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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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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ANS Winter Meeting: The momentum equation
While the featured speakers of the American Nuclear Society’s 2023 Winter Meeting and Expo opening plenary—West Virginia senators Shelley Moore Capito and Joe Manchin and Nuclear Regulatory Commission chair Christopher Hanson—generated a lot of buzz, the rest of the session provided constructive insights into the current state of nuclear technology and a glimpse of what the future may hold.
Tomaz Zagar, Matjaz Ravnik
Nuclear Technology | Volume 140 | Number 1 | October 2002 | Pages 113-126
Technical Paper | Radioisotopes | doi.org/10.13182/NT02-A3327
Articles are hosted by Taylor and Francis Online.
The results of activation studies of TRIGA research reactor concrete shielding are given. Samples made of ordinary and barytes concrete were irradiated in the reactor to simulate neutron activation in the shielding concrete. Long-lived neutron-induced gamma-ray-emitting radioactive nuclides were measured in the samples with a high-purity germanium detector. The most active long-lived radioactive nuclides in the ordinary concrete samples were found to be 60Co and 152Eu. In the barytes concrete samples, the most active long-lived radioactive nuclides were 60Co, 133Ba, and 152Eu. Activation in the concrete was also calculated using the ORIGEN2 code and compared to experimental results. Simple radioactive nuclide generation and depletion calculation using one-group cross-section libraries provided together with the ORIGEN2 code did not give conservative results. Significant discrepancies were observed for some nuclides. For accurate long-lived radioactive nuclide generation in reactor shielding, material-specific cross-section libraries should be generated and verified by measurement.