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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Fusion Science and Technology
Latest News
NRC wants input on Hermes 2 test reactor construction permit
The Nuclear Regulatory Commission is seeking input on its draft environmental assessment and draft finding of no significant impact for Kairos Power’s application to build the Hermes 2 test reactor facility in Oak Ridge, Tenn.
Hosny M. Attaya, Mohamed E. Sawan
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 608-613
Blanket and First-Wall Engineering | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40106
Articles are hosted by Taylor and Francis Online.
A computer program for evaluating the poloidal distribution of the neutron wall loading (NWL) in toroidal fusion reactors is developed using numerical integration for general plasma and wall shapes. The neutron source within the plasma could be uniform or could be described to properly represent the neutron density associated with the magnetic flux surfaces. The method and techniques used in NEWLIT are presented. A comparison with the Monte-Carlo code MCNP shows excellent agreement with substantial savings in computer time and required user time. To verify the validity of the NWL as calculated by NEWLIT, a detailed 3-D neutronics calculation was carried out for a representative tokamak reactor. The poloidal distribution of the important responses is compared to the NWL poloidal distribution.