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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
L. F. Hansen, C. Wong, T. T. Komoto, B. A. Pohl, R. J. Howerton
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 70-77
Technical Paper | Material | doi.org/10.13182/NT80-A32557
Articles are hosted by Taylor and Francis Online.
Spherical assemblies of copper with radii (R) equal to 1.0, 3.0, and 5.0 mean-free-paths (mfp) for 14-MeV neutrons, niobium (R = 0.9 and 3.2 mfp), 232Th (R = 1.0 mfp), and 238U (R = 1.0 and 3.1 mfp) have been bombarded with a centered nominal 14-MeV neutron source. The neutron leakage spectra have been measured from 0.8 to 14 MeV using a stilbene scintillator, time-of-flight techniques, pulse-shape discrimination and ∼10-m flight paths. The measured spectra are compared with calculations carried out with TARTNP, a coupled neutron-photon Monte Carlo transport code, using the ENDF/B-IV and -V neutron libraries. For copper and 238U, the reevaluated cross sections at ∼14 MeV in ENDF/B-V are somewhat less satisfactory in fitting the experimental results than those in ENDF/B-IV. For 232Th, ENDF/B-V shows significant improvement. The niobium cross sections, which were not reevaluated between ENDF/B-IV and -V, provide poor fits to the measurements.