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Author: Donald E. McCabe Publisher: ISBN: Category : Bend bar Languages : en Pages : 13
Book Description
A surface crack embedded in the clad layer of a reactor pressure vessel (RPV) has been identified as a critical safety assessment criterion in a pressurized thermal shock accident. This project was initiated to determine the severity of such cracks experimentally by using irradiated material, and to identify the material properties and stress conditions in the local region of the crack that are significant to the analysis. Bend bar tests provided an experimental simulation of the subject RPV surface crack. This report covers the analysis techniques used and presents the findings indicated by the experimental results for irradiated and unirradiated materials.
Author: Donald E. McCabe Publisher: ISBN: Category : Bend bar Languages : en Pages : 13
Book Description
A surface crack embedded in the clad layer of a reactor pressure vessel (RPV) has been identified as a critical safety assessment criterion in a pressurized thermal shock accident. This project was initiated to determine the severity of such cracks experimentally by using irradiated material, and to identify the material properties and stress conditions in the local region of the crack that are significant to the analysis. Bend bar tests provided an experimental simulation of the subject RPV surface crack. This report covers the analysis techniques used and presents the findings indicated by the experimental results for irradiated and unirradiated materials.
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: Naoki Soneda Publisher: Elsevier ISBN: 0857096478 Category : Technology & Engineering Languages : en Pages : 437
Book Description
Reactor Pressure Vessels (RPVs) contain the fuel and therefore the reaction at the heart of nuclear power plants. They are a life-determining structural component: if they suffer serious damage, the continued operation of the plant is in jeopardy. This book critically reviews irradiation embrittlement, the main degradation mechanism affecting RPV steels, and mitigation routes for managing the RPV lifetime. Part I reviews RPV design and fabrication in different countries, with an emphasis on the materials required, their important properties, and manufacturing technologies. Part II then considers RVP embrittlement in operational nuclear power plants using different reactors. Chapters are devoted to embrittlement in light-water reactors, including WWER-type reactors and Magnox reactors. Finally, Part III presents techniques for studying embrittlement, including irradiation simulation techniques, microstructural characterisation techniques, and probabilistic fracture mechanics. Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants provides a thorough review of an issue that is central to the safety of nuclear power generation. The book includes contributions from an international team of experts, and will be a useful resource for nuclear plant operators and managers, relevant regulatory and safety bodies, nuclear metallurgists and other academics in this field - Discusses reactor pressure vessel (RPV) design and the effect irradiation embrittlement can have, the main degradation mechanism affecting RPVs - Examines embrittlement processes in RPVs in different reactor types, as well as techniques for studying RPV embrittlement
Author: O. K. Chopra Publisher: ISBN: Category : Austenitic stainless steel Languages : en Pages : 86
Book Description
Austenitic stainless steels (SSs) are used extensively as structural alloys in the internal components of reactor pressure vessels because of their superior fracture toughness properties. However, exposure to high levels of neutron irradiation for extended periods leads to significant reduction in the fracture resistance of these steels. Experimental data are presented on fracture toughness and crack growth rates (CGRs) of austenitic SSs irradiated to fluence levels up to 2.0 x 10{sup 21} n/cm{sup 2} (E> 1 MeV) ({approx}3.0 dpa) at {approx}288 C. Crack growth tests were conducted under cycling loading and long hold time trapezoidal loading in simulated boiling water reactor (BWR) environments, and fracture toughness tests were conducted in air. Neutron irradiation at 288 C decreases the fracture toughness of the steels; the data from commercial heats fall within the scatter band for the data obtained at higher temperatures. In addition, the results indicate significant enhancement of CGRs of the irradiated steels in normal water chemistry BWR environment; the CGRs for irradiated steels are a factor of {approx}5 higher than the disposition curve proposed for sensitized austenitic SSs. The rates decreased by more than an order of magnitude in low-dissolved-oxygen BWR environment.
Author: Donald E. McCabe
Author: Donald E. McCabe
Author: MG. Horsten
Author: Naoki Soneda
Author: O. K. Chopra
Author: Stan T. Rosinski
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Author: 
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Author: Materials Engineering Associates
Author: F. J. Loss