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ELEMENTARY FAULTS DELAY COMMISSIONING OF HTGR STATION IN UNITED STATES1972; ELECTR. REV.; G.B.; DA. 1972; VOL. 191; NO 17; PP. 561-562Serial Issue

FORT ST. VRAIN NUCLEAR GENERATING STATION1972; DOCKET-50267-42 A DOCKET-50267-45; U.S.A.; DA. 1972; PP. (635 P.); MICROFICHEReport

FORT ST. VRAIN UNIT 1 PCRV PRESSURE TEST REPORT FOR THE PUBLIC SERVICE COMPANY OF COLORADOOPLE FS JR; GOTSCHALL HL.1971; GULF-GA-A10839; U.S.A.; DA. 1971; PP. 1-58; BIBL. 2 REF.; MICROFICHEReport

FORT ST VRAIN HTGR STEAM GENERATOR AIR FLOW TESTKAUFMAN JS.1972; GULF-GA-A10833; U.S.A.; DA. 1972; PP. (115 P.); BIBL. 5 REF.; MICROFICHEReport

RELIABILITY DEMONSTRATION TEST OF FORT ST VRAIN STANDBY DIESEL GENERATOR SETS. FINAL REPORTBENHAM RG; SWART FE.1972; GULF-GA-A12075; U.S.A.; DA. 1972; PP. (26 P.); MICROFICHEReport

FORT ST. VRAIN UNIT 1 PCRV LEAK TEST REPORT FOR PUBLIC SERVICE COMPANY OF COLORADOBARKER R; RATH UK; TAMMADGE CE et al.1972; GULF-GA-A10875; U.S.A.; DA. 1972; PP. 1-124; BIBL. 4 REF.; MICROFICHEReport

QUALIFICATION OF FORT ST. VRAIN SAFE SHUTDOWN EQUIPMENT FOR STEAM ENVIRONMENT RESULTING FROM PIPE RUPTURESBENHAM RG; BURWELL EJ; DUNCAN DS et al.1972; GULF-GA-A 12045; U.S.A.; DA. 1972; PP. (325 P.); MICROFICHEReport

Erste Betriebserfahrungen mit dem Hochtemperaturreaktor Fort St. Vrain. VI: Kraftwerksbetrieb bis Ende 1981 = Premières expériences d'exploitation de la centrale à réacteur haute température de Fort St Vrain VI. Bilan d'exploitation jusqu'à fin 1981SCHÜTZENDÜBEL, W. G.Wärme. 1983, Vol 89, Num 3, pp 39-41, issn 0372-7114Article

ENTWICKLUNG, BAU UND BETRIEB VON KERNKRAFTWERKEN MIT GASGEKUEHLTEN HOCHTEMPERATURREAKTOR = DEVELOPPEMENT, CONSTRUCTION ET EXPLOITATION DES CENTRALES NUCLEAIRES A REACTEUR A HAUTE TEMPERATURE REFROIDI PAR GAZJOHNSTON TA; FISCHER PU.1972; V.G.B. KRAFTWERKSTECH.; DTSCH.; DA. 1972; VOL. 52; NO 5; PP. 390-396; ABS. ANGL. DAN. FINN. FR. NEERL. RUSSE SUEDOIS; BIBL. 2 REF.Serial Issue

GAS-COOLED REACTORS1972; TRANS. AMER. NUCL. SOC.; U.S.A.; DA. 1972; VOL. 15; NO 2; PP. 5-9; BIBL. DISSEM.Serial Issue

In-reactor oxidation of Fort St. Vrain support graphiteBEAVAN, L. A; BURNETTE, R. D; ENGLE, G. B et al.Biennal conference on carbon. 16. sd, pp 564-565Conference Paper

The fort St. Vrain high temperature gas-cooled reactor. IX: Rise-to-power physic testsOLSON, H. G; BREY, H. L; WARENBOURG, D. W et al.Nuclear engineering and design. 1983, Vol 76, Num 1, pp 71-77, issn 0029-5493Article

THE FORT ST. VRAIN HIGH TEMPERATURE GAS-COOLED REACTOR. IV: RISE TO POWER TEST PROGRAM. V: STEAM SYSTEM PERFORMANCE TESTS. VI: EVALUATION AND REMOVAL OF PRIMARY COOLANT CONTAMINANTS. IX: CONTROL ROD DRIVE AND ORIFICE ASSEMBLIESOLSON HG; BREY HL; SWART FE et al.1980; NUCL. ENG. DES.; ISSN 0029-5493; NLD; DA. 1980; VOL. 61; NO 3; PP. 295-329; BIBL. 13 REF.Article

POWER REACTOR OPERATING EXPERIENCE.1977; TRANS. AMER. NUCL. SOC.; U.S.A.; DA. 1977; VOL. 26; SUPPL. 1; PP. 56-61; BIBL. DISSEM.; (CONF. REACT. OPER. EXPER.; CHATTANOOGA, TENN.; 1977). RESUMESConference Paper

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