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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Ensuring Safety and Cleanliness: The Crucial Role of Industrial Vacuums in Nuclear Power Facilities
The primary culprits behind contamination in a nuclear facility are fission products resulting from nuclear reactions and activated corrosion products like rust and metal. While these radioactive materials remain within the reactor system, the risk of contamination is minimal. However, the reality of a complex network of pipes and valves introduces vulnerabilities, leading to potential leaks and spills. The necessity for periodic system openings, required for sampling and maintenance, further heightens the risk of contamination. Once outside the system, radioactive materials can disperse, jeopardizing other plant components, areas, and even personnel.
Sunday, June 16, 2024|1:00–5:00PM PDT
Palm H
Session Organizers: Yeon Sang Jung / Shikhar Kumar (ANL)
Namjae Choi (INL)
Cost: $49 (SOLD OUT)
Maximum Attendance: 40
The objective of the Griffin workshop at the ICAPP/ANS conference is to offer participants an introduction and comprehensive understanding of advanced reactor simulation capabilities in Griffin. The workshop will primarily focus on fast reactor applications but will also briefly introduce applications to other reactor types. It is a 4-hr-long session that will include an overview of Griffin's methodologies, benchmark solutions, cross-section generation workflow, reference core calculations, and fuel cycle calculation using typical benchmark problems. Griffin/SAM multiphysics steady-state and transient calculations will be included as well. The session will also feature a hands-on exercise, allowing participants to engage with a small core example. The exercise will cover key aspects such as cross-section generation, core input generation, reference core calculation, and fuel cycle calculation. This interactive workshop aims to enhance participants' proficiency in utilizing Griffin for reactor simulations. While focusing on the fast reactor capabilities of Griffin, the workshop should be interesting to general users who want to explore cross-section generation and fuel cycle calculation capabilities of Griffin as well. This workshop requires participants to complete a quick code access licensing process beforehand.
Agenda:
The workshop will use the resources of the INL High Performance Computing (HPC) center. Participants can either apply for: A) an INL HPC account and code licenses directly via (https://inl.gov/ncrc/) or B) temporary INL HPC account and temporary access to the codes. Either way, details on the INL’s Nuclear Computational Resource Center training signup process will be shared with registered participants. Participants must bring their own laptops in order to run hands-on exercises. Details on the process will be shared with registered participants. Note the following cutoffs required for INL HPC account and license applications:
Cutoff for U.S.A. nationals INL HPC account and licenses is June 10, 2024.
Cutoff for foreign nationals INL HPC account and licenses is May 8, 2024.
