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AbstractAbstract
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Nuclear science symposium; San Francisco, Calif; 3 Nov 1971
Record Type
Journal Article
Literature Type
Conference
Journal
IEEE (Inst. Electr. Electron. Eng.) Trans. Nucl. Sci; v. NS-19(1); p. 843-845
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AbstractAbstract
No abstract available
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Source
Conference on nuclear power for tomorrow; Atlantic City, NJ; 22 Aug 1972; Published in summary form only.
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Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 15(suppl. no. 2); p. 5
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AbstractAbstract
[en] A prestressed concrete reactor vessel (PCRV) was used in the design of the 330-MW(e) Fort St. Vrain power demonstration plant. Use of the PCRV made the integration of all the nuclear steam supply system components practical. The primary coolant inventory was reduced and external piping and steam generator pressure shells were eliminated. A once-through-type steam generator system was selected. Materials selected for use in the pressure parts exceeded American Society of Mechanical Engineers Code requirements. The next step in the development of HTGR technology is the large commercial HTGR plant, which has once-through-type steam generators with a nominal capacity of 500 MW(th). Materials used in the main steam section range from 21/4 Cr--1 Mo to Ni--Fe--Cr (Alloy 800). High carbon levels were used to increase the creep strength of the materials. Gas cooling for fast breeder reactors is being studied by designing a 300-MW(e) demonstration plant. The steam generators are similar to the design of the Fort St. Vrain and large commercial plants. Tubes made of Alloy 800 are used
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Journal Article
Journal
Nuclear Technology; v. 28(3); p. 315-327
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AbstractAbstract
No abstract available
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15 Mar 1972; 68 p
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Report
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AbstractAbstract
[en] A dry, natural draught cooling tower, consisting of a cable netting is presented. Its characteristics are given and the construction is described
[fr]
On donne les caracteristiques et on decrit la construction d'une tour de refroidissement seche a tirage naturel constituee d'un reseau de cablesOriginal Title
Tour de refroidissement a reseau de cables
Primary Subject
Record Type
Journal Article
Journal
Technique Moderne; v. 68(1); p. 39-40
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AbstractAbstract
No abstract available
Original Title
Land Nordrhein-Westfalen. Bekanntmachung ueber die Auslegung des 5. atomrechtlichen Teilgenehmigungsbescheides fuer die Errichtung eines Kernkraftwerkes mit einem Thorium-Hochtemperatur-Reaktor in Hamm-Uentrop, Gemarkung Schmehausen. Vom 5. Februar 1975
Primary Subject
Secondary Subject
Source
Short communication only.
Record Type
Journal Article
Journal
Bundesanzeiger; v. 27(47); p. 5
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INIS VolumeINIS Volume
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Roberts, D.I.; Hedgecock, P.D.; Watson, J.F.
Symposium on materials performance in operating nuclear systems, Ames, Iowa, August 28--30, 19731973
Symposium on materials performance in operating nuclear systems, Ames, Iowa, August 28--30, 19731973
AbstractAbstract
No abstract available
Primary Subject
Source
Wechsler, M.S.; Smith, W.H. (eds.); Ames Lab., Iowa (USA); p. 325-358; Aug 1973
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Report
Literature Type
Conference
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AbstractAbstract
No abstract available
Original Title
Bekanntmachung betreffend Antraege der Kernkraftwerk Hamm GmbH, Dortmund, auf Genehmigung zur Errichtung und zum Betrieb eines Kernkraftwerkes mit einem Druckwasserreaktor sowie eines Naturzug-Nasskuehlturms in Hamm-Uentrop, Stadtteil Schmehausen
Primary Subject
Secondary Subject
Source
Short communication only.
Record Type
Journal Article
Journal
Bundesanzeiger; v. 27(219); p. 6
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AbstractAbstract
No abstract available
Primary Subject
Source
Transactions of the American Nuclear Society conference on reactor operating experience; Chattanooga, TN, USA; 7 Aug 1977; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society. Supplement; v. 26(1); p. 26
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AbstractAbstract
No abstract available
Original Title
Das 300-MW-Kernkraftwerk Uentrop mit THTR
Primary Subject
Source
3 figs.
Record Type
Journal Article
Journal
Atom und Strom; v. 17(11/12); p. 199-201
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