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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 Annual Meeting
June 12–16, 2022
Anaheim, CA|Anaheim Hilton
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
June 2022
Nuclear Technology
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Latest News
Deadline extended to apply for ANS's 2023 ANS Congressional Fellowship
The deadline for applications to the ANS's Glenn T. Seaborg Congressional Science and Engineering Fellowship has been extended. All ANS members are invited to apply to help the Society fulfill its strategic goal of informing nuclear public policy.
All applications and supporting documents are now due by 11:59 p.m. (EDT) on Monday, May 23.
Technical Session|Sponsored by MSTD
Tuesday, June 15, 2021|11:00AM–12:45PM (12:00–1:45PM EDT)
Session Chair:
Simon M. Pimblott
Alternate Chair:
Kenneth J. Geelhood
Session Organizer:
Staff Producer:
Rick Michal (ANS)
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Emulation of Fast Reactor Irradiated 21Cr32Ni Model Alloy using Dual-Ion Beam
Muhammet Ayanoglu (Pennsylvania State Univ.), Arthur T. Motta (Pennsylvania State Univ.)
Summary
Comparison of Calculated and Measured Performance of an Optical Fiber Based Gamma Thermometer
Anthony Birri (Ohio State Univ.), Christian Petrie (ORNL), Kelly McCary (INL), Thomas E. Blue (The Ohio State Univ.)
Experimental Validation of an Eddy Current Flow Meter Simulation
Greg Kinzler (Univ. of Pittsburgh), Heng Ban (Univ. of Pittsburgh)
Reference — Updated Summary
Effect of Core Material Properties on Wireless Power Transmission in Nuclear Reactors
Raza Sheikh (Univ. of Pittsburgh), Jerry Potts (Univ. of Pittsburgh), Paul Cox (Univ. of Pittsburgh), Heng Ban (Univ. of Pittsburgh)
Temperature Effect Uncertainty Analysis of a Mutual Inductance Level Sensor for use in Metallic Environments
Duane DiCenzo (Univ. of Pittsburgh), Brady Cameron (Univ. of Pittsburgh), Teddy Kent (ANL), Heng Ban (Univ. of Pittsburgh)
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