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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
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.