1 |
J. Xing, D. Song, Y. Wu, HPR1000: advanced pressurized water reactor with active and passive safety, Engineering 2 (1) (2016) 79-87.
DOI
|
2 |
B.-U. Bae, B.-J. Yun, S. Kim, K.H. Kang, Design of condensation heat exchanger for the PAFS (passive auxiliary feedwater system) of APR+ (advanced power reactor plus), Ann. Nucl. Energy 46 (2012) 134-143.
DOI
|
3 |
H. Liu, N. Todreas, M. Driscoll, An experimental investigation of a passive cooling unit for nuclear plant containment, Nucl. Eng. Des. 199 (3) (2000) 243-255.
DOI
|
4 |
F. De Cachard, S. Lomperski, G.-R. Monauni, Thermal-HydraulicModeling of finned tube containment condensers, in: Proceedings of the 6th International Conference on Nuclear Engineering, ICONE 6, 1998, pp. 1-14. Paper 6099.
|
5 |
M. Leiendecker, N. Todreas, M. Driscoll, A. Hurtado, Design and numerical simulation of a two-phase thermosyphon loop as a passive containment cooling system for PWRs, Cambridge, MIT Cent. Adv. Nucl. Energy Syst. 1 (1997). I and II, MIT-ANP-TR-053, Rev.
|
6 |
N. Aksan, H. Choi J, J. Chung Y, J. Cleveland, F.S. D'Auria, N. Fil, O. Gimenez M, M. Ishii, H. Khartabil, K. Korotaev, Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants, 2009. IAEA-TECDOC-1624.
|
7 |
J. Reyes, Natural Circulation in Water Cooled Nuclear Power Plants Phenomena, Models, and Methodology for System Reliability Assessments, Dr. Jose Reyes (US), 2005.
|
8 |
A. Ahmad, I. Catton, M. Cuesta-Gonzalez, F. Gazzillo, W. Kastenberg, R. Wong, PWR Severe Accident Delineation and Assessment, NUREG/CR-2666, 1983. UCLA-ENG-8284.
|
9 |
V. Cavicchia, E. Fiorino, P. Vannini, Innovative containment cooling for a double concrete containment, in: Proceedings of the International Topical Meeting on Advanced Reactors Safety vol. 2, 1997.
|
10 |
Z. Huang, W. Ma, Performance evaluation of passive containment cooling system of an advanced PWR using coupled RELAP5/Gothic simulation, Nucl. Eng. Des. 310 (2016) 83-92.
DOI
|
11 |
S.W. Lee, S. Heo, H.U. Ha, H.G. Kim, The concept of the innovative power reactor, Nucl. Eng. Technol. 49 (7) (2017) 1431-1441.
DOI
|
12 |
T.L. Schulz, Westinghouse AP1000 advanced passive plant, Nucl. Eng. Des. 236 (14-16) (2006) 1547-1557.
DOI
|
13 |
L. Changdong, J. Wenying, Y. Jiang, C. Wei, W. Ting, C. Cheng, X. Hong, Experimental and computational analysis of a passive containment cooling system with closed-loop heat pipe technology, Prog. Nucl. Energy 113 (2019) 206-214.
DOI
|
14 |
M. Gavrilas, P. Hejzlar, N.E. Todreas, M.J. Driscoll, Gothic code evaluation of alternative passive containment cooling features, Nucl. Eng. Des. 166 (3) (1996) 427-442.
DOI
|
15 |
E.P.M.F. Rahnm, Gothic THERMAL HYDRAULIC ANALYSIS PACKAGE TECHNICAL MANUAL Version 8.0(QA). NAI 8907e06, Rev. 19, Numerical Applications Inc., 2012.
|
16 |
L.E. Herranz, J.L. Munoz-Cobo, M.a.J. Palomo, Modeling condensation heat transfer on a horizontal finned tube in the presence of noncondensable gases, Nucl. Eng. Des. 201 (2-3) (2000) 273-288.
DOI
|
17 |
S. Estevez-Albuja, G. Jimenez, K. Fernandez-Cosials, C. Queral, Analysis of the AP1000® equipment and instrumentation qualification criteria for a DEGB LOCA with a 3D containment Gothic model, 27 th International Conferece Nuclear Energy of New Europe (NENE) (2018) 10-13. September.
|
18 |
IAEA Advanced Reactors Information System (ARSI), Status Report 100- Economic Simplified Boiling Water Reactor, ESBWR), 2011.
|
19 |
IAEA Advanced Reactors Information System (ARSI), Status Report 108- VVER1200 (V-491), 2011. VVER-1200 (V-491).
|
20 |
KHNP, Hanuel 3,4 Final Safety Analysis Report, 1998.
|
21 |
E.P.M.F. Rahnm, Gothic THERMAL HYDRAULICS ANALYSIS PACKAGE USER MANUAL Version 8.0(QA). NAI 8907e8909, Rev. 12, Numerical Applications Inc., 2012.
|
22 |
S.-S. Jeon, Y.-J. Chooa, S.-J. Hong, Gothic multi-dimensional analysis for containment implemented with passive containment cooling system (PCCS), in: Transactions of the Korean Nuclear Society Spring Meeting, 2017.
|
23 |
C. Zhao, J. Chen, Dynamic characteristics of AP1000 shield building for various water levels and air intakes considering fluid-structure interaction, Prog. Nucl. Energy 70 (2014) 176-187.
DOI
|
24 |
C. Byun, D. Jerng, N. Todreas, M. Driscoll, Conceptual design and analysis of a semi-passive containment cooling system for a large concrete containment, Nucl. Eng. Des. 199 (3) (2000) 227-242.
DOI
|
25 |
H. Ha, S. Lee, H. Kim, Optimal design of passive containment cooling system for innovative PWR, Nucl. Eng. Technol. 49 (5) (2017) 941-952.
DOI
|
26 |
Z.-Y. Hung, Y.-M. Ferng, W.-S. Hsu, B.-S. Pei, Y.-S. Chen, Analysis of AP1000 containment passive cooling system during a loss-of-coolant accident, Ann. Nucl. Energy 85 (2015) 717-724.
DOI
|