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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.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
A. Klix, Ch. Adelhelm, U. Fischer, D. Gehre, T. Kaiser
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 196-203
Blanket Materials Technology | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14135
Articles are hosted by Taylor and Francis Online.
A consortium of several European laboratories has performed neutronics experiments with a representative mock-up of the European helium-cooled lithium-lead (HCLL) test blanket module (TBM) irradiated with DT neutrons from intense neutron generators. The aim of these experiments was to provide experimental data for checking nuclear data and calculational tools for the prediction accuracy of important parameters such as the tritium production rate and neutron and gamma-ray flux spectra. The mock-up consisted of bricks of solid LiPb arranged in layers separated by Eurofer sheets. The 6Li concentration in the LiPb determines the slow neutron flux distribution in the mock-up, and an accurate knowledge of this value is of paramount importance for the analysis of these neutronics experiments. The analysis of the tritium production rate experiments revealed discrepancies between the real 6Li concentration and the one specified by the manufacturer of the LiPb (natural Li composition). Here we report on the investigation of the 6Li concentration in the LiPb with several experimental techniques: 1) time-of-arrival neutron spectra measured inside the mock-up irradiated with short pulses of 14-MeV neutrons from a DT neutron generator, 2) transmission measurements on LiPb bricks with moderated neutrons from an AmBe source to check for differences between bricks, and 3) mass spectroscopic methods on small samples taken from selected LiPb bricks. We found that the 6Li concentration varies only very little between the bricks. The weight fraction of lithium in the LiPb was 0.61 wt% as quoted by the manufacturer, but the 6Li abundance was half of the natural value in lithium, 3.8 at% instead of 7.5 at%.