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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Science and Engineering
November 2021
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Fusion Science and Technology
August 2021
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Ensuring a role for nuclear in the response to climate change
Richard Meserve
Nuclear power is an important tool in the response to climate change, and advanced reactors may offer advantages over existing plants in providing carbon-free generation at the scale necessary to respond to the existential challenge that climate change presents. The International Atomic Energy Agency is aggressively addressing issues related to the possible transition to advanced reactors. This letter is to urge a redoubling of effort by Member States to put in place the necessary capabilities to deal with the challenges that they present.
Wednesday, November 10, 2021 | 1:00-3:00 EST
Schedule
Description: The Fire Risk Investigation in 3D (FRI3D) software was initially developed as part of the research for enhanced fire analysis under Light Water Reactor Sustainability (LWRS) program. The goal of this software has two parts: (1) provide industry with a tool to simplify the process for developing and using detailed fire models; (2) provide a back-end for future enhanced fire analysis and possible extension to dynamic probabilistic risk analysis models. The FRI3D software was developed over the last two years to integrate 3D spatial modeling with existing fire probabilistic risk assessment (PRA) models and fire simulation codes.
Purpose of Workshop: Learn how to use FRI3D software to perform fire modeling and PRA. FRI3D encapsulates the fire and plant data into a unified database and simplifies the process with automated simulations using CFAST, THIEF, Heat Soak Methods. The workshop will serve as a guide to use FRI3D to perform Fire PRA and advanced fire modeling.
Presenter Bios: Ramprasad (Ram) Sampath is the founder and CEO of Centroid LAB an engineering software consultancy firm performing Advanced Visualization and Computational Dynamics and Simulations.
Steven Prescott, is a software analysis/integration engineer for the Risk Assessment and Management Services Department at Idaho National Laboratory. He specializes scientific and technical software design and development.
Description: To facilitate the deployment of advanced nuclear power reactors, it is time-critical to focus on the risk-informed analysis of advanced reactors prior to, or in parallel with, technology developments. In recent years, there have been major efforts in the PRA developments for advanced reactors and its use in risk-informed decision-making, such as the Licensing Modernization Project (LMP), development of Title 10 of the Code of Federal Regulations, Part 53 (10CFR53) and other regulatory guidance by the Nuclear Regulatory Commission (NRC), as well as issuance of the ASME/ANS Non-LWR Probabilistic Risk Assessment Standard (RA-S-1.4-2021); however, there are still significant research needs for methodology developments. One of the key methodological challenges is that a design-specific experiential database is often limited or not available for advanced reactors, while the applicability and relevancy of the experiential data from the existing fleet to advanced reactors may be questionable due to differences in design principles, physical conditions, and operation and maintenance procedures. This workshop discusses the challenges and highlights possible research paths to alleviate them. As an example of the recent research activities, the methodological advancements and benchmark studies in an International Atomic Energy Agency (IAEA) Coordinated Research Project, “Methodology for Assessing Pipe Failure Rates in Advanced Water Cooled Reactors (WCRs),” are demonstrated. Based on the outcomes and insights from this IAEA project and other recent research activities, recommendations regarding the risk-informed analysis of advanced reactors are provided.
Purpose of Workshop: Identify the needs and methodological challenges in risk-informed analysis for advanced nuclear power reactors. Discuss research directions and paths to address those needs and challenges to facilitate the deployment of advanced reactors. As a case study, demonstrate the ongoing IAEA coordinated research project and provide recommendations.
This workshop will be led by the Socio-Technical Risk Analysis (SoTeRiA) Research Laboratory in the Department of Nuclear, Plasma, and Radiological Engineering at the University of Illinois at Urbana-Champaign.
Last modified October 12, 2021, 11:16am EDT
