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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
2022 ANS Winter Meeting and Technology Expo
November 13–17, 2022
Phoenix, AZ|Arizona Grand 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!
Latest Magazine Issues
Sep 2022
Jul 2022
Latest Journal Issues
Nuclear Science and Engineering
October 2022
Nuclear Technology
Fusion Science and Technology
Latest News
OPG, Microsoft to work toward net-zero future for Ontario
Ontario Power Generation and Microsoft Canada have formed a partnership aimed at combatting climate change and driving sustainable growth across the province of Ontario, the Canadian utility announced this week.
Under the partnership, Microsoft will procure clean energy credits (CECs) sourced from OPG’s nuclear and hydro assets in Ontario on an hourly basis. (OPG’s nuclear assets include the four-unit Darlington plant and six-unit Pickering facility.) According to the announcement, this will enable Microsoft to advance toward its 100/100/0 by 2030 goal, which commits the software firm to powering its data centers globally with zero-carbon energy, 24/7.
Technical Session
Thursday, May 19, 2022|8:00–9:45AM EDT|Brighton III/IV
Session Chair:
Carlo Fiorina (EPFL)
Track Organizer:
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Recent Developments in the OpenMC Monte Carlo Particle Transport Code
Paul K. Romano (ANL), Patrick C. Shriwise (ANL), Sterling M. Harper (TerraPower), Andrew E. Johnson (Ultra Safe Nuclear Corp.), Amanda L. Lund (ANL), Jingang Liang (Tsinghua Univ.), John R. Tramm (ANL), Andrew Davis (Culham Centre for Fusion Energy), Daniel Short (Culham Centre for Fusion Energy), Younghui Park (Univ. Wisconsin, Madison)
Summary
Automatic Conversion of MCNP Geometries to TRIPOLI-4®
Davide Mancusi (CEA)
Verification of OpenMC Neutronic Code for Transuranic Waste Incineration in Reduced Moderation Boiling Water Reactor
Sivakorn Sansawas (King Mongkut's Univ. Technology Thonburi), Saksorn Ruangtanusak (King Mongkut's Univ. Technology Thonburi), Yanin Sukjai (King Mongkut's Univ. Technology Thonburi)
Pre-Release Validation Database for the Multi-Dimensional Fuel Performance Code OFFBEAT
A. Scolaro (École Polytechnique Fédérale de Lausanne), C. Fiorina (École Polytechnique Fédérale de Lausanne), I. Clifford (Paul Scherrer Institute), E. Brunetto (École Polytechnique Fédérale de Lausanne), A. Pautz (Paul Scherrer Institute)
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