Mechanical Properties of Unirradiated and Irradiated Zr-1% Nb Cladding: Procedures and Results of Low Temperature Biaxial Burst Tests and Axial Tensile Tests (NUREG/IA-0199, IPSN 01-16, NSI RRC 2241)
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Date Published: April 2001
E. Kaplar, L. Yegorova, K. Lioutov, A. Konobeyev, N. Jouravkova
Nuclear Safety Institute of Russian Research Centre "Kurchatov Institute"
Kurchatov Square 1, Moscow 123182 Russian Federation
V. Smirnov, A. Goryachev, V. Prokhorov, 0. Makarov, S. Yeremin, A. Svyatkin
State Research Centre "Research Institute of Atomic Reactors"
Dimitrovgrad 433510, Russian Federation
U.S. Nuclear Regulatory Commission, Institute for Protection and Nuclear Safety (France), and
Ministry of Science and Technologies (Russian Federation)
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
This report contains the description of the test conditions, procedures, and main results of the following types of mechanical tests of unirradiated and irradiated Zr-1% Nb cladding:
- biaxial burst tests with liquid pressurized tube specimens in the temperature range 293–723 K;
- uniaxial tensile tests in axial direction with tube specimens in the temperature range 293–1200 K.
Results of these tests are compared with test results obtained in 1997–1999 using simple ring specimens (293–1200 K) and gas pressurized tube specimens (900–1400 K).
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