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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
W. E. Downs, M. W. Davis
Nuclear Technology | Volume 7 | Number 5 | November 1969 | Pages 466-471
Instrument | doi.org/10.13182/NT69-A28449
Articles are hosted by Taylor and Francis Online.
Parameters of a 124Sb-Be neutron source used for “on-stream” elemental analysis are described. An analytical study of a basic on-stream system is given and some preliminary experimental results are compared with the calculations. The system consists of an irradiation chamber containing the 124Sb-Be source and a counting chamber with a delay line connecting the two. The unit can handle up to 7200 Ci of 124Sb which gives a thermal-neutron flux of ∼2 × 108 n/(cm2 sec) on the inside surface of the cylindrical irradiation chamber. A 13-liter irradiation chamber was found to be an optimum volume for all but very short-lived isotopes. In separate solutions, the elements Al, Hf, In, Mn, Ag, and V can be analyzed repetitively in 5 to 10 min cycles at <100 ppm using a 2.7-liter counting chamber. Calculated sensitivities for a number of elements and actual measured values for Al, Cl, Co, Hf, Mg, Na, and Cu are given.
