Kurihara Akikazu

クリハラアキカズ | Kurihara Akikazu

Affiliation and department：
Papers (54)：

Ezure Toshiki, Akimoto Yuta, Onojima Takamitsu, Kurihara Akikazu, Tanaka Masaaki. Transient behavior of multi-dimensional core cooling by D-DHX in sodium-cooled fast reactors. Proceedings of 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) (Internet). 2023. 3652-3662
Aizawa Kosuke, Hiyama Tomoyuki, Kobayashi Jun, Kurihara Akikazu. Study on performance evaluation of self-actuated shutdown system for sodium-cooled fast reactor; Investigation on flow field around curie point electromagnet. Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet). 2023. 6
Akimoto Yuta, Ezure Toshiki, Onojima Takamitsu, Kurihara Akikazu. Study on uncertainty evaluation methodology for decay heat removal experiment in sodium experimental facility. Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet). 2023. 9
Tsuji Mitsuyo, Aizawa Kosuke, Kobayashi Jun, Kurihara Akikazu. 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. Proceedings of 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12) (Internet). 2022. 6
Aizawa Kosuke, Tsuji Mitsuyo, Kobayashi Jun, Kurihara Akikazu. 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. Proceedings of 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12) (Internet). 2022. 7

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MISC (22)：

Kobayashi Jun, Aizawa Kosuke, Ezure Toshiki, Nagasawa Kazuyoshi*, Kurihara Akikazu, Tanaka Masaaki. 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. JAEA-Research 2022-009. 2023. 125
Hiyama Tomoyuki, Aizawa Kosuke, Nishimura Masahiro, Kurihara Akikazu. 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. JAEA-Research 2021-009. 2021. 29
Akimoto Yuta, Ezure Toshiki, Onojima Takamitsu, Kurihara Akikazu. Development of experimental database for decay heat removal system of sodium-cooled fast reactor; Uncertainty evaluation of temperature measurement data in PLANDTL-2 experiment. Dai-25-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet). 2021. 5
Hashidate Ryuta, Kato Shoichi, Kurihara Akikazu. Material test data of SUS316 and SUS321, 1. JAEA-Data/Code 2019-005. 2019. 117
Umeda Ryota, Shimoyama Kazuhito, Kurihara Akikazu. Phenomenon elucidation experiment for target wastage caused in steam generator of sodium-cooled fast reactor; Corrosion experiment in flowing high-temperature sodium hydroxide environment. JAEA-Technology 2017-018. 2017. 70

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Lectures and oral 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
(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
(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
(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
(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
(日本保全学会第12回学会賞(論文賞)講演会)

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