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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
J. K. Dickens, T. A. Love, J. W. McConnell, R. W. Peelle
Nuclear Science and Engineering | Volume 74 | Number 2 | May 1980 | Pages 106-129
Technical Paper | doi.org/10.13182/NSE80-A19627
Articles are hosted by Taylor and Francis Online.
Fission-product decay energy-release rates have been measured for thermal-neutron fission of 235U. Spectral data were obtained using scintillation spectrometers for beta and gamma rays separately, and were processed to the form of total yield and total energy-release integrals for each set of time-interval parameters. The irradiations were for 1, 10, and 100 s, and measurements were made covering times following irradiation from 1.7 to 13 950 s. The separate beta- and gamma-ray energy-release data were summed to obtain the total (β + γ) energy-release rates for the cases studied. The data are processed to provide two standard representations of decay energy release, the one following a pulse of fissions, and the other following an infinite period of irradiation. A complete representation of estimated uncertainties is given in the form of a variance-covariance matrix. For the pulse representation of the data, diagonal components correspond to uncertainties in the range of 3 to 4%, with correlation coefficients in the range from 0.1 to 0.5. The experimental data are compared with other experimental data. The present results are generally smaller than other data, in some cases by more than the estimated uncertainties. The present results are smaller than the proposed 1973 American Nuclear Society (ANS) Decay-Heat Standard by as much as 10% for times following fission between 2 and 400 s, and are also smaller than the presently proposed (1978) ANS Decay-Heat Standard by 5 to 8% for the time interval 2 to 600 s. The reasons for these differences are discussed, and the importance for analyses using the new standard is presented.