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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
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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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.
K.-M. Song et al.
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1010-1013
Measurement, Monitoring, and Accountancy | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12587
Articles are hosted by Taylor and Francis Online.
A calorimeter was integrated in KEPTL (KEPCO Research Institute Tritium Laboratory) and the various performance tests were performed. The inventory of tritium transport vessels delivered to the ITER tritium plant will be measured by calorimetry. For calorimetry measurement the tritium transport vessel will be inserted in an aluminum secondary container for the tritium leak prevention. The heat capacity and geometry of measuring objects, however, can affect the performance of the calorimeter such as measuring time, sensitivity, etc. In this study, the effect of the heat capacity of the tritium vessel on the performance of the twin cell calorimeter is studied by using JEC and aluminum container which are dummy vessels simulating the tritium decay heat with electric heaters. The average sensitivity in the test with aluminum containers is measured to be 96 V/mW which is similar that with JEC so it does not depend directly on the heat capacity of the tritium vessel. The aluminum container, however, makes the measuring time increase and the heat flow signal could be unstable in the range of low tritium and high heat capacity like a waste vessel after tritium loading out.