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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
A. Fessler, A. J. M. Plompen, D. L. Smith, J. W. Meadows, Y. Ikeda
Nuclear Science and Engineering | Volume 134 | Number 2 | February 2000 | Pages 171-200
Technical Paper | doi.org/10.13182/NSE99-14
Articles are hosted by Taylor and Francis Online.
Cross sections have been measured with the activation technique at various neutron energies in the range of 16.0 to 20.5 MeV for the following 22 reactions: 19F(n,p)19O, 23Na(n,p)23Ne, 23Na(n,)20F, 25Mg(n,p)25Na, 27Al(n,p)27Mg, 28Si(n,p)28Al, 29Si(n,p)29Al, 29Si(n, np + pn + d)28Al, 31P(n,)28Al, 35Cl(n,2n)34mCl, 37Cl(n,p)37S, 46Ti(n,p)46mSc, 50Ti(n,p)50g+mSc, 51V(n,p)51Ti, 55Mn(n,)52V, 56Fe(n,p)56Mn, 57Fe(n, np + pn + d)56Mn, 57Fe(n,p)57Mn, 93Nb(n,)90mY, 93Nb(n,2n)92mNb, 119Sn(n,p)119gIn, and 138Ba(n,2n)137mBa. The half-lives for the reaction products range from 11 s to 10.15 days. Quasi-monoenergetic neutrons were produced via the 3H(d, n)4He reaction. In some cases isotopically enriched materials were used to enhance the reaction yield or to facilitate correction for interfering reactions leading to the same product. The gamma rays emitted from the irradiated samples were measured with a high-purity germanium detector. A pneumatic sample transport system was used to limit the decay of the radioactive products between neutron irradiation and gamma-ray counting. All cross sections were obtained as ratios to the standard reaction 27Al(n,)24Na, using as secondary neutron fluence references the 27Al(n,p)27Mg reaction as well as a calibrated Bonner sphere. Corrections have been applied for sample-irradiation and counting environment geometric effects, neutron absorption and multiple scattering, time variation of neutron-source strength, neutron-source angular distributions, secondary neutrons from the target, gamma-ray absorption, and gamma-ray sum coincidences. A detailed analysis of the uncertainty sources was performed. The present results are compared with other measurements and evaluated data. For seven reactions, measured cross sections have been obtained for the first time beyond 15 MeV. These new data help appreciably to resolve discrepancies in evaluated data files.
