Results 121 to 130 of about 302 (158)
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Probabilistic Strength Analysis of the Main Joint of a VVER-1000 Reactor
Atomic Energy, 2013A method of calculating the probability of a leak occurring in the main joint of the reactor and the probability of the head detaching from the vessel body of VVER-TOI as a result of stud-bolt failure and the computational results are presented. The stresses in the stud bolts are calculated taking account of their redistribution in intact stud bolts ...
P. V. Alekseev +5 more
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Uncertainty analysis of rod ejection accident in VVER-1000 reactor
Annals of Nuclear Energy, 2019Abstract In present work the coupling of neutronics code PARCS and thermo-hydraulics code TRACE was performed with adoption of GRS (Gesellschaft fur Anlagen- und Reaktorsicherheit) uncertainty method for rod ejection accident in VVER-1000 reactor core.
Bruno Miglierini +2 more
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PRIZMA predictions of in-core detection indications in the VVER-1000 reactor
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, 2014The paper describes calculations which were done by the PRIZMA code(1) to predict indications of in-core rhodium detectors in the VVER-1000 reactor for some core fragments with allowance for fuel and rhodium burnout.
Yadgar Z. Kandiev +4 more
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Irradiation capabilities of LR-0 reactor with VVER-1000 mock-up core
Applied Radiation and Isotopes, 2013Even low power reactors, such as zero power reactors, are sufficient for semiconductor radiation hardness effect investigation. This reflects the fact that fluxes necessary for affecting semiconductor electrical resistance are much lower than fluxes necessary to affect material parameters. The paper aims to describe the irradiation possibilities of the
Michal, Košťál +5 more
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Analysis of Severe Accidents in VVER-1000 Reactors Using the Integral Code ASTEC
Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 2009The studies presented are aiming at a detailed investigation of the behaviour of a VVER-1000/V-320 reactor and the containment structures during a postulated severe accident, including the ways and means by which these accidents may be prevented or mitigated. A hypothetical station blackout scenario (loss of the offsite electric power system concurrent
Tusheva, P. +5 more
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Simulation of mixing effects in a VVER-1000 reactor
Nuclear Engineering and Design, 2007Abstract This work has been performed in the framework of the OECD/NEA thermalhydraulic benchmark V1000CT-2. This benchmark is related to fluid mixing in the reactor vessel during a MSLB accident scenario in a VVER-1000 reactor. Coolant mixing in a VVER-1000 V320 reactor was investigated in plant experiments during the commissioning of the Unit 6 of ...
Bieder, U. +4 more
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Improvement of the axial power distribution control capabilities in VVER-1000 reactors
Annals of Nuclear Energy, 2000Abstract This article describes an automatic reactor power control system for VVER-1000 reactor and reports simulation analysis results for a typical daily load follow operation. The associated reactor control algorithm is called “mode G” that uses a heavy-worth bank (H-bank) dedicated to axial power shape control and the light-gray banks (G-banks ...
F. Yousefpour, M.B. Ghofrani
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Thermal-hydraulic noise analysis of a VVER-1000 reactor with nanofluid as coolant
Progress in Nuclear Energy, 2018Abstract The noise issue, especially in industrial scale systems including nuclear power plants, there has been always an interesting subject in system stability analysis. In this paper the effects of fluctuations in coolant temperature and velocity at the inlet of a fuel assembly of a VVER-1000 reactor with Al 2 O 3 nanofluid ...
Reza Nourollahi +2 more
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Flexible modeling complex for the operator support systems of UPP’s with VVER-1000 reactor
Automation and Remote Control, 2006zbMATH Open Web Interface contents unavailable due to conflicting licenses.
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Annular Fuel for Vver-1000 Reactor: Moderation Impact on Neutronic Behavior
Progress in Nuclear Energy, 2023Md Tanvir Ahmed, Afroza Shelley
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