Results 111 to 120 of about 311 (155)
Some of the next articles are maybe not open access.
Calculation with MCNP of capture photon flux in VVER-1000 experimental reactor
Radiation Protection Dosimetry, 2005The aim of this study is to obtain by Monte Carlo method the high energy photon flux due to neutron capture in the internals and vessel layers of the experimental reactor LR-0 located in REZ, Czech Republic, and loaded with VVER-1000 fuel. The calclated neutron, photon and photon to neutron flux ratio are compared with experimental measurements ...
Candan, Töre, Pedro, Ortego
openaire +2 more sources
Equilibrium thorium fuel loading in VVER-1000 reactor
Proceedings of the 2014 15th International Scientific Conference on Electric Power Engineering (EPE), 2014Thorium can be utilized in Pressurized Water Reactors (PWR) as ThO 2 fuel matrix supported by fissile materials. In this analysis, VVER-1000 reactor was taken as a representative of the PWR reactor group. The thorium fuel matrix was mixed with fissile material in form of pure 233U, enriched uranium (19.7 % enrichment) and Reactor-Grade plutonium ...
openaire +1 more source
Simulation of the Flow Rotation and Mixing in the Downcomer of a VVER-1000 Reactor
Nuclear Technology, 2007Flow rotation and mixing in a WER-1000 reactor is investigated using two system codes with three-dimensional fluid-dynamics modeling capabilities (RELAP5-3D and TRACE) and a computational fluid-dynamics (CFD) code (FLUENT). Coarse-mesh models were developed for the system codes, and their applicability is evaluated using the test data as well as the ...
Emilian Popov +3 more
openaire +1 more source
Study of in-vessel melt retention for VVER-1000/v320 reactor
Nuclear Engineering and Design, 2016Abstract This study aims to assess the applicability of the in-vessel melt retention (IVMR) strategy with external vessel water cooling to the reactors of VVER-1000/v320 type. IVMR strategy is one of the feasible solutions to mitigate reactor vessel failure and further fission products release to the containment and to the environment outside.
Gencheva, R. +4 more
openaire +1 more source
CFD Simulation of Slug Mixing in VVER-1000 Reactor
Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 2006Recently, the safety analyses of VVER and PWR reactors have dealt with the possibility of reactivity-induced accidents related to the penetration of a water slug with low boron concentration into the reactor core. Loop seals at the reactor coolant pump (RCP) suction are the most likely places for the formation of these slugs.
openaire +1 more source
Full-core reactor physics analysis for accident tolerant cladding in a VVER-1000 reactor
Annals of Nuclear Energy, 2021Abstract Advanced accident tolerant cladding materials have brought up the potential to delay the deleterious consequences of loos of coolant accidents related to slowing down hydrogen formation from reaction of zirconium with steam in order to minimize the additional heat generation and improve fuel and cladding retention of fission products.
O. Safarzadeh, M. Qarani-tamai
openaire +1 more source
Examination of VVER-1000 Reactor Pressure Vessel Head
2006This article presents examination VVER-1000 Reactor Pressure Vessel Head (RPVH). The scope of this examination includes the following: visual examination of RPVH interior as well as inside surface of penetration tube ; ultrasound examination of penetration tube from inner side and examination of J-weld area ; eddy current examination of inside surface ...
Pajnić, Mladen, Novosel, Dino
openaire +2 more sources
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
openaire +1 more source
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
openaire +1 more source
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
openaire +1 more source