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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Richard D. Peters, Urban P. Jenquin, Langdon K. Holton, Jr.
Nuclear Technology | Volume 90 | Number 1 | April 1990 | Pages 78-86
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT90-A34387
Articles are hosted by Taylor and Francis Online.
Measurement and prediction of outside surface exposure rates and measurement of gamma photon spectra from radioactive sources are described. The sources were 30-cm-diam canisters filled with borosilicate glass to a height of ∼100 cm. Each canister contained up to 237 kCi of 137 Cs and 159 kCi of 90Sr. Exposure rates on the outside surfaces ranged from 26 000 to 320 000 R/h, chiefly from decay of 137 Cs. The radiation field around the canisters was modeled using two codes based on point kernel theory (ISOSHLD-II and QAD-CG) and a transport theory code (ANISN). It was found that the point kernel codes overpredicted surface exposure rates for the radioactive canisters by a factor of ∼2. The surface exposure rates calculated by the transport theory code were ∼25% higher than the measurements. Spectral measurements indicate that most exposure is associated with gamma radiation in the 0.1- to 0.5-MeV range.
