Filters
Results 1 - 10 of 29
Results 1 - 10 of 29.
Search took: 0.023 seconds
Sort by: date | relevance |
AbstractAbstract
[en] The wall of the vessel consists of an outer mantle from prestressed concrete, a temperature insulating zone and an inner sealing liner, preferably from steel. According to the invention the temperature insulation zone is free from expansion joints, fits to the concrete mantle and has an insulating capacity much higher than that of the concrete. Preferably there are provided temperature regulating systems as well within the temperature insulating zone as within the concrete mantle. The material of the temperature insulating zone may contain porous ceramic compression resistant admixtures. (P.K.)
Original Title
Druckbehaelter fuer hohe Innendruecke und hohe Temperaturen, insbesondere zur Aufnahme von Kernkraftwerkskomponenten
Primary Subject
Source
15 Jan 1975; 5 p; AT PATENT DOCUMENT 325 724/B/; Available from the Oesterreichisches Patentamt, Kohlmarkt 8-10, A-1010 Vienna, Austria
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Based on results gained with the common project of Reaktorbau Forschungs- und Baugesellschaft (RFB), Oesterreichische Studiengesellschaft fuer Atomenergie (OeSGAE) and industrial partners, 'Prestressed Concrete Reactor Pressure Vessel with Hot Liner and Elevated Wall Temperature' the problem of instrumentation of PCRV at elevated concrete temperature has been investigated. Temperature, strain and stress gauges were selected and tested in a laboratory and in the concrete structure. From the test results possibilities for the measurement of strains and stresses at elevated temperatures were derived. (orig.)
[de]
Aufbauend auf die von der Reaktorbau Forschungs- und Baugesellschaft (RFB) mit der Oesterreichischen Studiengesellschaft fuer Atomenergie (OeSGAE) und Industriepartnern im Forschungszentrum Seibersdorf/Oesterreich durchgefuehrten Arbeiten am Gemeinschaftsprojekt 'Spannbetonbehaelter mit heisser Dichthaut und erhoehter Wandtemperatur' wurden Untersuchungen zur Frage der Instrumentierung von Reaktordruckbehaeltern aus Spannbeton bei erhoehten Temperaturen durchgefuehrt. Auf Grund von Literaturstudium ausgesuchte Temperatur-, Dehnungs- und Spannungsgeber wurden im Laboratorium und im Bauwerk untersucht und aus den Ergebnissen Moeglichkeiten fuer die Spannungs- und Dehnungsmessungen im Beton bei hohen Temperaturen abgeleitet. (orig.)Original Title
Spannbeton-Reaktordruckbehaelter Instrumentierung
Primary Subject
Source
Deutscher Ausschuss fuer Stahlbeton; no. 253; 1975; 27 p; Ernst; Berlin, F.R. Germany; ISBN 3433007306; ; 45 figs.; 4 refs.
Record Type
Book
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
2. international conference on structural mechanics in reactor technology; Berlin, Germany; 10 Sep 1973
Record Type
Journal Article
Literature Type
Conference
Journal
Nuclear Engineering and Design; v. 29(2); p. 189-195
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Reaktordruckbehaelter aus Spannbeton mit heisser Dichthaut
Primary Subject
Source
Jaeger, T.A. (comp.); Commission of the European Communities, Brussels (Belgium); Bundesanstalt fuer Materialpruefung, Berlin (F.R. Germany); v. 4 (pt. H) p. 413-435; 1972; First international conference on structural mechanics in reactor technology; Berlin, F.R. Germany; 20 Sep 1971; 5 figs.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
v. 3(pt.H); 1973; H 3/8, 1 p; 2. international conference on structural mechanics in reactor technology; Berlin, F.R. Germany; 10 Sep 1973; Published in summary form only.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Weissbacher, L.; Nemet, J.; Zemann, H.
