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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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.
J. J. Ritts, M. Solomito, P. N. Stevens
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 246-258
Technical Paper | Radiation | doi.org/10.13182/NT71-A30889
Articles are hosted by Taylor and Francis Online.
Improved multicollision neutron fluence-to-dose conversion factors have been calculated for a phantom exposed to neutrons with energies from 15 MeV down to thermal. The phantom was a 30-cm-thick slab composed of the 11 most common elements in the standard man. The calculations consisted of the simultaneous solution of the neutron and secondary gamma-ray transport problem with the ANISN computer code for both a beam source and an isotropic flux source, and for a slab having both infinite and finite transverse dimensions. The fluence-to-dose conversion factors were based on new neutron fluence-to-kerma factors and improved secondary gamma-ray yields determined for the individual elements comprising the slab. The neutron and gamma-ray cross sections used in the calculations are from the ENDF/B file and the OGRE library, respectively.