[1] |
OKA Y. Review of high temperature water and steam cooled reactor concepts[C]∥Proc. of SCR-2000. Tokyo: [s. n.], 2000.
|
[2] |
CHENG X, LIU X J, YANG Y H. A mixed core for supercritical water-cooled reactor[J]. Nucl Eng Technol, 2008, 40(2): 117-126.
|
[3] |
程旭,刘晓晶. 混合能谱超临界水堆堆芯设计分析[J]. 核科学与工程,2009,29(1):43-49.CHENG Xu, LIU Xiaojing. A mixed core for supercritical water-cooled reactors[J]. Chin J Nucl Sci Eng, 2009, 29(1): 43-49(in Chinese).
|
[4] |
LIU X J, YANG T, CHENG X. Core and sub-channel analysis of SCWR with mixed spectrum core[J]. Annals of Nuclear Energy, 2010, 37: 1674-1682.
|
[5] |
LIU X J, CHENG X. Steady-state thermal hydraulic analysis of SCWR assembly[J]. Frontiers of Energy and Power Engineering in China, 2008, 2(4): 475-478.
|
[6] |
LIU X J, CHENG X. Coupled thermal-hydraulics and neutron-physics analysis of SCWR with mixed spectrum core[J]. Progress in Nuclear Energy, 2010, 52(7): 640-647.
|
[7] |
LIU X J, CHENG X. Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly[J]. Annals of Nuclear Energy, 2009, 36: 28-36.
|
[8] |
LIU X J, CHENG X. Core and sub-channel evaluation of a thermal SCWR[J]. Nuclear Engineering and Technology, 2009, 41(5): 677-690.
|
[9] |
ISHIWATARI Y. Safety of super LWR: Ⅱ. Safety analysis at supercritical pressure[J]. J Nucl Sci Technol, 2005, 42(11): 935-948.
|
[10] |
MacDONALD P E. Supercritical water reactor (SCWR): Progress report for the FY-03 generation-Ⅳ R&D activities for the development of the SCWR in the U. S., INEEL/EXT-03-01210[R]. US: INEEL, 2003.
|
[11] |
The RELAP5 Code Development Team. RELAP5/MOD3.2 code manual[M]. USA: Idaho National Engineering Laboratory, 1995.
|
[12] |
BISHOP A A, SANDBERG R O, TONG L S. Forced convection heat transfer to water at near-critical temperatures and supercritical pressures, Report WCAP-2056 Part Ⅳ[R]. Pittsburgh: Westinghouse Electric Corporation, 1964.
|
[13] |
PETUKHOV B S, KURGANOV V A. Heat transfer and flow resistance in the turbulent pipe flow of a fluid with near-critical state parameters[J]. Teplofizika Vysokikh Temperature, 1983, 21(1): 92-100.
|
[14] |
周翀,刘晓晶,杨燕华,等. ATHLET-SC程序的开发及适用性分析[J]. 原子能科学技术,2009,43(6):556-560.ZHOU Chong, LIU Xiaojing, YANG Yanhua, et al. Development and applicability analysis of ATHLET-SC code[J]. Atomic Energy Science and Technology, 2009, 43(6): 556-560(in Chinese).
|
[15] |
UK AP1000 probabilistic risk assessment[R]. USA: Westinghouse Electric Company, 2007.
|
[16] |
KYOO H B. Design options for the safety injection system of Korean next generation reactor[J]. Annals of Nuclear Energy, 2000, 27(11): 1011-1028.
|
[17] |
TAHIR M. Response of proposed passive safety injection system for an intermediate size break LOCA on CHASNUPP-1[J]. Annals of Nuclear Energy, 2008, 35(11): 1986-1993.
|