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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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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. Bahrami, G. Danko
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 247-264
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3732
Articles are hosted by Taylor and Francis Online.
The long-term thermal, hydrologic, and psychrometric storage environment of nuclear waste is analyzed within an emplacement drift at Yucca Mountain Repository in Nevada. Pertinent issues regarding temperature, relative humidity, and liquid water in contact with the waste packages are studied for a modified design currently considered by the U.S. Department of Energy (DOE). For cost reduction and improved repository performance, the proposed design implements a slight modification in the waste package emplacement sequence and thermal load. The main change is an increase from 44 boiling water reactor (BWR) to 52 BWR fuel assemblies to reduce the number of waste packages for the same storage capacity. The results of the analysis show that acceptable temperature, moderate relative humidity, and no liquid water are expected on the hot waste package including the new BWR containers of the proposed design for the 5000-yr study period. The cold DOE high-level waste and the colder defense spent nuclear fuel containers in the alternative design will experience about the same amount of condensates as those in the DOE baseline design.