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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Technical Session|Sponsored by IRD
Monday, June 12, 2023|3:15–5:00PM EDT|Marriott 9
Session Chair:
Brenden J. Heidrich
Session Organizer:
Alternate Chair:
Lei R. Cao
The DRIFT series of experiments at Idaho National Laboratory’s TREAT transient testing facility explored pellet cracking behavior in ceramic UO2 fuel pellets at LWR-relevant conditions to create data to support modeling and simulation of fuel performance. This session will march through the irradiation testing process to highlight the steps required to turn a hypothesis into an irradiation test that can produce usable data. The DRIFT-UO2 experiment at TREAT is based on the IRP-16-10905 - Heng Ben (PITT), Mary Lou Dunzig-Gougar (ISU), “Transient Reactor (TREAT) Experiments to Validate MBM Fuel Performance Simulations” https://neup.inl.gov/SiteAssets/FY%202016%20Abstracts/IRP/IRP-16-10905_TechnicalAbstract_2016CFAAbstract10905.pdf Benjamin Spencer, et al., “Dry in-pile fracture test (DRIFT) for separate-effects validation of ceramic fuel fracture models,” Journal of Nuclear Materials, 568 (2022), https://doi.org/10.1016/j.jnucmat.2022.153816
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Structure and Process of Managing the UO2 Dry In-Pile Fracture Test Irradiation Experiment
3:15–3:35PM EDT
Leigh A. Astle (INL), Trevor J. Smuin (INL)
Paper
Neutronics Programmatic and Safety Evaluation of the DRIFT Experiment in TREAT
3:35–3:55PM EDT
Connie M. Hill (INL)
Research Objectives and Findings from the DRIFT Experiments
3:55–4:15PM EDT
Benjamin Spencer (INL), Nicolas E. Woolstenhulme (INL), Jason L. Schulthess (INL), Austin D. Fleming (INL)
Experiment Safety Analysis Process for the DRIFT Irradiation Experiment at TREAT
4:15–4:35PM EDT
Sterling S. Morrill (INL)
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