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Considerations about the reliability of nuclear pressure vessels status and research planning

Conference ·
OSTI ID:4412658
Second lnternational Conference on Pressure Vessel Technology. l. New York; American Society of Mechanical Engineers (1973). From 2nd international congress for pressure vessel and piping technology; San Antonio, Texas, USA (1 Oct 1973). See CONF731003-P1. The Research Program Reactor Safety of the government of the Federal Republic of Germany (FRG) consists of two subprograms: Accidents and Engineered Safeguards'' and Improvement of Operational Safety''. A Status Report Reactor Pressure Vessels (RPV) shall analyze the situation in the field of pressure vessels of light water reactors (LWR) and thus provide a basis for research planning. At the end of 1972 a research project Priority Program 22 NiMoCr 37'' has been initiated. Prior to other activities, it is expected to yield information on special welding problems. Nonoptimal fabrication conditions may cause incipient cracks and/or decreased toughness in plates and forgings. Incipient cracks in the heat affected zone (HAZ) of connecting welds, as have been observed, represent a particular problem. The open boundary conditions in the practical application of fracture mechanics technology consist of the exact determination of critical states in the material and, also, in the evaluation of special types of cracking and of residual stresses. (auth)
Research Organization:
Technischer Ueberwachungs-Verein, Cologne
NSA Number:
NSA-29-002088
OSTI ID:
4412658
Country of Publication:
Country unknown/Code not available
Language:
English