Propagation of stress corrosion cracks in Zr-1% Nb claddings

Bibilashvily, Yu.K.; Dolgov, Yu. N.; Nesterov, Boris; Новиков, В. В.

doi:10.1016/0022-3115(95)00114-x

Cited by 12 publications

(8 citation statements)

References 8 publications

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“…The data from [13,14] on tubular samples of the VVER type 9.1 0.65 mm [13] and of the RBMK type 13.6 0.9 mm [14] presented for comparison are in satisfactory agreement with the data of this work.…”

Section: Research Methods and Simulation Results Of The Initiation Ansupporting

confidence: 82%

“…The summarized test results, including the calculated data of the current values of stress intensity factor and subcritical crack propagation rate are also shown in the table. The table presents some of the data from [13,14] for comparison purposes.…”

Section: Research Methods and Simulation Results Of The Initiation Anmentioning

confidence: 99%

“…Models of the second group use a relatively traditional approach of fracture mechanics, which relates the design survivability to the crack propagation kinetics, that is, to the dependence of its extension rate on the parameter characterizing the stress state at the top. Assuming that stress corrosion damage occurs by cleavage, the stress intensity factor (K ISCC ) is taken as such a parameter [12,14,15].…”

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confidence: 99%

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Simulation of Initiation and Development of Corrosion Cracks in Zirconium Fuel Claddings Under Conditions of Stress Corrosion Cracking in Environment of Iodine

Sotnikov

2019

HoBMSTU.SME

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KeywordsThe process models of iodine corrosion cracking of zirconium fuel claddings, used to calculate the durability of the cladding (time for loss of tightness) are considered. A method for determining the corrosion crack propagation rate in claddings made of E110 alloy Ø 9.1 0.65 mm and the results of corresponding studies (estimation of corrosion crack propagation rate and stress intensity factor K ISCC ) are given at a temperature of 380 C in iodine environment at a concentration of ~ 0.2 mg/cm 2 . Studies were performed using tubular samples with a fatigue crack. A fatigue crack on the inner surface of cladding made of E110 Ø 9.1 × 0.65 mm alloy is the initiator of a corrosion crack emergence (nucleation). The results of corresponding studies are consistent with data from the literature. The proposed study of the corrosion cracking process of fuel claddings in accordance with the results of fracture mechanics is of practical importance for substantiation of the regulation of reactor operating conditions E110 zirconium alloy, Introduction. The experience of operating nuclear power plants (NPP) with thermal neutron reactors made it possible, based on fuel elements failure cause analysis, to determine that the interaction between the fuel and the cladding during non-stationary (transient) operating conditions may lead to burst of the fuel claddings. The most probable mechanism for such burst is cracking of zirconium claddings due to stress corrosion (SCC) at iodine exposure [1], which is released from the fuel during uranium fission. The release of atomic iodine in a fuel element can occur both as a result of chemical reactions involving oxygen and uranium fission products, and as a result of cesium iodide radiolysis [2], that determines the actual possibility of iodine corrosion of the claddings made from zirconium alloys in the presence of tensile stresses in them.

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Section: Research Methods and Simulation Results Of The Initiation Ansupporting

confidence: 82%

Section: Research Methods and Simulation Results Of The Initiation Anmentioning

confidence: 99%

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Simulation of Initiation and Development of Corrosion Cracks in Zirconium Fuel Claddings Under Conditions of Stress Corrosion Cracking in Environment of Iodine

Sotnikov

2019

HoBMSTU.SME

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“…ISCC crack velocity with respect to the applied K I was evaluated to determine the K ISCC level below which no further crack propagation occurred. The K I value was selected so that stress state round the crack tip was a plane-strain condition according to the following relationship [13]:…”

Section: Test Proceduresmentioning

confidence: 99%

Stress-corrosion crack initiation and propagation behavior of Zircaloy-4 cladding under an iodine environment

Park¹,

Kim²,

Lee³

et al. 2008

Journal of Nuclear Materials

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“…Next, we calculated the ISCC crack velocity with respect to the applied K I in order to determine the threshold stress intensity factor (K ISCC ). Finally, we adjusted the K I value so that the stress state near the tip of the crack could be a plane strain condition, which is expressed as (1) where V y is the yield stress and t is the thickness of the cladding [13]. Thus, with a given yield stress of 330 MPa and a thickness of 0.57 mm, the applied K level is limited to a value of less than 10.8 MPa·m 1/2 .…”

Section: Test Proceduresmentioning

confidence: 99%

Crack initiation and propagation behavior of zirconium cladding under an environment of iodine-induced stress corrosion

et al. 2007

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Tests of iodine-induced stress corrosion cracking (ISCC) were carried out to elucidate the initiation and propagation of cracks in the claddings of zirconium alloys. Zircaloy-4 cladding and Nb-contained zirconium cladding were pressurized with and without a pre-cracked state at 350 o C in an iodine environment. The results show that pitting nucleation and growth play an important role in initiating ISCC. Pits preferentially grow and agglomerate around the grain boundary, where the number of pits increases with the iodine concentration and the hoop stress of the claddings. A model of grain-boundary pitting coalescence and a model of pitting-assisted slip cleavage, which were proposed to clearly elucidate the crack initiation and propagation process under ISCC, produce reasonable results. The Nb-contained zirconium cladding exhibits higher ISCC resistance than Zircaloy-4 from the standpoint of a higher threshold stress-intensity factor and a lower crack propagation rate.

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Propagation of stress corrosion cracks in Zr-1% Nb claddings

Cited by 12 publications

References 8 publications

Simulation of Initiation and Development of Corrosion Cracks in Zirconium Fuel Claddings Under Conditions of Stress Corrosion Cracking in Environment of Iodine

Simulation of Initiation and Development of Corrosion Cracks in Zirconium Fuel Claddings Under Conditions of Stress Corrosion Cracking in Environment of Iodine

Stress-corrosion crack initiation and propagation behavior of Zircaloy-4 cladding under an iodine environment

Crack initiation and propagation behavior of zirconium cladding under an environment of iodine-induced stress corrosion

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