Results 221 to 230 of about 3,020,549 (269)
Some of the next articles are maybe not open access.

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
openaire   +1 more source

Stainless steel reactor pressure vessels

Nuclear Engineering and Design, 1970
Abstract The properties of stainless steels preferred for nuclear reactor pressure vessel construction, the austenitic-chromium-nickel types, are reviewed along with other bases for this nuclear application. The engineering criteria which establish the limits for design and operation, the various aspects of vessel fabrication and the implications of ...
P.J. Karnoski   +3 more
openaire   +1 more source

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
openaire   +1 more source

Reactor pressure vessel surveillance

open access: yes, 2014
This publication summarizes techniques suitable for surveillance program for the objective of  long term operation (LTO) on European NPPs and provides recommendations on reactor pressure vessel (RPV) irradiation surveillance based on the work preformed ...
Ballesteros, A.   +10 more
openaire   +2 more sources

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   +2 more
openaire   +1 more source

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,
openaire   +1 more source

Reactor Pressure Vessel Modification Approaches

Volume 6: Materials and Fabrication, 2005
Stress corrosion cracking of Alloy 600 has lead to the modification and replacement of many nuclear power plant components. Among these components are the Bottom Mounted Nozzles (BMN) of the Reactor Pressure Vessel (RPV). Modifications of these components have been performed on an emergent basis.
Ronald J. Payne, Stephen Levesque
openaire   +1 more source

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 ...
openaire   +1 more source

Lift of Shippingport Reactor Pressure Vessel

Journal of Construction Engineering and Management, 1990
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 con...
openaire   +1 more source

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
openaire   +1 more source

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