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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 Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Om Prakash Joneja, Michel Schaer, Cherif Sahraoui, J.-P. Schneeberger, Vijay R. Nargundkar, K. Subba Rao
Fusion Science and Technology | Volume 23 | Number 4 | July 1993 | Pages 408-418
Technical Paper | Blanket Engineering | doi.org/10.13182/FST93-A30133
Articles are hosted by Taylor and Francis Online.
It is important to know the neutron yield, the spatial distribution, and the spectra emitted from a generator when performing any quantitative measurements. An extremely intense (d, t)-driven neutron generator is used in the LOTUS fusion blanket program. The planned measurements include integral tritium and 233U breeding as well as heat deposition rate studies in blankets representative of fusion reactor blankets. Quantitative estimates of these integral parameters demand precise determination of the characteristics of the neutron generator. Extensive foil activation measurements have been carried out to determine the reaction rate distribution and the neutron yield by a proposed method. A comparison between the calculated and measured reaction rates and the distribution confirm the adequacy of the cross-section sets and the geometry description of the complete experimental arrangement.
