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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
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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Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Technical Session|Sponsored by MSTD
Tuesday, June 9, 2020|12:00–2:10PM EDT
Alternate Chair:
Kenneth J. Geelhood
Session Organizer:
Staff Producer:
Jay Bogardus (American Nuclear Society)
To access the session recording, you must be logged in and registered for the meeting.
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To access paper attachments, you must be logged in and registered for the meeting.
Preliminary Results from In-Pile Transient Boiling Experiments at the TREAT Facility
R. Christensen (Univ. of Idaho), K. Terrill (Univ. of Idaho), N. Brown (Univ. of Tenn., Knoxville), R. Hernandez (Univ. of Tenn., Knoxville), D. Wachs (INL), R. Armstrong (INL), A. Fleming (INL), N. Woolstenhulme (INL), C. Folsom (INL), C. Jensen (INL)
Paper
Informing Transient Testing of Fuel Designs for the Transformational Challenge Reactor
Robert Kile (Univ. of Tenn., Knoxville), Nicholas R. Brown (Univ. of Tenn., Knoxville), Kurt A. Terrani (ORNL), Gokul Vasudevamurthy (ORNL), Aaron J. Wysocki (ORNL), Daniel Schappel (ORNL)
Strontium Diffusivity in IG-110 Graphite Using a Time-Release Method
Taylor Mae Weilert (Univ. of Missouri)
Establishing Maximal Core Excess Reactivity Envelope for TREAT Test Vehicle Insertion
James R. Parry (INL), Nicolas E. Woolstenhulme (INL), John D. Bess (INL)
HFIR Irradiation Testing Supporting the Transformational Challenge Reactor
R. H. Howard (ORNL), K. A. Terrani (ORNL), T. S. Byun (ORNL), X. Hu (ORNL), P. Champlin (ORNL), K. D. Linton (ORNL), A. G. Le Coq (ORNL)
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