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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
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.