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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
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Latest News
DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
R. A. Bennett, R. E. Heineman
Nuclear Science and Engineering | Volume 8 | Number 4 | October 1960 | Pages 294-299
Technical Paper | doi.org/10.13182/NSE60-A28859
Articles are hosted by Taylor and Francis Online.
The thermal neutron absorption rate in “1/v” materials has been observed near a discontinuity in the temperature of a graphite moderator. A plausible group diffusion model of the space and energy distributions of the thermal neutrons has been assumed. The experimental data have been used to obtain the transfer cross sections, called rethermalization cross sections, to be used with this model. The cross sections obtained for crystalline graphite are small compared to those expected for gaseous graphite; but they increase by a factor of about seven, from (1.9 ± 0.05) × 10−3 to (14.5 ± 2.6) × 10−3 cm−1, from the lowest temperature of 108°K to the highest temperature of 666°K.