In order to predict a time to failure of plant components due to stress corrosion cracking
(SCC), crack initiation and growth behavior must be understood. The crack growth
behavior is generally investigated using a pre-cracked specimen, and the relationship
between stress intensity factor (SIF) and crack growth rate is quantified according to fracture
mechanics. In nuclear power plants, this relation has been utilized to evaluate growth
behavior of cracks detected in operating plants according to fitness-for-service codes [1,2].
On the other hand, it is difficult to grasp crack initiation behavior. Although various test
methods, such as a constant load test, an U-bend test, a CBB test [3], and a slow strain rate
test, have been used in investigating crack initiation, the results obtained by these tests
have not fully contributed to understanding of crack initiation process in nuclear power
plant. If an initiation time and a size of each crack under a specified stress and environmental
condition can be predicted, the failure time of large components in nuclear power
plants could be estimated by the crack growth model combined with the crack initiation
model.
In order to predict a time to failure of plant components due to stress corrosion cracking
(SCC), crack initiation and growth behavior must be understood. The crack growth
behavior is generally investigated using a pre-cracked specimen, and the relationship
between stress intensity factor (SIF) and crack growth rate is quantified according to fracture
mechanics. In nuclear power plants, this relation has been utilized to evaluate growth
behavior of cracks detected in operating plants according to fitness-for-service codes [1,2].
On the other hand, it is difficult to grasp crack initiation behavior. Although various test
methods, such as a constant load test, an U-bend test, a CBB test [3], and a slow strain rate
test, have been used in investigating crack initiation, the results obtained by these tests
have not fully contributed to understanding of crack initiation process in nuclear power
plant. If an initiation time and a size of each crack under a specified stress and environmental
condition can be predicted, the failure time of large components in nuclear power
plants could be estimated by the crack growth model combined with the crack initiation
model.
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In Order to Predict a time to Failure Due to Stress corrosion cracking of Plant Components.
(SCC), Initiation and crack growth behavior must be Understood. The crack growth
behavior is generally Investigated using a Pre-Cracked Specimen, and The Relationship.
between Stress Intensity factor (SIF) and crack growth rate is quantified according to fracture.
Mechanics. In Nuclear Power Plants, this relation has been utilized to evaluate growth.
behavior of cracks detected in Plants operating according to fitness-for-Service Codes [1,2].
On The Other Hand, IT is Difficult to grasp crack Initiation behavior. Although Various test
methods, Such As a Constant load test, an U-Bend test, a CBB test [3], and a Slow Strain rate.
test, Have been Used in Investigating crack Initiation, The results obtained by these tests.
Have Not Fully Contributed to Understanding of crack Initiation Process in Nuclear Power.
Plant. IF an Initiation time and size of a crack under a specified Each and Environmental Stress.
condition Can be predicted, The Failure of Large Components in Nuclear Power time.
Plants could be Combined Model Estimated by The crack growth with crack The Initiation.
Model.
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In order to predict a time to failure of plant components due to stress corrosion cracking
(SCC), crack initiation and. Growth behavior must be understood. The crack growth
behavior is generally investigated using a, pre-cracked specimen and. The relationship
between stress intensity factor (SIF) and crack growth rate is quantified according to fracture
mechanics.? In nuclear, power plantsThis relation has been utilized to evaluate growth
behavior of cracks detected in operating plants according to fitness-for-service. Codes [,]. 1 2
On the other hand it is, difficult to grasp crack initiation behavior. Although various test
methods such,, As a constant, load test an U-bend test a CBB, test [3], and a slow strain rate
test have been, used in investigating crack. Initiation.The results obtained by these tests
have not fully contributed to understanding of crack initiation process in nuclear. Power
plant. If an initiation time and a size of each crack under a specified stress and environmental
condition can be. Predicted the failure, time of large components in nuclear power
plants could be estimated by the crack growth model combined. With the crack initiation
model.
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