ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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July 2025
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Latest News
Hinkley Point C gets over $6 billion in financing from Apollo
U.S.-based private capital group Apollo Global has committed £4.5 billion ($6.13 billion) in financing to EDF Energy, primarily to support the U.K.’s Hinkley Point C station. The move addresses funding needs left unmet since China General Nuclear Power Corporation—which originally planned to pay for one-third of the project—exited in 2023 amid U.K. government efforts to reduce Chinese involvement.
J. R. Hofmann, C. C. Meek
Nuclear Science and Engineering | Volume 64 | Number 3 | November 1977 | Pages 713-723
Technical Paper | doi.org/10.13182/NSE77-A27100
Articles are hosted by Taylor and Francis Online.
A model employing Darcy's law has been developed to describe the transient pressure field within interconnected porosity of mixed-oxide liquid-metal fast breeder reactor fuel during hypothetical reactor accidents. Pressure increases are due both to fission gas released from fuel grains and fill gas originally present within fuel pores. Calculations utilizing the model have been performed for an out-of-pile test prior to fuel melting with both clad and unclad conditions being treated. Redistribution of gas from the source region in the relatively high-porosity unrestructured fuel to a low-porosity restructured fuel was shown to exist in all cases considered. Even for the unclad case, significant internal pressurization was predicted by the model, which could prove important in subsequent fuel breakp and motion.