CN112730112B - Environment fracture evaluation method suitable for reactor structural component material after long-term service - Google Patents
Environment fracture evaluation method suitable for reactor structural component material after long-term service Download PDFInfo
- Publication number
- CN112730112B CN112730112B CN202011500508.XA CN202011500508A CN112730112B CN 112730112 B CN112730112 B CN 112730112B CN 202011500508 A CN202011500508 A CN 202011500508A CN 112730112 B CN112730112 B CN 112730112B
- Authority
- CN
- China
- Prior art keywords
- stress
- crack propagation
- equation
- propagation rate
- corrosion
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Images
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N3/00—Investigating strength properties of solid materials by application of mechanical stress
- G01N3/32—Investigating strength properties of solid materials by application of mechanical stress by applying repeated or pulsating forces
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N2203/00—Investigating strength properties of solid materials by application of mechanical stress
- G01N2203/0001—Type of application of the stress
- G01N2203/0005—Repeated or cyclic
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N2203/00—Investigating strength properties of solid materials by application of mechanical stress
- G01N2203/0014—Type of force applied
- G01N2203/0016—Tensile or compressive
- G01N2203/0017—Tensile
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N2203/00—Investigating strength properties of solid materials by application of mechanical stress
- G01N2203/0058—Kind of property studied
- G01N2203/0069—Fatigue, creep, strain-stress relations or elastic constants
- G01N2203/0073—Fatigue
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N2203/00—Investigating strength properties of solid materials by application of mechanical stress
- G01N2203/02—Details not specific for a particular testing method
- G01N2203/022—Environment of the test
- G01N2203/0236—Other environments
- G01N2203/024—Corrosive
Landscapes
- Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Chemical & Material Sciences (AREA)
- Analytical Chemistry (AREA)
- Biochemistry (AREA)
- General Health & Medical Sciences (AREA)
- General Physics & Mathematics (AREA)
- Immunology (AREA)
- Pathology (AREA)
- Testing Resistance To Weather, Investigating Materials By Mechanical Methods (AREA)
Abstract
The invention discloses an environmental fracture evaluation method suitable for a reactor structural component material after long-term service, which comprises the following steps: 1) carrying out accelerated aging tests on the samples to obtain aging samples with different aging degrees; 2) measuring a stress corrosion crack propagation rate equation and a corrosion fatigue crack propagation rate equation of the aged sample; 3) determining a crack propagation rate equation of the aged sample under the coupling stress; 4) substituting the stress corrosion crack propagation rate equation and the corrosion fatigue crack propagation rate equation obtained in the step 2) into the crack propagation rate equation under the coupling stress obtained in the step 3) for fitting to obtain an acceleration factor and a combined crack propagation equation; 5) and 4) evaluating the crack propagation rate of the actually-used component through the combined crack propagation equation obtained in the step 4), and evaluating the environmental fracture by combining the service current situation and the size of the component. According to the environmental fracture evaluation method, the evaluation result is more accurate and effective.
Description
Technical Field
The invention particularly relates to an environmental fracture evaluation method of a nuclear power station reactor structure component material after long-term service, in particular to a service condition of interaction of tensile stress and periodic cyclic stress.
Background
Nuclear power is the only modern clean energy source which can replace fossil fuels on a large scale at the present stage. In the stable operation process of the nuclear power station, part of metal materials such as stainless steel and the like can be subjected to constant tensile stress caused by high-temperature and high-pressure water, such as a primary pipeline, a secondary pipeline, a pressure vessel and the like. However, since the coolant temperature and pressure are constantly changing during operation, particularly during start-up and shut-down of the stack and during power adjustment, high-temperature and high-pressure equipment is often subjected to periodic alternating stress while being subjected to constant tensile stress. Under such severe service environments, both stress corrosion and corrosion fatigue failure are likely to occur.
