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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.
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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
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Seok Yoon, Jun-Seo Jeon, Seeun Chang, Deuk-Hwan Lee, Seung-Rae Lee, Geon-Young Kim
Nuclear Technology | Volume 206 | Number 3 | March 2020 | Pages 514-525
Technical Note | doi.org/10.1080/00295450.2019.1632093
Articles are hosted by Taylor and Francis Online.
A geological repository has been considered as one of the best options for the disposal of high-level radioactive waste (HLW), with the concepts of an engineered barrier system (EBS) and a natural barrier system. A compacted bentonite buffer is the most crucial component of the EBS. Because groundwater penetrates the compacted bentonite buffer, it is essential to investigate a water-retention curve (WRC) of the compacted bentonite buffer to evaluate the overall safety performance of the EBS because the WRC of the compacted bentonite buffer can affect the thermal-hydraulic–mechanical behavior of every component of the EBS. Therefore, this technical note reports on laboratory experiments conducted to analyze the WRC for a Korean Ca-type compacted bentonite considering dry density, confined or unconfined condition, and drying or wetting path. Models by Fredlund and Xing and by van Genuchten had the best fit with the experimental data. The results revealed higher water content with smaller dry density and in an unconfined condition and higher total suction during the drying path. Furthermore, the air-entry values (AEVs) and fitting parameters of the van Genuchten model were compared with other Ca-type bentonites produced in Europe. A smaller AEV showed lower expansibility since the AEV is affected in the low-suction range and expansibility.