ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
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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Latest News
IEA report: Challenges need to be resolved to support global nuclear energy growth
The International Energy Agency published a new report this month outlining how continued innovation, government support, and new business models can unleash nuclear power expansion worldwide.
The Path to a New Era for Nuclear Energy report “reviews the status of nuclear energy around the world and explores risks related to policies, construction, and financing.”
Find the full report at IEA.org.
S. K. Davis, J. A. De Juren, M. Reier
Nuclear Science and Engineering | Volume 23 | Number 1 | September 1965 | Pages 74-81
Technical Paper | doi.org/10.13182/NSE65-A19260
Articles are hosted by Taylor and Francis Online.
Measurements of the shape of the fundamental mode of a thermalized neutron pulse in graphite for rectangular stacks has yielded a value of the extrapolation length, d = 1.825 ± 0.025 cm. The pulsed-neutron decay constants in graphite have been measured over a buckling range from 1.946 × 10−3 to 1.230 × 10−2 cm −2 and fitted to three- and four-term power series in the buckling. To fit points at bucklings greater than 6.0 × 10−3 cm−2, a cubic fit is necessary. An iterative method of fitting the decay constants results in an extrapolation length of 1.78 ± 0.01 cm. The diffusion constant was (2.0896 ± 0.0093) × 105cm2/sec, and the diffusion cooling constant was (3.77 ± 0.35) × 106 cm4/sec at a density of 1.689 g/cm3. A technique of correcting the decay constants for the effect of spectral cooling has been developed. The decay constants corrected to room temperature can be fitted as a linear function of the buckling. This method interates on the heat-transfer coefficient, γ, and gives a value of γ = 1633 ± 89 sec−1 for graphite. The heat-transfer coefficient relates the rate of energy transfer from a moderator to a cooled-neutron spectrum. With this approach the entire buckling range can be fitted with three parameters.