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RADIOACTIVE FLUE GAS PURIFICATION SYSTEM IN NUCLEAR PLANTS WITH WATER MODERATED REACTORSNAKHUTIN IE; OCHKIN DV; PIS'MAN B YA et al.1978; ATOM. ENERG.; S.S.S.R.; DA. 1978; VOL. 44; NO 3; PP. 251-252Article

SAFETY PROBLEMS OF WATER COOLED AND MODERALED REACTORSSIDORENKO VA; VOZNESENSKIJ VA; STEKOL'NIKOV VV et al.1977; ATOM. ENERG.; S.S.S.R.; DA. 1977; VOL. 43; NO 6; PP. 449-457Article

IL CONTROLLO DELLA CORROSIONE NELL'IMPIANTO CIRENE. = CORROSION CONTROL IN THE CIRENE NUCLEAR PLANT = CONTROLE DE LA CORROSION DANS L'INSTALLATION NUCLEAIRE CIRENECONTE A; DI PIETRO R.1976; ENERG. NUCL.; ITAL.; DA. 1976; VOL. 23; NO 10; PP. 493-506; ABS. ANGL.; BIBL. 27 REF.Article

EXPERIMENTAL STUDY OF HYDRODYNAMIC PROCESSES DURING COOLANT FLOW FROM A VESSELDEMENT'EV BA; AL' BAKHILI KH M; IONOV BA et al.1979; TEPLOENERGETIKA; SUN; DA. 1979; NO 5; PP. 36-39; BIBL. 2 REF.Article

THE ANALYTICAL MODEL OF A WATER-COOLED AND -MODERATED REACTOR AS A PART OF THE WHOLE NUCLEAR POWER PLANT PRIMARY CIRCUIT MATHEMATICAL MODELANDREEV PA; VASIL'EV V YU; IVANOV VA et al.1978; TRUDY L.P.I., LENINGRAD; S.S.S.R.; DA. 1978; NO 358; PP. 74-78; BIBL. 6 REF.Article

POWER UP OF FUGEN REACTOR AND DEVELOPMENT OF DEMONSTRATION PLANTSAWAI S; AKEBI M; YAZAKI A et al.1979; CANADIAN NUCLEAR ASSOCIATION. ANNUAL INTERNATIONAL CONFERENCE. 19/1979/TORONTO; CAN; TORONTO: CANADIAN NUCLEAR ASSOCIATION; DA. 1979; PP. 6.4.1-6.4.9; BIBL. 3 REF.Conference Paper

PROSPECTS FOR THE USE OF NUCLEAR HEAT SOURCES IN CZECHOSLOVAKIADERIAN L.1977; IN: URBAN DIST. HEAT. USING NUCL. HEAT. I.A.E.A. ADVIS. GROUP MEET. PROC.; VIENNA; 1976; VIENNA; I.A.E.A.; DA. 1977; PP. 173-182; ABS. ANGL.; BIBL. 5 REF.Conference Paper

DIX-SEPTIEME RAPPORT ANNUEL. OCDE PROJET DE REACTEUR DE HALDEN = THE SEVENTEENTH ANNUAL REPORT OF THE OECD HALDEN REACTOR PROJECT1976; O.C.D.E., PROJET REACTEUR HALDEN; FRA; DA. 1976; VOL. 17; PP. 1-85Serial Issue

EQUIPMENTS AND PROCEDURES FOR LARGE SCALE LOCA TESTS RELEVANT TO THE CIRENE REACTORLOMBARDI C; MEDICH C; RAVETTA R et al.1978; ENERG. NUCL.; ITA; DA. 1978; VOL. 25; NO 8-9; PP. 393-405; ABS. ITA; BIBL. 3 REF.Article

WATER-COOLED REACTOR SAFETY.1977; TRANS. AMER. NUCL. SOC.; U.S.A.; DA. 1977; VOL. 25; PP. 225-257; BIBL. DISSEM.; (INT. CONF. WORLD NUCL. ENERGY. STATUS REP. PROC.; WASHINGTON; 1976)Conference Paper

