Citation: | Xu Rongshuan, Xia Hang, Xu Caihong, He Dongyu, Wang Ting, Li Jinggang. Verification and Uncertainty Evaluation of LOCUST Reflood Model[J]. Nuclear Power Engineering, 2024, 45(4): 111-117. doi: 10.13832/j.jnpe.2024.04.0111 |
[1] |
李冬,刘晓晶,杨燕华. RELAP5程序再淹没现象物理模型的敏感性分析[J]. 核动力工程,2014, 35(S1): 166-169.
|
[2] |
阮神辉,杨继涛,文青龙,等. 基于RBHT再淹没传热试验的RELAP5/MOD4再淹没计算模型验证研究[C]//第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集. 惠州: 2019: 119-129.
|
[3] |
李雪琳,张昊,杨燕华. COSINE程序再淹没模型验证及参数敏感性分析[J]. 核动力工程,2022, 43(6): 73-78.
|
[4] |
吕莉. 基于RELAP5程序的再淹没膜态沸腾传热模型研究[D]. 衡阳: 南华大学,2015.
|
[5] |
SKOREK T, DE CRÉCY A, KOVTONYUK A, et al. Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark[J]. Nuclear Engineering and Design, 2019, 354: 110199. doi: 10.1016/j.nucengdes.2019.110199
|
[6] |
XIONG Q W, DU P, DENG J, et al. Uncertainty evaluation of the ARSAC reflood model with Bayesian calibration[J]. Progress in Nuclear Energy, 2022, 143: 104055. doi: 10.1016/j.pnucene.2021.104055
|
[7] |
徐财红. 两相流热工水力系统分析软件LOCUST-1.2开发概述[C]//中国核学会核反应堆热工流体力学分会第一届学术年会暨中核核反应堆热工水力技术重点实验室2021年学术年会暨国家能源压水反应堆技术研发(实验)中心学术交流会. 重庆: 中国核学会核反应堆热工流体力学分会,中核核反应堆热工水力技术重点实验室与国家能源压水反应堆技术研发(实验)中心,2021.
|
[8] |
HOCHREITER L E, CHEUNG F B, LIN T F, et al. Rod bundle heat transfer test facility test plan and design: NUREG/CR-6975[R]. Washington: U. S. Nuclear Regulatory Commission, 2010.
|
[9] |
ROSAL E R, LIN T F, MCCLELLAN I S, et al. Rod bundle heat transfer test facility description: NUREG/CR-6976[R]. Washington: U. S. Nuclear Regulatory Commission, 2010.
|
[10] |
HOCHREITER L E, CHEUNG F B, LIN T F, et al. RBHT reflood heat transfer experiments data and analysis: NUREG/CR-6980[R]. Washington: U. S. Nuclear Regulatory Commission, 2012.
|
[11] |
WANG M J, QIU S Z, SU G H, et al. Preliminary study of parameter uncertainty influence on Pressurized Water Reactor core design[J]. Progress in Nuclear Energy, 2013, 68: 200-209. doi: 10.1016/j.pnucene.2013.07.002
|
[12] |
WILKS S S. Determination of sample sizes for setting tolerance limits[J]. The Annals of Mathematical Statistics, 1941, 12(1): 91-96. doi: 10.1214/aoms/1177731788
|
[13] |
HASSAN Y A, FU C. RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO2 fuel and mixed-oxide fuel[J]. Nuclear Technology, 2004, 148(3): 325-334. doi: 10.13182/NT04-A3570
|
[14] |
REVENTÓS F, DE ALFONSO E, SANZ R M, et al. PREMIUM: a benchmark on the quantification of the uncertainty of the physical models in system thermal-hydraulic codes: methodologies and data review: NEA/CSNI/R(2016)9[R]. OECD/NEA, 2016.
|