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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.
Meeting Spotlight
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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Latest News
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.
Po Hu, Paul P. H. Wilson
Nuclear Technology | Volume 172 | Number 2 | November 2010 | Pages 143-156
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT10-A10901
Articles are hosted by Taylor and Francis Online.
This paper studies the U.S. reference Supercritical Water Reactor (SCWR) design with the newly extended coupled codes PARCS/RELAP5. Steady-state, burnup, and loss-of-feedwater transients are simulated. A possible flow reversal in moderator channels is found in the simulations, and the impact of this reversal on power peaking and reactivity is observed. The transient results show that the assembly with the maximum cladding surface temperature (MCST) and the assembly with the maximum power are different and that the MCST is within the material limit under the current design.
