Development of data base with mechanical properties of un- and pre-irradiated VVER cladding
Conference
·
OSTI ID:305918
- Nuclear Safety Inst. of Russian Research Centre, Moscow (Russian Federation). Kurchatov Inst.
- 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. (BNL), Upton, NY (United States)
- OSTI ID:
- 305918
- Report Number(s):
- NUREG/CP-0162-Vol.2; CONF-9710101-Vol.2; ON: TI98007504; TRN: IM9906%%170
- Resource Relation:
- Conference: 25. water reactor safety information meeting, Bethesda, MD (United States), 20-22 Oct 1997; Other Information: PBD: Mar 1998; Related Information: Is Part Of Twenty-fifth water reactor safety information meeting: Proceedings. Volume 2: Human reliability analysis and human performance evaluation; Technical issues related to rulemakings; Risk-informed, performance-based initiatives; High burn-up fuel research; Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)]; PB: 236 p.
- Country of Publication:
- United States
- Language:
- English
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