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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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
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.
A. R. Boulogne, J. P. Faraci
Nuclear Technology | Volume 11 | Number 1 | May 1971 | Pages 75-83
Technical Paper | Radioisotope | doi.org/10.13182/NT71-A30903
Articles are hosted by Taylor and Francis Online.
Californium-252 makes an intense neutron point source that emits 2.34 × 1012 n/(sec g) through spontaneous fission. Sources are being prepared to investigate the value of this radionuclide for mineral, petroleum, and gas exploration, well logging and hydrology, activation analysis, neutron radiography, and other areas where isotopic neutron sources are used. Sources containing milligram amounts of 252Cf with active volumes of <25 mm3 are being prepared by precipitating and filtering californium oxalate on a small metallic filter, which is in the primary capsule in a totally enclosed apparatus. The oxalate is calcined to 252Cf2O3 before the primary capsule is sealed. These sources are doubly encapsulated under conservative design criteria to prevent leakage of radioactive material because they are used in a wide variety of environmental conditions. The neutron emission rate of the finished sources is within 10% of the desired value. Less than 1% of the 252Cf was lost in the process. Because the practical upper limit for the present capsule design is about ten milligrams of 252Cf, procedures are being developed for preparing sources containing up to several hundreds of milligrams of the isotope.