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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.
Kazumi Ozawa, Sosuke Kondo, Tatsuya Hinoki, Kouichi Jimbo, Akira Kohyama
Fusion Science and Technology | Volume 47 | Number 4 | May 2005 | Pages 871-875
Technical Paper | Fusion Energy - Fusion Materials | doi.org/10.13182/FST05-A796
Articles are hosted by Taylor and Francis Online.
The microstructural evolution of SiC/SiC composites after Si2+ with/without He+ ion irradiation was studied using transmission electron microscopy. The temperature, displacement damage level, and He/dpa ratio were 1273/1673K, 10/100dpa and 0/60appmHe/dpa, respectively. In 10dpa single-ion irradiation, no cavity was detected at 1273 and 1673K. But cavities were observed locally at 1673K, 100dpa. In dual-ion irradiation, cavities were observed at 1673K, 100dpa. Helium bubbles (d<5nm) were formed densely on {111} faulted planes in the fiber and matrix. And lens-shaped cavities (major axis 2a=20-50nm) were formed on grain boundaries in the matrix. The swelling by cavities in CVI matrix is about 0.5% at 80dpa and 0.7% at 130dpa. Loss of PyC layer beneath the irradiated surface was observed (single-ion: about 500nm, dual-ion: about 1 m). And the thickness of the PyC layer expands after single/dual-ion irradiation (single-ion: 12%, dual-ion: 29% increase). But Tyranno-SA/PyC/CVI composites shows showed better microstructural stability than expected at 1673K.