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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
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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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|Methods
Monday, April 22, 2024|10:15AM–12:00PM PDT|Continental Ballroom 1
Session Chair:
Ken-ichi Tada (Japan Atomic Energy Agency)
Alternate Chair:
Vaibhav Jaiswal (IRSN)
Session Organizer:
Go Chiba (Hokkaido University)
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An Optimization Approach to Improve Thermal Scattering Law Using Experimental Total Cross Section Data
10:15–10:35AM PDT
Paper
Generation of Enrichment-Dependent Thermal Neutron Scattering Data
10:35–10:55AM PDT
B.K. Laramee (NCSU), N.C. Fleming (NCSU), J.P.W. Crozier (NCSU), A.I. Hawari (NCSU)
Development of Thermal Scattering Law and Cross Sections of Hydrogen in Paraffin Wax
10:55–11:15AM PDT
T. Ahmed (NCSU), N.C. Fleming (NCSU), A.I. Hawari (NCSU)
Thermal Neutron Scattering Behavior of Nitrogen-Enriched Uranium Mononitride
11:15–11:35AM PDT
Amelia Trainer (Naval Nuclear Laboratory), Jonathan Wormald (Naval Nuclear Laboratory), Jesse Holmes (Naval Nuclear Laboratory), Mike Zerkle (Naval Nuclear Laboratory)
Embedding Neural Thermal Scattering (NeTS) Modules in SERPENT for Higher Fidelity Advanced Reactor Analysis
11:35–11:55AM PDT
Jonathan P.W. Crozier (NCSU), Ayman I. Hawari (NCSU)
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