At present, the life evaluation methods of stress corrosion and corrosion fatigue under high temperature and high pressure water environment have been widely researched worldwide. The part in actual working conditions is operated under the combined action of constant stress and periodic alternating stress, and the environmental fracture life evaluation under the complex stress environment cannot be effectively carried out. The method for evaluating stress corrosion cracking or periodic cyclic stress of single tensile stress cannot accurately and effectively evaluate the serving pipeline; meanwhile, the influence of the thermal aging behavior after long-time service on the environmental fracture service life of the material is not considered in the conventional method; the application of the method for evaluating the environmental fracture life of the reactor structural material is severely limited.
Disclosure of Invention
In view of the above, in order to overcome the defects of the prior art and achieve the above object, the present invention provides a method for evaluating environmental fracture after long-term service of a nuclear power plant reactor structural component material, and the evaluation result is more accurate and effective.
In order to achieve the purpose, the invention adopts the following technical scheme:
the environmental fracture evaluation method suitable for the reactor structural component material after long-term service comprises the following steps:
1) carrying out accelerated aging tests on the samples to obtain aging samples with different aging degrees;
2) measuring a stress corrosion crack propagation rate equation and a corrosion fatigue crack propagation rate equation of the aged sample;
3) determining a crack propagation rate equation of the aged sample under the coupling stress;
4) substituting the stress corrosion crack propagation rate equation and the corrosion fatigue crack propagation rate equation obtained in the step 2) into the crack propagation rate equation under the coupling stress obtained in the step 3) for fitting to obtain an acceleration factor and a combined crack propagation equation;
5) and 4) evaluating the crack propagation rate of the actually-used component through the combined crack propagation equation obtained in the step 4), and evaluating the environmental fracture by combining the service current situation and the size of the component.
According to some preferred embodiments of the present invention, in the accelerated aging test of step 1), the equivalent conversion is performed by using the arrhenius equation of formula 1:
k＝A exp(-Ea/RT) (1)
in formula 1, k is the rate constant, a is the pre-exponential factor, Ea is the activation energy, R is the gas constant, and T is the thermodynamic temperature.
According to some preferred embodiments of the present invention, if the sample is made of Z3CN20.09M cast austenitic stainless steel, Ea is 100KJ, and equation 1 is derived from the relationship between time T and temperature T in equation 2:
according to some preferred embodiments of the present invention, the sample in step 1) is prepared from the same material as the service material.
According to some preferred embodiments of the invention, in step 2), the aged sample is subjected to stress corrosion and corrosion fatigue crack propagation rate tests in a simulated service environment of the component, and different stress levels are set, wherein the stress corrosion test adopts single tensile stress, and the corrosion fatigue test adopts symmetric cyclic tensile stress, so as to obtain crack propagation rate equations of the aged samples with different aging degrees at different stress levels. According to some preferred embodiments of the invention, the stress corrosion crack growth rate equation obtained in step 2) is:
(da/dN)scc＝a×10x×ΔKy (3)
in formula 3, Δ K is a stress intensity factor in the test process, calculated from the stress level in the test process, and a, x, y are coefficients of a set of crack propagation rate equations for a determined material aging state and stress level.
According to some preferred embodiments of the invention, the corrosion fatigue crack growth rate equation obtained in step 2) is:
(da/dN)CF＝10r×ΔKs (4)
Δ K in equation 4 is the stress intensity factor during the test, calculated from the stress level during the test, where r, s are the coefficients of a set of measured crack propagation rate equations for a determined state of material aging and stress level.
According to some preferred embodiments of the invention, the crack propagation rate test under coupled stress in step 3), the selection of stress is combined according to the stress settings in step 2), being a combination of constant tensile stress and cyclic stress; the measured crack propagation rate equation is as follows:
(da/dN)(SCC+CF)＝a×10x×ΔKy+10r×ΔKs+Z (5)
Δ K in equation 5 is the stress intensity factor during the test, where a, x, y, r, s are the coefficients of the crack propagation rate equation for a set of determined material aging states and stress levels measured, and Z is a polynomial that depends on the actual test results. Z represents a polynomial which can exist after finishing in the process of adding and finishing two different crack propagation modes, and is a polynomial which can be determined in the data finishing process after the test.
