Evaluation of Single Failure Effects During Loss of Coolant Accidents For A VVER-440 Reactor
نویسندگان
چکیده
This paper describes the results of an analysis of loss of coolant accidents (LOCA's) for the Soviet designed, light water cooled and moderated reactors referred to as VVERs. The VVER unit selected for this analysis is designated as VvER-440 Model 213. This plant generates 440 Mwe and is of current interest since meen are now operating and additional units are in various stages of construction within Eastern Europe and the New Independent States. In addition to the analysis of two b&e case LOCA's, this paper also presents the results of several sensitivity studies related to single failures in various plant systems that have been included in the design to mitigate the effects of LOCA's on plant and fuel system performance. Examples of the safety systems selected for these sensitivity studies include the scram system, the accumulatok, and the high pressure injection system.
منابع مشابه
Detailed Cfx-5 Study of the Coolant Mixing within the Reactor Pressure Vessel of a Vver-1000 Reactor during a Non-symmetrical Heat-up Test
As part of the reactor dynamics activities of FZK/IRS, the qualification of a detailed 3D CFD model of a reactor pressure vessel is a key step in safety evaluations for improving predictive capabilities and acceptability of commercial CFD tools in reactor physics. The VVER-1000 Coolant Transient Benchmark, initiated by OECD, represents an excellent opportunity for validation. In this work a CFD...
متن کاملThermo-Hydraulic Investigation of Nanofluid as a Coolant in VVER-440 Fuel Rod Bundle
The main purpose of this study is to perform numerical simulation of nanofluids as the coolant in VVER-440 fuel rod bundle. The fuel rod bundle contains 60 fuel rods with length of 960 mm and 4 spacer grids. In VVER-440 fuel rod bundle the coolant fluid (water) is in high pressure and temperature condition. In the present Thermo-hydraulic simulation, water-AL2O3 nanofluids containing various vo...
متن کاملInspection and Replacement of Baffle Former Bolts in VVER-440 Reactor Type
Reactor vessel internals are structures located within the reactor vessel that support and orient the reactor fuel assemblies and direct coolant flow through the core. The core basket is part of the internals structure, which consists of vertical plates that surround the outer faces of the hexagonal peripheral fuel assemblies. The vertical plates are bolted to the edges of horizontal former pla...
متن کاملStudy of thorium advanced fuel cycle utilization in light water reactor VVER-440
The first step in investigation of thorium fuel is evaluation of the results obtained from the spectral code for this type of fuel. The benchmark summarized by IAEA in 2003 was used for partial validation of the code HELIOS 1.9. The benchmark was focused on a comparison of the methods and basic nuclear data. Acceptable results of benchmark comparison allowed examining and comparing different ad...
متن کاملWORKSHOP ON AEROSOL BEHAVIOUR AND THERMAL- HYDRAULICS IN THE CONTAINMENT Organized by OECDNUCLEARENERGYAGENCY in collaboration with COMMISSION OF THE EUROPEAN COMMUNITIES and COMMISSARIAT A L'ENERGIE ATOMIQUE
Humid conditions are expected in the containment during severe LWR accidents. In these conditions steam can condense on the containment structures and on existing aerosol particles or new particles may be formed by water vapor nucleation. In this paper the relative importance of each of these phenomena is evaluated. A mechanistic approach (NAUA-HYGRDS code) by solving the aerosol General Dynami...
متن کامل