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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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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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.
Mojtaba Taherzadeh, Peter J. Gingo
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 396-410
Technical Paper | Fuel | doi.org/10.13182/NT72-A16037
Articles are hosted by Taylor and Francis Online.
The major sources of neutrons from plutonium dioxide nuclear fuel are considered in detail. These sources include spontaneous fission of several of the plutonium isotopes, (α,n) reactions with low Z impurities in the fuel, and (α,n) reactions with 180. For spontaneous fission neutrons a value of (1.95 ± 0.07) × 103 n/sec/g PuO2 is used. The neutron yield from (α,n) reactions with oxygen is calculated by integrating the reaction rate equation over all alpha-particle energies and all centerofmass angles. The results indicate a neutron emission rate of (1.14 ± 0.26) × 104 n/sec/g PuO2. The neutron yield from (α,n) reactions with low Z impurities in the fuel is presented in tabular form for 1 ppm of each impurity. The total neutron yield due to the combined effects of all the impurities depends on the fractional weight concentration of each impurity. The total neutron flux emitted from a particular fuel geometry is estimated by adding the neutron yield due to the induced fission to the other neutron sources.