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Data Base on the Behavior of High Burnup Fuel Rods with Zr-1%Nb Cladding and U0 2 Fuel (VVER Type) Under Reactivity Accident Conditions

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Data Base on the Behavior of High Burnup Fuel Rods with Zr-1%Nb Cladding and U0 2 Fuel (VVER Type) Under Reactivity Accident Conditions NUREG/IA-0156 Vol. 2 IPSN 99/08-2 NSI RRC 2179 International Agreement Report Data Base on the Behavior of High Burnup Fuel Rods with Zr-1%Nb Cladding and U0 2 Fuel (VVER Type) under Reactivity Accident Conditions Description of Test Procedures and Analytical Methods Prepared by L. Yegorova, V Asmolov, G. Abyshov, V. Malofeev, A. Awakumov, E. Kaplar, K. Lioutov, A. Shestopalov Nuclear Safety Institute of Russian Research Centre "Kurchatov Institute" Kurchatov Square 1, Moscow 123182, Russia A Bortash, L. Maiorov, K. Mikitiouk, V Polvanov Institute of Nuclear Reactors of Russian Research Centre "Kurchatov Institute" Kurchatov Square 1, Moscow 123182, Russia V Smirnov, A Goryachev, V Prokhorov State Research Centre "Research Institute of Atomic Reactors" Dimitrovgrad 433510, Russia V Pakhnitz, A. Vurim Institute of Atomic Energy of National Nuclear Centre of Kazakhstan Republic Semipalatinsk 490021, Kazakhstan Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 July 1999 Prepared for U.S. Nuclear Regulatory Commission, Institute for Protection and Nuclear Safety (France) and Ministry of Science and Technologies of Russian Federation Published by U.S. Nuclear Regulatory Commission AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications NRC publications in the NUREG series, NRC regu- NRC Public Document Room lations, and Title 10, Energy,of the Code of Federal 2120 L Street, N.W., Lower Level Regulations, may be purchased from one of the fol- Washington, DC 20555-0001 lowing sources: <http://www.nrc.gov/NRC/PDR/pdrl .htm> 1-800-397-4209 or locally 202-634-3273 1. The Superintendent of Documents U.S. Government Printing Office Microfiche of most NRC documents made publicly RO. 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Codes and A portion of NRC regulatory and technical informa- standards are usually copyrighted and may be tion is available at NRC's World Wide Web site: purchased from the originating organization or, if they are American National Standards, from- <http://www.nrc.gov> American National Standards Institute All NRC documents released to the public are avail- 11 West 42nd Street able for inspection or copying for a fee, in paper, New York, NY 10036-8002 microfiche, or, in some cases, diskette, from the <http://www.ansi.org> Public Document Room (PDR): 212-642-4900 DISCLAIMER This report was prepared under an international cooperative party's use, or the results of such use, of any information, appa- agreement for the exchange of technical information. Neither ratus, product, or process disclosed in this report, or represents the United States Government nor any agency thereof, nor any that its use by such third party would not infringe privately of their employees, makes any warranty, expressed or implied, owned rights. or assumes any legal liability or responsibility for any third NUREG/IA-0156 Vol. 2 IPSN 99/08-2 -I r iNSI RRC 2179 International Agreement Report Data Base on the Behavior of High Burnup Fuel Rods with Zr-1%Nb Cladding and U0 2 Fuel (VVER Type) under Reactivity Accident Conditions Description of Test Procedures and Analytical Methods Prepared by L Yegorova, V. Asmolov, G. Abysbov, V. Malofeev, A. Awakumov, F. Kaplar, K ljoutov, A Shestopalov Nuclear Safety Institute of Russian Research Centre "Kurchatov Institute" Kurchatov Square 1, Moscow 123182, Russia A. Bortash, L Maiorov, K. Mikitiouk, V. Polvanov Institute of Nuclear Reactors of Russian Research Centre "Kurchatov Institute" Kurchatov Square 1, Moscow 123182, Russia V. Smirnov, A. Goryachev, V.Prokhorov State Research Centre "Research Institute of Atomic Reactors" Dimitrovgrad 433510, Russia V. Pakhnitz, A. VuArim Institute of Atomic Energy of National Nuclear Centre of Kazakhstan Republic Semipalatinsk 490021, Kazakhstan Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 July 1999 Prepared for U.S. Nuclear Regulatory Commission, Institute for Protection and Nuclear Safety (France) and Ministry of Science and Technologies of Russian Federation Published by U.S. Nuclear Regulatory Commission ABSTRACT This volume of the report contains the following information on test conditions and basic procedures used to develop the data base: " objects and conditions of the IGR reactor tests; * test parameters of fuel rods before, during and after the RIA tests; " parameters of fuel rods during RIA tests calculated by FRAP-T6 and SCANAIR computer codes; * measured mechanical properties of Zr-I %Nb cladding obtained due to special tests; * parameters of Zr-l%Nb cladding failure of the ballooning type measured under the burst test conditions; * input data with original material properties of Zr-1%N'b cladding for the MATPRO package and SCANAIR code. iii TABLE OF CONTENTS Page 1. EXECUTIVE SUMMARY 1.1 1.1 I.Introduction ...................................................................................................................................... 1.1 1.2. The IGR/RIA tests with VVER high burnup fuel rods .................................................................... 1.1 1.3. Experiments to measure mechanical properties of Zr-l%Nb cladding ............................................ 1.4 1.4. Computational analysis of W ER fuel rod behavior under IGR/RIA test conditions ..................... 1.5 1.5. Structure of the generalized data base for IGR/RIA tests of VVER fuel rods ................................. 1.5 1.6. R eferences ........................................................................................................................................ 1.6 2. OBJECTIVES AND CONDITIONS OF THE IGR REACTOR TESTS 2.1 2. 1. Test objects ....................................................................................................................................... 2.1 2.2. Test conditions ................................................................................................................................. 2.3 2.3. References ........................................................................................................................................ 2.10 3. CHARACTERISTICS OF FUEL RODS BEFORE AND AFTER IGR TESTS 3.1 3.1. High burnup commercial fuel elements of power unit No 5 of NV NPP ......................................... 3.1 3.1.1. Geometric and thermo-physical characteristics of fuel elements [1, 2] ................................ 3.1 3.1.2. Burnup, fuel isotopic composition and chemical composition of the gas inside the fuel elem ent .................................................................................................................................. 3.1 3.2. Characteristics of refabricated fuel rods before IGR tests ............................................................... 3.2 3.2.1. High bumup fuel rods ............................................ 3.3 3.2.2. Axial distribution of the fuel mass in high burnup fuel rods ............................... 3.3 3.2.3. Isotopic composition of the high burnup fuel rods ................................................................ 3.7 3.2.4. Fuel rods with fresh fuel and irradiated cladding ................................................................. 3.13 3.2.5. Fresh fuel rods ......................................................................................................................
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