References

Roadmap References

Reference	Title	Publishing Agency
[1]	Reactor Safety Study: An Assessment of Accident Risks in U.S. Nuclear Power Plants (WASH 1400 / NUREG-75/014); US Nuclear Regulatory Commission: Washington DC (October 1975)	NRC
[2]	United States Code of Federal Regulations 10CFR52 - Licenses, Certifications, and Approvals for Nuclear Power Plants	NRC
[3]	Standard for Level 1 / Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications; ASME/ANS RA-Sa-2009; American Society of Mechanical Engineers; New York, NY (2009)	ASME
[4]	Insights on Risk Margins and Nuclear Power Plants: A Technical Evaluation of Margins in Relation to Quantitative Health Objectives and Subsidiary Risk Goals in the United States; 3002012967; Electric Power Research Institute; Palo Alto, CA (May 2018)	EPRI
[5]	The Nexus Between Safety and Operational Performance in the U.S. Nuclear Industry; Nuclear Energy Institute; Washington, DC (March 2020)	NEI
[6]	Probabilistic Risk Assessment Standard for Advanced Non-Light Water Reactor Nuclear Power Plants; ASME/ANS RA-S-1.4-2001; American Society of Mechanical Engineers; New York, NY (2021)	ASME
[7]	Acceptability of Probabilistic Risk Assessment Results for Non-Light-Water Reactor Risk-Informed Activities; Regulatory Guide 1.247 (For Trial Use); US Nuclear Regulatory Commission; Washington, DC, (March 2022)	NRC
[8]	Risk-Informed Performance-Based Technology Inclusive Guidance for Non-Light Water Reactor Licensing Basis Development; NEI 18-04 (Revision 1); Nuclear Energy Institute; Washington, DC (August 2021)	NEI
[9]	Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications and Approvals for Non-Light-Water Reactors; Regulatory Guide 1.233; US Nuclear Regulatory Commission; Washington, DC, (June 2020)	NRC
[10]	Advances in Small Modular Reactor Technology Developments A Supplement to: IAEA Advanced Reactors Information System (ARIS) 2020 Edition; International Atomic Energy Agency; Vienna, Austria (September 2022)	IAEA
[11]	United States Code of Federal Regulations 10CFR50 Appendix A: General Design Criteria for Nuclear Power Plants	NRC
[12]	Guidance for Developing Principal Design Criteria for Non-Light Water Reactors; Regulatory Guide 1.232 Revision 0; US Nuclear Regulatory Commission; Washington, DC, (2018)	NRC
[13]	The Canadian Nuclear Safety Commission’s Strategy Readiness to Regulate Advanced Reactor Technologies; Canadian Nuclear Safety Commission; Ottawa, Ontario (December 2019)	CNSC
[14]	IAEA Safety Standards Series No. SSR-2/1 Rev 1; Safety of Nuclear Power Plants: Design; IAEA Safety Standards; International Atomic Energy Agency; Vienna, Austria (2016)	IAEA
[15]	IAEA-TECDOC-1366; Considerations in the Development of Safety Requirements for Innovative Reactors: Application to Modular High Temperature Gas Cooled Reactors, International Atomic Energy Agency; Vienna, Austria (2003)	IAEA
[16]	IAEA-TECDOC-1570; Proposal for a Technology-Neutral Safety Approach for New Reactor Designs; International Atomic Energy Agency; Vienna, Austria (2003)	IAEA
[17]	IAEA-TECDOC-2010; Approach and Methodology for the Development of Regulatory Safety Requirements for the Design of Advanced Nuclear Power Reactors, Case Study on Small Modular Reactors; International Atomic Energy Agency; Vienna, Austria (2022)	IAEA
[18]	CNSC REGDOC-3.5.3, Regulatory Fundamentals, version 2.0, Canadian Nuclear Safety Commission; Ottawa, Ontario (February 2020)	CNSC
[19]	Memorandum of Cooperation on Advanced Reactor and Small Modular Reactor Technologies between the United States Nuclear Regulatory Commission and the Canadian Nuclear Safety Commission (August 2019)	NRC & CNSC
[20]	Technology Inclusive and Risk-Informed Reviews for Advanced Reactors: Comparing the US Licensing Modernization Project with the Canadian Regulatory Approach	NRC & CNSC
[21]	Guidance for Developing Principal Design Criteria for Advanced (Non-Light Water) Reactors, Rep. INL/EXT-14-31179, Revision 1; Idaho National Laboratory; Idaho Falls, ID (December 2014)	INL
