Interim Results from the Heavy Section Steel Technology (HSST) Shallow-Crack Fracture Toughness Program

2009 ◽  
pp. 131-131-21
Author(s):  
TJ Theiss ◽  
DKM Shum ◽  
ST Rolfe
Keyword(s):  
Fracture Toughness ◽  
Heavy Section ◽  
Steel Technology ◽  
Shallow Crack

Heavy-Section Steel Technology and Irradiation Programs—Retrospective and Prospective Views

2010 ◽  
Vol 132 (6) ◽  
Author(s):  
Randy K. Nanstad ◽  
B. Richard Bass ◽  
John G. Merkle ◽  
Claud E. Pugh ◽  
Thomas M. Rosseel ◽  
...  
Keyword(s):  
Fracture Toughness ◽  
Thermal Shock ◽  
Crack Arrest ◽  
High Energy ◽  
Material Behavior ◽  
Chemical Compositions ◽  
Irradiation Effects ◽  
Oak Ridge ◽  
Heavy Section ◽  
Steel Technology

In 1965, the Atomic Energy Commission, at the advice of the Advisory Committee on Reactor Safeguards, initiated the process that resulted in the establishment of the Heavy Section Steel Technology (HSST) program at Oak Ridge National Laboratory. In 1989, the Heavy-Section Steel Irradiation (HSSI) program, formerly the HSST task on irradiation effects, was formed as a separate program, and in 2007, the HSST/HSSI programs, sponsored by the U.S. Nuclear Regulatory Commission (USNRC), celebrated 40 years of continuous research oriented toward the safety of light-water nuclear reactor pressure vessels (RPVs). This paper presents a summary of results from those programs with a view to future activities. The HSST program was established in 1967 and initially included extensive investigations of heavy-section low-alloy steel plates, forgings, and welds, including metallurgical studies, mechanical properties, fracture toughness (quasi-static and dynamic), fatigue crack-growth, and crack-arrest toughness. Also included were irradiation effects studies, thermal shock analyses, testing of thick-section tensile and fracture specimens, and nondestructive testing. In the subsequent decades, the HSST Program conducted extensive large-scale experiments with intermediate-size vessels (with varying size flaws) pressurized to failure, similar experiments under conditions of thermal shock and even pressurized thermal shock (PTS), wide-plate crack-arrest tests, and biaxial tests with cruciform-shaped specimens. Extensive analytical and numerical studies accompanied these experiments, including the development of computer codes such as the recent Fracture Analysis of Vessels Oak Ridge code currently being used for PTS evaluations. In the absence of radiation damage to the RPVs, fracture of the vessel is improbable. However, it was recognized that exposure to high energy neutrons can result in embrittlement of radiation-sensitive RPV materials. The HSSI Program conducted a series of experiments to assess the effects of neutron irradiation on RPV material behavior, especially fracture toughness. These studies included RPV plates and welds, varying chemical compositions, and fracture toughness specimens up to 101.6 mm (4 in.) thickness. The results of these investigations, in conjunction with results from commercial reactor surveillance programs, are used to develop a methodology for the prediction of radiation effects on RPV materials. Results from the HSST and HSSI programs are used by the USNRC in the evaluation of RPV integrity and regulation of overall nuclear plant safety.

Heavy-Section Steel Technology and Irradiation Programs: Retrospective and Prospective Views

2007 ◽  
Author(s):  
Randy K. Nanstad ◽  
B. Richard Bass ◽  
Thomas M. Rosseel ◽  
John G. Merkle ◽  
Mikhail A. Sokolov
Keyword(s):  
Fracture Toughness ◽  
Thermal Shock ◽  
Crack Arrest ◽  
High Energy ◽  
Material Behavior ◽  
Chemical Compositions ◽  
Irradiation Effects ◽  
Oak Ridge ◽  
Heavy Section ◽  
Steel Technology

