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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!
Latest Magazine Issues
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
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.
E. S. Occhipinti, P. E. Mix, J. S. Stutheit, F. R. Field
Nuclear Technology | Volume 2 | Number 5 | October 1966 | Pages 363-370
Technical Paper and Note | doi.org/10.13182/NT66-A27612
Articles are hosted by Taylor and Francis Online.
An analog computer was developed to measure the safety factor against film-boiling burnout of reactor fuel surfaces. The instrument was used at the Savannah River Plant as an aid in manual control of power in one heavy-water-cooled and -moderated production reactor which operated with a specific power of over 220 kW/g of 235U and at neutron flux levels up to 6 × 1015 n/(cm2 sec).
