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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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.
Juraj Vaclav (Nuclear Regulatory Authority), Mária ?arnogurská, Tomáš Brestovi? (Technical Univ in Košice), Jaroslav Sivák (ALFA Security Technologies a.a.), Andrea Václavová (Slovak Univ of Technology in Bratislava)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 587-594
During transport and storage of spent nuclear fuel sub-criticality, protection of environment against radiation, and residual heat removal have to be ensured.
The paper describes the evaluation of modeling and calculation of temperature field for transport container C-30.
The aim of thermal calculations of transport container is to prove that residual heat produced by spent fuel could be safely led away without any damage to the fuel and to the container. All previous calculations considered the inventory of the container (spent fuel assemblies, cask, and water) as a homogenous entity with internal heat source.
3D model was created using ANSYS CFX software. It models in a simply way fuel assemblies as well as a cooling medium flow.
Each spent fuel assembly is divided into two parts. The central circular part represents the area of water between fuel pins. This part does not produce any heat. The rest of the assembly is bordered by hexagon on the outer periphery and by a circle inside of the fuel assembly. Only this part is responsible for heat production.
The calculations were made for residual heat output of 5, 10, 15, 20 and 24 kW.
The results were compared with experimentally obtained values.