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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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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.
Hans K. Fauske
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 10-17
Technical Paper | doi.org/10.13182/NSE74-A23388
Articles are hosted by Taylor and Francis Online.
This paper discusses some aspects of pin-to-pin failure propagation in a sodium-cooled fast-reactor subassembly resulting from (a) fission-gas release, (b) a local blockage, and (c) release of small amounts of molten fuel. The consequence of a severe flow dilution due to fission-gas release from a highly burned-up fuel pin is shown to give rise to only minor overheating because of the strong effects of fuel heat capacity, radial heat conduction, and mixing. Analysis has also shown that the occurrence of local boiling due to local blockage of detectable size appears unlikely to lead to dryout and flow instability because of the large subcooling effect in the wake downstream of the blockage. Moreover, even if a pin in a fuel assembly is assumed to fail and release small amounts of molten fuel, calculations indicate that heat losses and condensation will prevent any significant pressure generation and void propagation and therefore reduce the likelihood of rapid failure propagation.