Structural mechanics in reactor technology. Transactions. Vol. H1979
Structural mechanics in reactor technology. Transactions. Vol. H1979
AbstractAbstract
No abstract available
Primary Subject
Source
Jaeger, T.A.; Boley, B.A. (eds.); Commission of the European Communities, Brussels (Belgium); Bundesanstalt fuer Materialpruefung, Berlin (Germany, F.R.); International Association for Structural Mechanics in Reactor Technology; p. H1/1 (1); ISBN 0 444 85364 2; ; 1979; p. H1/1 (1); North-Holland Publishing Co; Amsterdam, Netherlands; 5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2); Berlin, Germany, F.R; 9 - 21 Aug 1979; INKA-CONF--79-321-279; Short communication only.
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Jaeger, T.A.; Boley, B.A. (eds.); Commission of the European Communities, Brussels (Belgium); Bundesanstalt fuer Materialpruefung, Berlin (Germany, F.R.); International Association for Structural Mechanics in Reactor Technology; p. H6/1 (1); ISBN 0 444 85364 2; ; 1979; p. H6/1 (1); North-Holland Publishing Co; Amsterdam, Netherlands; 5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2); Berlin, Germany, F.R; 9 - 21 Aug 1979; INKA-CONF--79-321-310; Short communication only.
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The main scope of the development and experimental verification of a new type of Prestressed Concrete Pressure Vessel (PCPV) was a significant gain in operational safety and, as a consequence, availability. An analysis of possible disturbances and down-times of conventional PCPV's shows two ways to improve the operational safety: a) to make the working conditions of the liner, the most essential component, safer, thus decreasing the probability of a leak; b) to improve the possibilities for inspection, leak detection and repair, thus reducing shut-down times. The Austrian PCPV offers a solution to these requirements. The main characteristics of the new vessel concept, developed and tested in Austria, are: Elastic hot liner, accessible for inspection and repair; adjustable wall temperature, matching the respective operating conditions of HTR's optimally; leak limitation and detection, controlled leak evacuation
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria). International Working Group on High-Temperature Reactors; p. 58-63; Mar 1979; p. 58-63; Specialists meeting on vessel concepts for gas-cooled reactors; Lausanne, Switzerland; 23 - 25 Oct 1978
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] As a contribution to improve further the operational safety of prestressed concrete pressure vessels (PCPV) a concept was developed based on a hot liner in direct contact with coolant. Thus the liner is accessible for inspection, leak detection and repair, leading to an increased availability of the plant. As a further safety consequence the concept calls for a liner which is kept in all operational and emergency conditions under elastic compression well below the yield point. This second requirement is satisfied by using specially suited high strength liner materials in combination with a simple temperature control system adjusting the vessel wall temperature in relation to the liner temperature. In this way the vessel can also be adapted readily to varying working conditions. The principles of the concept are discussed in comparison with other existing or future vessels and design details are given. (U.K.)
Primary Subject
Source
British Nuclear Energy Society, London; p. 39-48; ISBN 07277 0169 X (COMPLETE SET); ; 1983; p. 39-48; British Nuclear Energy Society; London (UK); Symposium on gas-cooled reactors today; Bristol (UK); 20-24 Sep 1982; Available from B.N.E.S., 1-7 Great George St., London SW1P 3AA
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A hot liner in direct contact with the coolant has been developed to improve the operational safety of prestressed concrete pressure vessels (PCPV). The liner is accessible for inspection, leak detection and repair, leading to an increased availability of the plant. High strength liner materials combined with a simple temperature control system to adjust the vessel wall temperature in relation to the liner temperature keep the liner in the elastic compression eliminating the danger of plastification. The liner is also an effective control of possible leakages. Comparisons with existing vessels have been made and the experiments to verify the concept are outlined. The PCPV concept can be applied to gas cooled thermal and fast reactors and light and heavy water-cooled reactors. Many shapes are possible including mono-cavern, multicavern and satellite designs and the feasibility studies which have been carried out are discussed. (U.K.)
Primary Subject
Source
British Nuclear Energy Society, London; 328 p; ISBN 0 7277 0168 1; ; 1983; p. 39-48; BNES; London (UK); Gas-cooled reactors today; Bristol (UK); 20-24 Sep 1982
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |