[1] |
郑明光. 从AP1000到CAP1400, 我国先进三代非能动核电技术自主化历程[J]. 中国核电, 2018, 11(1):41-45.
|
|
ZHENG Mingguang. From AP1000 to CAP1400, self-reliant process of China’s third generation nuclear power[J]. China Nuclear Power, 2018, 11(1):41-45.
|
[2] |
SHI G B, GU P W, LU W, et al. CAP1400 IVR related design features and assessment[J]. Nuclear Engineering and Design, 2019, 346:35-45.
doi: 10.1016/j.nucengdes.2019.03.002
URL
|
[3] |
THEOFANOUS T G, LIU C, ADDITON S, et al. In-vessel coolability and retention of a core melt: TRN: 97: 012637 [R]. Office of Scientific and Technical Information (OSTI): U.S. Department of Energy Office of Scientific and Technical Information, 1996.
|
[4] |
THEOFANOUS T G, TU J P, SALMASSI T,, et al. Quantification of limits to coolability in ULPU-2000 configuration IV [R/OL]. (2002-06-06)[2020-06-15]. https://www.nrc.gov/docs/ML0216/ML021620559.pdf.
|
[5] |
DINH T N, TU J P, SALMASSI T, et al. Limits of the coolability in the AP1000-related ULPU-2400 configuration V facility[J]. International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH), 2003: 1-14.
|
[6] |
LEE J, CHANG S H. An experimental study on CHF in pool boiling system with SA508 test heater under atmospheric pressure[J]. Nuclear Engineering and Design, 2012, 250:720-724.
doi: 10.1016/j.nucengdes.2012.05.024
URL
|
[7] |
DEWITT G, MCKRELL T, BUONGIORNO J, et al. Experimental study of critical heat flux with alumina-water nanofluids in downward-facing channels for in-vessel retention applications[J]. Nuclear Engineering and Technology, 2013, 45(3):335-346.
doi: 10.5516/NET.02.2012.075
URL
|
[8] |
TROJER M, AZIZIAN R, PARAS J, et al. A margin missed: The effect of surface oxidation on CHF enhancement in IVR accident scenarios[J]. Nuclear Engineering and Design, 2018, 335:140-150.
doi: 10.1016/j.nucengdes.2018.05.011
URL
|
[9] |
KAM D H, CHOI Y J, JEONG Y H. CHF experiment with downward-facing carbon and stainless steel plates under pressurized conditions[J]. International Journal of Heat and Mass Transfer, 2018, 125:670-680.
doi: 10.1016/j.ijheatmasstransfer.2018.04.026
URL
|
[10] |
SAKASHITA H, ONO A, NYUI J. Critical heat flux and near-wall boiling behaviors in saturated and subcooled pool boiling on vertical and inclined surfaces[J]. Journal of Nuclear Science and Technology, 2009, 46(11):1038-1048.
doi: 10.1080/18811248.2009.9711614
URL
|