According to some preferred embodiments of the invention, fitting is performed by substituting equations 3 and 4 into equation 5 to obtain the acceleration factor of the co-stress, and to obtain the combined crack propagation equation under different aging conditions, different cyclic stresses and different tensile stresses:
in formula 6, m and n are acceleration factors after fitting the stress corrosion crack propagation rate equation and the corrosion fatigue crack propagation rate, respectively.
According to some preferred implementation aspects of the invention, the stress state of the in-service component in the field is monitored in step 5), the stress is decomposed into superposition of cyclic stress and constant stress, the corresponding crack propagation rate and acceleration factor are selected from step 4) according to the stress level, a crack propagation rate equation of the in-service component is obtained, and environmental fracture evaluation is carried out by combining the service status and the size of the component. The specific method comprises the following steps:
substituting equation 6 into equation 7 yields the length of crack propagation for a given crack propagation rate and time, and when the crack length L reaches the thickness of the part in the crack propagation direction, the part will leak and fail.
Compared with the prior art, the invention has the advantages that: according to the assessment method for the environmental fracture of the nuclear power plant reactor structural component material after long-term service, the thermal aging state and the stress state of the material are fully considered, so that the assessment result is more accurate and effective, the crack propagation rate of the nuclear reactor structural material in the service environment is more accurately and effectively assessed, the service state of the nuclear power plant key structural material is more accurately grasped, and important data support is provided for safe operation of the nuclear power plant.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings needed to be used in the description of the embodiments will be briefly introduced below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without creative efforts.
Fig. 1 is a schematic flow chart of an environmental fracture evaluation method after long-term service of a nuclear power plant reactor structural component material in a preferred embodiment of the present invention.
Detailed Description
In order to make those skilled in the art better understand the technical solution of the present invention, the technical solution in the embodiment of the present invention will be clearly and completely described below with reference to the drawings in the embodiment of the present invention, and it is obvious that the described embodiment is only a part of the embodiment of the present invention, and not a whole embodiment. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
As shown in fig. 1, the method for evaluating environmental fracture after long-term service of reactor structural component material according to the embodiment includes the following steps:
1) carrying out accelerated aging test to obtain aging samples with different aging times
The sample is prepared by adopting the same material as a service material. The following temperatures were selected for accelerated simulated aging tests: the aging degree is equivalent to different aging degrees, such as 10 years, 20 years, 30 years, 40 years, 50 years, 60 years and the like, by converting the Arrhenius equation at 330 ℃, 360 ℃ and 390 ℃. The calculation by the arrhenius equation is as follows:
k＝A exp(-Ea/RT) (1)
where K is the rate constant, A is the pre-exponential factor, Ea is the activation energy, R is the gas constant, and T is the thermodynamic temperature (K).
For cast austenitic stainless steel Z3CN20.09M, Ea may take 100 KJ. Equation (1) can be derived as the relationship between time t (h) and temperature t (k), as shown in equation 2:
the accelerated aging is converted by the formula, for example, the service temperature of Z3CN20.09M stainless steel is 290 ℃, and the service time and the accelerated aging temperature are substituted to obtain the accelerated aging time.
2) Determination of stress corrosion (SCC) and Corrosion Fatigue (CF) crack growth rate equations for materials after different aging times
Aging samples with different thermal aging degrees are made into test samples, then the test of the crack propagation rates of SCC and CF is carried out in the simulated service environment of the component, and different stress levels are set. The stress corrosion SCC test adopts single tensile stress, the corrosion fatigue CF test adopts symmetrical cyclic tensile stress, and a crack propagation rate equation of materials with different aging degrees and different stress levels is obtained. A series of data were then measured, including crack propagation rates for different levels of thermal aging and different stress levels. The measured crack propagation rate equation is of the form:
the stress corrosion (SCC) crack propagation rate equation is:
the Corrosion Fatigue (CF) crack propagation rate equation is:
Δ K in equations (3) and (4) is the stress intensity factor during the test, calculated from the stress level during the test, where a, x, y, r, s are the coefficients of a measured set of crack propagation rate equations for a determined state of material aging and stress level.
