Design and Evaluation of a Ring Tension Test Grip for Remote Mechanical Testing of Irradiated Tubular Specimens

被引:0
作者
Petersen, Philip G. [1 ]
Hansen, Robert S. [1 ]
Cappia, Fabiola [2 ]
Kamerman, David
Baird, Katelyn [2 ,3 ]
Christensen, Cad [4 ]
机构
[1] Idaho Natl Lab, Struct Mat Postirradiat Examinat, 1955 N Fremont Ave, Idaho Falls, ID 83415 USA
[2] Idaho Natl Lab, Fuels Postirradiat Examinat, 1955 N Fremont Ave, Idaho Falls, ID 83415 USA
[3] Idaho Natl Lab, Fuel Dev Performance & Qualificat, 1955 N Fremont Ave, Idaho Falls, ID 83415 USA
[4] Idaho Natl Lab, Nucl Remote Syst, 1955 N Fremont Ave, Idaho Falls, ID 83415 USA
关键词
mechanical testing; ring tension test; cladding; remote design; mechanical design; FUEL; BEHAVIOR;
D O I
10.1520/JTE2024010
中图分类号
TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
The ring tension test (RTT) is a mechanical testing method for determining bulk mechanical behavior in the circumferential or hoop direction for tubular materials. The test is especially useful for testing materials with anisotropic mechanical properties, such as zirconium alloys, which are commonly used as nuclear fuel cladding. Anisotropy requires direction-specific testing to determine the hoop strength. Historically, several RTT methods and grips have been used, each method has its strengths and weaknesses, and, in all cases, the measured strength is subject to uncertainty due to variations of the testing geometry and experimental tolerances. Recent analysis has shown that grips with a hemicylindrical mandrel configuration are recommended as the most robust configuration. The two strictest aspects to be controlled are the ability to determine gage region orientation and closely matching the size of the mandrels to the test specimen. This last requirement is particularly challenging when the dimensions of the specimen vary because of environmental effects such as dimensional changes due to irradiation. This paper presents a new RTT grip designed to incorporate this mandrel shape, hold the gage at the desired orientation, be suitable for remote operation in a hot-cell environment, and be adaptable for different sizes or variations in the specimen size. The general description and the unique design features of the test specimen and grips are given in detail. The performance of the grips in mechanical testing, including in a remote hot-cell environment, is also provided.
引用
收藏
页码:1 / 20
页数:20
相关论文
共 31 条
[1]  
Abe T, 2012, COMPREHENSIVE NUCLEAR MATERIALS, VOL 2: MATERIAL PROPERTIES/OXIDE FUELS FOR LIGHT WATER REACTORS AND FAST NEUTRON REACTORS, P393
[2]  
Arsene S, 1996, J TEST EVAL, V24, P386
[3]   Strength and rupture geometry of un-irradiated C26M FeCrAl under LOCA burst testing conditions [J].
Bell, S. B. ;
Kane, K. A. ;
Massey, C. P. ;
Baldesberger, L. A. ;
Lutz, D. ;
Pint, B. A. .
JOURNAL OF NUCLEAR MATERIALS, 2021, 557
[4]   Anisotropic damage behavior of SiC/SiC composite tubes: Multiaxial testing and damage characterization [J].
Bernachy-Barbe, Fabien ;
Gelebart, Lionel ;
Bornert, Michel ;
Crepin, Jerome ;
Sauder, Cedric .
COMPOSITES PART A-APPLIED SCIENCE AND MANUFACTURING, 2015, 76 :281-288
[5]  
Cleveland-Cliffs Inc, 2021, 17-4 PH Stainless Steel Product Bulletin
[6]   The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA) [J].
Desquines, J. ;
Koss, D. A. ;
Motta, A. T. ;
Cazalis, B. ;
Petit, M. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 412 (02) :250-267
[7]   Mechanics and full-field deformation study of the Ring Hoop Tension Test [J].
Dick, Chris P. ;
Korkolis, Yannis P. .
INTERNATIONAL JOURNAL OF SOLIDS AND STRUCTURES, 2014, 51 (18) :3042-3057
[8]  
Evans C., 2014, PhD diss
[9]  
Fast Reactor Working Group, 2018, White Paper 18-01
[10]  
Field K.G., 2018, Handbook on the material properties of FeCrAl allpoys for nuclear power production applications