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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
S. M. Zivi, M. Epstein, R. W. Wright, J. J. Barghusen, D. H. Cho, F. J. Testa, G. T. Goldfuss, R. W. Mouring
Nuclear Science and Engineering | Volume 56 | Number 3 | March 1975 | Pages 229-240
Technical Paper | doi.org/10.13182/NSE75-A26737
Articles are hosted by Taylor and Francis Online.
Two in-pile transient experiments were performed in the TREAT Reactor Facility to investigate fuel-coolant interaction phenomena that might occur in a hypothetical prompt-burst disassembly accident involving extensive fuel vaporization in a nearly unvoided liquid-metal fast breeder reactor core. In these tests, a single fuel pin containing 28 g of UO2 was subjected to a self-limited 23-msec-period TREAT power excursion which deposited fission energy of 1700 cal/g of UO2 in the fuel. The pin was contained in an instrumented autoclave filled with stagnant sodium. Failure of the fuel pins occurred at a mean energy input of about 540 cal/g, corresponding to a UO2 vapor pressure of about 100 atm. Results of these tests indicated that no energetic fuel-coolant interaction was produced and that the measured transient pressures can be reasonably described by the time history of the fuel vapor pressure.