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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
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.
Hyeong Il Kim, M. Herman, S. F. Mughabghab, P. Oblozinský, D. Rochman, Young-Ouk Lee
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 168-189
Technical Paper | doi.org/10.13182/NSE160-168
Articles are hosted by Taylor and Francis Online.
Neutron cross sections for a complete set of Nd isotopes, 142,143,144,145,146,147,148,150Nd, were evaluated in the incident energy range from 10-5 eV to 20 MeV. In the low-energy region, including thermal and resolved resonances, our evaluations are based on the latest data published in the Atlas of Neutron Resonances, Fifth Edition: Resonance Parameters and Thermal Cross Sections, Z = 1 - 100. In the unresolved resonance region, we performed additional evaluation by using the averages of the resolved resonances and adjusting them to the experimental data. In the fast neutron region, we used the nuclear reaction model code EMPIRE-2.19 validated against the experimental data. The results are compared to the existing nuclear data libraries, including ENDF/B-VI.8, JENDL-3.3, and JEFF-3.1, and to the available experimental data. The new evaluations are suitable for neutron transport calculations, and they were adopted by the new U.S. evaluated nuclear data ENDF/B-VII.0, released in December 2006.