[22]	IAEA-TECDOC-1909; Consideration on Performing Integrated Risk Informed Decision Making; IAEA, Vienna, Austria (2020)	IAEA
[23]	Generation IV International Forum (GIF), 2002. A Technology Roadmap for Generation IV Nuclear Energy Systems. GIF-002-00	DOE
[24]	Brandon Chisholm, Steve Krahn, Amir Afzali, and Eric Harvey; Application of a Method to Estimate Risk in Advanced Nuclear Reactors: A Case Study on the Molten Salt Reactor Experiment; Probabilistic Safety Assessment and Management PSAM 14; September 2018; Los Angeles, CA	PSAM
[25]	OECD/NEA, “A Joint Report on PSA for New and Advanced Reactors"; Nuclear Safety NEA/CSNI/R(2012)17; 2012; Organisation for Economic Cooperation and Development - Nuclear Energy Agency; Paris, France	OECD/NEA
[26]	Brandon Chisholm, Steve Krahn, Andrew Sowder, Amir Afzali, Development of a Methodology for Early Integration of Safety Analysis into Advanced Reactor Design, American Nuclear Society PSA 2019, Charleston, SC, April 28 - May 3, 2019	ANS
[27]	Brandon M. Chisholm, Steven L. Krahn, Karl N. Fleming, "A systematic approach to identify initiating events and its relationship to Probabilistic Risk Assessment: Demonstrated on the Molten Salt Reactor Experiment", Progress in Nuclear Energy 129 (2020) 103507	Vanderbilt
[28]	Program on Technology Innovation: Early Integration of Safety Assessment into Advanced Reactor Design - Project Capstone Report: EPRI, Palo Alto, CA: 2019. 3002015752.	EPRI
[29]	Compilation of Molten Salt Reactor Experiment (MSRE) Technical, Hazard, and Risk Analyses: A Retrospective Application of Safety-in-Design Methods. EPRI, Palo Alto, CA: 2020. 3002018340.	EPRI
[30]	Mostafa Hamza and Mihai A. Diaconeasa, "A framework to implement human reliability analysis during early design stages of advanced reactors"; Progress in Nuclear Energy; 146 (2022); 104171	NC State
[31]	Program on Technology Innovation: Probabilistic Risk Assessment Requirements for Passive Safety Systems. EPRI, Palo Alto, CA: 2007. 1015101.	EPRI
[32]	Program on Technology Innovation: Comprehensive Risk Assessment Requirements for Passive Safety Systems. EPRI, Palo Alto, CA; 2008. 1016747.	EPRI
[33]	Samuel Abiodun Olatubosun and Carol Smidts; "Reliability analysis of passive systems: An overview, status and research expectations"; Progress in Nuclear Energy; 143 (2022); 104057	Ohio State
[34]	Zhi'ao Huang, Huifang Miao, Morten Lind, Xinxin Zhang, and Jing Wu; "Probabilistic safety margin characterization of an integrated small modular reactor using MFM and adaptive polynomial chaos"; Annals of Nuclear Energy; 171 (2022); 109016	Xiamen University
[35]	Kyungho Jin, Hyeonmin Kim, Seunghyoung Ryu, Seunggeun Kim, and Jinkyun Park; "An approach to constructing effective training data for a classification model to evaluate the reliability of a passive safety system"; Reliability Engineering and System Safety; 222 (2022); 108446	KAERI
[36]	R.B. Solanki, Harshavardhan D. Kulkarni, Suneet Singh, P.V. Varde, and A.K. Verma; "Reliability assessment of passive systems using artificial neural network based response surface methodology"; Annals of Nuclear Energy; 144 (2020); 107487	Multi
[37]	Jalil Jafari, Francesco D'Auria, Hossein Kazeminejad, Hadi Davilu, "Reliability evaluation of a natural circulation system"; Nuclear Engineering and Design, Volume 224, Issue 1, September 2003, Pages 79-104	Multi
[38]	Marques, M., Pignatel, J. F., Saignes, P., D'Auria, P., Burgazzi, L., Müller, C. "Methodology for the reliability evaluation of a passive system and its integration into a probabilistic safety assessment"; Nucl. Eng. Des. 235, 2612-2631. Doi:10.1016/j.nucengdes.2005.06.008 (2005)	Multi
[39]	Nayak, A. K., and Vijayan, P. K. (2008). "Flow instabilities in boiling two-phase natural circulation systems a review"; Sci. Technol. Nucl. Install. (2008), 15. Doi:10.1155/2008/573192	Multi
