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Division Spotlight
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
Standards Program
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.
César Queral, Antonio Expósito, Alberto Concejal, Pablo Niesutta
Nuclear Technology | Volume 171 | Number 1 | July 2010 | Pages 53-73
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT10-A10772
Articles are hosted by Taylor and Francis Online.
An analysis of the PKL midloop tests E3.1 and F2.2 run 2 was performed with the TRACE (TRAC/RELAP Advanced Computational Engine) and RELAP5/MOD3.3 codes. Both tests allow study of the phenomenology and different accident management actions after a loss of the residual heat removal system at midloop conditions with the primary side closed. A comparison of the results obtained with both codes and the experimental data shows that in general, the main phenomena are well reproduced. The good results obtained allow one to confirm that the modelization methodology is adequate for this kind of transient. However, there are still a few phenomena that are not well predicted, like pressurizer water level behavior.
