Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
To prepare for this project, EPRI and BWRVIP conducted a workshop at Ponte Vedra Beach, Florida during February 19-21, 2003 (EPRI report 1007822). Attendees were invited to exchange relevant information on the effects of irradiation on austenitic materials in light water reactors and to produce recommendations for further work. EPRI reviewed the data, recommendations, and conclusions derived from the workshop and developed prioritized test matrices defining new data needs. Proposals were solicited, and selected proposals are the basis for the program described in this report. Results The planned test matrix for fracture toughness testing includes 21 tests on 5 materials.
BWRVIP-140NP: BWR Vessel and Internals Project Fracture Toughness and Crack Growth Program on Irradiated Austenitic Stainless Steel
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
To prepare for this project, EPRI and BWRVIP conducted a workshop at Ponte Vedra Beach, Florida during February 19-21, 2003 (EPRI report 1007822). Attendees were invited to exchange relevant information on the effects of irradiation on austenitic materials in light water reactors and to produce recommendations for further work. EPRI reviewed the data, recommendations, and conclusions derived from the workshop and developed prioritized test matrices defining new data needs. Proposals were solicited, and selected proposals are the basis for the program described in this report. Results The planned test matrix for fracture toughness testing includes 21 tests on 5 materials.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
To prepare for this project, EPRI and BWRVIP conducted a workshop at Ponte Vedra Beach, Florida during February 19-21, 2003 (EPRI report 1007822). Attendees were invited to exchange relevant information on the effects of irradiation on austenitic materials in light water reactors and to produce recommendations for further work. EPRI reviewed the data, recommendations, and conclusions derived from the workshop and developed prioritized test matrices defining new data needs. Proposals were solicited, and selected proposals are the basis for the program described in this report. Results The planned test matrix for fracture toughness testing includes 21 tests on 5 materials.
Crack Growth Rates of Irradiated Austenitic Stainless Steel Weld Heat Affected Zone in BWR Environments
Author:
Publisher:
ISBN:
Category : Austenitic stainless steel
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category : Austenitic stainless steel
Languages : en
Pages : 0
Book Description
Crack Growth Rate and Fracture Toughness Tests on Irradiated Cast Stainless Steels
An Investigation of Fracture Toughness, Fatigue-crack Growth, Sustained-load Flaw Growth, and Impact Properties of Three Pressure Vessel Steels
Author: Charles Michael Hudson
Publisher:
ISBN:
Category : Impact
Languages : en
Pages : 60
Book Description
Publisher:
ISBN:
Category : Impact
Languages : en
Pages : 60
Book Description
Fatigue Crack Propagation and Fracture Studies of a Pressure Vessel Steel Temper Embrittled to Simulate Irradiation Damage
Author: T. W. Crooker
Publisher:
ISBN:
Category :
Languages : en
Pages : 17
Book Description
Fatigue crack propagation tests were conducted using plate bend specimens machined from shell material of the PM-2A half-scale model pressure vessel. The material is a Cr-Mo-V rotor steel, temper embrittled to represent the irradiated shell of the PM-2A reactor vessel. The fatigue tests were conducted in a room-air environment at 80 F, which is 160 F below the NDT (nil-ductility transition) temperature for this steel. Fatigue crack growth rates were correlated with total strain range, and were found to be similar to fatigue crack growth rates in other structural steels which possess comparable yield strength levels. Fracture occurred in the plate bend specimens of the test material during fatigue cycling. This represents a significant departure from the behavior of previously studied structural steels, and is attributed to the very high NDT temperature of the test material. An analysis of the fractures using an approximate solution for the stress-intensity factor, K, gave good agreement with previous plane strain fracture toughness measurements on the test material. (Author).
Publisher:
ISBN:
Category :
Languages : en
Pages : 17
Book Description
Fatigue crack propagation tests were conducted using plate bend specimens machined from shell material of the PM-2A half-scale model pressure vessel. The material is a Cr-Mo-V rotor steel, temper embrittled to represent the irradiated shell of the PM-2A reactor vessel. The fatigue tests were conducted in a room-air environment at 80 F, which is 160 F below the NDT (nil-ductility transition) temperature for this steel. Fatigue crack growth rates were correlated with total strain range, and were found to be similar to fatigue crack growth rates in other structural steels which possess comparable yield strength levels. Fracture occurred in the plate bend specimens of the test material during fatigue cycling. This represents a significant departure from the behavior of previously studied structural steels, and is attributed to the very high NDT temperature of the test material. An analysis of the fractures using an approximate solution for the stress-intensity factor, K, gave good agreement with previous plane strain fracture toughness measurements on the test material. (Author).
