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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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November 2024
Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
Tae-Hoon Lee, Spencer Menlove, Howard O. Menlove, Hee-Sung Shin, Ho-Dong Kim
Nuclear Technology | Volume 206 | Number 7 | July 2020 | Pages 984-992
Regular Technical Paper | doi.org/10.1080/00295450.2020.1743598
Articles are hosted by Taylor and Francis Online.
The transuranic (TRU) ingot is considered to be the most prominent target material of pyroprocessing in terms of safeguards since it contains almost all of the Pu of the feed spent fuel. Due to the high density, excessively high neutron emission rates, and high neutron multiplication of the U/TRU ingot, it is impractical to apply gamma-ray spectroscopy or neutron coincidence counting techniques to the quantification of the Pu content of the U/TRU ingot. Since the passive neutron albedo reactivity (PNAR) technique is known to be sensitive to the total fissile mass of target material and the uncertainty of its singles Cd ratio is independent of the accidental coincidence coming from the high neutron emission rate, the capability of the PNAR technique for the quantification of the Pu content of the U/TRU ingot has been investigated using the MCNPX code with a spent fuel library with 81 different cases of various kinds of initial enrichment, burnup, and cooling time. The MCNPX simulation results for the Cd ratio versus Pu content of the U/TRU ingot show the maximum error in the Pu mass between the linear fit and the real Pu content in the U/TRU ingot is 2.14% for 4.5 wt% initial enrichment cases. The results of this study show that the PNAR technique can be one possible method for the direct nondestructive assay for the Pu of the U/TRU ingot.
