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Author: MG. Horsten Publisher: ISBN: Category : Fracture resistance Languages : en Pages : 15
Book Description
A comprehensive testing programme was undertaken to evaluate the effects of irradiation, thermal ageing, specimen orientation, and test temperature on the fracture oughness and tensile behaviour of a Type 309L/308L stainless steel strip clad deposit. Specimens were irradiated in the high flux reactor (HFR) Petten to nominal neutron doses of 0.05 dpa and 0.1 dpa at 295°C. Testing was performed at room temperature, 100, 200 and 295°C. The fracture resistance properties of the clad material were unaffected by irradiation to 0.1 dpa, which is approximately twice the predicted end-of-life dose. The same neutron dose resulted in an increase in 0.2% yield stress (15-20 MPa) and a small loss of ductility (3%). Thermal ageing to the simulated pressurised water reactor (PWR) end-of-life thermal condition (1000 hrs at 400°C) had no significant effect on the fracture resistance behaviour or tensile properties of clad material in either irradiated or unirradiated condition. Clad fracture resistance properties were unaffected by orientation in the plane of the clad layer and were only dependent on test temperature.
Author: MG. Horsten Publisher: ISBN: Category : Fracture resistance Languages : en Pages : 15
Book Description
A comprehensive testing programme was undertaken to evaluate the effects of irradiation, thermal ageing, specimen orientation, and test temperature on the fracture oughness and tensile behaviour of a Type 309L/308L stainless steel strip clad deposit. Specimens were irradiated in the high flux reactor (HFR) Petten to nominal neutron doses of 0.05 dpa and 0.1 dpa at 295°C. Testing was performed at room temperature, 100, 200 and 295°C. The fracture resistance properties of the clad material were unaffected by irradiation to 0.1 dpa, which is approximately twice the predicted end-of-life dose. The same neutron dose resulted in an increase in 0.2% yield stress (15-20 MPa) and a small loss of ductility (3%). Thermal ageing to the simulated pressurised water reactor (PWR) end-of-life thermal condition (1000 hrs at 400°C) had no significant effect on the fracture resistance behaviour or tensile properties of clad material in either irradiated or unirradiated condition. Clad fracture resistance properties were unaffected by orientation in the plane of the clad layer and were only dependent on test temperature.
Author: J. Koutský Publisher: Elsevier ISBN: 1483291626 Category : Technology & Engineering Languages : en Pages : 362
Book Description
Maintaining the integrity of nuclear power plants is critical in the prevention or control of severe accidents. This monograph deals with both basic groups of structural materials used in the design of light-water nuclear reactors, making the primary safety barriers of NPPs. Emphasis is placed on materials used in VVER-type nuclear reactors: Cr-Mo-V and Cr-Ni-Mo-V steel for RPV and Zr-Nb alloys for fuel element cladding. The book is divided into 7 main chapters, with the exception of the opening one and the chapter providing a phenomenological background for the subject of radiation damage. Chapters 3-6 are devoted to RPV steels and chapters 7-9 to zirconium alloys, analysing their radiation damage structure, changes of mechanical properties due to neutron irradiation as well as factors influencing the degree of their performance degradation. The recovery of damaged materials is also discussed. Considerable attention is paid to a comparison of VVER-type and western-type light-water materials. This monograph will be of great value to postgraduate students in nuclear engineering and materials science, and for designers and research workers in nuclear energy.
Author: DR. Ireland Publisher: ISBN: Category : Bituminous materials Languages : en Pages : 20
Book Description
The effect of radiation on tensile properties, notch bend properties, and fracture toughness was determined on A212B steel from the Pathfinder reactor surveillance program and on A533B steel from the U.S. AEC Heavy Section Technology program. Impact tests were performed on an instrumented Charpy machine which provided load-deflection data in addition to energy absorption data. Valid fracture toughness values were obtained from precracked Charpy specimens.
Author: MG. Horsten
Author: MG. Horsten
Author: Stan T. Rosinski
Author: Arvind S. Kumar
Author: W. R. Corwin
Author: John Moteff
Author: F. H. Huang
Author: J. Koutský
Author: DR. Ireland
Author: United States. Congress. Joint Committee on Atomic Energy
Author: United States. Congress. Joint Committee on Atomic Energy