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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
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.
Richard G. Bock, John D. Duncan, James E. Leonard
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 532-543
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30850
Articles are hosted by Taylor and Francis Online.
The first full-length, electrically heated, 49-rod, Zircaloy-clad simulated BWR fuel bundle with internally pressurized rods was spray cooled under loss-of-coolant conditions. The heater rods were internally pressurized with argon to simulate fission product gas inventory. Many perforations and severe rod distortions occurred near the center of the bundle. Nevertheless, spray cooling, initiated at a maximum cladding temperature of 1920°F, was effective in limiting cladding temperatures to ≈2250°F. Electrical failure of 10 heater rods complicated interpretation of the results, and it is estimated that the maximum temperature would have been ≈2360°F had the failures not occurred. The maximum coolant flow area reduction around a single rod caused by local perforations was 50%. However, this flow area reduction did not appreciably impair the effectiveness of the spray cooling system. That is, analysis performed using current General Electric (GE) loss-of-coolant technique s and heat transfer coefficients derived from stainless-steel-clad bundle tests predicted the maximum cladding temperature to within 20°F.