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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Tennessee senators call on Trump to “rescue TVA from itself”
Hagerty
Blackburn
In a strongly worded opinion piece published by Power Magazine on March 24, Tennessee Sens. Marsha Blackburn and Bill Hagerty call for new leadership at the Tennessee Valley Authority to jumpstart its small modular reactor program.
The GOP lawmakers are looking to President Donald Trump and Energy Secretary Chris Wright to overhaul TVA’s board of directors to drive America’s role in the nuclear renaissance. TVA is the first and only U.S. energy company to obtain an early site permit for a small modular reactor, but the utility has not progressed on physical deployment of a unit since the permit was awarded in 2019.
The Consortium for Advanced Simulation of Light Water Reactors Virtual Meeting
Technical Session|Panel|Sponsored by Radiation Transport Methods
Wednesday, November 18, 2020|4:50–6:30PM EST
Session Chair:
Tara Pandya (ORNL)
Alternate Chair:
Bill Martin (Univ. of Michigan)
Track Organizer:
Scott Palmtag (NC State Univ.)
Staff Producers:
Monica V Pham (MIT)
Ralph Wiser (MIT)
The panel members will present their thoughts on the prospects (near-term and far-term) for Monte Carlo to be a routine tool for full-core reactor analysis including depletion and thermal-hydraulic feedback. Following these brief remarks, questions from the audience will be entertained.
To access the session recording, you must be logged in and registered for the meeting.
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Prospects for Full Core Monte Carlo Depletion with T/H Feedback
Daniel J. Kelly (BMPC)
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