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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
NuScale Energy Exploration Center opens at SC State
NuScale Power Corporation’s latest Energy Exploration (E2) Center has opened at South Carolina State University, in Orangeburg. E2 Centers are designed to provide visitors with hands-on experiences in simulated scenarios of operations at nuclear power plants. NuScale has established 10 such centers around the world. The company officially presented the fully installed E2 Center to SC State on May 21, after a collaborative setup and training process was completed.
H. D. Knox, R. M. White, R. O. Lane
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 223-230
Technical Paper | doi.org/10.13182/NSE79-A20612
Articles are hosted by Taylor and Francis Online.
Differential cross sections for neutrons scattered elastically from 6Li and 7Li have been measured at 14 incident neutron energies between 4 and 7.5 MeV. For 7Li, neutrons inelastically scattered from the 0.478 MeV-level were not resolved from the elastic group and have been included with the elastic group in calculating the cross sections. The present 6Li data are in good agreement with the ENDF/B-IV evaluation, while the present 7Li(n,n0 + n1) data are generally larger than the corresponding ENDF/B-IV evaluation particularly at forward angles.
