ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
2022 ANS Winter Meeting and Technology Expo
November 13–17, 2022
Phoenix, AZ|Arizona Grand Resort
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!
Latest Magazine Issues
Latest Journal Issues
Nuclear Science and Engineering
Fusion Science and Technology
Environmental Management: GAO Report Shows Mission Far From Complete
This spring, the U.S. Government Accountability Office (GAO) released an insightful report reviewing and summarizing the status and performance of the largest projects and operations within the Department of Energy’s Office of Environmental Management (EM), which is responsible for the cleanup of hazardous and radioactive waste at sites and facilities that have been contaminated from decades of nuclear weapons production and nuclear energy research.
Workshop 1 (below)
Wednesday, November 10, 2021 | 12:40-2:40 PM EST
Cost: $100 Workshop Only; $50 Full Meeting Paid Attendee
Ramprasad (Ram) SampathCentroid LAB
Steven PrescottIdaho National Laboratory
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.
Attendees will receive a certificate of attendance for these workshops.
Workshop #1 will be recorded and have access to the recorded presentations after the workshop.
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.
Wednesday, November 10, 2021 | 12:40-4:10 PM EST
Bengt LydellSigma-Phase Inc.
Tatsuya Sakurahara University of Illinois Urbana-Champaign
Klaus HeckmannGesellschaft für Anlagen- und
Robertas AlzbutasLithuanian Energy Institute
Zahra MohagheghUniversity of Illinois Urbana-Champaign
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 November 9, 2021, 2:22pm EST