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Division Spotlight
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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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 updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
D. Kontogeorgakos, F. Tzika, I. E. Stamatelatos
Nuclear Technology | Volume 175 | Number 2 | August 2011 | Pages 435-444
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT175-435
Articles are hosted by Taylor and Francis Online.
A computational method for the radiological characterization of the Greek Research Reactor (GRR-1) core supporting grid plate is presented. It is based on three-dimensional Monte Carlo neutron and photon transport simulations, analytical radionuclide inventory calculations, and measured gamma dose rates. The spatial distribution of neutron fluxes and spectra were derived by an implicit MCNP reactor core model. The radionuclide inventory was estimated using the FISPACT code. The associated source term was included in an accurate MCNP model of the grid plate assembly deriving the resulting gamma dose rates. The dominant gamma dose-producing nuclide was 60Co generated by activation of cobalt impurity in the stainless steel parts. The cobalt impurity concentration in the stainless steel parts was determined on the basis of best agreement between gamma dose rate calculations and measurements. The specific activity of grid plate components was evaluated as a function of cooling time after reactor shutdown. The proposed methodology provides a useful tool for work planning, control of occupational exposure and waste management during reactor renovation, and maintenance or decommissioning activities.