Irradiation Behavior of Pressurized Water Reactor Control Materials
Richard V. Demars, Charles G. Dideon, Thomas A. Thornton, James S. Tulenko, Wayne A. Pavinich, Elma Beth S. Pardue
Abstract
Richard V. Demars, Charles G. Dideon, Thomas A. Thornton, James S. Tulenko, Wayne A. Pavinich, Elma Beth S. Pardue
Abstract
Postirradiation examinations have been conducted as part of an extensive Babcock & Wilcox (B&W) program in reactor control materials performance characterization. These examinations of fixed burnable poison rods and control rods confirmed operational performance and extended the material behavior data base for irradiated absorber materials used in B&W-designed pressurized water reactors. These examinations included visual, dimensional, and destructive examinations. They were conducted at B&W’s Lynchburg Research Center hot cell facilities on Ag-In-Cd control rods, Al2O3-B4C burnable poison rods, and B4C control rods. The visual and dimensional exams revealed no discernible exterior damage on any of these components. Destructive examinations provided data on absorber swelling, gas release, and open porosity.
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Postirradiation examinations have been conducted as part of an extensive Babcock & Wilcox (B&W) program in reactor control materials performance characterization. These examinations of fixed burnable poison rods and control rods confirmed operational performance and extended the material behavior data base for irradiated absorber materials used in B&W-designed pressurized water reactors. These examinations included visual, dimensional, and destructive examinations. They were conducted at B&W’s Lynchburg Research Center hot cell facilities on Ag-In-Cd control rods, Al2O3-B4C burnable poison rods, and B4C control rods. The visual and dimensional exams revealed no discernible exterior damage on any of these components. Destructive examinations provided data on absorber swelling, gas release, and open porosity.
Key concepts: Control rod, Rod, Pressurized water reactor, Irradiation, Materials science, Porosity, Nuclear engineering, Light-water reactor