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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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 joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
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.