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== | ==Sortable List of References== | ||
{| class="wikitable sortable mw-datatable" style="margin:auto" | {| class="wikitable sortable mw-datatable" style="margin:auto" | ||
! Reference !! Title !! Publishing Agency | ! Reference !! Title !! Year !! Publishing Agency | ||
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| [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 | | [1] || [https://www.nrc.gov/docs/ML1533/ML15334A199.pdf 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 | ||
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| [2] || United States Code of Federal Regulations 10CFR52 - Licenses, Certifications, and Approvals for Nuclear Power Plants || NRC | | [2] || [https://www.ecfr.gov/current/title-10/chapter-I/part-52 United States Code of Federal Regulations 10CFR52 - Licenses, Certifications, and Approvals for Nuclear Power Plants] || 2007 || NRC | ||
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| [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 | | [3] || [https://www.asme.org/codes-standards/find-codes-standards/standard-for-level-1-large-early-release-frequency-probabilistic-risk-assessment-for-nuclear-power-plant-applications 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 | ||
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| [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 | | [4] || [https://www.epri.com/research/products/3002012967 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 | ||
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| [5] || The Nexus Between Safety and Operational Performance in the U.S. Nuclear Industry; Nuclear Energy Institute; Washington, DC (March 2020)|| NEI | | [5] || [https://www.nei.org/resources/reports-briefs/performance-safety The Nexus Between Safety and Operational Performance in the U.S. Nuclear Industry; Nuclear Energy Institute; Washington, DC (March 2020)] || 2020 || NEI | ||
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| [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 | | [6] || [https://www.asme.org/codes-standards/find-codes-standards/probabilistic-risk-assessment-standard-for-advanced-non-light-water-reactor-nuclear-power-plants 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 | ||
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| [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 | | [7] || [https://www.federalregister.gov/documents/2022/03/24/2022-06222/acceptability-of-probabilistic-risk-assessment-results-for-advanced-non-light-water-reactor 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 | ||
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| [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 | | [8] || [https://www.nrc.gov/docs/ML1924/ML19241A472.pdf 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 | ||
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| [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 | | [9] || [https://www.nrc.gov/docs/ml2009/ml20091l698.pdf 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 | ||
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| [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 | | [10] || [https://aris.iaea.org/publications/smr_book_2020.pdf 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 | ||
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| [11] || United States Code of Federal Regulations 10CFR50 Appendix A: General Design Criteria for Nuclear Power Plants || NRC | | [11] || [https://www.ecfr.gov/current/title-10/chapter-I/part-50/subject-group-ECFR89aa6ca4aada73c/appendix-Appendix%20A%20to%20Part%2050 United States Code of Federal Regulations 10CFR50 Appendix A: General Design Criteria for Nuclear Power Plants] || 2007 || NRC | ||
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| [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 | | [12] || [https://www.federalregister.gov/documents/2018/04/09/2018-07214/guidance-for-developing-principal-design-criteria-for-non-light-water-reactors 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 | ||
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| [13] || The Canadian Nuclear Safety Commission’s Strategy Readiness to Regulate Advanced Reactor Technologies; Canadian Nuclear Safety Commission; Ottawa, Ontario (December 2019) || CNSC | | [13] || [https://www.cnsc-ccsn.gc.ca/eng/reactors/regulating-nuclear-reactors-power-plants/new-nuclear-projects/strategy-readiness-regulate-advanced-reactor-technologies/ The Canadian Nuclear Safety Commission’s Strategy Readiness to Regulate Advanced Reactor Technologies; Canadian Nuclear Safety Commission; Ottawa, Ontario (December 2019)] || 2019 || CNSC | ||
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| [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 | | [14] || [https://www-pub.iaea.org/MTCD/Publications/PDF/Pub1715web-46541668.pdf 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 | ||
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| [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 | | [15] || [https://www-pub.iaea.org/MTCD/Publications/PDF/te_1366_web.pdf 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 | ||
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| [16] || IAEA-TECDOC-1570; Proposal for a Technology-Neutral Safety Approach for New Reactor Designs; International Atomic Energy Agency; Vienna, Austria (2003) || IAEA | | [16] || [https://www-pub.iaea.org/MTCD/Publications/PDF/TE_1570_web.pdf IAEA-TECDOC-1570; Proposal for a Technology-Neutral Safety Approach for New Reactor Designs; International Atomic Energy Agency; Vienna, Austria (2003)] || 2003 || IAEA | ||
