Zobrazeno 1 - 10
of 417
pro vyhledávání: '"Nuclear reactor safety systems"'
Autor:
I. M. Russkikh
Publikováno v:
Atomic Energy. 121:235-239
Physical startup of the IVV-2 nuclear research reactor at nominal power 5 MW was conducted 50 years ago. Designers, builders, and personnel at the Institute of Reactor Materials needed about 10 years to develop a new reactor – IVV-2M – on the bas
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a3f2e8053e78f32612051578e280667e
https://doi.org/10.1007/s10512-017-0190-7
https://doi.org/10.1007/s10512-017-0190-7
Publikováno v:
Current Opinion in Solid State and Materials Science. 20:401-410
Despite the very demanding operational environment in nuclear reactors, there have been relatively few advanced high-performance materials introduced into fission reactors during the past 50 years. Some of the regulatory and operational barriers to t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8b2c8d7b0e7b0b3ca8bb6e78b8cecca3
https://doi.org/10.1016/j.cossms.2016.10.004
https://doi.org/10.1016/j.cossms.2016.10.004
Publikováno v:
Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2018, 330, pp.400-408. ⟨10.1016/j.nucengdes.2018.01.002⟩
Nuclear Engineering and Design, Elsevier, 2018, 330, pp.400-408. ⟨10.1016/j.nucengdes.2018.01.002⟩
International audience; Thermal-Hydraulic (TH) codes are used to simulate the response of nuclear safety systems under transient and accident conditions. The outcomes of the simulations are used to verify the safety margins required for safe operatio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6873ddafd21f561553d4d7c52e29a4fa
https://hal-centralesupelec.archives-ouvertes.fr/hal-01786566/file/2018_A-Regional-Sensitivity-Analysis-based-Expert-System-for-safety-margins-control.pdf
https://hal-centralesupelec.archives-ouvertes.fr/hal-01786566/file/2018_A-Regional-Sensitivity-Analysis-based-Expert-System-for-safety-margins-control.pdf
Autor:
Maciej Skrzypek, Rafał Laskowski
Publikováno v:
Nukleonika, Vol 60, Iss 3, Pp 537-544 (2015)
The main object of interest was a typical fuel assembly, which constitutes a core of the nuclear reactor. The aim of the paper is to describe the phenomena and calculate thermal-hydraulic characteristic parameters in the fuel assembly for a European
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a3c3ecf2d9477f53515f93609d281817
http://www.degruyter.com/view/j/nuka.2015.60.issue-3/nuka-2015-0110/nuka-2015-0110.xml?format=INT
http://www.degruyter.com/view/j/nuka.2015.60.issue-3/nuka-2015-0110/nuka-2015-0110.xml?format=INT
Autor:
Meng Hongshe
Publikováno v:
Proceedings of The 20th Pacific Basin Nuclear Conference ISBN: 9789811023132
In accordance with the Twelfth Five-Year Plan and 2020 Prospective Target, China will see a coexistence of multiple reactors, different nuclear technologies, and standards in the development of nuclear power, and it is foreseeable that similar situat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9e98a036e23c5ecad992a89132726d9e
https://doi.org/10.1007/978-981-10-2314-9_45
https://doi.org/10.1007/978-981-10-2314-9_45
Autor:
Matthew Griffiths, Y. Yoshida, Ikuo Kinoshita, Joshua P. Schlegel, Mamoru Ishii, Takashi Hibiki
Publikováno v:
Progress in Nuclear Energy. 73:51-63
Currently Appendix K of 10 CFR 50 is used in the United States to evaluate models for the emergency cooling systems of light-water reactors. To assure that these models are accurate enough to ensure that the cooling systems are satisfactory, code sca
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e7fde7303ceffd5b8e9ccafb182794e3
https://doi.org/10.1016/j.pnucene.2014.01.008
https://doi.org/10.1016/j.pnucene.2014.01.008
Publikováno v:
Transactions of the Atomic Energy Society of Japan. 13:17-26
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bcf7e2cce1af15ddf1829ea5836f9212
https://doi.org/10.3327/taesj.j13.013
https://doi.org/10.3327/taesj.j13.013
Publikováno v:
Nuclear Technology. 184:297-309
This paper presents the architecture of the Safety Programmable Logic Controller (SPLC) for advanced nuclear safety systems and describes the evaluation and analyses of reliability for the SPLC usi...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1eaa52502adabfa7bf1ac678f4b24caa
https://doi.org/10.13182/nt13-a24987
https://doi.org/10.13182/nt13-a24987