Zobrazeno 1 - 10
of 18
pro vyhledávání: '"Keiko Chitose"'
Autor:
Naoyuki Takaki, Keiko Chitose
Publikováno v:
Annals of Nuclear Energy. 127:364-371
The core geometry of sodium-cooled fast spectrum reactor (SFR) is not generally in its most reactive configuration. Therefore, the study of postulated Core Disruptive Accident (CDA) has been recognized as one of the most important themes for SFR. The
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8fbb3d02dd18c7c0532c5db3fcdb4c61
https://doi.org/10.1016/j.anucene.2018.12.022
https://doi.org/10.1016/j.anucene.2018.12.022
Publikováno v:
Energy Procedia. 131:86-93
The objective of the present study is to evaluate the temperature profile of a convex shaped reactor core to confirm the thermal hydraulic feasibility. The convex core configuration intends to achieve negative reactivity insertion by fuel compaction
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9563ae07bc92ff5f0a7bec8edad29dda
http://t2r2.star.titech.ac.jp/cgi-bin/publicationinfo.cgi?q_publication_content_number=CTT100758093
http://t2r2.star.titech.ac.jp/cgi-bin/publicationinfo.cgi?q_publication_content_number=CTT100758093
Publikováno v:
Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs.
In sodium-cooled fast reactors, the core is not arranged in its most reactive configuration. In this case, when the fuel melts to form a molten pool, the recriticality may occur by positive reactivity insertion due to core compaction. To prevent such
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b628433cff90d475f7950ab77d5d2c1b
https://doi.org/10.1115/icone26-81331
https://doi.org/10.1115/icone26-81331
Publikováno v:
Nuclear Engineering and Design. 238:1996-2004
It is important to estimate the cooling possibility of the molten jet in coolant during a core disruptive accident (CDA) of a fast breeder reactor (FBR). In the present study, the molten jet of U-alloy78 simulating the core material is injected into
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9f8b5a8a9091e632d3e161e37cdccf98
https://doi.org/10.1016/j.nucengdes.2007.11.011
https://doi.org/10.1016/j.nucengdes.2007.11.011
Publikováno v:
Cryogenics. 48:238-247
The 3-D structure of the liquid atomization behavior of an LH 2 jet flow through a pinhole nozzle is numerically investigated and visualized by a new type of integrated simulation technique. The present computational fluid dynamics (CFD) analysis foc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e2484964fc7dae7cb2a84cbe97066981
https://doi.org/10.1016/j.cryogenics.2008.03.006
https://doi.org/10.1016/j.cryogenics.2008.03.006
Autor:
Yuta Uchiyama, Eiji Matsuo, Keiko Chitose, Hideki Nariai, Kazuhiro Itoh, Kazuya Koyama, Yutaka Abe, Akiko Fujiwara
Publikováno v:
The Proceedings of the National Symposium on Power and Energy Systems. :513-516
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6500d5e3a355fb4cbb49e73be3c70777
https://doi.org/10.1299/jsmepes.2008.13.513
https://doi.org/10.1299/jsmepes.2008.13.513
Autor:
Keiji Takeno, Keiko Chitose, Kazuki Okabayashi, T. Nonaka, Akinori Kouchi, Kazuaki Hashiguchi
Publikováno v:
International Journal of Hydrogen Energy. 32:2144-2153
To make “Hydrogen vehicles and refueling station systems” fit for public use, research on hydrogen safety and designing mitigation measures are significant. For compact storage, it is planned to store under high pressure up to 40 MPa at the refue
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4a581e2d22f68b305e072828a2c229ac
https://doi.org/10.1016/j.ijhydene.2007.04.018
https://doi.org/10.1016/j.ijhydene.2007.04.018
Autor:
Kazuya Koyama, Hideki Nariai, Kazuhiro Itoh, Eiji Matsuo, Keiko Chitose, Takahiro Arai, Yutaka Abe
Publikováno v:
Nuclear Engineering and Design. 236:1668-1681
A safe design for a fast breeder reactor (FBR) requires post-accident heat removal (PAHR) for any potential core disruptive accident (CDA). It is important to ensure that the molten core material solidifies in the sodium coolant in the reactor vessel
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f0325709bcc8550e5e8c48568e364348
https://doi.org/10.1016/j.nucengdes.2006.04.008
https://doi.org/10.1016/j.nucengdes.2006.04.008
Publikováno v:
TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series B. 71:947-953
In a core disruptive accident (CDA) of a Fast Breeder Reactor, the post accident heat removal (PAHR) is crucial for the accident mitigation. The molten core material should be solidified in the sodium coolant in the reactor vessel. In the present exp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e753f14fbace3869ee5dd51133405168
https://doi.org/10.1299/kikaib.71.947
https://doi.org/10.1299/kikaib.71.947
Publikováno v:
The Proceedings of the National Symposium on Power and Energy Systems. :139-142
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e0774f3ac3a28165dbd98af73fa518d5
https://doi.org/10.1299/jsmepes.2005.10.139
https://doi.org/10.1299/jsmepes.2005.10.139