Results 231 to 240 of about 3,020,549 (269)

Spectral effects on defect production in the reactor pressure vessel of a pressurized heavy-water reactor

Philosophical Magazine A, 2000
Abstract Embrittlement predictions of reactor pressure vessels of typical pressurized water reactors are conventionally carried out using well established trend curves developed in terms of fast fluence as the correlation parameter. However, such quantification of irradiation damage cannot be applied when large spectral differences appear.
M. Caro, A. Caro
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Reactor pressure vessel design and practice

Progress in Nuclear Energy, 1982
Abstract This paper attempts to review the state of the art of methods of analysis and design of the concrete reactor pressure vessels and their components. Existing vessels have been examined for elastic, inelastic and cracking conditions. The results obtained from the analyses given in the appendices are well collaborated with those available from ...
openaire   +1 more source

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.
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Design Pressure for a Reactor Containment Vessel

Journal of the Structural Division, 1960
Magnitude of reactor accident against which containment vessel must provide protection; limiting accident is analyzed; numerical example and generalized curves are presented.
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“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.
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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
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Fracture of reactor pressure vessel steels

Materials Testing, 1975
J. C. Radon, A. P. Glover, F. A. Johnson
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Characterizing the flux effect on the irradiation embrittlement of reactor pressure vessel steels using machine learning

Acta Materialia, 2023
Dane Morgan, Yu-chen Liu, G Robert Odette   +2 more
exaly  

Embrittlement of reactor pressure vessels (RPVs) in pressurized water reactors (PWRs)

2015
M. Tomimatsu, T. Hirota, T. Hardin, P. Todeschini   +3 more
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High temperature creep behavior of a low alloy Mn-Mo-Ni reactor pressure vessel steel

Journal of Nuclear Materials, 2021
Apu sarkar
exaly