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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.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
M. D. Freshley, E. A. Aitken, D. C. Wadekamper, R. L. Johnson, W. G. Lussie
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 239-248
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31148
Articles are hosted by Taylor and Francis Online.
Transient tests were conducted on nonirradiated oxide pellet-containing fuel pins at SPERT to investigate the possible effects of large single 550-μm diam PuO2 particles on transient behavior. Results show that the effect of the large PuO2 particles was to reduce slightly the cladding failure threshold energy from the range of 225 to 274 cal/g of fuel to the range of 200 to 213 cal/g of fuel. Clad perforation occurs by localized melting caused by the expulsion of PuO2 particles through the cladding. The presence of single 550-μm diam PuO2 particles in mixed-oxide fuels does not appear to affect significantly the cladding failure threshold energy from that of mixed-oxide fuels with the normal PuO2 particle size and distribution. Therefore, product specifications which limit the maximum PuO2 particle size to 550-μm diam in mixed-oxide fuels do not appear warranted from the standpoint of transient fuel performance considerations.