3) Method for measuring crack propagation rate equation of material under coupling stress after different aging time
And (3) carrying out crack propagation rate tests under coupling stress on samples in different aging states, wherein the stress is selected and combined according to the stress setting in the step 2) and is the combination of constant tensile stress and cyclic stress. The measured crack propagation rate equation is of the form:
……
Δ K in equation (5) is the stress intensity factor during the test, where a, x, y, r, s are the coefficients of a set of measured crack propagation rate equations for a determined state of material aging and stress level, and Z is a polynomial, depending on the actual test results. Z represents a polynomial which can exist after finishing in the process of adding and finishing two different crack propagation modes, and is a polynomial which can be determined in the data finishing process after the test.
4) Fitting to obtain an acceleration factor
Fitting two crack propagation rate equations (formula (3) and (4)) in the step 2) into a formula (5) in the step 3) according to the combination of the stresses to obtain a synergistic stress acceleration factor. This allows a series of crack propagation equations to be derived for different aging states, different combinations of cyclic stress and tensile stress. As follows:
where m and n are the acceleration factors after SCC and CF crack propagation rates, respectively, after fitting.
5) Crack propagation rate evaluation of components in actual service
Through the experimental research and the fitting calculation, a series of crack propagation rate equations of different materials under different stress conditions in the aging state are obtained, and acceleration factors under corresponding coupling stress are obtained through fitting. And (3) monitoring the stress state of the on-site service component, decomposing the stress state into superposition of cyclic stress and constant stress, selecting corresponding crack propagation rate and acceleration factor from the step 4) according to the stress level to obtain a crack propagation rate equation of the on-site service component, and effectively performing environmental fracture evaluation by combining the service current situation and the size of the component.
Specifically, substituting equation (6) into equation (7) yields the length of crack propagation for a given crack propagation rate and time, and when the crack length reaches the thickness of the component in the crack propagation direction, the component will leak and fail.
The basic principle of the invention is as follows: accelerated aging of reactor structural materials at different time and different temperature is carried out in a laboratory, service time under actual service working condition is equivalently converted through an Arrhenius equation, then stress corrosion (SCC), Corrosion Fatigue (CF) and a life evaluation equation under coupling stress are carried out on the reactor structural materials after thermal aging, and the two equations are fitted with the latter to obtain an acceleration factor. By monitoring the stress state of the in-service pipeline, the obtained data are decomposed into constant stress and periodic cyclic stress, and the constant stress and the periodic cyclic stress are brought into a crack propagation rate equation with an acceleration factor, so that the crack propagation rate equation of the in-service pipeline can be obtained, and the environmental fracture evaluation of the in-service pipeline is realized.
The core technical scheme of the invention is as follows: and respectively measuring crack propagation rate equations under periodic cyclic stress and constant tensile stress in different aging states, testing multiple groups of crack propagation rates under different aging states and different stress levels in the test process, and fitting the crack propagation rates with the crack propagation rates under coupling stress to obtain an acceleration factor. Finally, a series of crack propagation rate equations in different stress states and aging states are formed for the on-site service parts to use in crack propagation rate evaluation.
According to the assessment method for the environmental fracture of the nuclear power plant reactor structural component material after long-term service, the thermal aging state and the stress state of the material are fully considered, so that the assessment result is more accurate and effective, the crack propagation rate of the nuclear reactor structural material in the service environment is more accurately and effectively assessed, the service state of the nuclear power plant key structural material is more accurately grasped, and important data support is provided for safe operation of the nuclear power plant.
The above embodiments are merely illustrative of the technical concept and features of the present invention, and the purpose thereof is to enable those skilled in the art to understand the content of the present invention and implement the invention, and not to limit the scope of the invention, and all equivalent changes or modifications made according to the spirit of the present invention should be covered by the scope of the present invention.
