ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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 begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
R. A. Schrack, O. A. Wasson,D. C. Larson, J. K. Dickens, J. H. Todd
Nuclear Science and Engineering | Volume 114 | Number 4 | August 1993 | Pages 352-362
Technical Paper | doi.org/10.13182/NSE93-A24044
Articles are hosted by Taylor and Francis Online.
Relative cross-section measurements for the 10B(n, α1γ)7Li reaction were made using the Oak Ridge Electron Linear Accelerator Laboratory neutron source. The cross sections were measured by observing the 478-keV photon using an intrinsic germanium detector. The neutron flux was monitored with a high-efficiency plastic scintillator. Monte Carlo calculations were used to provide multiple-scattering and neutron-attenuation corrections to the data. The measured cross sections differ as much as 40% from the ENDF/B-VI evaluation for incident neutron energies greater than 1.5 MeV.
