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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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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.
Dong Won Lee, Jae Sung Yoon, Ki Sok Jung, Suk Kwon Kim, Eo Hwak Lee, Seungyon Cho
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 171-179
Blanket Materials Technology | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14131
Articles are hosted by Taylor and Francis Online.
Korea has developed a liquid breeder blanket and participated in the test blanket module program for ITER. To develop liquid breeder technologies with not only liquid lithium but also lead-lithium (PbLi), an experimental loop for the liquid breeder was constructed at the Korea Atomic Energy Research Institute. The main purposes of the loop are developing components such as an electromagnetic pump, testing the effects of magnetohydrodynamics, and investigating the compatibility between the liquid breeder and other materials. Before operating the loop, the melting and solidifying temperatures of the PbLi and its contamination were experimentally investigated considering cyclic use with the prepared reaction chamber. Melting and solidifying temperatures were [approximately]235°C, and there was no change even with the cyclic test. Because of contamination such as oxidation, however, the composition of PbLi can be changed, which should be considered when operating the loop. The reactions of PbLi and Li with air and water were observed. The PbLi did not react with air or water, but Li showed a severe reaction with them. However, reaction mitigation using nano-particles was found in the experiment.