Filters
Results 1 - 10 of 154
Results 1 - 10 of 154.
Search took: 0.032 seconds
| Sort by: date | relevance |
AbstractAbstract
No abstract available
Primary Subject
Source
European nuclear conference; Paris, France; 21 Apr 1975; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 20 p. 200-202
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] KNK, the Kompakte Natriumgekuehlte Kernreaktoranlage is a 20 MW(e) sodium-cooled experimental nuclear power plant located at Karlsruhe, West Germany. The paper describes the special technical features of this plant, experiences from the commissioning phase, licensing problems, the organizational setup and the future experimental programs
Primary Subject
Source
Anon; p. 89-95; 1976; p. 89-95; American Society of Mechanical Engineers; New York; ASME-ANS joint international conference on advanced nuclear energy systems; Pittsburgh, PA, USA; 13 Mar 1976
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Kompakte natriumgekuehlte Kernreaktoranlage (KNK): Umbau wird fortgesetzt
Primary Subject
Record Type
Journal Article
Journal
Pressedienst. Bundesminist. Bild. Wiss; (no. 14); p. 5-6
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
European nuclear conference; Paris, France; 21 Apr 1975; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 20 p. 168-169
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] No fuel element damage has occured during the KNK operation with thermal reactor core. The fission products observed in spite of this originated from a surface contamination of the fuel elements. The measured results given thus describe the behaviour of fission products under normal operational conditions of the KNK-I. The methods discussed to determine fission products, however, simultaneously outline the possibilities for quantitative analytical monitoring of the fission product inventory in the KNK-II primary system in accidents with the occurence of cladding damage. (orig./LH)
[de]
Waehrend des KNK-Betriebs mit thermischem Reaktorkern ist kein Brennelementschaden aufgetreten. Die trotzdem beobachteten Spaltprodukte entstammten einer Oberflaechenkontamination der Brennelemente. Die mitgeteilten Messergebnisse beschreiben daher das Verhalten von Spaltprodukten unter normalen Betriebsbedingungen der KNK-I. Die eroerterten Verfahren zur Bestimmung von Spaltprodukten umreissen jedoch zugleich die Moeglichkeiten zur quantitativ-analytischen Ueberwachung des Spaltprodukt-Inventars im KNK-II-Primaersystem bei Stoerfaellen mit Auftreten von Brennelement-Huellrohrschaeden. (orig.)Original Title
Bestimmung von Spaltprodukten in der KNK
Primary Subject
Source
1976; 9 p; Specialist's meeting on fission product release in reactor accidents; Karlsruhe, F.R. Germany; 1 Jun 1976; 9 figs.; 4 tabs.; 18 refs.
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Richard, H.; Stade, K.C.; Breitlaender, H.; Zschetke, H.
Proceedings of the international conference on liquid metal technology in energy production1976
Proceedings of the international conference on liquid metal technology in energy production1976
AbstractAbstract
[en] A discussion is presented of methods used to clean sodium-wetted components at the KNK facility. Both the activated and non-activated components such as valves, gripping devices for handling and core components, and large components such as the steam generators and cyclones are dealt with
Primary Subject
Source
Cooper, M.H. (ed.); American Nuclear Society, Hinsdale, Ill.; American Inst. of Mining, Metallurgical, and Petroleum Engineers, Inc., New York; Energy Research and Development Administration, Washington, D.C. (USA); American Nuclear Society, Pittsburgh, Pa. Pittsburgh Section; p. 561-566; Nov 1976; p. 561-566; International conference on liquid metal technology in energy production; Champion, Pennsylvania, United States of America (USA); 3 - 6 May 1976
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ALKALI METALS, BREEDER REACTORS, ELEMENTS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, HYDRIDE MODERATED REACTORS, LIQUID METAL COOLED REACTORS, METALS, POWER REACTORS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS, SZR TYPE REACTORS, THERMAL REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] With the start of the test reactor KNK I the collection and evaluation of reliability data was performed up to the final shut-down on 2 September 1974, the beginning of the reconstruction phase for the insertion of a fast core (KNK II). Reliability data useful for applications must contain the components that have not failed. To estimate, for example, the failure rates it is necessary to know the total operating time of the population as well as the number of failures. Data collection that included information on all components in the plant was not feasible. Thus an important step was to select a limited number of sodium component categories. By agreement with the operating company - the Kernkraftwerk Betriebsgesellschaft mbH, Leopoldshafen - the order forms for repairs were changed slightly to include the most important reliability information. For the evaluation a computer program was used. Results were obtained especially for valves, pumps, heat exchangers, cold traps and other sodium components. It is shown that useful reliability data can be achieved with limited effort if one concentrates on selected components. (author)
Primary Subject
Secondary Subject
Source
International Atomic Energy Agency, Vienna (Austria); United Nations, Geneva (Switzerland). Economic Commission for Europe; Proceedings series; p. 83-89; ISBN 92-0-050075-7; 
; 1975; IAEA; Vienna; Symposium on the reliability of nuclear power plants; Innsbruck, Austria; 14 Apr 1975; IAEA-SM--195/31
; 1975; IAEA; Vienna; Symposium on the reliability of nuclear power plants; Innsbruck, Austria; 14 Apr 1975; IAEA-SM--195/31
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Weiterentwicklung und Erprobung von Reaktor-Na-Absperrschiebern
Primary Subject
Source
Kerntechnische Gesellschaft im Deutschen Atomforum e.V., Bonn (F.R. Germany); p. 605-608; 1976; ZAED; Eggenstein-Leopoldshafen, F.R. Germany; Reactor meeting; Duessledorf, F.R. Germany; 30 Mar 1976; AED-CONF--76-013-151; 3 figs. Short communication only.
Record Type
Book
Literature Type
Conference
Country of publication
ALKALI METALS, CONTROL EQUIPMENT, ELEMENTS, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, FLOW REGULATORS, FLUID FLOW, HYDRIDE MODERATED REACTORS, LIQUID METAL COOLED REACTORS, METALS, POWER REACTORS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS, SZR TYPE REACTORS, TESTING, THERMAL REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Entladen und Abtransport des KNK I-Cores
Primary Subject
Secondary Subject
Source
Kerntechnische Gesellschaft im Deutschen Atomforum e.V., Bonn (F.R. Germany); p. 762-765; 1976; ZAED; Eggenstein-Leopoldshafen, F.R. Germany; Reactor meeting; Duesseldorf, F.R. Germany; 30 Mar 1976; AED-CONF--76-013-191; 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
International Atomic Energy Agency, Vienna (Austria); Proceedings series; p. 343-351; 1974; IAEA; Vienna; Symposium on experience from operating and fuelling nuclear power plants; Vienna, Austria; 8 Oct 1973; IAEA-SM--178/17
Record Type
Book
Literature Type
Conference
Country of publication
ALKALI METAL COMPOUNDS, ALKALI METALS, BOILERS, CHALCOGENIDES, ELEMENTS, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, HYDRIDE MODERATED REACTORS, LIQUID METAL COOLED REACTORS, METALS, OXIDES, OXYGEN COMPOUNDS, POWER REACTORS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COMPOUNDS, SODIUM COOLED REACTORS, SZR TYPE REACTORS, THERMAL REACTORS, VAPOR GENERATORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
| 1 | 2 | 3 | Next |