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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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U.S. nuclear capacity factors: Ideal for data centers?
Baseload nuclear generation doesn’t get the respect it deserves, if you ask nuclear operators. But the hyperscale data centers that process our digital lives—like the one right next to the Susquehanna plant in northeastern Pennsylvania—are pushing electricity demand up. Clean, reliable capacity now looks a lot more valuable.
Kyle Remley, Farzad Rahnema
Nuclear Science and Engineering | Volume 183 | Number 2 | June 2016 | Pages 161-172
Technical Paper | doi.org/10.13182/NSE15-97
Articles are hosted by Taylor and Francis Online.
This paper presents a formulation for a method for the adaptive selection of angular flux expansion orders for use in COarse MEsh radiation Transport (COMET) method solutions to whole-core reactor problems. An important aspect of the COMET method is an assumed angular flux expansion on mesh interfaces. Previously, this expansion was held constant throughout a problem. However, the adaptive method described in this paper chooses the angular flux expansions automatically and allows them to vary between meshes. To demonstrate the method, a pressurized water reactor benchmark problem with UO2 and mixed oxide fuel assemblies is solved. Three different configurations for different insertions of control rods were considered. For all configurations, the agreement between the standard and adaptive COMET solutions was excellent, with eigenvalue agreement being 2 pcm or less and average pin fission errors never exceeding 0.1%. Increases in computational efficiency by factors of 2 to 2.6 were observed over standard COMET solutions employing the full flux expansion considered in the problem. In addition, a lower flux expansion suggested by literature as well as the results of the adaptive calculation was used in the standard COMET method to solve the problem. The adaptive COMET solution has a run time similar to this lower expansion, which is to be expected since many of the flux expansions chosen with the adaptive method match this lower flux expansion. The results of this study are encouraging and imply that adaptive COMET solutions improve upon the standard method by increasing computational efficiency when a flux expansion is used that is higher than required for desired accuracy. The method also limits the need for intuition and numerical experimentation in achieving flux expansions that result in COMET calculations that achieve satisfactory accuracy.