| Reference |
Title |
Year |
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) |
2015 |
NRC
|
| [2] |
United States Code of Federal Regulations 10CFR52 - Licenses, Certifications, and Approvals for Nuclear Power Plants |
2007 |
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) |
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) |
2018 |
EPRI
|
| [5] |
The Nexus Between Safety and Operational Performance in the U.S. Nuclear Industry; Nuclear Energy Institute; Washington, DC (March 2020) |
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) |
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) |
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) |
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) |
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) |
2022 |
IAEA
|
| [11] |
United States Code of Federal Regulations 10CFR50 Appendix A: General Design Criteria for Nuclear Power Plants |
2007 |
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) |
2018 |
NRC
|
| [13] |
The Canadian Nuclear Safety Commission’s Strategy Readiness to Regulate Advanced Reactor Technologies; Canadian Nuclear Safety Commission; Ottawa, Ontario (December 2019) |
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) |
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) |
2003 |
IAEA
|
| [16] |
IAEA-TECDOC-1570; Proposal for a Technology-Neutral Safety Approach for New Reactor Designs; International Atomic Energy Agency; Vienna, Austria (2003) |
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) |
2022 |
IAEA
|
| [18] |
CNSC REGDOC-3.5.3, Regulatory Fundamentals, version 2.0, Canadian Nuclear Safety Commission; Ottawa, Ontario (February 2020) |
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) |
2019 |
NRC & CNSC
|
| [20] |
Technology Inclusive and Risk-Informed Reviews for Advanced Reactors: Comparing the US Licensing Modernization Project with the Canadian Regulatory Approach |
2022 |
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) |
2014 |
INL
|
| [22] |
IAEA-TECDOC-1909; Consideration on Performing Integrated Risk Informed Decision Making; IAEA, Vienna, Austria (2020) |
2020 |
IAEA
|
| [23] |
Generation IV International Forum (GIF), 2002. A Technology Roadmap for Generation IV Nuclear Energy Systems. GIF-002-00 |
2002 |
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 |
2018 |
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 |
2012 |
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 |
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 |
2020 |
Vanderbilt
|
| [28] |
Program on Technology Innovation: Early Integration of Safety Assessment into Advanced Reactor Design - Project Capstone Report: EPRI, Palo Alto, CA: 2019. 3002015752. |
2019 |
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. |
2020 |
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 |
2022 |
NC State
|
| [31] |
Program on Technology Innovation: Probabilistic Risk Assessment Requirements for Passive Safety Systems. EPRI, Palo Alto, CA: 2007. 1015101. |
2007 |
EPRI
|
| [32] |
Program on Technology Innovation: Comprehensive Risk Assessment Requirements for Passive Safety Systems. EPRI, Palo Alto, CA; 2008. 1016747. |
2008 |
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 |
2022 |
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 |
2022 |
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 |
2022 |
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 |
2020 |
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 |
2003 |
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) |
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 |
2008 |
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 |
2014 |
Multi
|
| [41] |
United Kingdom National Nuclear Regulator Position Paper, “Considerations of External Events for New Nuclear Installations”; PP-0014, Rev 0 |
2022 |
NNR
|
| [42] |
TECDOC-1487, “Advanced Nuclear Power Plant Design Options to Cope with External Events”, IAEA-TECDOC-1487 ¦ 92-0-100506-7, 2006 |
2006 |
IAEA
|
| [43] |
IAEA, Technical Approach to Probabilistic Safety Assessment for Multiple Reactor Units, Safety Report Series To Be Published, IAEA, Vienna (2019) |
