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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Wei Shen, Dimitar Altiparmakov
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 109-134
Technical Paper | doi.org/10.13182/NSE12-42
Articles are hosted by Taylor and Francis Online.
This paper presents a multicell correction method that has been developed and implemented in the code suite WIMS-AECL/RFSP to capture the effects of the lattice-cell neighborhood while maintaining the basic structure of the single-cell-based reactor-physics methodology traditionally used for Canada Deuterium Uranium (CANDU)-reactor calculations for decades. To validate the effectiveness in treating the core-reflector interface heterogeneity as well as the checkerboard-voiding scenario, the results of WIMS-AECL/RFSP calculations (with and without the multicell correction) are compared with the results of MCNP5 full-core calculations for CANDU-type reactors. The presented results show that the multicell correction method is effective, generic, and capable of capturing the heterogeneity effects of the neighborhood in CANDU-type reactors.