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Results 1 to 25 of 2027

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Réacteurs RBMK = RBMK reactorsBASTIEN, Daniel.Techniques de l'ingénieur. Génie nucléaire. 2000, Vol BN2, Num BN3215, pp BN3215.1-BN3215.12, issn 1762-875XArticle

Advanced boiling water reactor core supervision and analysisLEMKE, H.-D; LEMBCKE, R.Siemens Forschungs- und Entwicklungsberichte. 1987, Vol 16, Num 1, pp 9-14, issn 0370-9736Article

Application of noise analysis technique for monitoring the moderator temperature coefficient of reactivity in pressurized water reactorsSHIEH, D. J; UPADHYAYA, B. R; SWEENEY, F. J et al.Nuclear science and engineering. 1987, Vol 95, Num 1, pp 14-21, issn 0029-5639Article

Hydrogen water chemistry for boiling water reactorsCOWAN, R. L; LAW, R. J; KASS, J. N et al.Proceedings of the American Power Conference. 1985, Vol 47, pp 1083-1089, issn 0097-2126Conference Paper

A study of heat capacity temperature limit of BWRWANG, Shih-Jen; JYH JUN CHEN; CHIEN, Chun-Sheng et al.Nuclear engineering and design. 2012, Vol 243, pp 279-286, issn 0029-5493, 8 p.Article

Decay ratio estimation using the instantaneous autocorrelation functionTORRES-FERNANDEZ, José E; PRIETO-GUERRERO, Alfonso; ESPINOSA-PAREDES, Gilberto et al.Nuclear engineering and design. 2010, Vol 240, Num 10, pp 3559-3570, issn 0029-5493, 12 p.Article

Additional competitiveness and safety by modernization at OlkiluotoRASTAS, A. J.Atw. Internationale Zeitschrift für Kernenergie. 2003, Vol 48, Num 6, issn 1431-5254, 374, 384-387 [5 p.]Article

An analysis of stability and oscillation modes in boiling multichannel loops using parameter perturbation methodsCLAUSSE, A; LAHEY, R. T. JR; PODOWSKI, M et al.International journal of heat and mass transfer. 1989, Vol 32, Num 11, pp 2055-2064, issn 0017-9310Article

Passive BWR integral LOCA testing at the Karlstein test facility INKADRESCHER, Robert; WAGNER, Thomas; LEYER, Stephan et al.VGB powertech. 2014, Num 5, pp 33-37, issn 1435-3199, 5 p.Article

Gamma ray dose rate measurements at a boiling water reactorLOBDELL, J. L; HERTEL, N. E.Radiation protection dosimetry. 1997, Vol 74, Num 3, pp 163-171, issn 0144-8420Article

Feedwater control system design with the Kuosheng plant analyzerSHIH-JEN WANG; SHIH-HSIIN CHANG; CHUN-SHENG CHIEN et al.Nuclear technology. 1995, Vol 109, Num 1, pp 153-160, issn 0029-5450Article

Perspective channel-type reactor with enhanced safetyADAMOV, E. O; GROZDOV, I. I; KUZNETSOV, S. P et al.Nuclear engineering and design. 1993, Vol 147, Num 1, pp 23-28, issn 0029-5493Article

Operating experience with BWR nuclear powerVON BONSDORF, M.Modern power systems. 1986, pp 15-17, issn 0260-7840, 2 p., suppl. marsArticle

Spécial TchernobylRevue générale nucléaire. 1986, Num 3, pp 258-286, issn 0335-5004Article

Etude de la répartition de la phase vapeur du fluide caloporteur dans un modèle de réacteur à eau bouillanteDROBKOV, V. P; KULAKOV, I. V; KHALMEH, M. V et al.Teploenergetika (Moskva, 1954). 1987, Num 4, pp 37-39, issn 0040-3636Article

Criteria for the selection of significant load conditions for fatigue analysis demonstrated at a BWR RPV componentKENNERKNECHT, H; HENKEL, F.-O.International journal of pressure vessels and piping. 1986, Vol 23, Num 3, pp 237-246, issn 0308-0161Article

Dilute chemical decontamination of BWR primary recirculation pipingHEMMINGS, R. L.Proceedings of the American Power Conference. 1985, Vol 47, pp 746-752, issn 0097-2126Conference Paper

Automatic boiling water reactor control rod pattern design using particle swarm optimization algorithm and local searchWANG, Cheng-Der; LIN, Chaung.Nuclear engineering and design. 2013, Vol 255, pp 273-279, issn 0029-5493, 7 p.Article

Signal reconstruction by a GA-optimized ensemble of PCA modelsBARALDI, P; ZIO, E; GOLA, G et al.Nuclear engineering and design. 2011, Vol 241, Num 1, pp 301-309, issn 0029-5493, 9 p.Article

Advanced neutronics tools for BWR design calculationsSANTAMARINA, A; HFAIEDH, N; LETELLIER, R et al.Nuclear engineering and design. 2008, Vol 238, Num 8, pp 1965-1974, issn 0029-5493, 10 p.Conference Paper

Benchmarking and qualification of the NUFREQ-NPW code for best estimate prediction of multichannel core stability marginsTALEYARKHAN, R. P; MCFARLANE, A. F; LAHEY, R. T et al.Nuclear engineering and design. 1994, Vol 151, Num 1, pp 157-171, issn 0029-5493Article

Applicability of pipelocks as a remedy for intergranular stress corrosion cracking in BWRsABEL, J. S; STRAIT, M. C; GILMAN, J et al.International journal of pressure vessels and piping. 1986, Vol 25, Num 1-4, pp 25-145, issn 0308-0161Article

Modeling and Analysis of Aging Behavior of Concrete Structures in Nuclear Power Plants : FONTEVRAUD 7: LES MATERIAUX DANS LE NUCLEAIRERASHID, Joseph Y. R; JAMES, Randy J; DUNHAM, Robert S et al.Revue générale nucléaire (Paris). 2011, Num 1, pp 115-126, issn 0335-5004, 12 p.Article

Fluid-to-fluid modeling of natural circulation boiling loops for stability analysisMARCEL, C. P; ROHDE, M; VAN DER HAGEN, T. H. J. J et al.International journal of heat and mass transfer. 2008, Vol 51, Num 3-4, pp 566-575, issn 0017-9310, 10 p.Article

Adding 250 MWe at oskarshamn 3AKHTAR, Amel.Modern power systems. 2007, Num SEP, pp 39-39, issn 0260-7840, 1 p.Article

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