WINFRITH SGHWR OPERATING EXPERIENCES 1968-1981NEGUS B; BLACK WS.1981; NUCLEAR ENERGY (1978); ISSN 0140-4067; GBR; DA. 1981; VOL. 20; NO 5; PP. 347-358Article

DIRECTORY OF NUCLEAR REACTORS. X. POWER AND RESEARCH REACTORS.1976; VIENNA; INT. AT. ENERGY AGENCY; DA. 1976; PP. (429P.); BIBL. DISSEM.; ISBN 920152076X; (STI-PUB-397)Book

Generalization of the analytical exponential model to solve the point kinetics equations of Be-and D2O-moderated reactorsNAHLA, Abdallah A.Nuclear engineering and design. 2008, Vol 238, Num 10, pp 2648-2653, issn 0029-5493, 6 p.Article

DEVELOPMENT OF FUGEN TYPE HWR IN JAPANSAWAI S.1981; NUCLEAR ENERGY (1978); ISSN 0140-4067; GBR; DA. 1981; VOL. 20; NO 5; PP. 367-373; BIBL. 8 REF.Article

Modernization of the 220 MW turbines of NPO Turboatom for nuclear power stationsLEVCHENKO, E. V; GALATSAN, V. N; ARKAD'EV, B. A et al.Thermal engineering. 1997, Vol 44, Num 7, pp 535-541, issn 0040-6015Article

Full-scale experimental facility for the development technologies for the reprocessing of tritium contamined light and heavy water wastes by CECE process and cryogenic distillationTRENIN, V. D; ALEKSEEV, I. A; KARPOV, S. P et al.Fusion technology. 1995, Vol 28, Num 3, pp 767-771, issn 0748-1896, 1Conference Paper

Development of severe accident management guidance (SAMG) for the Canadian CANDU 6 nuclear power plantsNGUYEN, Thinh; JAITLY, Raj; DINNIE, Keith et al.Nuclear engineering and design. 2008, Vol 238, Num 4, pp 1093-1099, issn 0029-5493, 7 p.Article

A novel technique to remove deuterium from CANDU pressure tubesQIN, Z; ZHANG, C.-S; GRIFFITHS, K et al.Journal of nuclear materials. 2001, Vol 299, Num 1, pp 77-82, issn 0022-3115Article

CANDU steam generator life managementTAPPING, R. L; NICKERSON, J; SPEKKENS, P et al.Nuclear engineering and design. 2000, Vol 197, Num 1-2, pp 213-223, issn 0029-5493Conference Paper

Epuration de l'eau utilisée de générateurs de vapeurs de centrales nucléaires avec réacteur eau/eau 440 en régimes complexesLUCHKIN, V. G; MARGULOVA, T. KH.Teploenergetika (Moskva, 1954). 1986, Num 6, pp 66-69, issn 0040-3636Article

Potential improvement of CANDU NPP safety margins by shortening the response time of shutdown systems using FPGA based implementationJINGKE SHE; JIN JIANG.Nuclear engineering and design. 2012, Vol 244, pp 43-51, issn 0029-5493, 9 p.Article

Rapid estimation of core-power ratio in coupled-core system by rod drop methodHASHIMOTO, Kengo; SANO, Tadafumi; UNESAKI, Hironobu et al.Journal of Nuclear Science and Technology. 2000, Vol 37, Num 7, pp 565-571, issn 0022-3131Article

Element bowing assessments of CANFLEX fuel bundle during in-reactor service and refuellingHO CHUN SUK; SIM, K.-S; JOO HWAN PARK et al.Nuclear engineering and design. 1996, Vol 165, Num 1-2, pp 81-99, issn 0029-5493Article

Etude des générateurs de vapeur du bloc principal d'une centrale nucléaire avec réacteur modéré et refroidi à l'eauTARANKOV, G. A; TITOV, V. F; LOGVINOV, S. A et al.Ènergomašinostroenie. 1986, Num 5, pp 30-32, issn 0131-1336Article

Principales tendances d'étude et de développement de générateurs de vapeur du type horizontal pour centrales nucléaires avec réacteurs modérés et refroidis à l'eauTITOV, V. F; TARANKOV, G. A; LUKASEVICH, B. I et al.Ènergomašinostroenie. 1986, Num 5, pp 27-29, issn 0131-1336Article

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