CRACKING OF CLADDING TUBES CAUSED BY POWER RAMPING AND BY LABORATORY STRESS-CORROSION EXPERIMENTS

被引:16
作者
VIDEM, K [1 ]
LUNDE, L [1 ]
HOLLOWELL, T [1 ]
VILPPONEN, K [1 ]
VITANZA, C [1 ]
机构
[1] ORG ECON COOPERAT DEV,HALDEN REACTOR PROJECT,HALDEN,NORWAY
关键词
D O I
10.1016/0022-3115(79)90562-2
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The report describes experiments focused on improving the understanding of the phenomena leading to PCI failures. The first part treats out-of-reactor iodine stress corrosion experiments in which the stress, strain or stress intensity were carefully controlled. Crack initiation was found to be a function of stress, while crack growth was a function of stress intensity. Conditions leading to transgranular and intergranular cracking, and to a large mechanical rupture zone are clarified. The second part summarizes the results from studies conducted at the Halden Project to correlate the occurrence of PCI/SCC failures with fuel design and operating parameters. The following parameters and their influence on fuel failure propensity have been studied: pellet cladding interaction factors derived from in-reactor elongation/deformation measurements, fuel temperature and cladding strain, derived from correlations based on cladding deformation and fuel centre line temperature measurements and transient fission products released during a power ramp. The analysis of the out-of-reactor and in-reactor experiments has provided an improved understanding of the critical events in the PCI/SCC processes. © 1979.
引用
收藏
页码:259 / 267
页数:9
相关论文
共 8 条
[1]  
AAS S, 1973, BNES C NUCLEAR FUEL
[2]  
COX B, 1974, CORROSION PROBLEMS E
[3]   FRACTURE OF ZIRCALOY CLADDING UNDER SIMULATED POWER RAMP CONDITIONS [J].
GARLICK, A .
JOURNAL OF NUCLEAR MATERIALS, 1973, 49 (02) :209-224
[4]  
ROBERTS JTA, 1978, 4TH INT C ZIRC NUCL
[5]  
VIDEM K, 1975, ENS ANS C NUCLEAR EN
[6]  
VIDEM K, 1978, 4TH INT C ZIRC NUCL
[7]  
VIDEM K, 1977, TOPICAL M WATER REAC
[8]  
VIDEM K, 1977, M EUROPEAN FEDERATIO