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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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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|Experimental Reactor Physics
Monday, April 22, 2024|1:30–3:15PM PDT|Franciscan B
Session Chair:
Tomas Peltan (Research Center Rez)
Alternate Chair:
Antonin Krasa
Session Organizer:
Luka Snoj
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Reactor Pressure Vessel Characterization Methods Development for the High Flux Isotope Reactor to Support Future Vessel Replacement
1:30–1:50PM PDT
D. Chandler (ORNL), K. Burg (ORNL)
Paper
Californium-252 Production Validation Studies at the High Flux Isotope Reactor with Campaign 78 Data
1:50–2:10PM PDT
D. Hartanto (ORNL), D. Chandler (ORNL), G. Power (ORNL), J. Bae (ORNL), K. Burg (ORNL)
Prediction of the TREAT Facility Power and Temperature of Sirius-2c Nuclear Propulsion Fuel Experiment
2:10–2:30PM PDT
Mustafa K. Jaradat (INL), Sebastian Schunert (INL), Frederick N. Gleicher (INL), Mark DeHart (INL)
Testing and Implementation of 6% Enriched UO2 Fuel at the PULSTAR Reactor
2:30–2:50PM PDT
N.C. Fleming (NCSU), A.I. Hawari (NCSU)
Current Status of the Water Activation Loop at JSI TRIGA Reactor
2:50–3:10PM PDT
D. Kotnik (Jožef Stefan Institute), J. Peric (Jožef Stefan Institute), L. Snoj (Jožef Stefan Institute), I. Lengar (Jozef Stefan Institute)
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