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Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
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About Studsvik Scandpower
Studsvik Scandpower (SSP) is the leading global provider of vendor-independent, state-of-the-art nuclear fuel management software and world-class engineering services. SSP offers a full suite of software product offerings, training, and engineering services, to support operating utilities, fuel vendors, safety authorities, and research organizations around the world.
Technical Session
Wednesday, May 18, 2022|1:30–3:15PM EDT|Haselton
Session Chair:
Baocheng Zhang
Alternate Chair:
Petri Guimaraes (Studsvik Scandpower)
Session Organizer:
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An Inline Burn-up Algorithm: Proposal and Preliminary Analysis
P. Cosgrove (Univ. Cambridge), E. Shwageraus (Univ. Cambridge), J. Leppänen (VTT Technical Research Centre of Finland)
Paper
Study of Reference Burnup Steps Optimization in Fuel Segment Data File Generation for NEXUS/ANC9 Code System
Baocheng Zhang (Westinghouse Electric Co. ), Mike Gavalek (Westinghouse Electric Co.)
Application of the bRapid Fission Matrix Burnup Methodology to the JSI TRIGA Mark II Research Reactor
Anze Pungercic (Jožef Stefan Institute), Alireza Haghighat (Virginia Tech), Luka Snoj (Jožef Stefan Institute)
An APEC-Corrected 2-D NEM Macroscopic Depletion Analysis of Partial MOX SMRs
Seongdong Jang (KAIST), Taesuk Oh (KAIST), Yonghee Kim (KAIST)
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