THERMAL REACTOR SAFETY: GENERAL SAFETY ANALYSIS. = SECURITE DES REACTEURS THERMIQUES: ANALYSE GENERALE DE SECURITE1976; TRANS. AMER. NUCL. SOC.; U.S.A.; DA. 1976; VOL. 23; PP. 276-282; BIBL. DISSEM.Article

HTRG OFFERS WIDEST RANGE OF PROCESS HEAT OPTIONS. = LE REACTEUR HTGR OFFRE UNE GRANDE GAMME DE POSSIBILITES D'APPLICATION DANS LE DOMAINE DE LA CHALEUR INDUSTRIELLEQUADE RN.1975; ENERGY INTERNATION.; U.S.A.; DA. 1975; VOL. 12; NO 10; PP. 55-57Article

PREOPERATIONAL CHEMICAL CLEANING OF FORT ST. VRAIN NUCLEAR GENERATING STATION SYSTEMS. = NETTOYAGE CHIMIQUE, AVANT MISE EN ROUTE, DES CIRCUITS DE LA CENTRALE NUCLEAIRE DE FORT ST. VRAINTATUM CB; SCHUETZENDUEBEL WG; RIEBE JJ et al.1975; PROC. AMER. POWER CONF.; U.S.A.; DA. 1975; VOL. 37; PP. 772-780; (AM. POWER CONF. ANNU. MEET. 37. PROC.; THE PALMER HOUSE; 1975)Conference Paper

DETERMINATION OF NEUTRON FLUX AND NEUTRON FLUENCE FROM THE SIGNAL CURRENT OF A SELF-POWERED RHODIUM DETECTORHUDRITSCH WW.1973; NUCL. TECHNOL.; U.S.A.; DA. 1973; VOL. 18; NO 1; PP. 25-28; BIBL. 1 REF.Serial Issue

ETAT DES RECHERCHES SUR LES PARTICULES ENROBEESKOBAYASHI S.1973; J. ATOM. ENERGY SOC. JAP.; JAP.; DA. 1973; VOL. 15; NO 2; PP. 69-85; BIBL. 13 REF.Serial Issue

THERMAL REACTOR SAFETY: ACCIDENT ANALYSIS DEVELOPMENT. = SECURITE DES REACTEURS THERMIQUES: DEVELOPPEMENT DE L'ANALYSE DES ACCIDENTS1976; TRANS. AMER. NUCL. SOC.; U.S.A.; DA. 1976; VOL. 23; PP. 283-294; BIBL. DISSEM.Article

ZINC- AND ALUMINIUM MAKING PROCESSES USING HTGR PROCESS HEAT.HUWYLER S; SEIFRITZ W; VON KAENEL B et al.1976; BER. KERNFORSCH.-ANLAGE JUELICH-JUEL.-CONF.; DTSCH.; DA. 1976; NO 23; PP. 77-82; BIBL. 8 REF.; (NUCL. ENERGY APPL. OTHER ELECTR. PROD. SYMP., JUELICH; 1976)Conference Paper

THE GAS TURBINE HTGR PLANT - ECONOMICAL DRY COOLING OR A WET-COOLED HIGH-EFFICIENCY BINARY CONFIGURATION. = CENTRALE HTGR A TURBINE A GAZ - REFROIDISSEMENT PAR VOIE SECHE ECONOMIQUE OU CYCLE BINAIRE A HAUT RENDEMENT A REFROIDISSEMENT HUMIDESCHOENE TW; WINKLER EO; FORTHESCUE P et al.1975; PROC. AMER. POWER CONF.; U.S.A.; DA. 1975; VOL. 37; PP. 363-378; BIBL. 4 REF.; (AM. POWER CONF. ANNU. MEET. 37. PROC.; THE PALMER HOUSE; 1975)Conference Paper

DEVELOPMENT TREND IN HIGH-TEMPERATURE-GAS-COOLED REACTOR (HTGR) IN JAPAN = TENDANCES DE DEVELOPPEMENT DES REACTEURS HAUTE TEMPERATURE REFROIDIS PAR GAZ (HTGR) AU JAPONHARADA T.1974; CHEM. ECON. ENGNG REV.; JAP.; DA. 1974; VOL. 6; NO 10; PP. 11-44 (6 P.)Article

2300 MW-KERNKRAFTWERK MIT GASGEKUEHLTEN HOCHTEMPERATURREAKTOREN = CENTRALE NUCLEAIRE DE 2300 MW A REACTEUR HAUTE TEMPERATURE REFROIDI PAR GAZWAAGE JU; SCHUZENDUBEL WG; FISCHER PU et al.1972; BRENNST. WAERME KRAFT; DTSCH.; DA. 1972; VOL. 24; NO 10; PP. 363-368; BIBL. 3 REF.Serial Issue

DEVELOPMENTS OF HELIUM-COOLED REACTOR SYSTEMS = DEVELOPPEMENT DU REACTEUR REFROIDI PAR HELIUMFORTESCUE P; GOODJOHN AJ; MELESE D'HOSPITAL G et al.1974; CHEM. ECON. ENGNG REV.; JAP.; DA. 1974; VOL. 6; NO 10; PP. 16-25; BIBL. 17 REF.Article