Effect of Irradiation on Elastic-Plastic Toughness of Pressure Vessel Steels
Author: P. Soulat
Publisher:
ISBN:
Category : Elastic-plastic fracture mechanics
Languages : en
Pages : 22
Book Description
Irradiation experiments were conducted in order to determine the effect of radiation damage on the elastic-plastic ductile fracture toughness of pressure vessel steels. Curves for the J-integral versus crack growth resistance (?a) were established on specimens taken out of two nuclear reactor pressure vessel steels before and after neutron irradiation at 290°C to a fluence of 3.1019 n/cm2 (work function energy E > 1 MeV). The J-?a tests were performed at room temperature (25°C) and service temperature (290°C). The main results obtained are as follows:.
Publisher:
ISBN:
Category : Elastic-plastic fracture mechanics
Languages : en
Pages : 22
Book Description
Irradiation experiments were conducted in order to determine the effect of radiation damage on the elastic-plastic ductile fracture toughness of pressure vessel steels. Curves for the J-integral versus crack growth resistance (?a) were established on specimens taken out of two nuclear reactor pressure vessel steels before and after neutron irradiation at 290°C to a fluence of 3.1019 n/cm2 (work function energy E > 1 MeV). The J-?a tests were performed at room temperature (25°C) and service temperature (290°C). The main results obtained are as follows:.
Final Results from the Crack Initiation and Arrest of Irradiated Steel Materials Project on Fracture Mechanical Assessments of Pre-Irradiated RPV Steels Used in German PWR
Author: H. Hein
Publisher:
ISBN:
Category : Crack arrest
Languages : en
Pages : 24
Book Description
Pre-irradiated original reactor pressure vessel (RPV) materials covering all four German pressurized water reactors (PWR) construction lines were tested in the Crack Initiation and Arrest of Irradiated Steel Materials program to create a database of fracture toughness and arrest values for neutron fluences beyond the end of life range. The new database comprises data from both unirradiated and irradiated RPV base and weld materials generated by tensile, Charpy-V impact, fracture toughness KJc, and crack arrest KIa tests. The test matrix consists of materials with optimized chemical composition and with high Copper or high Nickel content, respectively. Based on the generated and already existing data the RTNDT and the RTT0 (Master Curve) concepts are applied with specific view on reference temperatures, transition temperature shifts, and on possible correlations between the criteria used in both concepts. In this context the consequences of some influencing factors like type and chemical composition of the RPV steel, its manufacturing conditions, and the specimen type and size on the reference temperatures are discussed. Moreover, the test results are assessed with respect to the American Society of Mechanical Engineers (ASME) code and German Nuclear Safety Standards Commission safety standards. The crack arrest characteristics for these typical RPV materials are also determined in a twofold way by testing Compact Crack Arrest specimens and by evaluation of instrumented Charpy-V impact test data. The available results made a good point that crack arrest is a reliable phenomenon that doubtless exists. It is also shown that the obtained KIa data can be enveloped by applying the ASME KIc lower bound curve indexed by different reference temperatures. Finally, the results show that the used RPV materials are well designed in terms of material behavior under irradiated conditions and that optimized manufacture specifications are of great benefit particularly after long operation times.
