Two new American Nuclear Society standards recently received approval from the American National Standards Institute (ANSI). The new standard ANSI/ANS-56.2-2026, Containment Isolation Provisions for Fluid Systems After a LOCA, is a revision of historic ANS-56.2-1984 (W1999). ANS-GS-30.1-2026, Integrating Risk and Performance Objectives into Standards for New Reactor Designs, is a new guidance standard.

Both standards are available for purchase in the ANS Online Store.

The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) held another presentation in its monthly Community of Practice (CoP) series. Former RP3C chair N. Prasad Kadambi opened the April 24 meeting with brief introductory remarks about the RP3C and the overall importance of risk-informed, performance-based (RIPB) design principles.

The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) held another presentation in its monthly Community of Practice (CoP) series. Former RP3C chair N. Prasad Kadambi opened the March 27 meeting with brief introductory remarks about the RP3C and the recent incorporation of risk-informed, performance-based (RIPB) design principles in the Nuclear Regulatory Commission’s Part 53 framework. He then welcomed this month’s speaker: Lyndsey Fyffe, a nuclear safety engineer with Strategic Management Solutions, who presented “RIPB Terminology Across the Nuclear Industry.”

The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) has held another presentation in its monthly Community of Practice (CoP) series. Former RP3C chair N. Prasad Kadambi opened the meeting with brief introductory remarks about the RP3C and the need for new approaches to nuclear design that go beyond conventional and deterministic methods. He then welcomed this month’s speaker: Craig Benson from the University of Wisconsin–Madison, who presented “Natural Systems Approach for Closure of Uranium Mill Tailing Facilities.”

The 4th Annual Advanced Reactor Codes and Standards Collaborative (ARCSC) Workshop will take place on December 4 from 9:00 a.m. to 5:00 p.m. (EST). The event, which will be hosted at the Electric Power Research Institute’s office Washington, D.C., has a hybrid format, offering the opportunity for both in-person and virtual attendance. It’s focus is on sharing the ARCSC’s progress on developing codes and standards to support advanced reactor development and will also feature industry-focused breakout discussions, conversations with industry leaders, and more.

Click here to register for the workshop.

The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) has held another presentation in its monthly Community of Practice (CoP) series. Former RP3C chair N. Prasad Kadambi opened the meeting with brief introductory remarks about the RP3C and the need for new approaches to nuclear design that go beyond conventional and deterministic methods. He then welcomed this month’s speaker: Doug Gerstner, a nuclear safety engineer at Idaho National Laboratory, who presented “Application of a Qualitative RIPB Approach for the MARVEL Microreactor at INL.”

Watch the full webinar here.

The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) has held another presentation in its monthly Community of Practice (CoP) series. Former RP3C chair N. Prasad Kadambi opened the meeting with brief introductory remarks about the RP3C and the need for new approaches to nuclear design that go beyond conventional and deterministic methods. He then welcomed this month’s speaker: Kent Welter, a member of the ANS Standards Board and chief engineer of testing and analysis at NuScale, who presented “RIPB Design and Licensing of the NuScale US460 Small Modular Reactor.”

Watch the full webinar here.

The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) has held another presentation in its monthly Community of Practice (CoP) series. Former RP3C chair N. Prasad Kadambi opened the June 27 meeting with brief introductory remarks about the RP3C and the need for new approaches to nuclear design that go beyond conventional and deterministic methods. He then welcomed this month’s speaker: Tim Sande, a senior manager responsible for probabilistic risk assessments (PRA) and risk-informed engineering at Enercon, who presented “A Risk-Informed Framework for Managing Nuclear Facility Security Risks.”

Watch the full webinar here.

The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) held another presentation in its monthly Community of Practice (CoP) series.

Watch the full webinar here.

The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) held another presentation in its monthly Community of Practice (CoP) series on April 4.

In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.