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| [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 | | [17] || [http://www.iaea.org/publications/15180/approach-and-methodology-for-the-development-of-regulatory-safety-requirements-for-the-design-of-advanced-nuclear-power-reactors 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 | ||
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| [18] || CNSC REGDOC-3.5.3, Regulatory Fundamentals, version 2.0, Canadian Nuclear Safety Commission; Ottawa, Ontario (February 2020) || CNSC | | [18] || [https://www.cnsc-ccsn.gc.ca/eng/acts-and-regulations/regulatory-documents/published/html/regdoc3-5-3-v2/ CNSC REGDOC-3.5.3, Regulatory Fundamentals, version 2.0, Canadian Nuclear Safety Commission; Ottawa, Ontario (February 2020)] || 2020 || CNSC | ||
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| [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 | | [19] || [https://www.nrc.gov/docs/ML1927/ML19275D578.pdf 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 | ||
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| [20] || Technology Inclusive and Risk-Informed Reviews for Advanced Reactors: Comparing the US Licensing Modernization Project with the Canadian Regulatory Approach || NRC & CNSC | | [20] || [https://www.cnsc-ccsn.gc.ca/eng/corporate/agreements-partnerships/international-agreements/joint-report-smr-licensing-modernization-project/ Technology Inclusive and Risk-Informed Reviews for Advanced Reactors: Comparing the US Licensing Modernization Project with the Canadian Regulatory Approach] || 2022 || NRC & CNSC | ||
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| [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 | | [21] || [https://art.inl.gov/licensing/Licensing%20Documents/Guidance%20for%20Developing%20Principal%20Design%20Criteria%20(INL-EXT-14-31179-R1).pdf 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 | ||
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| [22] || IAEA-TECDOC-1909; Consideration on Performing Integrated Risk Informed Decision Making; IAEA, Vienna, Austria (2020) || IAEA | | [22] || [http://www.iaea.org/publications/13509/considerations-on-performing-integrated-risk-informed-decision-making IAEA-TECDOC-1909; Consideration on Performing Integrated Risk Informed Decision Making; IAEA, Vienna, Austria (2020)] || 2020 || IAEA | ||
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| [23] || Generation IV International Forum (GIF), 2002. A Technology Roadmap for Generation IV Nuclear Energy Systems. GIF-002-00 || DOE | | [23] || [https://www.gen-4.org/gif/upload/docs/application/pdf/2013-09/genivroadmap2002.pdf Generation IV International Forum (GIF), 2002. A Technology Roadmap for Generation IV Nuclear Energy Systems. GIF-002-00] || 2002 || DOE | ||
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| [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 | | [24] || [https://www.iapsam.org/psam14/proceedings/paper/paper_383_1.pdf 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 | ||
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| [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 | | [25] || [https://www.oecd-nea.org/jcms/pl_19234/a-joint-report-on-psa-for-new-and-advanced-reactors?details=true 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 | ||
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| [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 | | [26] || [https://epubs.ans.org/download/?a=45680 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 | ||
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| [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 | | [27] || [https://www.sciencedirect.com/science/article/pii/S0149197020302559 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 | ||
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| [28] || Program on Technology Innovation: Early Integration of Safety Assessment into Advanced Reactor Design - Project Capstone Report: EPRI, Palo Alto, CA: 2019. 3002015752. || EPRI | | [28] || [https://www.epri.com/research/products/000000003002015752 Program on Technology Innovation: Early Integration of Safety Assessment into Advanced Reactor Design - Project Capstone Report: EPRI, Palo Alto, CA: 2019. 3002015752.] || 2019 || EPRI | ||
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| [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 | | [29] || [https://www.epri.com/research/products/000000003002018340 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 | ||
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| [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 | | [30] || [https://www.sciencedirect.com/science/article/pii/S0149197022000518 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 | ||
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| [31] || Program on Technology Innovation: Probabilistic Risk Assessment Requirements for Passive Safety Systems. EPRI, Palo Alto, CA: 2007. 1015101. || EPRI | | [31] || [https://www.epri.com/research/products/000000000001015101 Program on Technology Innovation: Probabilistic Risk Assessment Requirements for Passive Safety Systems. EPRI, Palo Alto, CA: 2007. 1015101.] || 2007 || EPRI | ||
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| [32] || Program on Technology Innovation: Comprehensive Risk Assessment Requirements for Passive Safety Systems. EPRI, Palo Alto, CA; 2008. 1016747. || EPRI | | [32] || [https://www.epri.com/#/pages/product/1016747/ Program on Technology Innovation: Comprehensive Risk Assessment Requirements for Passive Safety Systems. EPRI, Palo Alto, CA; 2008. 1016747.] || 2008 || EPRI | ||
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| [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 | | [33] || [https://www.sciencedirect.com/science/article/abs/pii/S0149197021004133 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 | ||
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| [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 | | [34] || [https://www.sciencedirect.com/science/article/abs/pii/S0306454922000512 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 | ||
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| [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 | | [35] || [https://www.sciencedirect.com/science/article/pii/S0951832022001119 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 | ||
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| [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 | | [36] || [https://www.sciencedirect.com/science/article/abs/pii/S0306454920301857 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 | ||
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| [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 | | [37] || [https://www.sciencedirect.com/science/article/abs/pii/S0029549303001055 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 | ||
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| [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 | | [38] || [https://indico.ictp.it/event/a09155/session/43/contribution/36/material/0/0.pdf 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 | ||
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| [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 | | [39] || [https://onlinelibrary.wiley.com/doi/10.1155/2008/573192 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 | ||
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| [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 | | [40] || [https://www.frontiersin.org/journals/energy-research/articles/10.3389/fenrg.2014.00040/full 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 | ||
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| [41] || United Kingdom National Nuclear Regulator Position Paper, “Considerations of External Events for New Nuclear Installations”; PP-0014, Rev 0 || NNR | | [41] || [https://nnr.co.za/wp-content/uploads/2023/02/RSA_CNS-Report-2022.pdf United Kingdom National Nuclear Regulator Position Paper, “Considerations of External Events for New Nuclear Installations”; PP-0014, Rev 0] || 2022 || NNR | ||
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| [42] || TECDOC-1487, “Advanced Nuclear Power Plant Design Options to Cope with External Events”, IAEA-TECDOC-1487 ¦ 92-0-100506-7, 2006 || IAEA | | [42] || [http://www.iaea.org/publications/7431/advanced-nuclear-power-plant-design-options-to-cope-with-external-events TECDOC-1487, “Advanced Nuclear Power Plant Design Options to Cope with External Events”, IAEA-TECDOC-1487 ¦ 92-0-100506-7, 2006] || 2006 || IAEA | ||
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| [43] || IAEA, Technical Approach to Probabilistic Safety Assessment for Multiple Reactor Units, Safety Report Series To Be Published, IAEA, Vienna (2019) || IAEA | | [43] || [http://www.iaea.org/publications/12228/technical-approach-to-probabilistic-safety-assessment-for-multiple-reactor-units IAEA, Technical Approach to Probabilistic Safety Assessment for Multiple Reactor Units, Safety Report Series To Be Published, IAEA, Vienna (2019)] || 2019 || IAEA | ||
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| [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 | | [44] || [https://proceedings.cns-snc.ca/index.php/pcns/article/view/5626 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 | ||
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| [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 | | [45] || [https://www.nrc.gov/docs/ML1415/ML14150A330.pdf 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 | ||
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| [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 | | [46] || [https://www.iaea.org/sites/default/files/19/12/smr_rf_dsa_interim_report.pdf 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 | ||
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| [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 | | [47] || [https://www.epri.com/research/programs/061177/results/3002020765 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 | ||
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| [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 | | [48] || [https://www.sciencedirect.com/science/article/pii/S2095809917306124 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 | ||
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| [49] || HAZCADS: Hazards and Consequences Analysis for Digital Systems (Revision 1). EPRI, Palo Alto, CA: 2021. 3002016698. || EPRI | | [49] || [https://www.epri.com/research/programs/065093/results/3002016698 HAZCADS: Hazards and Consequences Analysis for Digital Systems (Revision 1). EPRI, Palo Alto, CA: 2021. 3002016698.] || 2025 || EPRI | ||
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| [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 | | [50] || [https://www.sciencedirect.com/science/article/abs/pii/S0029549323001243 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 | ||
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