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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.
2022 ANS Annual Meeting
June 12–16, 2022
Anaheim, CA|Anaheim Hilton
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
Fusion Science and Technology
Majority of Americans favor new nuclear plants
Pollster Scott Rasmussen reports that 53 percent of American voters support the construction of new nuclear power plants in the United States, while 31 percent oppose new plants. He further reports that 21 percent strongly favor and 14 percent strongly oppose new nuclear facilities.
Technical Session|Sponsored by HFICD
Friday, December 3, 2021|12:00–1:45PM (1:00–2:45PM EST)|Columbia 4
Steven Arndt (ORNL)
Jamie Coble (University of Tennessee-Knoxville)
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Methods to Evaluate Embedded Sensor Performance for the Transformational Challenge Reactor
12:05–12:25PM (1:05–1:25PM EST)
William H. Ferrell IV (Analysis and Measurement Services Corp.), Jacob R. Houser (Analysis and Measurement Services Corp.), Holden C. Hyer (ORNL), Christian M. Petrie (ORNL)
Transit Time Flow Measurement via High-Temperature Irradiation-Resistant Thermocouples
12:25–12:45PM (1:25–1:45PM EST)
Alexander H. Hashemian (Analysis and Measurement Services Corp.), Richard Skifton (INL)
Trace Xenon Measurements Using Laser-Induced Breakdown Spectroscopy for Fuel Failure Monitoring in Generation IV Gas-Cooled Fast Reactors
12:45–1:05PM (1:45–2:05PM EST)
M. Burger (Univ. of Michigan), L. Garrett (Univ. of Michigan), A. Burak (Univ. of Michigan), V. Petrov (Univ. of Michigan), A. Manera (Univ. of Michigan), X. Sun (Univ. of Michigan), P. Sabharwall (INL), I. Jovanovic (Univ. of Michigan)
Design of a High Temperature Eddy Current Flow Meter via Thermal-Mechanical Simulation
1:05–1:25PM (2:05–2:25PM EST)
G. Kinzler (Univ. of Pittsburgh), U. Zangrilli (Univ. of Pittsburgh), H. Ban (Univ. of Pittsburgh)
Improvements in Antineutrino Detector Response by Including Fission Product Transitions
1:25–1:45PM (2:25–2:45PM EST)
Wei Eng Ang (Texas A&M Univ.), Sanghun Lee (Texas A&M Univ.), Shikha Prasad (Texas A&M Univ.)
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