Publisher:
ISBN:
Category : Crack arrest
Languages : en
Pages : 24
Book Description
Pre-irradiated original reactor pressure vessel (RPV) materials covering all four German pressurized water reactors (PWR) construction lines were tested in the Crack Initiation and Arrest of Irradiated Steel Materials program to create a database of fracture toughness and arrest values for neutron fluences beyond the end of life range. The new database comprises data from both unirradiated and irradiated RPV base and weld materials generated by tensile, Charpy-V impact, fracture toughness KJc, and crack arrest KIa tests. The test matrix consists of materials with optimized chemical composition and with high Copper or high Nickel content, respectively. Based on the generated and already existing data the RTNDT and the RTT0 (Master Curve) concepts are applied with specific view on reference temperatures, transition temperature shifts, and on possible correlations between the criteria used in both concepts. In this context the consequences of some influencing factors like type and chemical composition of the RPV steel, its manufacturing conditions, and the specimen type and size on the reference temperatures are discussed. Moreover, the test results are assessed with respect to the American Society of Mechanical Engineers (ASME) code and German Nuclear Safety Standards Commission safety standards. The crack arrest characteristics for these typical RPV materials are also determined in a twofold way by testing Compact Crack Arrest specimens and by evaluation of instrumented Charpy-V impact test data. The available results made a good point that crack arrest is a reliable phenomenon that doubtless exists. It is also shown that the obtained KIa data can be enveloped by applying the ASME KIc lower bound curve indexed by different reference temperatures. Finally, the results show that the used RPV materials are well designed in terms of material behavior under irradiated conditions and that optimized manufacture specifications are of great benefit particularly after long operation times.
Ductile Fracture Toughness of Heavy Section Pressure Vessel Steel Plate
Author: J. A. Williams
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 60
Book Description
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 60
Book Description
Comparison of Irradiation-induced Shifts of Kjc and Charpy Impact Toughness for Reactor Pressure Vessel Steels
Author: M. A. Sokolov
Publisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 69
Book Description
Publisher:
ISBN:
Category : Nuclear pressure vessels
Languages : en
Pages : 69
Book Description
Crack-Arrest Testing of Irradiated Nuclear Reactor Pressure Vessel Steels at the Oak Ridge National Laboratory
Author: SK. Iskander
Publisher:
ISBN:
Category : ASME KIa curve
Languages : en
Pages : 9
Book Description
Crack-arrest testing of nuclear pressure vessel steels has been conducted at Oak Ridge National Laboratory for many years. Four methods have been used to initiate fast-running cracks in crackarrest specimens: (1) the deposition of a brittle weld bead using hardfacing weld electrodes, (2) water quenching a chevron crack tip, (3) quenching the crack tip by discharging a large current into the crack tip region, and (4) the use of duplex specimens. A problem often encountered with Methods 1 and 4 is the control of the width of the heat-affected zone (HAZ). The HAZ is generally tough and can arrest crack propagation before it has run into the test section. Irradiated crack-arrest specimens were prepared using Methods 1, 3, and 4. Method 1 was the most successful, while Method 4 was the least successful. This paper will discuss some of the reasons for the success, or lack of, as well as the results of testing both a high-copper weldment and a low-copper forging in terms of the shift and shape of the Ka toughness curve compared to the Charpy V-notch shift. The present ASTM Test Method for Determining Plane-Strain Crack-Arrest Fracture Toughness, KIa, of Ferritic Steels (E 1221-88) validity criteria will also be discussed in light of the results.
Publisher:
ISBN:
Category : ASME KIa curve
Languages : en
Pages : 9
Book Description
Crack-arrest testing of nuclear pressure vessel steels has been conducted at Oak Ridge National Laboratory for many years. Four methods have been used to initiate fast-running cracks in crackarrest specimens: (1) the deposition of a brittle weld bead using hardfacing weld electrodes, (2) water quenching a chevron crack tip, (3) quenching the crack tip by discharging a large current into the crack tip region, and (4) the use of duplex specimens. A problem often encountered with Methods 1 and 4 is the control of the width of the heat-affected zone (HAZ). The HAZ is generally tough and can arrest crack propagation before it has run into the test section. Irradiated crack-arrest specimens were prepared using Methods 1, 3, and 4. Method 1 was the most successful, while Method 4 was the least successful. This paper will discuss some of the reasons for the success, or lack of, as well as the results of testing both a high-copper weldment and a low-copper forging in terms of the shift and shape of the Ka toughness curve compared to the Charpy V-notch shift. The present ASTM Test Method for Determining Plane-Strain Crack-Arrest Fracture Toughness, KIa, of Ferritic Steels (E 1221-88) validity criteria will also be discussed in light of the results.