[40]	Arun Kumar Nayak, Amit Chandrakar and Gopika Vinod, "A review: passive system reliability analysis - accomplishments and unresolved issues"; Front. Energy Res., 10 October 2014, Sec. Nuclear Energy, Volume 2 - 2014	Multi
[41]	United Kingdom National Nuclear Regulator Position Paper, “Considerations of External Events for New Nuclear Installations”; PP-0014, Rev 0	NNR
[42]	TECDOC-1487, “Advanced Nuclear Power Plant Design Options to Cope with External Events”, IAEA-TECDOC-1487 ¦ 92-0-100506-7, 2006	IAEA
[43]	IAEA, Technical Approach to Probabilistic Safety Assessment for Multiple Reactor Units, Safety Report Series To Be Published, IAEA, Vienna (2019)	IAEA
[44]	1st International Conference on Generation IV and Small Modular Reactors, Whole-Site Risk Considerations for Small Modular Reactors, J. Vecchiarelly, C. Lorencez and G. Archinoff, Ottawa (2018)	N/A
[45]	U.S. NRC, Exploring the Need for Standard Approaches to Addressing Risk Associated with Multi-Module Operation in Plants Using Small Modular Reactors, M. A. Caruso, US NRC, Washington DC	NRC
[46]	Small Modular Reactors Regulators' Forum: Design and Safety Analysis Working Group Report on Multi-unit/Multi-module aspects specific to SMRs, INTERIM REPORT, 15 December 2019	SMRRF
[47]	Framework for Assessing Multi-Unit Risk to Support Risk-Informed Decision-Making: General Framework and Application-Specific Requirements. EPRI, Palo Alto, CA: 2001. 3002020765.	EPRI
[48]	Nicholas W. Touran, John Gilleland, Graham T. Malmgren, Charles Whitmer, William H. Gates III, “Computational Tools for the Integrated Design of Advanced Nuclear Reactors”; Engineering 3 (2017) 518–526	TerraPower
[49]	HAZCADS: Hazards and Consequences Analysis for Digital Systems (Revision 1). EPRI, Palo Alto, CA: 2021. 3002016698.	EPRI
[50]	Ibrahim A. Alrammah, “Analysis of nuclear accident scenarios and emergency planning zones for a proposed Advanced Power Reactor 1400 (APR1400)”; Nuclear Engineering and Design, Volume 407, June 2023, 112275	KACST
[51]	Federica C.V. Mancini, Eduardo Gallego, Marco E. Ricotti, "Revising the Emergency Management Requirements for new generation reactors"; Progress in Nuclear Energy, Volume 71, March 2014, Pages 160-171	Multi
[52]	H.D. Gougar, D.A. Petti,, P.A. Demkowicz,, W.E. Windes, G. Strydom, J.C. Kinsey, J. Ortensi, M. Plummer, W. Skerjanc, R.L. Williamson, R.N. Wright, D. Li, A. Caponiti, M.A. Feltus, and T.J. O'Connor, "The US Department of Energy's high temperature reactor research and development program - Progress as of 2019"; Nuclear Engineering and Design; Volume 358, March 2020; 110397	INL
[53]	Enterprise Risk Management and Risk-Informed Decision-Making. EPRI, Palo Alto, CA: 2022. 3002023855.	EPRI
[54]	Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities; Regulatory Guide 1.200 Revision 3; December 2020; United States Nuclear Regulatory Commission; Washington, DC	NRC
[55]	F. Bianchi, et al.; "The REPAS Approach to the Evaluation of Passive Safety Systems Reliabilit"; Passive System Reliability - A Challenge to Reliability Engineering and Licensing of Advanced Nuclear Power Plants: Proceedings of an International Workshop Hosted by the Commissariat à l'Energie Atomique (CEA); NEA/CSNI/R(2002)10; Cadarache, France (26 June 2002)	OECD/NEA
[56]	M. E. Ricotti, et al.; "Reliability Methods for Passive Systems (RMPS) Study-Strategy and Results," Passive System Reliability - A Challenge to Reliability Engineering and Licensing of Advanced Nuclear Power Plants; Proceedings of an International Workshop Hosted by the Commissariat à l'Energie Atomique (CEA); NEA/CSNI/R(2002)10; Cadarache, France (26 June 2002)	OECD/NEA
[57]	Systems Engineering Process: Methods and Tools for Digital Instrumentation and Control Projects. EPRI, Palo Alto, CA: 2016. 3002008018.	EPRI
[58]	HFAM - Human Factors Analysis Methodology for Digital Systems: A Risk-Informed Approach to Human Factors Engineering. EPRI, Palo Alto, CA: 2021. 3002018392.	EPRI
[59]	Advanced Reactor Roadmap – Phase 1: North America. EPRI, Palo Alto, CA: 2023. 3002027504.	EPRI