DECONTAMINATION OF HTGR REPROCESSING OFF-GASESWHATLEY ME; GLASS RW; HAAS PA et al.1972; CONF-720823-12; U.S.A.; DA. 1972; PP. (22 P.); BIBL. 11 REF.; (12TH AIR CLEAN. CONF.; OAK RIDGE, TENN.; 1972). MICROFICHEConference Proceedings

I. NUCLEAR REACTORS FOR HYDROGEN PRODUCTION. II. HYDROGEN AS A FUEL: SOME ASPECTS OF ITS COMBUSTION PROCESSES.SEVILLA A; GARCIA F; SANCHEZ TARIFA C et al.sdIN: WORLD ENERGY CONF. 10; ISTANBUL; 1977; S.L.; DOGUS MATBAASI; DA. S.D.; PP. 1-21; ABS. FR.; BIBL. 19 REF.Conference Paper

LATEST DIRECT CYCLE CONCEPT AIMS FOR HIGH EFFICIENCY. = LE DERNIER PRINCIPE DE CYCLE DIRECT A POUR OBJECTIF UN RENDEMENT ELEVEKRASE JM; NEILL JM.1976; ENERGY INTERNATION.; U.S.A.; DA. 1976; VOL. 13; NO 3; PP. 31-33Article

STEAM-TURBINE-DRIVEN CIRCULATORS FOR HIGH-TEMPERATURE GAS-COOLED REACTORS. II. DEVELOPMENT = POMPES DE CIRCULATION ENTRAINEES PAR TURBINE A VAPEUR POUR REACTEURS HAUTE TEMPERATURE REFROIDIS PAR GAZ. II. DEVELOPPEMENTBARBAT VJ; KAPICH D; DAHMS FC et al.1974; J. ENGNG POWER; U.S.A.; DA. 1974; VOL. 96; NO 2; PP. 102-108Article

RAPID DEPRESSURIZATION OF A THERMAL INSULATION SYSTEM FOR HIGH TEMPERATURE GAS REACTORSARANOVITCH E; VAN ASSELT D.1972; EUR-4880E; LUXEMBOURG; DA. 1972; PP. 1-53Report

THE HIGH TEMPERATURE GAS-COOLED REACTOR: AN OVERVIEW OF SAFETY ISSUESSOLOMON KENNETH A; SALEM STEVEN L.1980; ; USA; SANTA MONICA CA: RAND; DA. 1980; RAND/N-1589-GCRA; 83 P.; BIBL. 24 REF.Report

THE HTGR AND ITS APPLICATIONSGOODJOHN AJ; DAHLBERG RC; QUADE RN et al.1980; A FOREST OF ENERGY DICISION TREES: THE 1980'S. INSTITUTE OF ELECTRICAL AND ELECTRONICS ENGINEERS. 1980 REGION 6 CONFERENCE/1980/SAN DIEGO CA; USA; NEW YORK: IEEE; DA. 1980; PP. 132-136Conference Paper

HTGR-DAMPFERZEUGER. = STEAM GENERATOR FOR THE HTGR PLANT = GENERATEUR DE VAPEUR POUR REACTEUR REFROIDI PAR GAZ A HAUTE TEMPERATURESCHUTZENDUBEL WG.1976; WAERME; DTSCH.; DA. 1976; VOL. 82; NO 4; PP. 74-80; BIBL. 1/2 P.Article

ECHANGEURS DE CHALEUR UTILISES EN SIDERURGIE NUCLEAIRE, UTILISANT DES REACTEURS HAUTE TEMPERATURE REFROIDIS PAR GAZMORI Y; NAKADA T; SANOKAWA K et al.1975; J. ATOM. ENERGY SOC. JAP.; JAP.; DA. 1975; VOL. 17; NO 6; PP. 303-313; ABS. ANGL.; BIBL. 2 REF.Article

TURBOMACHINERY DESIGN CONSIDERATIONS FOR THE NUCLEAR HTGR-GT POWER PLANTMCDONALD CF; SMITH MJ.1981; J. ENG. POWER; ISSN 0022-0825; USA; DA. 1981; VOL. 103; NO 1; PP. 65-77; BIBL. 20 REF.Article

TWO DIMENSIONAL VIBRATION TEST AND ITS SIMULATION ANALYSIS FOR VERTICAL SLICE MODEL OF HTGR COREMUTO K; KURODA T; MURAKAMI H et al.1977; J. ATOM. ENERGY SOC.; JAP.; DA. 1977; VOL. 19; NO 12; PP. 853-861; ABS. ANGL.; BIBL. 6 REF.Article

ELECTROLYTICAL DISGREGATION TESTS OF IRRADIATED AND NON-IRRADIATED GRAPHITEBEONE G; LAZZARETTO G; MOCCIA A et al.1973; KERNTECHNIK; DTSCH.; DA. 1973; VOL. 15; NO 6; PP. 270-272; ABS. ALLEM.; BIBL. 8 REF.Serial Issue

COMPARISON BETWEEN FORCED DRAFT DRY COOLING SYSTEMS AND A NATURAL DRAFT WET COOLING TOWER FOR THE HIGH TEMPERATURE GAS-COOLED REACTOR.MAYOR JC; MUSTOE FJ; LEUENBERGER JM et al.sdIN: NUCLEX 75. FOIRE INT. JOURN. INF. IND. 4; BALE; 1975; S.L.; NUCLEX; DA. S.D.; PP. (7P.); H.T. 7; ABS. ALLEM. FR.; BIBL. 6 REF.Conference Paper

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