In 1965, the Atomic Energy Commission (AEC), at the advice of the Advisory Committee on Reactor Safeguards (ACRS), initiated the process that resulted in the establishment of the Heavy Section Steel Technology (HSST) Program at Oak Ridge National Laboratory (ORNL). Dr. Spencer H. Bush of Battelle Northwest Laboratory, the man being honored by this symposium, representing the ACRS, was one of the Staff Advisors for the program and helped to guide its technical direction. In 1989, the Heavy-Section Steel Irradiation (HSSI) Program, formerly the HSST task on irradiation effects, was formed as a separate program, and this year the HSST/HSSI Programs, sponsored by the U.S. Nuclear Regulatory Commission (USNRC), celebrate 40 years of continuous research oriented toward the safety of light-water nuclear reactor pressure vessels. This paper presents a summary of results from those programs with a view to future activities. The HSST Program was established in 1967 and initially included extensive investigations of heavy-section low-alloy steel plates, forgings, and welds, including metallurgical studies, mechanical properties, fracture toughness (quasi-static and dynamic), fatigue crack-growth, and crack arrest toughness. Also included were irradiation effects studies, thermal shock analyses, testing of thick-section tensile and fracture specimens, and non-destructive testing. In the subsequent decades, the HSST Program conducted extensive large-scale experiments with intermediate-size vessels (with varying size flaws) pressurized to failure, similar experiments under conditions of thermal shock and even pressurized thermal shock (PTS), wide-plate crack arrest tests, and biaxial tests with cruciform-shaped specimens. Extensive analytical and numerical studies accompanied these experiments, including the development of computer codes such as the recent Fracture Analysis of Vessels Oak Ridge (FAVOR) code currently being used for PTS evaluations. In the absence of radiation damage to the RPV, fracture of the vessel is improbable. However, exposure to high energy neutrons can result in embrittlement of radiation-sensitive RPV materials. The HSSI Program has conducted a series of experiments to assess the effects of neutron irradiation on RPV material behavior, especially fracture toughness. These studies have included RPV plates and welds, varying chemical compositions, and fracture toughness specimens up to 4 in. thickness. The results of these investigations, in conjunction with results from commercial reactor surveillance programs, are used to develop a methodology for the prediction of radiation effects on RPV materials. Results from the HSST and HSSI Program are used by the USNRC in the evaluation of RPV integrity and regulation of overall nuclear plant safety.

RMI 6Al-2Sn-2Zr-2Mo-0.15Si

Alloy Digest ◽  
2001 ◽  
Vol 50 (9) ◽  
Keyword(s):  
Fracture Toughness ◽  
High Temperature ◽  
Physical Properties ◽  
Tensile Properties ◽  
High Strength ◽  
Bend Strength ◽  
High Modulus ◽  
Temperature Performance ◽  
Heavy Section

Abstract Ti-6Al-2Sn-2Zr-2Mo-0.05Si alloy is used as heavy section forgings that require high strength, fracture toughness, and high modulus. It is used as forgings and sheet for air frames. This datasheet provides information on composition, physical properties, elasticity, tensile properties, and bend strength as well as fracture toughness and creep. It also includes information on high temperature performance as well as joining. Filing Code: TI-119. Producer or source: RMI Company.

ZA-27

Alloy Digest ◽  
1977 ◽  
Vol 26 (10) ◽  
Keyword(s):  
Fracture Toughness ◽  
Copper Alloy ◽  
High Strength ◽  
Heat Treating ◽  
General Purpose ◽  
Corrosion And Wear ◽  
Heavy Section ◽  
Thin Walled ◽  
Aluminum Copper Alloy ◽  
Lower Material

Abstract ZA-27 is a zinc-aluminum-copper alloy that offers exceptionally high strength (58,000 to 64,000 psi tensile strength as cast) at modest cost. It performs best in thin-walled castings (down to 0.10 inch) which means reduced weight and lower material costs when castings are redesigned. It is similar to the general-purpose ZA-12 alloy (Alloy Digest Zn-31, September 1977) except for its higher strength and elongation, but with higher casting temperatures and poor heavy-section castability. This datasheet provides information on composition, physical properties, hardness, tensile properties, and shear strength as well as fracture toughness and creep. It also includes information on corrosion and wear resistance as well as casting, forming, heat treating, machining, and surface treatment. Filing Code: Zn-32. Producer or source: Eastern Alloys Inc.. See also Alloy Digest Zn-50, June 1990.

Comparative analysis and verification of engineering methods of shallow cracks effect for fracture toughness prediction for reactor pressure vessels

2020 ◽  
pp. 140-165
Author(s):  
V. I. Kostylev ◽  
B. Z. Margolin
Keyword(s):  
Experimental Data ◽  
Fracture Toughness ◽  
Comparative Analysis ◽  
Nuclear Reactor ◽  
Probabilistic Approach ◽  
Pressure Vessels ◽  
Local Methods ◽  
European Method ◽  
Shallow Crack ◽  
Reactor Pressure

The main features of shallow cracks fracture are considered, and a brief analysis of methods allowing to predict the temperature dependence of the fracture toughness KJC (T) for specimens with shallow cracks is given. These methods include DA-method, (JQ)-method, (J-T)-method, “local methods” with its multiparameter probabilistic approach, GP method uses power approach, and also two engineering methods – RMSC (Russian Method for Shallow Crack) and EMSC (European Method for Shallow Crack). On the basis of 13 sets of experimental data for national and foreign steels, a detailed verification and comparative analysis of these two engineering methods were carried out on the materials of the VVER and PWR nuclear reactor vessels considering the effect of shallow cracks.

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