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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
R. C. Lloyd, S. R. Bierman, E. D. Clayton, B. M. Durst
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 148-158
Technical Paper | Plant Water Chemistry / Radioisotope | doi.org/10.13182/NT78-A31982
Articles are hosted by Taylor and Francis Online.
Critical experiments were performed on an annular assembly of 93,2 wt% 235U enriched U-Al alloy fuel elements in light water to provide data for the design and operation of a subcritical neutron multiplier of a 252Cf neutron source. The various factors affecting criticality were determined. In addition to measurement of the critical fuel rod loading under various conditions, values of /ceff were determined as a function of fuel rod loading by means of pulsed neutron source experiments. The data provide the design basis for operation of the neutron multiplier, yielding a maximum flux value in the internal irradiation column consistent with maintaining a degree of subcriticality in operation.
