Zobrazeno 1 - 10
of 39
pro vyhledávání: '"Ken Ichi Matsuba"'
Publikováno v:
Mechanical Engineering Journal, Vol 8, Iss 4, Pp 21-00172-21-00172 (2021)
In order to improve the safety of nuclear power plants, it is necessary to make sure measures against their severe accidents. Especially, in the case of a sodium-cooled fast reactor, there is a possibility that molten core material would be discharge
Externí odkaz:
https://doaj.org/article/2b733b23142447b898c29f235e84eb23
Publikováno v:
Mechanical Engineering Journal, Vol 4, Iss 3, Pp 16-00597-16-00597 (2017)
For the prototype sodium-cooled fast reactor, MONJU, the mechanical energy and structural response under energetics caused by neutronic power excursion during Unprotected Loss of Flow (ULOF) accident were preliminarily evaluated. In the first licensi
Externí odkaz:
https://doaj.org/article/029d69babe974376bf8abaf7ec1bda13
Autor:
Ken-ichi MATSUBA, Kenji KAMIYAMA, Jun-ichi TOYOOKA, Yoshiharu TOBITA, Vladimir A. ZUYEV, Alexander A. KOLODESHNIKOV, Yuri S. VASSILIEV
Publikováno v:
Mechanical Engineering Journal, Vol 3, Iss 3, Pp 15-00595-15-00595 (2016)
In a probable scenario for core disruptive accidents of Sodium-cooled Fast Reactors (SFRs), it is foreseen that molten core material would be discharged into lower sodium plenums through control rod guide tubes. Such material relocation might lead to
Externí odkaz:
https://doaj.org/article/9877750203b441dda8153840459b7097
Autor:
Kei Ito, Naoya Odaira, Akito Fujitsu, Kenji Kamiyama, Yuya Imaizumi, Daisuke Ito, Ken-ichi Matsuba, Yasushi Saito
Publikováno v:
The Proceedings of the Fluids engineering conference. 2020:OS12-08
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a42c102990132a7ed23798fbd6302758
https://doi.org/10.1299/jsmefed.2020.os12-08
https://doi.org/10.1299/jsmefed.2020.os12-08
Autor:
Songbai Cheng, Ken-ichi Matsuba, Mikio Isozaki, Kenji Kamiyama, Tohru Suzuki, Yoshiharu Tobita
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2015 (2015)
Studies on local fuel-coolant interactions (FCI) in a molten pool are important for the analyses of severe accidents that could occur for sodium-cooled fast reactors (SFRs). To clarify the mechanisms underlying this interaction, in recent years, seve
Externí odkaz:
https://doaj.org/article/e3217409a61e4e5ca734ffb8089389e2
Publikováno v:
Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation.
In order to obtain experimental knowledge on fragmentation and cooling behavior of molten core material discharged into regions where the depth and volume of sodium are limited, a series of out-of-pile experiments using alumina (Al2O3) as a simulated
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5050a87ce0363b83325d40c762032958
https://doi.org/10.1115/icone28-64500
https://doi.org/10.1115/icone28-64500
In order to improve the safety of nuclear power plants, it is necessary to make sure measures against their severe accidents. Especially, in the case of a sodium-cooled fast reactor (SFR), there is a possibility of significant energy release due to f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::acab03b40aa9b53f82d5d4b1ef782c4f
https://doi.org/10.1115/1.0000381v
https://doi.org/10.1115/1.0000381v
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2021, 151, pp.107881-. ⟨10.1016/j.anucene.2020.107881⟩
Annals of Nuclear Energy, 2021, 151, pp.107881-. ⟨10.1016/j.anucene.2020.107881⟩
Annals of Nuclear Energy, Elsevier Masson, 2021, 151, pp.107881-. ⟨10.1016/j.anucene.2020.107881⟩
Annals of Nuclear Energy, 2021, 151, pp.107881-. ⟨10.1016/j.anucene.2020.107881⟩
High-resolution X-ray imaging was employed at the JAEA MELT facility to visualize a kilogram-scale interaction between a jet of high temperature molten stainless steel and sodium, mimicking a sodium-cooled fast-neutron reactor in the aftermath of a c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7b01377760e8d9f04180d8a12c67032f
https://hal.archives-ouvertes.fr/hal-03493093
https://hal.archives-ouvertes.fr/hal-03493093
Autor:
Frédéric Payot, Kenji Kamiyama, Michael S. Johnson, Shifali Singh, Yuki Emura, Ken-ichi Matsuba, Christophe Journeau
Publikováno v:
EPJ Web of Conferences, Vol 253, p 06005 (2021)
During a severe accident in either sodium-cooled or water-cooled nuclear reactors, jets of molten nuclear fuel may impinge on the coolant resulting in fuel-coolant interactions (FCI). Experimental programs are being conducted to study this phenomenol
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8e1faee0df626c455edc02136d1cf2a6
https://www.epj-conferences.org/articles/epjconf/pdf/2021/07/epjconf_animma2021_06005.pdf
https://www.epj-conferences.org/articles/epjconf/pdf/2021/07/epjconf_animma2021_06005.pdf
Autor:
Yuya IMAIZUMI, Mitsuhiro AOYAGI, Kenji KAMIYAMA, Ken-ichi MATSUBA, Assan S. AKAEV, Anatoly V. MIKISHA, Viktor V. BAKLANOV, Alexandr D. VURIM
Publikováno v:
The Proceedings of the National Symposium on Power and Energy Systems. :A222
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b8c51a8b8f685ba4c0147f2640df8b4b
https://doi.org/10.1299/jsmepes.2022.26.a222
https://doi.org/10.1299/jsmepes.2022.26.a222