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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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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Latest News
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.
Michael B. Stanka, James M. Adams, Charles M. Eisenhauer
Nuclear Science and Engineering | Volume 134 | Number 1 | January 2000 | Pages 68-76
Technical Paper | doi.org/10.13182/NSE00-A2100
Articles are hosted by Taylor and Francis Online.
Proton recoil measurements of the 252Cf fission neutron leakage spectrum from a 50-cm-diam iron sphere are performed as a means of checking the degree to which the ENDF/B-VI iron inelastic scattering cross section resolves the well-known discrepancy between predicted and observed neutron transport. These measurements were performed at the National Institute of Standards and Technology using a rotating proton-recoil spectrometer over an energy range of 50 keV to 4.5 MeV. In addition, Monte Carlo neutron transport calculations were performed of the iron-moderated neutron spectrum generated in the experiment. Below 1 MeV, the spectral measurements are in good agreement with a corresponding calculation for the iron-moderated neutron leakage spectrum obtained using the ENDF/B-VI cross-section library. However, the calculation continues to underpredict the neutron fluence above 1 MeV by as much as 11%, which is greater than the average statistical uncertainty of the measured data. Finally, the measurements are compared with those obtained from a similar set of experiments made by two different laboratories in the Czech Republic. The results compare favorably with both of these measurements and indicate the best agreement with the Monte Carlo transport calculations with respect to the integral neutron fluence.