Results 121 to 130 of about 8,242 (166)

Overview of reactor pressure vessel cladding

International Journal of Nuclear Knowledge Management, 2010
Licence extension of NPPs requires a new safety analysis of the plant covering the extended operating life. One of the most important safety considerations is the integrity of the RPV (Reactor Pressure Vessels). The RPV material suffers several ageing-related effects during operating service: neutron (and gamma) irradiation embrittlement, thermal ...
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Thermal Annealing of Reactor Pressure Vessels

Volume 7: Operations, Applications and Components, 2015
Some of the current fleet of nuclear power plants is poised to reach their end of life and will require an operating life time extension. Therefore, the main structural components, including the reactor pressure vessel (RPV), will be subject to higher neutron exposures than originally planned.
Mikhail A. Sokolov, William L. Server, Randy K. Nanstad   +2 more
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Reactor pressure vessel integrity program

Nuclear Engineering and Design, 1998
Abstract The reactor vessel report provides a technical evaluation of the effects of aging on the reactor vessel shell, lower vessel head, closure head, nozzles (and safe ends, if provided), interior attachments, and all associated pressure-retaining bolting. The evaluation is performed in accordance with the requirements of the license renewal rule,
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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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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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A PROCEDURE OF DYNAMIC FRACTURE ANALYSIS FOR REACTOR PRESSURE VESSEL

Nuclear Engineering and Design, 1989
Abstract A two-dimensional dynamic fracture-mechanics program using J - integral concept was developed. Crack propagation problems in thick-wall cylinders subjected to thermal shock were analyzed using this program. The results showed that under mechanical loading the increase in fracture energy prior to crack arrest is usually ...
Yoshio Urabe, Kiminobu Hojo, Kinji Baba
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Transportation of Shippingport Reactor Pressure Vessel

Journal of Construction Engineering and Management, 1991
The Shippingport Atomic Power Station in western Pennsylvania is the first nuclear electric generating station to be decommissioned with the goal of restoring the site to a radiologically clean condition acceptable for unrestricted use. In February, 1989, the 921 ton (836 metric tons) reactor pressure vessel/neutron‐shield tank assembly was hauled from
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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, G. O. Johnson, A. B. Lidiard   +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.
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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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