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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
General Atomics tests fuel as space nuclear propulsion R&D powers on
General Atomics Electromagnetic Systems (GA-EMS) has announced that it has subjected nuclear thermal propulsion (NTP) fuel samples to several “high-impact” tests at NASA’s Marshall Space Flight Center (MSFC) in Huntsville, Ala. That news comes as NASA, the Department of Defense, the Department of Energy, and multiple nuclear and space technology companies continue to build on recent progress in nuclear thermal rocket design and demonstration.
P. Jansson, A. Håkansson, A. Bäcklin, S. Jacobsson
Nuclear Science and Engineering | Volume 141 | Number 2 | June 2002 | Pages 129-139
Technical Paper | doi.org/10.13182/NSE02-A2272
Articles are hosted by Taylor and Francis Online.
A method for determining the residual thermal power in spent nuclear fuel using gamma-ray spectroscopy is suggested. It is based on the correlation between the residual power and the 137Cs activity, which is nearly linear for fuel with cooling times between 10 and 50 yr. Using available data of calorimetrically measured values of the decay heat in 69 boiling water reactor and pressurized water reactor spent-fuel assemblies resulted in agreement with a standard deviation of 3%.
