EN TCHEQUE = CAPTURE DE L'IODE RADIOACTIF DANS DES SYSTEMES DE PULVERISATION POUR ENCEINTESTOMASEK M.1973; JADER. ENERG.; CESKOSL.; DA. 1973; VOL. 19; NO 2; PP. 66-68; BIBL. 3 REF.Serial Issue

INSTRUMENTIERUNG VON SIEDEWASSERREAKTOREN = INSTRUMENTS DE MESURE POUR REACTEURS A EAU BOUILLANTEPREUSCHE G; GROSSE SCHULTE M.1973; V.G.B. KRAFTWERKSTECH.; DTSCH.; DA. 1973; VOL. 53; NO 3; PP. 165-171; ABS. ANGL. DANOIS FINNOIS FR. NEERL. ITAL. RUSSE SUEDOISSerial Issue

BOILING WATER REACTOR CONTAINMENT SYSTEMS AND CONSTRUCTIONPALMERI A.1972; INGEGNER. NUCL.; ITAL.; DA. 1972; VOL. 13; NO 3; PP. 17-28Serial Issue

ENCEINTE DE SECURITE DE CENTRALES NUCLEAIRES A REACTEURS PWRMISAK J.1972; JADER. ENERG.; CESKOSL.; DA. 1972; VOL. 18; NO 8; PP. 279-283; BIBL. 3 REF.Serial Issue

A1055 FT/SEC IMPACT TEST OF A TWO FOOT DIAMETER MODEL NUCLEAR REACTOR CONTAINMENT SYSTEM WITHOUT FRACTUREPUTHOFF RL.1972; N72-27721, NASA-TM-X-68103; U.S.A.; DA. 1972; PP. (26 P.); BIBL. 6 REF.; MICROFICHEReport

ENGINEERING INNOVATIONS FOR DAVIS-BESSE CONTAINMENTWAHL HW.1973; PROC. AMER. SOC. CIV. ENGRS, J. POWER DIV.; U.S.A.; DA. 1973; VOL. 99; NO 1; PP. 125-137Serial Issue

SPRAY CC-SPRAY CM-SPRAY EV. SEMPLICI CODICI PER LO STUDIO DELLE QUANTITA DI CALORE E DI MASSA ASPORTATE DA UN SISTEMA A PIOGGIA IN UNA ATMOSFERA DI ARIA E VAPORE D'ACQUA = SPRAY CC-SPRAY CM-SPRAY EV. REGLES SIMPLES POUR L'ETUDE DES QUANTITES DE CHALEUR ET DE MATIERE TRANSPORTEES PAR UN SYSTEME DE BROUILLARD DANS UNE ATMOSPHERE D'AIR ET DE VAPEUR D'EAUDESOGUS C; HOLTBECKER H.1973; EUR-4911I; LUSSEMBURGO; DA. 1973; PP. 1-77; ABS. ANGL.; BIBL. 4 REF.Report

SAFETY FACTORS AND PROBABILITY IN STRUCTURAL DESIGNBURNUP TE; ROBERTS D.1972; SRD-R-12; G.B.; DA. 1972; PP. 1-28; BIBL. 3 REF.Report

THE DESIGN OF A THIN SHELL NUCLEAR CONTAINMENT VESSEL FOR SEISMIC LOADINGHAGSTROM J.1972; J. ENGNG INDUSTRY; U.S.A.; DA. 1972; VOL. 94; NO 3; PP. 803-806; BIBL. 8 REF.Serial Issue

STAHLCONTAINMENT FUER EIN KERNKRAFTWERK IN PUERTO-RICO = ENCEINTE EN ACIER POUR UNE CENTRALE NUCLEAIRE DE PORTO-RICOJEMIELEWSKI J.1972; SCHWEIZ. BAUZTG; SCHWEIZ; DA. 1972; VOL. 90; NO 41; PP. 1025-1026Serial Issue

A 640 FT-SEC IMPACT TEST OF A TWO-FOOT DIAMETER MODEL NUCLEAR REACTOR CONTAINMENT SYSTEM WITHOUT FRACTUREPUTHOFF RL.1971; N72-16519, NASA-TM-X-67997; U.S.A.; DA. 1971; PP. (20 P.); BIBL. 5 REF.; MICROFICHEReport

NONLINEAR SEISMIC ANALYSIS OF THIN REACTOR CONTAINMENT VESSELSCITERLEY RL; BALL RE.1972; J. ENGNG INDUSTRY; U.S.A.; DA. 1972; VOL. 94; NO 3; PP. 925-929; BIBL. 12 REF.Serial Issue

