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Division Spotlight
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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Joseph A. Angelo, Jr., Roy G. Post
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 323-330
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31494
Articles are hosted by Taylor and Francis Online.
The heat generated by spent fuel elements and typical processing waste from both a 1000 MW(e) reference design pressurized water reactor (PWR) and 1160 MW(e) reference design high temperature gas-cooled reactor (HTGR) were calculated for times up to 1000 years. To compensate for differences in exposure, the heat generated was expressed in terms of watts of heat generated per megawatt day of exposure. Examination of both tabular data and graphical presentations of these normalized heat generation data indicates noticeable differences in the contribution of different isotopes for each system. As anticipated, the heat generation for each fuel was greatly influenced by the transmuted isotopes 233Pa and 238Pu for the HTGR with 137Cs and 90Sr for the PWR. Data provide quantitative detailed information on the thermal power output of typical processing waste for both reactor systems for the first millennium of cooling.