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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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
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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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Latest News
DTE Energy studying uprate at Fermi-2, considers Fermi-3’s prospects
DTE Energy, the owner of Fermi nuclear power plant in Michigan, is considering an extended uprate for Unit 2 that would increase its 1,100-MW generation capacity by 150 MW.
Donald J. Dudziak
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 328-337
Technical Paper | doi.org/10.13182/NSE67-A18272
Articles are hosted by Taylor and Francis Online.
Effective two-group gamma-ray spectra have been determined for thermal-neutron capture in sodium, nickel, type-304 stainless steel, and tantalum, as well as for 235 U prompt-fission gamma rays. A seven-group compilation of capture gamma rays was used as the basis for this study. Absorbed dose (uncollided and builtup) in several materials was calculated for varying thicknesses of several intervening shielding materials. The resulting function for each combination was reduced to two exponential functions over a range of 0 up to 560 g/cm2. Effective spectra were determined to be as follows: sodium, 6.09 MeV/capture at 5.5 MeV and 5.74 MeV/capture at 2.0 MeV; nickel, 8.33 MeV/capture at 8.0 MeV and 1.62 MeV/capture at 2.0 MeV; type-304 SS, 5.86 MeV/capture at 8.0 MeV and 1.95 MeV/capture at 2.0 MeV; tantalum, 3.76 MeV/capture at 4.0 MeV and 2.88 MeV/capture at 1.5 MeV; prompt fission, 2.31 MeV/fission at 4.0 MeV and4.92 MeV/fission at 1.25 MeV. These effective spectra reproduce, to within an average absolute deviation of less than 7.4%, the absorbed doses (uncollided and builtup) calculated by the detailed spectra, within the ranges of areal density considered.
