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Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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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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ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
H. Guo, G. Martin, L. Buiron (CEA)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1231-1240
CEA is largely involved in the study of GEN-IV Sodium Fast Reactors (SFR). Some innovative reactivity control systems are proposed such as utilization of different absorbers or moderators materials, modification of absorber pin geometry, and application of burnable neutron poison. These designs possess potentials to improve its safety margin, economical performance or core characteristics while its complete analysis requires notably more accurate calculation of efficiency and evolution of isotopes’ concentrations under irradiation.
At the same time, the new determinist transport code APOLLO3® is under development at CEA and it will replace ERANOS code for fast reactors analysis. The scheme in APOLLO3® is constituted with two steps: sub-assembly calculation and core calculation with Multi-Parametric Output Library as connectors which enable the interpolation of cross-sections according to specific parameter. In this paper, each step and different cross-section scheme are detailed and validated by continuous energy Monte Carlo calculations. These results are also compared with determinist code system ERANOS.
Our works show high adaptability of TDT solver in APOLLO3® to complexes geometries and evolution of isotopes. With the ability of MINARET to treat unstructured mesh, the heterogeneous geometry, keeping absorber pins at core level calculation, improves significantly the calculation of control rods’ efficiency. APOLLO3® compute more accurately core’s reactivity variation with burn-up tabulated cross section scheme. Although variation of spatial self-shielding effect is very significant in absorber depletion, tabulated cross-sections scheme is able to bring this variation from sub-assembly calculation to core calculation. Hence, even homogeneous control rod description at core level shows accurate computation of reactivity variation.
Consequently, with development and validations, APOLLO3® shows improvement on SFR control rods neutronic simulation and analysis. With these new schemes presented in this paper, innovative reactivity control systems designs will be completely characterized and investigated in the near future.