DIE REAKTORANLAGE DES KERNKRAFTWERKES TULLNERFELD = INSTALLATION DU REACTEUR DE LA CENTRALE NUCLEAIRE DE TULLNERFELDKRAMMER JH; SCHABACKER P.1972; OSTERR. INGR-Z.; OSTERR.; DA. 1972; VOL. 15; NO 11; PP. 332-336Serial Issue

THREE MILE ISLAND NUCLEAR STATION, UNIT 11972; DOCKET-50289-59, DOCKET-50289-60; U.S.A.; DA. 1972; PP. (99 P.); MICROFICHEReport

L'ENVELOPPE DE SECURITE POUR LE REACTEUR DE LA CENTRALE NUCLEAIRE PHILIPPSBURG ILEIDL; WEBER; ZWINGENBERGER et al.1972; ACIER STAHL STEEL; FR.; DA. 1972; VOL. 37; NO 9; PP. 353-361; BIBL. 2 REF.Serial Issue

REACTOR PLANT STRUCTURES AND CONTAINMENT. J. ANALYSIS OF SHELL STRUCTURES; CONTAINMENTsdEUR-4820-D-F-E; LUXEMBOURG; DA. S.D.; VOL. 5; PP. 1-430; ABS. ANGL.; BIBL. DISSEM.; (PROC. 1ST INT. CONF. STRUCT. MECH. REACT. TECHNOL.; BERLIN; 1971)Conference Proceedings

COMPARISON OF A TWO-DIMENSIONAL HYDRODYNAMICS CODE (REXCO) TO EXCURSION EXPERIMENTS FOR FAST REACTOR CONTAINMENTASH JE; CHANG YW; JULKE RT et al.1972; ANL-7911 SUPPLEMENT 1; U.S.A.; DA. 1972; PP. (18 P.); BIBL. 23 REF.; MICROFICHEReport

FFTF DESIGN FLEXIBILITY FOR HYPOTHETICAL ACCIDENT MITIGATIONPETERSON RE.1971; HEDL-TME 71-125; U.S.A.; DA. 1971; PP. (20 P.); BIBL. 1 REF.; MICROFICHEReport

STATUSBERICHT UEBER PROBLEME DER HEUTE UEBLICHEN CONTAINMENTKONZEPTE = ETAT ACTUEL DU PROBLEME DU CONCEPT D'ENCEINTE USUELLEBROSCHE D; ENGEL M; KIRST O et al.1971; MRR-91; DTSCH.; DA. 1971; PP. (91 P.); ABS. ANGL.; BIBL. 35 REF.; MICROFICHEReport

FAST REACTOR FUEL INTERACTIONS WITH FLOOR MATERIAL AFTER A HYPOTHETICAL CORE MELTDOWNJANSEN G; STEPNEWSKI DD.1973; NUCL. TECHNOL.; U.S.A.; DA. 1973; VOL. 17; NO 1; PP. 85-95; BIBL. 23 REF.Serial Issue

POST-ACCIDENT HYDROGEN GENERATION FROM PROTECTIVE COATINGS IN POWER REACTORSZITTEL HE.1973; NUCL. TECHNOL.; U.S.A.; DA. 1973; VOL. 17; NO 2; PP. 143-146; BIBL. 2 REF.Serial Issue

THE DESIGN OF THE VACUUM BUILDING FOR PICKERING GENERATING STATIONCARTHEW CW; KNAUTZ FA; CHAN GT et al.1972; NUCL. ENGNG DESIGN; NETHERL.; DA. 1972; VOL. 23; NO 2; PP. 198-208; BIBL. 7 REF.Serial Issue

PROZESSDAMPFERZEUGUNG MIT HOCHTEMPERATURREAKTOREN = PRODUCTION DE VAPEUR DE PROCESSUS PAR REACTEUR A HAUTE TEMPERATUREKUGELER K.1972; JUEL-870-RG; DTSCH.; DA. 1972; PP. (44 P.); ABS. ANGLReport

THEORETICAL TREATMENT OF AEROSOL BEHAVIOR IN CLOSED CYLINDRICAL CONTAINERS (PARDISEKO 1)KELLER K.1971; EURFNR-978, KFK-1490; U.S.A.; DA. 1971; PP. (23 P.); BIBL. 7 REF.; MICROFICHEReport

REACTOR COMPONENTS. E. SHOCK AND VIBRATION ANALYSIS OF REACTOR COMPONENTSsdEUR-4820-D-F-E; LUXEMBOURG; DA. S.D.; VOL. 3; PP. 1-475; ABS. ANGL.; BIBL. DISSEM.; (PROC. 1ST INT. CONF. STRUCT. MECH. REACT. TECHNOL.; BERLIN; 1971)Conference Proceedings