Claims (3)
1. The method for evaluating the environmental fracture after the long-term service of the reactor structural component material is characterized by comprising the following steps of:
1) carrying out accelerated aging tests on the samples to obtain aging samples with different aging degrees;
2) measuring a stress corrosion crack propagation rate equation and a corrosion fatigue crack propagation rate equation of the aged sample;
3) determining a crack propagation rate equation of the aged sample under the coupling stress;
4) substituting the stress corrosion crack propagation rate equation and the corrosion fatigue crack propagation rate equation obtained in the step 2) into the crack propagation rate equation under the coupling stress obtained in the step 3) for fitting to obtain an acceleration factor and a combined crack propagation equation;
5) evaluating the crack propagation rate of the actually-used component through the combined crack propagation equation obtained in the step 4), and evaluating environmental fracture by combining the service current situation and the size of the component;
in the step 2), the aged sample is subjected to stress corrosion and corrosion fatigue crack propagation rate tests in a simulated service environment of the component, and different stress levels are set, wherein the stress corrosion test adopts single tensile stress, and the corrosion fatigue test adopts symmetrical cyclic tensile stress, so that crack propagation rate equations of the aged sample with different aging degrees under different stress levels are obtained;
the stress corrosion crack propagation rate equation obtained in the step 2) is as follows:
(da/dN)SCC＝a×10x×ΔKy (3)
in the formula 3, delta K is a stress intensity factor in the test process, the stress intensity factor is calculated according to the stress level in the test process, and a, x and y are coefficients of a group of crack propagation rate equations of the determined material aging state and the stress level;
the corrosion fatigue crack propagation rate equation obtained in the step 2) is as follows:
(da/dN)CF＝10r×ΔKs (4)
in the formula 4, Δ K is a stress intensity factor in the test process and is calculated from the stress level in the test process, wherein r and s are coefficients of a crack propagation rate equation of a set of determined material aging state and stress level;
in the crack propagation rate test under the coupling stress in the step 3), the selection of the stress is combined according to the stress setting in the step 2), and the stress is the combination of constant tensile stress and cyclic stress; the measured crack propagation rate equation is as follows:
(da/dN)(SCC+CF)＝a×10x×ΔKy+10r×ΔKs+Z (5)
Δ K in equation 5 is the stress intensity factor during the test, where a, x, y, r, s are the coefficients of a set of measured crack propagation rate equations for a determined state of material aging and stress level, and Z is a polynomial that depends on the actual test results;
substituting the formulas 3 and 4 into the formula 5 for fitting to obtain a synergistic stress acceleration factor and obtain a combined crack propagation equation under different aging states, different cyclic stresses and different tensile stresses:
in the formula 6, m and n are acceleration factors after fitting a stress corrosion crack propagation rate equation and a corrosion fatigue crack propagation rate respectively;
monitoring the stress state of the existing field service component in the step 5), decomposing the stress into superposition of cyclic stress and constant stress, selecting corresponding crack propagation rate and acceleration factor from the step 4) according to the stress level, obtaining a crack propagation rate equation of the existing service component, and performing environmental fracture evaluation by combining the service status and the size of the component;
substituting equation 6 into equation 7 yields the length of crack propagation for a given crack propagation rate and time:
2. the environmental fracture evaluation method according to claim 1, wherein in the accelerated aging test of step 1), the equivalent conversion is performed by using an arrhenius equation of formula 1:
k＝Aexp(-Ea/RT) (1)
in formula 1, k is the rate constant, a is the pre-exponential factor, Ea is the activation energy, R is the gas constant, and T is the thermodynamic temperature.
