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Fault diagnosis and classification based on wavelet transform and neural networkHADAD, Kamal; POURAHMADI, Meisam; MAJIDI-MARAGHI, Hosein et al.Progress in nuclear energy (New series). 2011, Vol 53, Num 1, pp 41-47, issn 0149-1970, 7 p.Article

Specification of a technical system to improve the operational monitoring of the Zaporosh'ye NPP by the state supervisory authority of the UkraineBEYER, M; CARL, H; LANGER, L et al.Symposium on nuclear reactor surveillance and diagnostics. 1995, 2Vol, vol.2, 14.3 [6 p.]Conference Paper

The calculation of main dynamic characteristics of core barrel for the VVER-1000GRIBKOV, V.Symposium on nuclear reactor surveillance and diagnostics. 1995, 2Vol, vol.2, 10.1 [2 p.]Conference Paper

A simulation of a steam generator tube rupture in a VVER-1000 plantNEMATOLLAHI, M. R; ZARE, A.Energy conversion and management. 2008, Vol 49, Num 7, pp 1972-1980, issn 0196-8904, 9 p.Conference Paper

Comparison of RELAP5 calculations of VVER-1000 coolant transient benchmark phase 1 at different powerSTEFANOVA, Antoaneta E; GROUDEV, Pavlin P.Progress in nuclear energy (New series). 2006, Vol 48, Num 8, pp 790-805, issn 0149-1970, 16 p.Conference Paper

Modelling effects and their impact on the results of ATHLET solutions of exercise 1 of the VVER-1000 Coolant Transient BenchmarkLANGENBUCH, S; HADEK, J; SCHMIDT, K.-D et al.Progress in nuclear energy (New series). 2006, Vol 48, Num 8, pp 912-921, issn 0149-1970, 10 p.Conference Paper

Probabilistic model for determining the operational lifetime of rod-shaped absorbing elements of a VVER-1000 reactorALEKSANDROV, D. A; GORLOV, V. N; CHERNYSHOV, V. M et al.Atomic energy (New York, N.Y.). 1997, Vol 82, Num 1, pp 16-20, issn 1063-4258Article

Problems of mathematical modelling of the thermohydraulic and water-chemistry processes in the steam generators of nuclear power stations with water-moderated water-cooled reactorsVORONOV, V. N; KRASNORYADTSEV, I. M.Thermal engineering. 1990, Vol 37, Num 10, pp 541-545, issn 0040-6015, 5 p.Article

HEXIRAN-SMABRE calculation of the VVER-1000 coolant transient-1 benchmarkSYRJÄLAHTI, Elina; HÄMÄLÄINEN, Anitta.Progress in nuclear energy (New series). 2006, Vol 48, Num 8, pp 849-864, issn 0149-1970, 16 p.Conference Paper

Etude et realisation des mesures visant a ameliorer la surete de l'exploitation et la duree de vie des générateurs de vapeur des centrales nucleaires avec les réacteurs du type VVER-1000 = Study and realization of methods of improvement of operating safety and lifetime of steam generators of VVER-1000 nuclear power plantsTITOV, V; TARANKOV, G; TCHERTOV, S et al.Fontevraud. Colloque international. 1998, pp 705-717, 2VolConference Paper

Advanced designs and operating strategies to enhance the safety, operability, and efficiency of VVER-1000 reactorsSECKER, J. R; MILLER, R. W; MAYHUE, L. T et al.Nuclear science and engineering. 1995, Vol 121, Num 1, pp 142-152, issn 0029-5639Article

Corrosion and mechanical strength of NPP material welded jointsTIMOFEEV, B. T; FEDOROVA, V. A.International journal of pressure vessels and piping. 1995, Vol 64, Num 1, pp 25-42, issn 0308-0161Article

Inbetriebnahme von Block 4 des Kernkraftwerkes Balachowo = Commmissioning of Unit4 of the Balachovo Nuclear power stationIPATOV, P; DISTLER, K; KEMMETER, H et al.Atw. Atomwirtschaft, Atomtechnik. 1994, Vol 39, Num 4, pp 290-293, issn 0365-8414Article

Essential experimental results of the CORA test program on severe core damage phenomenaHOFMANN, P; HAGEN, S; NOACK, V et al.Kerntechnik (1987). 1994, Vol 59, Num 4-5, pp 197-202, issn 0932-3902Article

Determination of the life and current stress state of elements of power equipment from parameters of the operating load with the use of methods of mathematical statisticsTIKHONOV, S. E; MAKHUTOV, N. A; KHURSHUDOV, G. KH et al.Strength of materials. 1990, Vol 22, Num 12, pp 1713-1719, issn 0039-2316Article

Radioactive release from VVER-1000 reactors after a terror attackSDOUZ, Gert.International journal of nuclear governance, economy and ecology (Print). 2007, Vol 1, Num 3, pp 305-311, issn 1742-4186, 7 p.Article

Analyses of the V1000CT-1 benchmark with the DYN3D/ATHLET and DYN3D/RELAP coupled code systems including a coolant mixing model validated against CFD calculationsKLIEM, S; KOZMENKOV, Y; HÖHNE, T et al.Progress in nuclear energy (New series). 2006, Vol 48, Num 8, pp 830-848, issn 0149-1970, 19 p.Conference Paper

Development of high-load water-lubricated radial-axial bearings for electric-pump units in the first loop of a nuclear power plantGERASIMOV, V. S; NIKIFOROV, S. A; PAUTOV, Yu. M et al.Atomic energy (New York, N.Y.). 2000, Vol 89, Num 6, pp 1027-1030, issn 1063-4258Article

Distribution of corrosion products in the steam-and-water circuit of a power-generating unit with water-moderated water-cooled VVER-1000 reactor during hydrazine water treatmentBYKOVA, V. V; ERPYLEVA, S. F; MAMET, V. A et al.Thermal engineering. 1991, Vol 38, Num 7, pp 356-359, issn 0040-6015Article

Simulation of the VVER-1000 pump start-up experiment of the OECD V1000CT benchmark with CATHARE and TRAC-PF1KOLEV, N; PETROV, N; IVANOV, B et al.Progress in nuclear energy (New series). 2006, Vol 48, Num 8, pp 922-936, issn 0149-1970, 15 p.Conference Paper

Methods for the evaluation of crack resistance of reactor P.V. materials under conditions of thermal shockTIMOFEEV, B. T; PETROV, V. A; KARZOV, G. P et al.International journal of pressure vessels and piping. 1992, Vol 52, Num 2, pp 159-175, issn 0308-0161Article

An adaptive system of automatic control of the level in the low-pressure heaters of the power units at nuclear power stationsROTACH, V. Ya; ZVER'KOV, V. P; KUZISHIN, V. F et al.Thermal engineering. 2001, Vol 48, Num 7, pp 580-587, issn 0040-6015Article

AFEN method and its solutions of the hexagonal three-dimensional VVER-1000 benchmark problemLEE, Jaejun; NAM ZIN CHO.Progress in nuclear energy (New series). 2006, Vol 48, Num 8, pp 880-890, issn 0149-1970, 11 p.Conference Paper

RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO2 fuel and mixed-oxide fuelHASSAN, Yassin A; CHUN FU.Nuclear technology. 2004, Vol 148, Num 3, pp 325-334, issn 0029-5450, 10 p.Article

Design and analysis of a thermal hydraulic integral test facility for Bushehr nuclear power plantKHOSHNEVIS, Toraj; JAFARI, Jalil; SOHRABPOUR, Mostafa et al.Progress in nuclear energy (New series). 2009, Vol 51, Num 3, pp 443-450, issn 0149-1970, 8 p.Article

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