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The reliability of pressurized water reactor vessels

1987
The mechanical integrity of major engineering structures such as pressure vessels, pipelines, nuclear reactors, aircraft and offshore oil platforms is a matter of great practical importance for both economic and safety reasons. In practice this integrity must be assured by careful attention to many aspects of design, materials, manufacture, inspection,
R. F. Cameron   +2 more
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Thermal and pressure stresses in cylindrical reactor pressure vessels

Nuclear Engineering and Design, 1970
Abstract Transient thermal stresses and steady pressure stresses developed in long, cylindrical pressure vessels of nuclear reactors are determined analytically. The computed results of the tangential thermal and pressure stress distributions in elastic and plastic states of the pressure vessels are obtained and shown by curves.
openaire   +1 more source

“ULTRASONIC EXAMINATION OF AUSTENITIC WELDS AT REACTOR PRESSURE VESSELS”

Nuclear Engineering and Design, 1989
Abstract Austenitic welds play an important role in reactor pressure vessels (RPV) both of pressurized water reactors (PWRs) and boiling water reactors (BWRs). These pressure retaining joints still pose problems for ultrasonic examination. During the last few years some progress has been achieved in overcoming these problems.
openaire   +1 more source

Conceptual design of a prestressed concrete reactor pressure vessel

Nuclear Structural Engineering, 1965
Abstract A conceptual design of a horizontal cylindrical prestressed concrete reactor pressure vessel for housing a large gas-cooled high power-density reactor and power generating equipment is presented. The evolution of the geometry of the vessel design is described. Structural considerations for a full chamber-size opening are outlined. The choice
openaire   +1 more source

Fracture of reactor pressure vessel steels

Materials Testing, 1975
J. C. Radon, A. P. Glover, F. A. Johnson
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Reactor Pressure Vessel

Bulbul Khan   +4 more
openaire   +1 more source

Simulation of JR-curves for reactor pressure vessels steels on the basis of a ductile fracture model

International Journal of Pressure Vessels and Piping, 2001
B Z Margolin, V I Kostylev
exaly  

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