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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.
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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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New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
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.