1 H. Gao, "Transient flow analysis in reactor coolant pump systems during flow coastdown period" 241 : 509-514, 2011
2 Yapei Zhang, "Transient analyses of station blackout accident for CPR1000" 9 : 1056-1059, 2011
3 Jianjun Zhou, "Three dimensional neutronic/thermal-hydraulic coupled simulation of MSR in transient state condition" 282 (282): 93-105, 2015
4 S. F. Mughabghab, "Thermal Neutron Captures Cross Sections Resonance Integrals and G-Factors, Indc International Nuclear Data Committee, Indcnds -440" IAEA nuclear data section 2003
5 J.M. Hawkes, "The simulation and study of conditions leading to axial Offset anomaly in pressurized water reactors" Georgia Institute of Technology 2004
6 L. K. Chang, "The effect of primary pump coastdown characteristics on loss-of-flow transients without scram in EBR-II" 97 (97): 49-59, 1986
7 WEC, "The Westinghouse Pressurized Water Reactor Nuclear Power Plant"
8 X. Liu, "Test study on safety features of station blackout accident for nuclear main pump" 43 : 448-451, 2009
9 EPRI, "Technical Report on the definition of primary coolant source terms used in the different EPR designs for shielding, radiation zoning, DBA consequences" Multinational Design Evaluation Programme 2015
10 N. Dobuchi, "Study on the relation between Doppler reactivity coefficient and resonance integrals of Thorium and Uranium in PWR fuels" 90 : 191-194, 2016
1 H. Gao, "Transient flow analysis in reactor coolant pump systems during flow coastdown period" 241 : 509-514, 2011
2 Yapei Zhang, "Transient analyses of station blackout accident for CPR1000" 9 : 1056-1059, 2011
3 Jianjun Zhou, "Three dimensional neutronic/thermal-hydraulic coupled simulation of MSR in transient state condition" 282 (282): 93-105, 2015
4 S. F. Mughabghab, "Thermal Neutron Captures Cross Sections Resonance Integrals and G-Factors, Indc International Nuclear Data Committee, Indcnds -440" IAEA nuclear data section 2003
5 J.M. Hawkes, "The simulation and study of conditions leading to axial Offset anomaly in pressurized water reactors" Georgia Institute of Technology 2004
6 L. K. Chang, "The effect of primary pump coastdown characteristics on loss-of-flow transients without scram in EBR-II" 97 (97): 49-59, 1986
7 WEC, "The Westinghouse Pressurized Water Reactor Nuclear Power Plant"
8 X. Liu, "Test study on safety features of station blackout accident for nuclear main pump" 43 : 448-451, 2009
9 EPRI, "Technical Report on the definition of primary coolant source terms used in the different EPR designs for shielding, radiation zoning, DBA consequences" Multinational Design Evaluation Programme 2015
10 N. Dobuchi, "Study on the relation between Doppler reactivity coefficient and resonance integrals of Thorium and Uranium in PWR fuels" 90 : 191-194, 2016
11 Q. Shi, "Study on the faults of nuclear power plant and effects on transient stability of power system" IEEE 1-, 2012
12 D. De la Fuente, "Studies of long-term weathering of aluminium in the atmosphere" 49 : 3134-3148, 2007
13 IAEA, "Status of Small and Medium Sized Reactor Designs, A Supplement to the IAEA Advanced Reactors Information System (ARIS)" International Atomic Energy Agency 2012
14 Advanced Reactor Information System, "Status Report 77 e System-Integrated Modular Advanced Reactor (SMART) (IAEA)" international Atomic Energy Agency
15 ARIS, "Status Report 77 - System-Integrated Modular Advanced Reactor (SMART), Advanced Reactors Information System (ARIS)" IAEA, International Atomic Energy Agency
16 Mansour, "Sorption of sulfate ions onto magnetite" 331 : 77-82, 2009
17 B. M. Caba~nas, "Sorption of nickel and cobalt ions onto cobalt and nickel ferrites" 360 : 695-700, 2011
18 A. M. Mirza, "Simulation of corrosion product activity in pressurized water reactors under flow rate transients" 25 (25): 331-345, 1998
19 N. M. Mirza, "Simulation of corrosion product activity for nonlinearly rising corrosion on inner surfaces of primary coolant pipes of a typical PWR under flow rate transients" 62 (62): 681-692, 2005
20 K. Natesan, "Significance of coastdown time on safety and availability of a pool type fast breeder reactor" 286 : 77-88, 2015
21 S. H. Yang, "Safety Analysis Report for SMART Basic Design" Korea Atomic Energy Research Institute 2002
22 IAEA, "Reference neutron activation library" Nuclear Data Section International Atomic Energy Agency 2002
23 S. Wheatley, "Reassessing the safety of nuclear power" 15 : 96-100, 2016
24 P. De-Regge, "Radioactivity and Corrosion Product Concentration during the Normal Operation and Revision Shutdown of 900MWe PWR- Doel 3" 175-181, 1988
25 Wu Guowei, "Primary pump coast-down characteristics analysis in lead cooled fast reactor under loss of flow transient" 103 : 1-9, 2017