3. The environmental fracture evaluation method according to claim 2, wherein if the sample is made of Z3CN20.09M cast austenitic stainless steel, Ea is 100KJ, and equation 1 is derived from the relationship between time T and temperature T in equation 2:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011500508.XA CN112730112B (en) | 2020-12-18 | 2020-12-18 | Environment fracture evaluation method suitable for reactor structural component material after long-term service |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011500508.XA CN112730112B (en) | 2020-12-18 | 2020-12-18 | Environment fracture evaluation method suitable for reactor structural component material after long-term service |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN112730112A CN112730112A (en) | 2021-04-30 |
| CN112730112B true CN112730112B (en) | 2022-07-01 |
Family
ID=75603108
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202011500508.XA Active CN112730112B (en) | 2020-12-18 | 2020-12-18 | Environment fracture evaluation method suitable for reactor structural component material after long-term service |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN112730112B (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114112668B (en) * | 2021-11-19 | 2024-03-12 | 华能国际电力股份有限公司 | Matrix crack propagation life prediction model of high-temperature static part of gas turbine |
| CN114965233A (en) * | 2021-12-14 | 2022-08-30 | 昆明理工大学 | Method for accelerating poor material performance |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0392471B1 (en) * | 1989-04-10 | 1997-01-02 | Hitachi, Ltd. | Method for evaluating life of connection |
| CN100549660C (en) * | 2007-05-17 | 2009-10-14 | 西北工业大学 | Three-dimensional cracks expansion analogy method based on embedded type finite element model |
| CN105651606A (en) * | 2016-01-26 | 2016-06-08 | 苏州热工研究院有限公司 | Method for assessing structural integrity of high-temperature and high-pressure welded member |
| CN106055741B (en) * | 2016-05-19 | 2018-04-24 | 北京航空航天大学 | A kind of Structural Metallic Fatigue crack expansion life span predication method based on Taylor perturbation series methods |
| CN111339700B (en) * | 2020-02-19 | 2023-04-07 | 广东核电合营有限公司 | Method and device for evaluating fatigue damage of nuclear turbine blade and storage medium |
-
2020
- 2020-12-18 CN CN202011500508.XA patent/CN112730112B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| CN112730112A (en) | 2021-04-30 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN112730112B (en) | Environment fracture evaluation method suitable for reactor structural component material after long-term service | |
| CN109781611B (en) | Quantitative evaluation method for stress corrosion cracking of main pipeline of pressurized water reactor of nuclear power station | |
| CN114936498A (en) | Creep fatigue damage grade determination method and system considering material performance degradation | |
| Kim et al. | Evaluation of Creep Properties of Alloy 690 Steam Generator Tubes at High Temperature Using Tube Specimen | |
| Molander et al. | Environmental effects on PWSCC initiation and propagation in alloy 600 | |
| CN114279944B (en) | Method for evaluating coupling effect of heat aging, stress and corrosion of stainless steel welding material | |
| CN103278525A (en) | Safety assessment method for pressure-bearing equipment after fire disaster | |
| Lucan et al. | Corrosion analysis and diagnosis–useful tools for plant life management and long term operation programmes in nuclear power plant | |
| Coleman et al. | Evaluation of Zircaloy-2 pressure tubes from NPD | |
| Diercks et al. | Steam generator tube integrity program | |
| JP2014142304A (en) | Life evaluation method for austenite stainless steel | |
| Petzová et al. | Application of small punch testing methods for thermal ageing monitoring at primary circuit components in nuclear power plant | |
| Pagan et al. | Characterization and structural integrity tests of ex-service steam generator tubes at Ontario Power Generation | |
| Zhang et al. | Assessment of prior fatigue damage and a new approach to predict remanent creep rupture of P92 steel | |
| CN116337731A (en) | Service life assessment method for stress corrosion cracking and environmental fatigue of material under complex stress state | |
| Kerezsi et al. | Using the ASME and BSI codes to predict crack growth due to repeated thermal shock | |
| Takakura et al. | IASCC evaluation method of irradiated cold worked 316SS baffle former bolt in PWR primary water | |
| Zhang et al. | Reliability analysis of main steam pipe containing defects | |
| Fang et al. | Environmental Fatigue Behavior of a Z3CN20. 09M Stainless Steel in High Temperature Water. Coatings 2022, 12, 317 | |
| Celovsky et al. | Material Surveillance of CANDU Zirconium 2.5% Wt Niobium Pressure Tubes | |
| Komazaki et al. | Fatigue strength assessment of SUS316 by small bulge fatigue (SBF) test | |
| Zhai et al. | Evaluation of Stress Corrosion Crack Initiation in Nickel-Base Alloys and Implications for PWR Components | |
| CN116793857A (en) | Service life assessment method for alloy seamless tube for nuclear power heat exchanger | |
| JPH06201680A (en) | Method and device for inspecting material | |
| Tice | Assessment of environmentally assisted cracking in PWR pressure vessel steels |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |