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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
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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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NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
C. Lepscky, G. M. Testa, H. Hougaard, K. W. Jones
Nuclear Technology | Volume 16 | Number 2 | November 1972 | Pages 367-395
Technical Paper | Fuel | doi.org/10.13182/NT72-A31203
Articles are hosted by Taylor and Francis Online.
Two instrumented fuel assemblies, containing Zircaloy-clad UO2 fuel, namely IF A-132 (pellet, 95% TD, 10.0 wt% 235U) and IFA-133 (vibrocompacted powder, 85% TD, 10.0 wt% 235U) were irradiated in the Halden Boiling Water Reactor (HBWR) in Norway, in order to investigate the performance of fuel pins under central melting conditions; the maximum linear heat generation rate (LHGR) was about 1400 W/cm and the final burnup was 11 000 MWd/MTU. The initial molten zone covered about 35 and 65% of the fuel radius for the pelleted and vibrocompacted fuel, respectively. By means of the in-pile instrumentation, the dimensional changes vs generated power were recorded during irradiation. Furthermore through extensive postirradiation examinations the in-pile behavior of fuel and cladding was evaluated. In spite of incipient burnout condition, contact of molten or plastic fuel with the cladding, and localized overheating up to 900°C, the overall behavior gave no indication that irradiation to a higher burnup could not proceed satisfactorily. On the basis of this experiment it seems justified to assume that central fuel melting should not be considered as a primary constraint in the fuel design criteria.
