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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
S. Benck, I. Slypen, J.-P. Meulders, V. Corcalciuc, M. B. Chadwick
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 86-95
Technical Paper | doi.org/10.13182/NSE02-A2246
Articles are hosted by Taylor and Francis Online.
Double-differential cross sections (spectra) for light charged particle (proton, deuteron, triton, and alpha) emission in fast neutron-induced reactions on aluminum are reported for eight incident neutron energies between 25 and 55 MeV, augmenting previous results at 63 MeV. Angular distributions were measured at 15 laboratory angles between 20 and 160 deg. Procedures for data taking and data reduction are presented. Deduced energy-differential and total production cross sections are also reported. Experimental cross sections are compared to existing experimental proton-induced data and to nuclear model calculations that include preequilibrium and compound nucleus decay mechanisms. These calculations formed the basis of a recent set of higher-energy ENDF/B-VI data evaluations (the LA150 Library), and therefore, the present measurements facilitate a testing of the accuracy of these evaluated cross sections. This is important for accelerator-driven-systems design, where radiation transport simulation codes require accurate nuclear data to guide engineering design. Comparisons between the experimental data and the calculated values indicate that while proton, triton, and alpha-particle emission are modeled fairly accurately, deuteron emission is only poorly described, and further improvements to the nuclear reaction models for preequilibrium cluster emission are needed.