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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
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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.
Yung-Shin Tseng, Chu Ching Hau, Jong-Rong Wang (NTHU), Po-Hsiu Lee, Chih-Tien Liu (Atomic Energy Council), Chunkuan Shih (NTHU)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 580-586
Since the Chloride-Induced Stress Corrosion Cracking (CI-SCC) has been attended in the Chinshan ISFSI project, the details of thermal information and humidity on the Transportable Storage Canister (TSC) becomes the valuable data for investigating the CISCC aging management. This is because that the temperature not only influenced the threshold of deliquescence but affected the growth rate of crack depth. Since the chloride salt only becomes deliquescent in specific situation depending on the site (e.g., the environment temperature and relative humidity) and cask (e.g., loading pattern and thermal load) condition of CSISFSI, which can be further evaluated by an applicable simulated methodology. In this study, a computational fluid dynamics (CFD), FLUENT, was utilized to investigate the temperature and considered the temperature with the relative humidity profile on each height of TSC shell of CSISFSI. A validated high-accuracy 2D model was developed to accelerate the simulation time due to the time scale of CISCC being up to 20 years. The result shows that the relative humidity will reduce as the temperature of TSC increases by decay heat of SNFs. For this reason, the maximum accumulated crack depth of the TSC will not exceed more than 0.36m height with 0.33mm/year, which is the maximum crack growth rate as the most conservative CaCl2 deliquescent threshold was assumed for prediction. Those quantized results not only prove that the re-inspection planning with 10 year period is enough to ensure the integrity of TSC but also provide a basis to reduce about 90% load for CSISFSI re-inspection work.