The Advanced Test Reactor (ATR) located at the Department of Energy’s Idaho National Laboratory, is the most powerful test reactor operating in the United States rated at a design power of 250 MW(t). Operating cycles are nominally seven per year with outages that last 7 to 14 days, allowing time for routine plant maintenance and experiment insertions and manipulations. While the ATR pressurized water loops can operate at the same temperature and pressure requirements of a pressurized water reactor, the loops also have the ability to operate at higher conditions. Hence, it is critical to ensure that when component replacements are called for, they can meet or exceed design requirements of a typical power reactor, while continuing to satisfy the design requirements of the ATR experiment loops.
Skip Nav Destination
14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4242-8
PROCEEDINGS PAPER
Installation of Valvtechnologies Ball Valves in Severe Service Applications Within the Advanced Test Reactor
Robert C. Howard
Robert C. Howard
Idaho National Laboratory, Idaho Falls, ID
Search for other works by this author on:
Robert C. Howard
Idaho National Laboratory, Idaho Falls, ID
Paper No:
ICONE14-89659, pp. 641-644; 4 pages
Published Online:
September 17, 2008
Citation
Howard, RC. "Installation of Valvtechnologies Ball Valves in Severe Service Applications Within the Advanced Test Reactor." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management. Miami, Florida, USA. July 17–20, 2006. pp. 641-644. ASME. https://doi.org/10.1115/ICONE14-89659
Download citation file:
7
Views
Related Proceedings Papers
Related Articles
Effects of Pressure Relief Valve Behavior on 2-Phase Energy Storage in a Pressure Vessel Exposed to Fire
J. Pressure Vessel Technol (May,2002)
Effects of Pressurized Water Reactor Medium on the Fatigue Life of Austenitic Stainless Steels
J. Pressure Vessel Technol (December,2015)
The Application of System CFD to the Design and Optimization of High-Temperature Gas-Cooled Nuclear Power Plants
J. Eng. Gas Turbines Power (May,2008)
Related Chapters
ASME Section IV: Rules for the Construction of Heating Boilers
Online Companion Guide to the ASME Boiler & Pressure Vessel Codes
ASME Section IV: Rules for the Construction of Heating Boilers
Companion Guide to the ASME Boiler and Pressure Vessel Codes, Volume 1, Fifth Edition
Compressive Deformation of Hot-Applied Rubberized Asphalt Waterproofing
Roofing Research and Standards Development: 10th Volume