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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
F. Schmittroth
Nuclear Science and Engineering | Volume 59 | Number 2 | February 1976 | Pages 117-139
Technical Paper | doi.org/10.13182/NSE76-A15684
Articles are hosted by Taylor and Francis Online.
The effect of uncertainties in the basic nuclear data needed in fission-product decay-heat summation calculations is considered. A variety of methods are developed to study the effect of errors in decay energies, half-lives, fission yields, and metastable states. Based on preliminary estimates of the uncertainties in the basic data, these methods show that decay heat for typical reactor exposures can be calculated with an accuracy of 7% or better for cooling times >10 sec. Attention is directed toward thermal fission of 235U, although the more general problem of other fissionable nuclides is considered. For cooling times <1000 sec, the major sources of error are due to uncertainties in the decay energies and fission-product charge distributions. All calculations are based on ENDF/B-IV cross sections.