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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
DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
E. Friedman
Nuclear Science and Engineering | Volume 19 | Number 2 | June 1964 | Pages 203-208
Technical Paper | doi.org/10.13182/NSE64-A28910
Articles are hosted by Taylor and Francis Online.
A new method for measuring neutron thermalizaton parameters that was proposed on theoretical grounds is tested experimentally for H2O. The characteristic thermalization parameters in the present formulation are where are Laguerre polynomials of order unity and degree i and T is the temperature of the system expressed in energy units. The present experimental results for H2O can be described using one parameter. The result is γ11 = (0.210 ± 0.026)cm-1 for 23 C. The value of this parameter as derived from diffusion-cooling measurements lies in the range of 0.4cm-1 to 0.8cm-1. A possible explanation for this discrepancy is given. The value of γ11 as calculated on the basis of Nelkin's model is about four times higher than the present result.
