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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 Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
Hans Häggblom, Åke Ahlin, Takashi Nakamura
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 411-422
Technical Note | doi.org/10.13182/NSE75-A26686
Articles are hosted by Taylor and Francis Online.
A theory is described for solving the integral neutron transport equation by the transmission probability method. Detailed attention is given to the problem in rectangular x-y geometry. Within a mesh the neutron flux is assumed to be linearly dependent on the x and y coordinates. The angular dependence is given by a double P1 approximation. At the mesh surfaces a term is considered that allows for an asymmetric flux distribution relative to the surface normal. The inner source is obtained from the equilibrium equation. Based on this method, the code COXY has been developed and applied to one- and two-dimensional rectangular cell calculations. The calculated results show good agreement with those of SN and collision probability codes.
