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Further Observations on A533-B Steel Plate Tailored for Improved Radiation Embrittlement Resistance
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: A series of advanced investigations on the radiation performance of four 6-in-thick plates from a large (30-ton) commercial melt of A533-B steel is described. The melt represented the first ...
Radiation and Temper Embrittlement Processes in Advanced Reactor Weld Metals
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Experimental weld filler metals having high resistance to radiation embrittlement at ≃550 F (288 C) have been developed for quenched and tempered A543 and A542 steel. The filler metals are ...
Yankee Reactor Pressure Vessel Surveillance: Notch Ductility Performance of Vessel Steel and Maximum Service Fluence Determined From Exposure During Cores II, III, and IV
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Charpy V-notch specimens representative of one of the several heats of A302-B steel forming the Yankee reactor pressure vessel, and irradiated as part of the Yankee surveillance program, have ...
Features and Results of Several Programs of Radiation-Damage Surveillance of Power Reactor Pressure Vessels
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The meaning and purpose of reactor pressure vessel surveillance is briefly discussed. Features of the surveillance programs in the Yankee, Big Rock Point, SM-1, and SM-1A reactors are briefly ...
Investigation of Warm Prestress for the Case of Small ΔT During a Reactor Loss-of-Coolant Accident
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: An experimental investigation was conducted to characterize the benefits of warm prestress (WPS) in limiting crack extension in the wall of a nuclear vessel during a LOCA-ECCS. The present ...
A Reassessment of Fracture-Safe Operating Criteria for Reactor Vessel Steels Based on Charpy-V Performance
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Fracture-safe operating criteria for commercial nuclear pressure vessels based on fracture analysis diagram procedures and Charpy-V energy trends are reappraised with respect to the effects of ...
Fatigue Crack Growth Resistance of Several Neutron Irradiated Pressure Vessel Steels and Welds
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Pre and postirradiation fatigue crack growth rates in A302-B, A533-B, and A543 steel plate and in two A543 welds (submerged arc and electroslag) were determined at 550 deg F (288 deg C) in ...
Analysis of Radiation-Induced Embrittlement Gradients on Fracture Characteristics of Thick-Walled Pressure Vessel Steels
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The fracture behavior of thick-walled nuclear vessels is considered for the case of a radiation-induced toughness gradient through the wall which characteristically results from neutron attenuation ...
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