26 EPRI, "Primary Water Chemistry, Fuel Rod Corrosion, and Crud Deposition in PWRs: A Comparison of European and U.S. Plant Performance Crud Comparison" 1996
27 R. E. Melchers, "Predicting long-term corrosion of metal alloys in physical infrastructure" 3 : 4-, 2019
28 Karl-Heinz Neeb, "Part 1, The Radiochemistry of Nuclear Power Plants with Light Water Reactors" Walter de Gruyter 1997
29 M. Rafique, "Parametric study of time-dependent corrosion product activity due to 56Mn, 58Co, and 60Co in the primary coolant circuit of a typical pressurized water reactor" 2015 : 1-10, 2015
30 Paul K. Romano, "OpenMC : a state-of-the-art Monte Carlo code for research and development" 82 : 90-, 2015
31 J. Zhu, "Nuclear Reactor Safety Analysis" Xi'an Jiaotong University Press 2000
32 S.P. Murarka, "Neutron Activation Analysis, Encyclopaedia of Materials: Science and Technology" 1-5, 2001
33 NNDC, "NNDCENDF/B-VII.1 evaluated nuclear data library" Google Scholar
34 P. Belouschek, "Modelling of transport and deposition of corrosion production in primary circuits. In Water chemistry of nuclear reactor systems 7" 1996
35 F. Deeba, "Modeling and simulation of corrosion product activity in pressurized water reactors under power perturbations" 26 (26): 561-578, 1999
36 A. Ferrer, "Mod elisation des m ecanismes de formation sous ebullition locale des d ep^ots sur les gaines de combustible des r eacteurs a eau sous pression conduisant a des activit es volumiques importantes, in: Physique Nucl eaire Exp erimentale, Universit e de Strasbourg"
37 J. Tidblad, "Marine corrosion in tropical environments, STP 1399" 18-32 : 18-32, 2000
38 J. Alc antara, "Marine atmospheric corrosion of carbon steel : a review" 4 (4): 406-, 2017
39 Rafique, "Kinetic study of corrosion product activity in primary coolant pipes of a typical PWR under flow rate transients and linearly increasing corrosion rates" 346 : 282-292, 2005
40 Ji-WoongHan, "Investigation into the effects of a coastdown flow on the characteristics of early stage cooling of the reactor pool in KALIMER-600" 36 : 1325-1332, 2009
41 Long Fei Zhang, "Influence of rotational inertia on transient performance of the main pump of marine nuclear power plant" 2 : 55-57, 2005
42 M. D. Carelli, "Handbook of Small Modular Nuclear Reactors" 2015
43 E. Wylie, "Fluid Transients in Systems" Prentice-Hall 1993
44 Y. Alatrash, "Experimental and analytical investigations of primary coolant pump coastdown phenomena for the Jordan Research and Training Reactor" 286 : 60-66, 2015
45 R. Nasir, "Evaluation of corrosion product activity in a typical PWR with extended cycles and flow rate perturbations" 7 : 24-34, 2017
46 R. G. Jaeger, "Engineering Compendium on Radiation Shielding, vol. III" Springer-Verlag 1970
47 F. Mehmood, "Dynamic response analysis of corrosion products activity under steady state operation and Mechanical Shim based powermaneuvering transients in AP-1000" 115 : 16-26, 2018
48 Q. Guo, "Develop CATE V3.0 code for multi-phase ACPs analysis in a typical PWR" 141 : 107345-, 2020
49 K. Mehboob, "Derivation of radiological source term of Korean design system-integrated modular advanced ReacTor(SMART)" 119 : 148-161, 2018
50 M. Zmítke, "Corrosion Products Transport in PWRS Primary Circuit- Computer Code CPPWR. ÚJV 9223 T" Nuclear Research Institute REZ e Czechoslovakia 1990
51 N. M. Mirza, "Computer simulation of corrosion product activity in primary coolants of a typical PWR under flow rate transients and linearly accelerating corrosion" 30 : 831-851, 2003
52 M. Jiang, "Coast-down model based on rated parameters of reactor coolant pump" 48 : 1435-1439, 2014
53 Fr ed eric Delabrouille, "Caract erisation par MET de fissures de corrosion sous contrainte d'alliages a base de nickel: influence de la teneur en chrome et de la chimie du milieu" Institut National Polytechnique de Toulouse 2004
54 B. M. Caba~nas, "Caba~nas, Comportement des produits de corrosion dans le circuit primaire des centrales REP - sorption du cobalt et du nickel sur des ferrites repr esentatifs, Energie electrique" Universit e Paris Sud 2010
55 In Kim Young, "CFD simulation for thermal mixing of a SMART flow mixing header assembly" 85 : 357-370, 2015
56 KAERI, "Basic Design Report of SMART" Korea Atomic Energy Research Institute 2002
57 M. H. Chang, "Basic Design Report of SMART" Korea Atomic Energy Research Institute 2002
58 M. Morcillo, "Atmospheric Corrosion" American Society for Testing and Materials 195-214, 1995
59 A. Volborth, "Analytical Methods for Coal and Coal Products, vol. 3" 303-336, 1979
60 Al-Zahrani, "Analysis of Doppler reactivity coefficient in small modular reactor with UO2, MOX and (Th/U) O2 fuel" 2020
61 P. Beslu, "Analyse hystorique" EDP Sciences 2014