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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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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.
F. Roelofs, D. Dovizio, H. Uitslag- Doolaard, B. Mikuž, A. Shams (NRG)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 474-481
Most fast reactor designs foresee wire-wraps as spacer between the fuel rods. The safety analyses of such reactors requires thorough understanding of the flow and heat transport in such wire-wrapped fuel assemblies. In the past, this relied on experimental investigations, derived correlations and in addition computational analyses on 0- or 1-dimensional system or sub-channel scale. Nowadays, Computational Fluid Dynamics (CFD) has become an integral tool for the advanced reactor designer allowing simulations in 3 dimensions. However, the application of CFD tools needs to be validated. This paper will discuss the ongoing efforts at NRG in the Netherlands on validation of CFD tools for wire-wrapped fuel assembly simulations for flow and heat transport.
