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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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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.
Kazuhiro Kobayashi, Osamu Terada, Hidenori Miura, Takumi Hayashi, Masataka Nishi
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 476-479
Technical Paper | Tritium Science and Technology - Containment, Safety, and Environment | doi.org/10.13182/FST05-A969
Articles are hosted by Taylor and Francis Online.
To obtain performance data of atmosphere detritiation system at the off normal events such as fire for the safety of ITER, the detritiation experiment was planned and performed at Tritium Process Laboratory (TPL) in Japan Atomic Energy Research Institute (JAERI) using a new scaled detritiation system for the oxidation performance test which can process gas flow rate of ~2.64 m3/hr in circulation through 2m3 tank. The detritiation system consists of two oxidation catalyst beds (473K and 773K) for converting hydrogen isotopes and tritiated methane in compounds to water vapor and a molecular sieve drying absorber for removing water vapor as the usual detritiation system. In this time, the performance of oxidation catalyst bed of the detritiation system for hydrogen and methane under existence of carbon monoxide or carbon dioxide which are produced in the fire was investigated.Basic performance of the detritiation system for hydrogen (1.9%) and methane (1.3%) in air was evaluated under maximum ventilation flow rate (2.64m3/h). Obtained oxidation efficiency was more than 99.99% for hydrogen in the catalyst bed at 473K and more than 99.9% for methane in the 773K one, respectively. It was confirmed that these performances were maintained even under carbon dioxide of up to 20% , carbon monoxide of up to 10% if sufficient oxygen remained in the process gas, and that the existence of carbon monoxide and carbon dioxide at the fire would not influence the performance of the oxidation catalyst bed in the detritiation system.