ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
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.
Ernesto C. Vanterpool, Rudolf E. Slovacek, Donald R. Harris, Robert C. Block
Nuclear Science and Engineering | Volume 110 | Number 2 | February 1992 | Pages 186-194
Technical Notes | doi.org/10.13182/NSE92-A23888
Articles are hosted by Taylor and Francis Online.
Interrogation neutrons from 3 eV to 3 keV are used to determine the relative sensitivity of a spent light water reactor fuel assembly assay system. The fuel assay system used for this measurement consists of three threshold fission chambers installed in the Rensselaer intense neutron spectrometer, a 75-t lead slowing-down-time spectrometer at the Gaerttner Linac Laboratory. The fission chambers detect fission neutrons from a simulated fuel assembly, an aluminum enclosure filled with depleted uranium oxide (0.2% 235U), and a 235U (93%) metal foil sample placed at various locations throughout the assembly. The measurements with the assembly are compared with a Monte Carlo analysis of an homogenized pressurized water reactor fuel assembly. This is concluded to be a practical method for the assay of spent fuel.