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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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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.
M. E. Anderson, R. A. Neff
Nuclear Technology | Volume 7 | Number 1 | July 1969 | Pages 62-66
Radioisotope | doi.org/10.13182/NT69-A28386
Articles are hosted by Taylor and Francis Online.
Neutron emission rates and neutron spectra were determined for two 238Pu power sources: SNAP 27-1, a 1482-W plutonium dioxide source for the Apollo Space Program, and HP 15-2, a 15.84-W plutonium metal source for the Artificial Heart Program. The measurements were made with a single stilbene crystal fast-neutron spectrometer and a long counter. The specific neutron yields were (2.2 ± 0.1) × 104 n/sec per gram of 238Pu for SNAP 27-1 and (3.9 ± 0.2) × 103 n/sec per gram of 238Pu for HP 15-2. Neutrons from these sources are due to spontaneous fission of 238Pu, neutron-induced fission of plutonium, and (α, n) reactions. The contributions to the two spectra due to neutrons from each of these reactions are shown. Factors for converting from neutron fluence to dose equivalent (whole body) were calculated to be (3.34 ± 0.11) × 10−5 mrem per n/cm2 for SNAP 27-1 and (3.13 ± 0.15) × 10−5 mrem per n/cm2 for HP 15-2.