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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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Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
IEA report: Challenges need to be resolved to support global nuclear energy growth
The International Energy Agency published a new report this month outlining how continued innovation, government support, and new business models can unleash nuclear power expansion worldwide.
The Path to a New Era for Nuclear Energy report “reviews the status of nuclear energy around the world and explores risks related to policies, construction, and financing.”
Find the full report at IEA.org.
R. M. Carroll and P. E. Reagan
Nuclear Science and Engineering | Volume 21 | Number 2 | February 1965 | Pages 141-146
Technical Paper | doi.org/10.13182/NSE65-A21037
Articles are hosted by Taylor and Francis Online.
The continuous release of fission gas from ceramic fuels is measured during irradiation in the Oak Ridge Research Reactor. The fuel specimens are heated by their own fission power which is controlled by moving the specimen holder into or out of the neutron flux. Fuel specimens with thin cross sections are used, both to prevent thermal stress rupture and to allow accurate temperature measurement. A continuously flowing sweep gas carries the fission gas outside the reactor where the radioactive isotopes are measured with a gamma-ray spectrometer. The specimen temperature is controlled by air cooling the specimen holder. The experiment is instrumented to function continuously and unattended.