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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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
DOE to award $900 million for milestone-based SMR deployment projects
Yesterday morning as Amazon, X-energy, Energy Northwest, and Dominion Energy were sharing a spotlight celebrating their investment in X-energy’s high-temperature gas-cooled reactor technology, the Department of Energy opened up the application process for up to $900 million in cost-shared funding to support the initial domestic deployment of a different type of reactor—light water reactors generating about 300 MWe that the DOE calls Gen III+ small modular reactors.
Michael D. Allen, Harlan W. Stockman, Kenneth O. Reil, Arthur J. Grimley
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 214-228
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT90-A34472
Articles are hosted by Taylor and Francis Online.
High-burnup uranium dioxide reactor fuel was heated in-pile at ∼2490 K in a reducing atmosphere (33% H2 in argon) for 16 min. Fission product aerosols and vapors released from the fuel were collected on a series of sequentially opened filters; the fractions of the original fuel inventory collected on the filters were f Cs = 0.56, f I = 0.38, f Ba = 0.078, f Sr = 0.053, f Eu = 0.064, and f Te < 0.002. The measured release rates for nonvolatile fission products were much higher than predicted by existing release codes, whereas tellurium release was much lower. Posttest examination of the fuel indicates extensive fuel/clad interaction, fuel swelling, and infiltration of the fuel by a zirconium-rich metallic melt; this melt kept oxygen potentials in the fuel very low. The low oxygen potentials and fuel disruption may account for the discrepancy between release codes and the test release results.