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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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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.
M. Roche, J. Morin, R. Musart, B. Pierre
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 244-258
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Technique | doi.org/10.13182/NT80-A32606
Articles are hosted by Taylor and Francis Online.
A new method for the detection of intense neutron fluxes is presented. It is based on the colorimetric measurement of the energy liberated by fission in a uranium wire whose temperature is obtained by measurement of its electrical resistance. Calorimetric operation is adiabatic for pulsed neutron fluxes, whereas continuous flux measurements use the principle of the leakage calorimeter.