The Nuclear Regulatory Commission has published a proposed rule that has been almost five years in the making: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors. The rule, which by law must take its final form before the end of 2027, would establish risk-informed, performance-based techniques the NRC can use to review and license any nuclear power reactor. This is a departure from the two licensing options with light water reactor–specific regulatory requirements that applicants can already choose.

Each month on the last Friday from 3:00 p.m. to 4:00 p.m. (ET), the American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) holds a Community of Practice (CoP), which is open to all. On February 23, N. Prasad Kadambi, director of his eponymous engineering consultancy firm, presented “Technology-Inclusive Implications of ANSI/ANS-30.3-2022, Light Water Reactor Risk-Informed, Performance-Based Design.”

The American Nuclear Society has published the first voluntary consensus standard for nuclear reactor design that formally incorporates risk-informed, performance-based (RIPB) decision-making in July 2022. ANSI/ANS-30.3-2022, Light Water Reactor Risk-Informed, Performance-Based Design, tells reactor designers how they can incorporate RIPB principles and methods to ensure safety in new commercial light water reactor designs, and it includes a spectrum of options using both deterministic and risk-based approaches. As the first such standard, ANSI/ANS-30.3-2022 represents progress toward the adoption of RIPB principles for nuclear regulation and licensing—a shift the Nuclear Regulatory Commission was directed to make in the Nuclear Energy Innovation and Modernization Act, which became law five years ago.

Nuclear Safety Design Criteria and Functional Performance Requirements for Liquid-Fuel Molten Salt Reactor Nuclear Power Plants (ANSI/ANS-20.2-2023) has just been issued and is now available for purchase. It was developed by the American Nuclear Society and received approval from the American National Standards Institute (ANSI) on January 4.

By all accounts, 2022 brought many successes for the American Nuclear Society’s Standards Committee, including the initiation of five projects, reaffirmation of 11 current standards, and publication of seven new or revised standards. The entire collection of ANS current standards has been approved or reaffirmed (reapproved without change) by the American National Standards Institute (ANSI) within the past five years, keeping ANS in 100 percent compliance with ANSI’s requirement on maintaining current American National Standards. Also, the ANS standards program was reaccredited by ANSI on August 19, 2022, with the approval of a revised set of rules and procedures. ANS’s new rules and procedures take advantage of the opportunity to develop standards-related technical reports that may be registered with ANSI.

As the largest ultra-low-carbon electricity source in the United States, nuclear energy is a vital pillar of the effort to mitigate climate change. Deployment of advanced nuclear reactor and fuel technologies has been identified as a unique challenge in the production of new nuclear power plants to help maintain and grow our nuclear generating capacity. The licensing of novel nuclear reactor technologies also continues to be a facet of the broader challenge of advanced reactor deployment. When it comes to non–light water reactors and Generation III+ light water reactors, such as the AP-1000 or EPR, deployment is “2X over budget and behind schedule.”¹ However, in the case of recent large Generation III+ light water reactors, licensing has not been the rate-limiting step in the reactor deployment timeline, nor has it had a first-order impact on cost. With that said, several significant advances have been made in the expedition of licensing. This article focuses on three areas where progress has been made since this grand challenge was formulated in 2017, with highlights of some examples where the American Nuclear Society has guided or supported this progress.

The American Nuclear Society has recently published a new standard:

ANSI/ANS-30.3-2022, Light Water Reactor Risk-Informed, Performance-Based Design.

The standard is available for purchase from the ANS Store.

The ASME/ANS Joint Committee on Nuclear Risk Management (JCNRM) has achieved a significant milestone in the advancement of probabilistic risk assessment (PRA) technology. ANSI/ASME/ANS RA-­S-­1.4–2021 [1], Probabilistic Risk Assessment Standard for Advanced Non-­Light Water Reactor Nuclear Power Plants, has been approved by the JCNRM, the ANS Standards Board, the ASME Board of Nuclear Codes and Standards, and the American Nuclear Standards Institute.

Caroline Cochran, chief operating officer of Oklo Inc., and Sarah Bristol, PRA supervisor at NuScale Power, have given presentations recently for the American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) Community of Practice (CoP).