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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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May 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|Methods
Wednesday, April 24, 2024|1:30–3:15PM PDT|Franciscan D
Session Chair:
Tamer Bahadir (Studsvik Scandpower)
Alternate Chair:
Qicang Shen (Univ. Michigan)
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Preliminary Study on Two-Dimensional SP3 Calculation Based on POD-Local/Global Iterations
1:30–1:50PM PDT
Masato Ito (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Yasuhiro Kodama (Nuclear Fuel Industries), Taichi Takeishi (Nuclear Fuel Industries), Hiroaki Nagano (Nuclear Fuel Industries)
Paper
Real-Time 3D Fine Spatial Mesh Kinetics Simulator Using POD for Coupled Core
1:50–2:10PM PDT
Kaito Ito (Nagoya Univ.), Kosuke Tsujita (Nuclear Engineering), Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.)
Neutron Flux Reconstruction from Out-Core Sparse Measurements Using Data-Driven Reduced Order Modelling
2:10–2:30PM PDT
Stefano Riva (Politecnico di Milano), Sophie Deanesi (Politecnico di Milano), Carolina Introini (Politecnico di Milano), Stefano Lorenzi (Politecnico di Milano), Antonio Cammi (Politecnico di Milano)
Presented by Lorenzo Loi (Politecnico di Milano)
Reconstruction of In-Core Power Distribution Based on POD Using Ex-Core Detector Signals
2:30–2:50PM PDT
Yuki Urase (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.)
Hybrid Reduced-Order Modeling Based on Reduced Basis and PCQM Methods for Time-Dependent Diffusion Problem with Cross Section Feedback
2:50–3:10PM PDT
Qicang Shen (Univ. Michigan), Brendan Kochunas (Univ. Michigan)
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