Results 231 to 240 of about 705,564 (243)

Subkanálová analýza aktivní zóny jaderného reaktoru VVER-1000

This master’s thesis deals with boiling crisis and with departure from nucleate boiling ratio. This thesis explains terms like the boiling crisis in nuclear reactors and the thesis deals with individual parameters of the reactor core, which have an impact on departure from nucleate boiling ratio.
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Management of the SBLOCA sequences with HPIS failure in VVER-1000/V320 reactors; comparison with Westinghouse PWR strategies

Progress in nuclear energy (New series)
E. Redondo-Valero, C. Queral, K. Fernández-Cosials, V. Sánchez-Espinoza, M. Sánchez-Perea, P. Groudev   +5 more
semanticscholar   +1 more source

Prediction of spent nuclear fuel isotopic composition for the VVER-1000 reactor utilizing regression tree

Annals of Nuclear Energy
Md. Tarequzzaman, Alexander Nakhabov
semanticscholar   +1 more source

3D analysis of spray effect on long-term depressurization of VVER-1000 containment during LB-LOCA

Progress in nuclear energy (New series)
Muhammet Enis Kanik, Omid Noori-kalkhoran, Massimiliano Gei, Kevin Fernández-Cosials   +3 more
semanticscholar   +1 more source

Accident Management Technology in VVER-1000

2006
D'AURIA, FRANCESCO SAVERIO, MELIKHOV O, SUSLOV A, BYKOV M, ELKIN I, ARANEO D, CHERUBINI M, DEL NEVO A, GIANNOTTI W, MUELLNER N.   +9 more
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Neutronic characteristics of the VVER-1000 fuel assembly with mechanical spectral shift regulation

Nuclear Engineering and Design
T. Elzayat, Y. Chertkov, O. Ashraf
semanticscholar   +1 more source

Assessment of loading scheme and moderation impact on minor actinide transmutation in VVER-1000 fuel assembly

Nuclear Engineering and Design
Md. Nobir Hosen, Md. Hossain Sahadath, H. R. K. Rohan   +2 more
semanticscholar   +1 more source

Experimental investigation of countercurrent flow limitation (CCFL) in a 1/19 scale of VVER-1000 geometry

Nuclear Engineering and Design
Aref Rahimian, E. Abedi, Seyed Khalil Mousavian, Masood Amin Mozafari, Seyed Mohammad Mirvakili   +4 more
semanticscholar   +1 more source

Posttest Calculations of Thermal-Hydraulic Conditions for Test Benches Simulating a Loss of Spent Fuel Pool Cooling Accident at BWR and VVER-1000/1200 Reactors

Thermal Engineering
N. V. Ivanova, M. M. Bedretdinov, O. E. Stepanov, A. G. Karetnikov, D. N. Moisin, C. Schuster   +5 more
semanticscholar   +1 more source

Modifikace utěsnění víka primárního kolektoru PG VVER 1000

Tato diplomová práce se zabývá záměnou těsnění víka primárního kolektoru parního generátoru reaktoru VVER 1000. Původní těsnění pomocí niklových kroužků je nahrazeno hřebenovým těsněním s expandovaným grafitem. V práci jsou srovnány vlastnosti obou typů těsnění a proveden výpočet nové i původní konfigurace přírubového spoje dle normy ČSN EN 1591 ...
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