CAS OpenIR  > 中科院上海应用物理研究所2011-2019年
ANALYSIS OF THE LIMITING SAFETY SYSTEM SETTINGS OF A FLUORIDE SALT-COOLED HIGH-TEMPERATURE TEST REACTOR
Xiao, Y; Hu, LW; Forsberg, C; Qiu, SZ; Su, GH; Chen, K; Wang, NX; lwhu@mit.edu
2014
Source PublicationNUCLEAR TECHNOLOGY
ISSN0029-5450
Volume187Issue:3Pages:221—234
AbstractThe fluoride salt-cooled high-temperature reactor (FHR) is an advanced reactor concept, which uses high-temperature TRISO fuel with a low-pressure liquid salt coolant. The design of a fluoride salt-cooled high-temperature test reactor (FHTR) is a key step in the development of the FHR technology and is currently in progress in both China and the United States. An FHTR based on a pebble bed core design with coolant temperature 600 degrees C to 700 degrees C is being planned for construction by the Chinese Academy of Sciences' Thorium Molten Salt Reactor Research Center, Shanghai Institute of Applied Physics (SINAP). This paper provides a preliminary thermal-hydraulic licensing analysis of an FHTR using SINAP' s pebble core design as a reference case. The operation limits based on criteria outlined in U.S. regulatory guidelines are evaluated. Limiting safety system settings (LSSSs) considering uncertainties for forced convection and natural convection are obtained. The LSSS power and coolant outlet temperature, respectively, are 24.83 MW and 720 degrees C for forced convection and 1.19 MW and 720 degrees C for natural convection. The maximum temperature for the structural materials of 730 degrees C is the most limiting constraint of the FHTR design.
KeywordThermal-hydraulic Analysis
Indexed BySCI
Language英语
WOS IDWOS:000341074800001
Citation statistics
Cited Times:13[WOS]   [WOS Record]     [Related Records in WOS]
Document Type期刊论文
Identifierhttp://ir.sinap.ac.cn/handle/331007/14010
Collection中科院上海应用物理研究所2011-2019年
Corresponding Authorlwhu@mit.edu
Recommended Citation
GB/T 7714
Xiao, Y,Hu, LW,Forsberg, C,et al. ANALYSIS OF THE LIMITING SAFETY SYSTEM SETTINGS OF A FLUORIDE SALT-COOLED HIGH-TEMPERATURE TEST REACTOR[J]. NUCLEAR TECHNOLOGY,2014,187(3):221—234.
APA Xiao, Y.,Hu, LW.,Forsberg, C.,Qiu, SZ.,Su, GH.,...&lwhu@mit.edu.(2014).ANALYSIS OF THE LIMITING SAFETY SYSTEM SETTINGS OF A FLUORIDE SALT-COOLED HIGH-TEMPERATURE TEST REACTOR.NUCLEAR TECHNOLOGY,187(3),221—234.
MLA Xiao, Y,et al."ANALYSIS OF THE LIMITING SAFETY SYSTEM SETTINGS OF A FLUORIDE SALT-COOLED HIGH-TEMPERATURE TEST REACTOR".NUCLEAR TECHNOLOGY 187.3(2014):221—234.
Files in This Item: Download All
File Name/Size DocType Version Access License
ANALYSIS OF THE LIMI(792KB) 开放获取CC BY-NC-SAView Download
Related Services
Recommend this item
Bookmark
Usage statistics
Export to Endnote
Google Scholar
Similar articles in Google Scholar
[Xiao, Y]'s Articles
[Hu, LW]'s Articles
[Forsberg, C]'s Articles
Baidu academic
Similar articles in Baidu academic
[Xiao, Y]'s Articles
[Hu, LW]'s Articles
[Forsberg, C]'s Articles
Bing Scholar
Similar articles in Bing Scholar
[Xiao, Y]'s Articles
[Hu, LW]'s Articles
[Forsberg, C]'s Articles
Terms of Use
No data!
Social Bookmark/Share
File name: ANALYSIS OF THE LIMITING SAFETY SYSTEM SETTINGS OF A FLUORIDE SALT-COOLED HIGH-TEMPERATURE TEST REACTOR.pdf
Format: Adobe PDF
All comments (0)
No comment.
 

Items in the repository are protected by copyright, with all rights reserved, unless otherwise indicated.