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Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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2024 ANS Annual Conference
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Fusion Science and Technology
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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
Anil Kumar, Yoichi Watanabe, Mahmoud Z. Youssef, Mohamed A. Abdou
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 1309-1314
Blanket Nucleonics Experiment | doi.org/10.13182/FST89-A39870
Articles are hosted by Taylor and Francis Online.
Phase IIC of the experimental program is to begin in fall of 1988. An extensive pre-analysis has been carried out to select the experimental configurations. The investigations were confined to looking at the effect of (i) multi-layer arrangement of Be multiplier, (ii) the presence of contiguous layers of structure and coolant, (iii) the introduction of protective graphite armor in front of the first wall, on tritium production rate (TPR) in a Li2O assembly. The basic materials and geometrical structure of the assembly, are derived from that of the Phase IIA. The structure is simulated by stainless steel (SS) and the coolant is either polyethylene (PE) or water. Generally, the heterogeneities strongly distort the local T6 and T7 distributions; their effect on global TPR is less marked. One of the two selected configurations has Be, in edge-on layered arrangement with Li2O, as multiplier. In the second configuration, three coolant channels (SS+PE) will be incorporated to simulate structural heterogeneity.