Zobrazeno 1 - 10
of 132
pro vyhledávání: '"ULOF"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 3, Pp 873-879 (2024)
A sodium-cooled fast reactor (SFR) core has a potential of prompt criticality due to a change of core material distribution during a severe accident, and the resultant energy release has been one of the safety issues of SFRs. In this study, the safet
Externí odkaz:
https://doaj.org/article/8c1fbc5d91eb4f30b55e255ba0808880
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 5, Pp 1813-1824 (2022)
This paper shows the verification work of SARAX code system in the reactor core transient calculation based on the simplified EBR-II Benchmark. The SARAX code system is an analysis package developed by Xi'an Jiaotong University and aims at the advanc
Externí odkaz:
https://doaj.org/article/221b0f6a67874670ae4deda2d99d2bdd
Autor:
Kenichi Kawada, Tohru Suzuki
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 3930-3943 (2021)
To improve the capability of the SAS4A code, which simulates the initiating phase of core disruptive accidents for MOX-fueled Sodium-cooled Fast Reactors (SFRs), the authors have investigated in detail the physical phenomena under unprotected loss-of
Externí odkaz:
https://doaj.org/article/6118bf437168400fb1e8b4aea57e6bed
Akademický článek
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Publikováno v:
Journal of Nuclear Engineering
Volume 4
Issue 1
Pages: 154-164
Volume 4
Issue 1
Pages: 154-164
The mechanical consequences of core disruptive accidents (CDAs) are a major safety concern in sodium-cooled fast reactors. Once core disruption occurs, liquefied core materials rapidly disperse vertically and radially. The dispersed materials penetra
Autor:
Pascal V., Gorsse Y., Alpy N., Ammar K., Anderhuber M., Baudron AM., Campioni G., Junquera A. Canas, Gerschenfeld A., Patricot C., Sciora P.
Publikováno v:
EPJ Web of Conferences, Vol 247, p 07001 (2021)
Sodium cooled fast neutron reactors (SFR) are one of the selected reactor concepts in the framework of the Generation IV International Forum. In this concept, unprotected loss of cooling flow transients (ULOF), for which the non-triggering of backup
Externí odkaz:
https://doaj.org/article/93e1ba6014ad415ab243eaf3998b3fdc
Autor:
Tohru Suzuki, Ken-ichi Kawada
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 3930-3943 (2021)
To improve the capability of the SAS4A code, which simulates the initiating phase of core disruptive accidents for MOX-fueled Sodium-cooled Fast Reactors (SFRs), the authors have investigated in detail the physical phenomena under unprotected loss-of
Autor:
Tohru Suzuki, Yoshiharu Tobita, Kenichi Kawada, Hirotaka Tagami, Joji Sogabe, Kenichi Matsuba, Kei Ito, Hiroyuki Ohshima
Publikováno v:
Nuclear Engineering and Technology, Vol 47, Iss 3, Pp 240-252 (2015)
In the original licensing application for the prototype fast-breeder reactor, MONJU, the event progression during an unprotected loss of flow (ULOF), which is one of the technically inconceivable events postulated beyond design basis, was evaluated.
Externí odkaz:
https://doaj.org/article/baffa6d771ac490fa8f36bfc63e3d623