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FORT ST VRAIN EXPERIENCEBREY HL; OLSON HG.1983; NUCLEAR ENERGY (1978); ISSN 0140-4067; GBR; DA. 1983; VOL. 22; NO 2; PP. 117-121; BIBL. 7 REF.Article

HTGR EXPERIENCE, PROGRAMS, AND FUTURE APPLICATIONSMOORE RA; KANTOR ME; BREY HL et al.1982; NUCLEAR ENGINEERING AND DESIGN; ISSN 0029-5493; NLD; DA. 1982; VOL. 72; NO 2; PP. 153-174; BIBL. 25 REF.Article

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

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