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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
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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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.
Kazuyoshi Miki, Kotaro Inoue
Nuclear Science and Engineering | Volume 59 | Number 2 | February 1976 | Pages 161-169
Technical Paper | doi.org/10.13182/NSE76-A15686
Articles are hosted by Taylor and Francis Online.
A new calculation code, the Hot Spot Probabilistic Evaluation Code (HOSPEC), is presented for evaluating hot-spot factors in a fast reactor. This code calculates the probability distribution of temperature in the whole core by means of a Monte Carlo method. Each Monte Carlo trial involves a complete thermal conduction analysis, thereby reducing errors due to assumptions in analytic procedures currently in use. With this code it is possible to determine the probability that fuel pellets, fuel pins, or subassemblies will exceed the limiting temperature, as well as determine the number of such “hot spots” that will develop. A quantitative comparison is made of the results obtained from this code with those from other analyses of a prototype fast reactor. The comparison has indicated, among other points, the following findings: 1. For zero hot spots, a conventional analytic evaluation code SHOSPA gives conservative results, i.e., ∼20°C at the fuel center, at a 3σ confidence level. 2. It is of crucial importance to take into account the temperature dependence of the properties of the materials. Neglecting such dependence leads to a much more conservative temperature prediction, e.g., ∼50°C at the fuel center.