Zobrazeno 1 - 10
of 38
pro vyhledávání: '"Kaichao Sun"'
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 3879-3891 (2021)
A heat pipe residual heat removal system is proposed to be incorporated into the reactor driven subcritical (RDS) facility, which has been proposed by MIT Nuclear Reactor Laboratory for testing and demonstrating the Fluoride-salt-cooled High-temperat
Externí odkaz:
https://doaj.org/article/64a0a826054341fb82126323a50bb5ff
Autor:
Suizheng Qiu, Wenwen Zhang, Dalin Zhang, Chenglong Wang, Guanghui Su, Kaichao Sun, Wenxi Tian
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 3879-3891 (2021)
A heat pipe residual heat removal system is proposed to be incorporated into the reactor driven subcritical (RDS) facility, which has been proposed by MIT Nuclear Reactor Laboratory for testing and demonstrating the Fluoride-salt-cooled High-temperat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2f6d775d335f8946346ccc578e3cb851
http://www.sciencedirect.com/science/article/pii/S173857332100334X
http://www.sciencedirect.com/science/article/pii/S173857332100334X
Publikováno v:
Progress in Nuclear Energy. 152:104368
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::703ea20b143e46c93a248e93158a30a9
https://doi.org/10.1016/j.pnucene.2022.104368
https://doi.org/10.1016/j.pnucene.2022.104368
Autor:
Kaichao Sun, Yu-Jou Wang, Ryan L. Marlow, Joseph W. Nielsen, Akshay J. Dave, Paul E. Murray, Lin-Wen Hu
Publikováno v:
Progress in Nuclear Energy. 113:186-195
The updated safety basis of the Advanced Test Reactor (ATR) has specific criteria for experiments that are cooled by the primary coolant. It requires that during a Condition 2 transient (where flow coastdown is typically the most limiting), the Criti
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::281c05fa09e77832b90be4c90d6e3dfb
https://doi.org/10.1016/j.pnucene.2019.01.022
https://doi.org/10.1016/j.pnucene.2019.01.022
There is renewed interest in developing small modular reactors and micro-reactors. Innovation is necessary in both construction and operation methods of these reactors to be financially attractive. For operation, an area of interest is the developmen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::45e5c240147e0d158a132241cd7300c2
http://arxiv.org/abs/2007.05435
http://arxiv.org/abs/2007.05435
Publikováno v:
Progress in Nuclear Energy. 109:171-179
The first Solid Fueled Thorium Molten Salt Reactor (TMSR-SF1), a Fluoride-salt-cooled High Temperature Reactor (FHR) designed by the TMSR group of Chinese Academy of Science (CAS), is expected to be constructed in the near years. The combination of T
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6bf711b0ef61c0f5464d04a341af72ec
https://doi.org/10.1016/j.pnucene.2018.08.005
https://doi.org/10.1016/j.pnucene.2018.08.005
Publikováno v:
Annals of Nuclear Energy. 113:270-278
A machine learning based system performance prediction model is currently created to support the development of autonomous control for small reactors, such as the Transportable Fluoride-salt-cooled High-temperature Reactor (TFHR), which is a 20 MWth
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::47776a86cc2e67f8b890184f44656426
https://doi.org/10.1016/j.anucene.2017.11.014
https://doi.org/10.1016/j.anucene.2017.11.014
Publikováno v:
Annals of Nuclear Energy. 112:400-410
The development of the Fluoride-salt-cooled High-temperature Reactor (FHR) is ongoing. The molten salt coolant provides several inherent safety characteristics that traditional water-cooled nuclear reactors lack. The first test reactor to be built in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c29dee80720f93a88a9ae953db070dcf
https://doi.org/10.1016/j.anucene.2017.10.037
https://doi.org/10.1016/j.anucene.2017.10.037
Publikováno v:
Nuclear Engineering and Design. 324:269-279
Reliable systematic uncertainty analysis is of great significance for reactor safety and licensing. In this paper, efforts have been made to quantify uncertainties of computational results. The uncertainty quantification and sensitivity analysis for
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cb7b56b7d4a87ca3c2e302fab35c2c60
https://doi.org/10.1016/j.nucengdes.2017.08.021
https://doi.org/10.1016/j.nucengdes.2017.08.021
Publikováno v:
International Journal of Energy Research. 42:1098-1114
Summary A 20 MWth, 540 EFPD once through fuel cycle small modular molten salt reactor with solid fuel is proposed by Massachusetts Institute of Technology for off-grid applications. In this paper, various thermal-hydraulic analysis methods including
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::034281f3c4b2e6454fe6ccb092946bae
https://doi.org/10.1002/er.3906
https://doi.org/10.1002/er.3906