Development of data base with mechanical properties of un- and pre-irradiated VVER cladding

Conference · Sun Mar 01 04:00:00 EST 1998

OSTI ID:305918

Asmolov, V; Yegorova, L; Kaplar, E; Lioutov, K ^[1]; Smirnov, V; Prokhorov, V; Goryachev, A ^[2]

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1. Nuclear Safety Inst. of Russian Research Centre, Moscow (Russian Federation). Kurchatov Inst.
2. State Research Centre, Dimitrovgrad (Russian Federation). Research Inst. of Atomic Reactors

Analysis of recent RIA test with PWR and VVER high burnup fuel, performed at CABRI, NSRR, IGR reactors has shown that the data base with mechanical properties of the preirradiated cladding is necessary to interpret the obtained results. During 1997 the corresponding cycle of investigations for VVER clad material was performed by specialists of NSI RRC KI and RIAR in cooperation with NRC (USA), IPSN (France) in two directions: measurements of mechanical properties of Zr-1%Nb preirradiated cladding versus temperature and strain rate; measurements of failure parameters for gas pressurized cladding tubes. Preliminary results of these investigations are presented in this paper.

• Research Organization: Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington, DC (United States); Brookhaven National Lab., Upton, NY (United States)
• OSTI ID: 305918
• Report Number(s): NUREG/CP--0162-Vol.2; CONF-9710101--Vol.2; ON: TI98007504
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
FUEL CANS
INFORMATION SYSTEMS
MECHANICAL PROPERTIES
NIOBIUM ALLOYS
PHYSICAL RADIATION EFFECTS
PWR TYPE REACTORS
STRAIN RATE
TEMPERATURE DEPENDENCE
WWER TYPE REACTORS
ZIRCONIUM BASE ALLOYS