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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.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
NRC holds public hearing on proposed Palisades restart
Dozens gathered last week at a public hearing hosted by the Nuclear Regulatory Commission to get feedback on the proposal to restart the Palisades nuclear power plant in Michigan.
The NRC is beginning its environmental review of plans to repower Palisades after it was shut down in May 2022 and was headed for permanent decommissioning. If the restart is successful, this would be the first return to service of a shuttered U.S. nuclear plant.
Y. D. Harker, R. A. Anderl, G. K. Becker, L. G. Miller
Nuclear Science and Engineering | Volume 110 | Number 4 | April 1992 | Pages 355-368
Technical Paper | doi.org/10.13182/NSE92-A23909
Articles are hosted by Taylor and Francis Online.
Neutron spectrum measurements are performed on the aluminum-oxide-filtered neutron beam at the Brookhaven Medical Research Reactor (BMRR). Two independent measurement techniques are used in the spectrum characterization: (a) foil activation spectrometry and (b) proton-recoil spectrometry. Activation foil assemblies are irradiated at the exit port of the beam facility. Dominant resonances in selected activation reactions are used to measure the epithermal neutron spectrum. The intermediate and fast energy ranges of the neutron spectrum are measured by threshold reactions and the 10B-filtered 235U fission reaction. Neutron spectral data are derived from the activation data by two approaches: (a) an analysis that yields neutron flux values at the energies of the dominant or primary resonances in the epithermal activation reactions and (b) an analysis that utilizes all the activation data simultaneously in a spectrum unfolding process using the FERRET data adjustment code. Hydrogen-filled proton-recoil proportional chambers are used at the beam port exit to acquire data of a higher energy resolution than that obtainable through foil activation techniques. These measurements are made to determine if structure in the aluminum scattering cross section would produce significant structure in the filtered spectrum in the fast neutron region.