Zobrazeno 1 - 10
of 24
pro vyhledávání: '"Lap-Yan Cheng"'
Autor:
Lap-Yan Cheng, Thomas Y. C. Wei
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2009 (2009)
The safety goal of the current designs of advanced high-temperature thermal gas-cooled reactors (HTRs) is that no core meltdown would occur in a depressurization event with a combination of concurrent safety system failures. This study focused on the
Externí odkaz:
https://doaj.org/article/be191c7f7e6149cda3fa2c4be6261098
Autor:
Robert A. Bari, Lap-Yan Cheng
This chapter defines proliferation resistance (PR) and physical protection (PP) and discusses their relevance to small modular reactors (SMR) in the context of the PR&PP-by-design paradigm. It provides an overview of the development, and applications
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3a77d16fde4bc717cf80aa48e01bb776
https://doi.org/10.1016/b978-0-12-823916-2.00009-6
https://doi.org/10.1016/b978-0-12-823916-2.00009-6
Autor:
Kathleen Araújo, Robert A. Bari, Nicholas J. Barron, Randall J. Belles, Geoffrey Black, Richard L. Black, S. Boarin, Shannon M. Bragg-Sitton, M.D. Carelli, Lap-Yan Cheng, Suhn Choi, Dara Cummins, Dario F. Delmastro, D. Goodman, Kevin W. Hesketh, Jacques Hugo, Daniel T. Ingersoll, Vladimir Kuznetsov, S. Lawler, G. Locatelli, M. Mancini, Gary Mays, Tsutomo Okubo, Bojan Petrovic, Edward (Ted) Quinn, M. Ricotti, David Shropshire, Danrong Song, Neil Todreas, N. Town, Andrew Worrall, Metin Yetisir
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b2fab341316cc3232106c21474d7ae6f
https://doi.org/10.1016/b978-0-12-823916-2.09992-6
https://doi.org/10.1016/b978-0-12-823916-2.09992-6
Publikováno v:
Nuclear Technology. 196:238-247
A TRACE/PARCS model has been developed to analyze anticipated transient without SCRAM (ATWS) events for a boiling water reactor (BWR) operating in the maximum extended load line limit analysis-plus (MELLLA+) expanded operating domain. The MELLLA+ dom
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0d5c7656a67d51a7f3349e77eeab3125
https://doi.org/10.13182/nt16-29
https://doi.org/10.13182/nt16-29
Publikováno v:
Nuclear Technology. 189:71-86
O-moderated researchreactor (NBSR) at the National Institute of Standardsand Technology. A RELAP5 model has been developed toanalyze postulated accidents in the NBSR with the presentHEU fuel and a proposed LEU fuel. The model includesthe reactor vess
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::71c6ad6f90a7d29a2cd356aeeb534cf1
https://doi.org/10.13182/nt13-124
https://doi.org/10.13182/nt13-124
Publikováno v:
Nuclear Technology. 185:1-20
Reactivity insertion accidents have been analyzed for the 20-MW D2O-moderated research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The analysis has been carried out for the present core, which contains highly enriched
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9a507c0c7dae5a7ad9db8395ee371d5c
https://doi.org/10.13182/nt13-26
https://doi.org/10.13182/nt13-26
Autor:
Thomas Y. C. Wei, Lap-Yan Cheng
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2009 (2009)
The safety goal of the current designs of advanced high-temperature thermal gas-cooled reactors (HTRs) is that no core meltdown would occur in a depressurization event with a combination of concurrent safety system failures. This study focused on the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::47bc7f2901d9bcbdbb6effcd79ba00a5
https://doi.org/10.1155/2009/797461
https://doi.org/10.1155/2009/797461
Publikováno v:
Nuclear Technology. 165:1-17
The purpose of this study is to evaluate the proliferation resistance characteristics for different fuel cycle arrangements in the context of a global nuclear energy system using a Markov approach,...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8c13c5e2554d888c28f6d145485c3d01
https://doi.org/10.13182/nt09-a4058
https://doi.org/10.13182/nt09-a4058
Publikováno v:
Nuclear Technology. 162:26-44
A Markov model approach is developed for the evaluation of proliferation resistance (PR) of nuclear energy systems. The focus of this study is to create a high-fidelity probabilistic assessment model that better represents nuclear energy systems. Bot
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4b8116628d1aaf3dd6b74226990aea63
https://doi.org/10.13182/nt08-a3931
https://doi.org/10.13182/nt08-a3931