United States Nuclear Regulatory Commission - Protecting People and the Environment

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 (NUREG/IA-0156, Volume 2, IPSN 99/08-2, NSI RRC KI-2179)

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Publication Information

Manuscript Completed: December 1998
Date Published: July 1999

Prepared by:
L. Yegorova, V. Asmolov, G. Abyshov, V. Malofeev, A. Avvakumov, 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

Prepared for:
U.S. Nuclear Regulatory Commission
Institute for Protection and Nuclear Safety (France)
Ministry of Science and Technologies of Russian Federation

Published by:
Division of Systems Analysis and Regulatory Effectiveness
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

The present report contains a data base used for analyzing the behavior of three types of VVER fuel rods (fresh fuel rods; fuel rods with fresh fuel and irradiated cladding; high burnup fuel rods) which have been tested in the Impulse Graphite Reactor (IGR) under reactivity accident conditions. The basic test parameters are as follows:

  • capsule tests with stagnant water or air coolant under ambient conditions;
  • pressurized fuel rods;
  • fuel burnup: 0 and 48 MWd/kg U;
  • pulse width: about 700 Ms.

The presented data base includes the results of reactor tests of 25 fuel rods as well as results of pre- and posttest examinations of fuel rods, computer simulations of fuel rod behavior under test conditions; in addition, the report presents the results of special out-of-pile tests carried out to measure mechanical properties of Zr-1%Nb cladding.

The report consists of three volumes, each volume contains the following information:

Volume 1: Brief description of the test program, testing and analytical techniques and summary of results;

Volume 2: Description and validation of procedures used to obtain the data base. Summarization of test results as supported by mechanical properties of Zr-1%Nb cladding;

Volume 3:

Data base consisting of:

  • parameters of VVER fuel rods before and after irradiation at the NovoVoronezh Nuclear Power Plant;
  • parameters of fresh and refabricated fuel rods before and after IGR tests;
  • results of out-of-pile mechanical tests of non-irradiated and irradiated Zr-1%Nb claddings.

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-1%Nb cladding obtained due to special tests;
  • parameters of Zr-1%Nb cladding failure of the ballooning type measured under the burst test conditions;
  • input data with original material properties of Zr-1%Nb cladding for the MATPRO package and SCANAIR code.
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