| Citation: | Liu Huannan, Yuan Hongsheng, Ju Zhongyun, Xu Caihong, He Dongyu, Li Jinggang, Wang Ting. Study on the Applicability of Transition Boiling Heat Transfer Models Based on LOCUST Code[J]. Nuclear Power Engineering, 2025, 46(5): 37-45. doi: 10.13832/j.jnpe.2024.090046 |
| [1] |
琚忠云, 徐财红, 袁红胜, 等. LOCUST 1.2软件现象级验证[C]. 黑龙江哈尔滨: 国家能源核电软件重点实验室2020年学术年会. 2020.
|
| [2] |
袁红胜, 贺青云, 琚忠云, 等. LOCUST堆芯壁面传热模型分离效应确认[C]. 黑龙江哈尔滨: 国家能源核电软件重点实验室2020年学术年会. 2020.
|
| [3] |
袁红胜, 徐财红, 琚忠云, 等. 基于THTF稳态传热试验的LOCUST 1.2确认[J]. 核科学与工程, 2022, 42(6): 1377-1382.
|
| [4] |
赵宁宁, 袁红胜, 文青龙, 等. 堆芯功率分布对CCTF试验再淹没现象影响的评价研究[J]. 核动力工程, 2021, 42(6): 58-64.
|
| [5] |
DU Q, WEN Q L, YUAN H S, et al. Benchmark study of RBHT experiment for the effect of spacer grids on reflood heat transfer with locust code[C]. Los Angeles, USA: Proceedings of 2021 28th International Conference on Nuclear Engineering, 2021.
|
| [6] |
CHEN J C, SUNDARAM R K, OZKAYNAK F T. A phenomenological correlation for post-CHF heat transfer: NUREG-0237[R]. Washington: Nuclear Regulatory Commission, 1977.
|
| [7] |
ELLION M E. A study of the mechanism of boiling heat transfer[D]. Pasadena: California Institute of Technology, 1954.
|
| [8] |
徐济鋆. 沸腾传热和气液两相流[M]. 第二版. 北京: 原子能出版社, 2001: 314-315.
|
| [9] |
TONG L S. Boiling heat transfer and two-phase flow[M]. New York: Routledge, 1997: 275-277.
|
| [10] |
MATTSON R J, CONDIE K G, BENGSTON S J, et al. Regression analysis of post-CHF flow boiling data[C]//Proceedings of the Fifth International Heat Transfer Conference. Tokyo: Atomic Energy Commission, 1974.
|
| [11] |
HSU Y Y. A tentative correlation for the regime of transition boiling and film boiling during reflood[C]//Paper Presented at the 3rd Water Reactor Safety Review Information Meeting. Washington: United States Nuclear Regulatory Commission, 1986.
|
| [12] |
GROENEVELD D C, FUNG K K. Forced convective transition boiling: review of literature and comparison of predictive methods: AECL-5543[R]. Chalk River, Ontario: Atomic Energy of Canada Limited, 1976.
|
| [13] |
BJORNARD T A, GRIFFITH P. PWR blowdown heat transfer[C]//Proceedings of the Thermal and Hydraulic Aspects of Nuclear Reactor Safety. Atlanta: American Society of Mechanical Engineers, 1977: 17-41.
|
| [14] |
U. S. Nuclear Regulatory Commission. TRACE V5.0 theory manual: field equations, solution methods, and physical models: DC 20555-0001[R]. Washington: U. S. Nuclear Regulatory Commission, 2007.
|
| [15] |
KIRCHNER W L. Reflood heat transfer in a light water reactor[D]. Cambridge: Massachusetts Institute of Technology, 1976.
|
| [16] |
JOHANNSEN K, WEBER P, FENG Q. Experimental investigation of heat transfer in the transition region: EUR 13235 EN[R]. Brussels: Commission of the European communities, 1990.
|
| [17] |
Information Systems Laboratories. RELAP5/MOD3.3 code manual volume I: code structure, system models, and solution methods: Rev 1[R]. Washington, U. S: Nuclear Regulatory Commission, 2001.
|
| [18] |
Gesellschaft für Anlagenund Reaktorsicherheit(GRS) mbH. ATHLET mod 3.0 cycle a models and methods: GRS-P-1/Vol.3, Rev.3[R]. Germany: Gesellschaft für Anlagen-und Reaktorsicherheit, 2014.
|
| [19] |
BROMLEY L A. Heat transfer in stable film boiling[J]. Chemical Engineering Progress, 1950, 46: 221-227.
|
| [20] |
BERENSON P J. Film-boiling heat transfer from a horizontal surface[J]. Journal of Heat Transfer, 1961, 83(3): 351-356. doi: 10.1115/1.3682280
|
| [21] |
TONG L S. Heat-transfer mechanisms in nucleate and film boiling[J]. Nuclear Engineering and Design, 1972, 21(1): 1-25. doi: 10.1016/0029-5493(72)90082-9
|
| [22] |
BENNETT A W, HEWITT G F, KEARSEY H A, et al. Heat transfer to steam-water mixtures flowing in uniformly heated tubes in which the critical heat flux has been exceeded: AERE-R5373[R]. Harwell: Atomic Energy Research Establishment 1968.
|
| [23] |
SJOBERG A, CARAHER D. Assessment of RELAP5/MOD2 against 25 dryout experiments conducted at the royal institute of technology: NUREG/IA-0009[R]. Washington: U. S. Nuclear Regulatory Commission, 1986.
|
| [24] |
YODER G L, MORRIS D G, MULLINS C B, et al. Dispersed-flow film boiling in rod-bundle geometry: steady-state heat-transfer data and correlation comparisons: NUREG/CR-2435[R]. Oak Ridge: Oak Ridge National Laboratory, 1982.
|
| [25] |
ANKLAM T M, MILLER R J, WHITE M D. Experimental investigations of uncovered-bundle heat transfer and two-phase mixture-level swell under high-pressure low heat-flux conditions: NUREG/CR-2456[R]. Oak Ridge: Oak Ridge National Laboratory, 1982.
|