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) |
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 |
2023 |
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 |
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. |
2021 |
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 |
2017 |
TerraPower
|
| [49] |
HAZCADS: Hazards and Consequences Analysis for Digital Systems (Revision 1). EPRI, Palo Alto, CA: 2021. 3002016698. |
2025 |
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 |
2023 |
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 |
2014 |
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 |
2020 |
INL
|
| [53] |
Enterprise Risk Management and Risk-Informed Decision-Making. EPRI, Palo Alto, CA: 2022. 3002023855. |
2022 |
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 |
2020 |
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) |
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) |
2002 |
OECD/NEA
|
| [57] |
Systems Engineering Process: Methods and Tools for Digital Instrumentation and Control Projects. EPRI, Palo Alto, CA: 2016. 3002008018. |
2016 |
EPRI
|
| [58] |
HFAM - Human Factors Analysis Methodology for Digital Systems: A Risk-Informed Approach to Human Factors Engineering. EPRI, Palo Alto, CA: 2021. 3002018392. |
2021 |
EPRI
|
| [59] |
Advanced Reactor Roadmap – Phase 1: North America. EPRI, Palo Alto, CA: 2023. 3002027504. |
2023 |
EPRI
|
| [60] |
EPRI 3002029252 Advanced Nuclear Technology: Guidance for Selection of Risk Metrics for Advanced reactors (2024). |
2024 |
EPRI
|
| [61] |
Hierarchical Structure of Safety Goals for Nuclear Installations, IAEA-TECDOC-1874. International Atomic Energy Agency, Vienna, Austria: 2019. |
2019 |
IAEA
|
| [62] |
Development of Surrogates for Core Damage Frequency and Large Early Release Frequency for Advanced Small Modular Reactors, Flanagan, George F ORNL/TM-2013/228, ORNL, Oak Ridge, TN (2013), available within INL/EXT-13-30170, Advanced Small Modular Reactor (SMR) Probabilistic Risk Assessment (PRA) Technical Exchange Meeting, C Smith, 2013. |
2013 |
INL
|
| [63] |
U.S. Code of Federal Regulation 51 FR 28044, Office of the Federal Register, National Archives and Records Administration, Washington, DC 20408, (Effective Date of 4 August 1986). |
1986 |
NRC
|
| [64] |
Memorandum for James M. Taylor on Implementation of the Safety Goals, SECY-89-102, U.S. Nuclear Regulatory Commission, from Samuel J. Chilk, June 1990. |
1990 |
SECY
|
| [65] |
Probabilistic Safety Assessment (PSA), IAEA Consultancy Meeting on the Safety Report on Safety Analysis for SMRs, SMR PSA experience: Terrestrial Energy, A. Moisin, March 2022. |
2022 |
IAEA
|
| [66] |
White Paper on Options for Risk Metrics for New Reactors, ML090160004, Nuclear Regulatory Commission (NRC), February, 2009. |
2009 |
NRC
|
| [67] |
EPRI 3002032218, Advanced Nuclear Technology: Evaluation of Passive System Reliability Approaches |
2025 |
EPRI
|
| [68] |
EPRI 3002032223, Advanced Nuclear Technology: Guidance for Passive System Reliability Analysis |
2025 |
EPRI
|
| [69] |
EPRI 3002034425, Evaluation of Probabilistic Safety Assessment Methods for Non-Light Water Small Modular Reactors (HTGR and MSR) |
2026 |
EPRI
|
| [70] |
EPRI 3002032224, Advanced Nuclear Technology: Application of EPRI Framework for Multi-Reactor Risk Analysis to Advanced Reactors |
2025 |
EPRI
|
| [71] |
EPRI 3002032230, Risk-Informed Performance-Based Application of Codes and Standards for Advanced Reactor Structural Design: Conceptual Approach |
2025 |
EPRI
|
| [72] |
EPRI 3002032031, Risk-Informed Considerations for Rare Seismic Events in Advanced Reactors |
2025 |
EPRI
|
| [73] |
EPRI 3002032238, Initial Probabilistic Risk Assessment (PRA) Technical Guidance for ASME Section XI Reliability and Integrity Management Programs |
2025 |
EPRI
|
| [74] |
EPRI 3002029295, Implementation of Licensing Modernization Project Risk-Informed Performance-Based Design Framework for External Hazards: Assessment of Challenges, Gaps, and Research Needs |
2024 |
EPRI
|