikuchi Shin, Kurihara Akikazu, Takata Takashi, Ohshima Hiroyuki

日本原子力学会2020年秋の大会
Development of multi-level, multi-scenario simulation systems for sodium cooled fast reactor, 17; Reaction behavior evaluation based on fundamental experiments for sodium-concrete reaction

Kikuchi Shin, Koga Nobuyoshi*, Kurihara Akikazu, Takata Takashi, Ohshima Hiroyuki

日本原子力学会2020年秋の大会
Study on cooling process of decay heat removal systems in a reactor vessel of sodium-cooled fast reactor by scaled water experiments, 3; Temperature measurement in a reactor vessel simulating operation of reactor vessel auxiliary cooling system

Aizawa Kosuke, Tsuji Mitsuyo, Kobayashi Jun, Kurihara Akikazu, Nakane Shigeru*, Ishida Katsuji*

日本原子力学会2020年春の年会