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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Mar 2025
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Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
J. C. Wang, Gary L. Jensen, J. B. Czirr
Nuclear Science and Engineering | Volume 113 | Number 1 | January 1993 | Pages 77-85
Technical Paper | doi.org/10.13182/NSE93-A23995
Articles are hosted by Taylor and Francis Online.
Rigorous tests of the Monte Carlo transport code MCNP have been performed by measuring the efficiency of a 6Li-glass moderating neutron detector using Lucite as the moderator relative to the efficiency of the detector using mineral oil as the moderator, and comparing this with the MCNP predicted value. The tests were done using both 252Cf fission-source neutrons and 1.2-MeV neutrons produced by a Van de Graaff accelerator.
