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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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May 2024
Jan 2024
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Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
How robust is HALEU from a nonproliferation perspective?
Shikha Prasad
High-assay low-enriched uranium (HALEU) has emerged as a popular fuel choice for advanced small modular reactors due to its long power production periods before refueling. It is currently being pursued by TerraPower, X-energy, BWX Technologies, Kairos, Oklo, and other reactor companies. HALEU has a uranium-235 enrichment ranging from 5 percent to 20 percent, whereas traditional LWRs use low-enriched uranium fuel enriched up to 5 percent.
HALEU will provide power for longer durations, compared with traditional LWRs. But could it also provide an opportunity for more rapid proliferation, as is speculated in a 2023 National Academy of Sciences report on advanced nuclear reactors (nap.nationalacademies.org/catalog/26630/)?
If a nuclear proliferator conspires to divert fresh nuclear fuel for weapons production when it has not been used in a reactor, the effort required in separative work units (SWUs) to enrich U-235 from 5 percent to 90 percent and that required to enrich from 20 percent to 90 percent are both very small, compared with the effort required to enrich U-235 from its natural abundance to the initial 5 percent.
Technical Session|Sponsored by Advanced/Novel Materials
Tuesday, December 12, 2023|10:00–11:40AM CST|Galerie 5
Session Chair:
Kevin G. Field (Univ. Michigan)
Track Organizers:
Janelle P. Wharry (Purdue Univeristy)
Grace Burke (INL)
Benjamin Sutton (Electric Power Research Institute (EPRI))
Alternate Chair:
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A Path Forward for Regulatory Acceptance of Combined Ion/Neutron Irradiation Data for Qualification
10:00–10:20AM CST
Stephen Taller (ORNL), Yiren Chen (ANL), Wei-Ying Chen (ANL), Rongjie Song (INL), Andrea Jokisaari (INL)
Paper
Ashby Maps for Nuclear Applications: New Opportunities for Nuclear Materials Design
10:20–10:40AM CST
M.I. Brand (Univ. New South Wales), M. Moschetti (Univ. New South Wales), P. Hosemann (Univ. California, Berkeley), J.J. Kruzic (Univ. New South Wales), E.G. Obbard (Univ. New South Wales), B. Gludovatz (Univ. New South Wales), P.A. Burr (Univ. New South Wales)
Design of Experiments for Qualifying Laser Powder Bed Fusion Processed Stainless Steel Components
10:40–11:00AM CST
Holden Hyer (ORNL), Josh Kendall (ORNL), David Collins (ORNL), Amir Ziabari (ORNL), Caleb Massey (ORNL)
Effect of Carbon Concentration on the Creep Resistance and Tensile Properties of Castable Nanostructured Alloys
11:00–11:20AM CST
Emily Proehl (Univ. Tennessee, Knoxville), Weicheng Zhong (ORNL), Ying Yang (ORNL), Lizhen Tan (ORNL), Steven Zinkle (Univ. Tennessee, Knoxville)
Radiation Tolerance of MX-Type Precipitates in Ferritic Martensitic Steels
11:20–11:40AM CST
K.G. Field (Univ. Michigan), T.M.K. Green (Univ. Michigan), K. Sun (Univ. Michigan), Robert Renfrow (Univ. Michigan), T. Graening (ORNL), W. Zhong (ORNL), E. Polselli (Univ. Michigan), L. Tan (ORNL), Y. Yang (ORNL)
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