WWER-1000
Swelling of the WWER-1000 Reactor Core Baffle
... We have performed swelling calculations for the WWER-1000 reactor core baffle using compiled for ANSYS User Subroutines. These calculations included detailed Stress-Strain Filed calculations with radiation ...
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Implementation the residual lifetime automatic control system (SACOR-320) in NPP Units with WWER-1000
... The experience of operation the residual lifetime automatic control system (SACOR-320) in NPP Units with WWER-1000 for three years and enhancement SACOR-320 functions on control material damage of ...
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Experimental Study of New Generation WWER-1000 Fuel Assemblies at JSC NCCP
... Expansion of the Russian nuclear fuel market and increase of nuclear fuel competitiveness require development of fuel assemblies (FAs) with improved operational characteristics. Serial WWER-1000 FA is a ...
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Performance Based Capacity Assessment of WWER-1000 Containment Structure for Internal Accidents
... The loads upon the structure in severe accident conditions are determined within the frames of PSA (Probabilistic Safety Analysis) Level 2 for WWER-1000 Unit. PSA Level 2 is the instrument for analysis of ...
8
Integrated Surveillance Specimen Program for WWER-1000/V-320 Reactor Pressure Vessels
... in WWER-1000/V-320 reactor pressure vessels have some deficiencies resulting from their design – nonuniformity of neutron field and even within individual specimen sets, large gradient in neutron flux ...
6
Study of Accident Progression in Unsealed WWER 1000/V320 Reactor during Maintenance
... In Bulgaria, the main regulatory requirements related to the safety analysis for NPP are specified by the Bul- garian nuclear legislation [3]. The regulation requires that NPP safety analysis shall be included all ...
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Aging Problems and Residual Life Time Evaluation of the WWER-1000 MW Containment Shell Structure
... The main goal of this paper is to generalize the specific aging problems and the residual life time evaluation of the WWER-1000 MW containment shell reinforced concrete structures of Unit 5 and 6 in ...
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Calculations of Fuel Rod Cladding Deformation for a Reactor Plant Wwer-1000 Under LB Loca (C180)
... of WWER-1000 RP for the analysis of design basis accident of LB LOCA type according to thermohydraulic computer code TRAP comprises several calculated channels into which the fuel rods with similar power ...
6
Analytical-and-Experimental Simulation of WWER-1000 Fuel Rod Behaviour under Initial Stage of LB LOCA at the Test Bench "Parameter"
... at WWER-1000 RP, also called as the first stage and characterized by quick variation of coolant parameters within the first 15÷20 s, is the least studied process of the accident ...in ...
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Calculational Analysis of WWER-1000 Fuel Assembly Operational Deformation (C179)
... The considered simplified model of deformation of separate FA and the model of contact interaction of FA ensemble formed the basis of computer code intended for calculation of behaviour of FA ensemble in the reactor ...
6
Seismic Qualification of Bubbler at WWER-1000 MW Type NPP
... The objective of the study is seismic qualification of already installed bubbler in operating WWER-1000 MW type NPP. The criteria of ASME code are applied. A series of finite element models are developed to ...
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Seismic Qualification of Heatexchanger at WWER-1000 MW Type NPP
... The objective of the study is seismic qualification of already installed heat exchanger and its supporting structure in operating WWER-1000 MW type NPP. The criteria of ASME code are applied both for the ...
8
Discussion on Practical Elimination of Early or Large Releases for WWER 1000/V320
... The Kozloduy NPP is used as an example for providing a discussion on “practic- al elimination” of early or large releases for NPP with a WWER-1000/V320 reactor types. A number of significant modifications ...
8
Dynamic Behavior and Functional Reliability of WWER 1000 Turbine Foundation
... The proposed paper reflects the main parts - the methodology and results, of a complex study on the dynamic behavior, serviceability and bearing capacity of 1000 MW turbine foundation at NPP “Kozloduy”. The study ...
15
Experience of Operating the Automatic System of Residual Service Life Monitoring for WWER-1000
... Gathering of the information consist in the organization of communication and transfer of the information from the Unit COMPUTER (UC) on a personal computer of the automated workplace (PC AWP) of SACOR-M. The ...
8
Frequency Response Analysis of NPP Containment with WWER-1000 Type Reactor
... In this paper we represent methods of frequency response analysis of the generating unit 1 (RO-1) reactor compartment at Kalininskaya NPP on the basis of technogenic vibration.. Main vi[r] ...
5
Seismic Evaluation of Containment Shell - WWER-1000 Type Reactor Building
... A global finite element model is used for investigation of the seismic response of the whole building structure.. This model describes all main parts of the reactor [r] ...
6
Upgrading of WWER-1000 NPP Safety on Spent Fuel Transportation (J106)
... Preliminary analysis has shown that in case of dropping down of a Cask from a height of 38.05 m on a floor of transportation corridor shall definitely cause more than 3 times overloadin[r] ...
8
Surveillance Specimen Programmes for WWER Reactor Vessels in the Czech Republic (D026)
... of WWER type reactors manufactured in Czech ...for WWER-440/V-213 type reactors is described and its deficiencies together with main results obtained are ...of WWER-1000/V-320 type reactor ...
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Key Elements of the Ageing Management of the WWER-440/213 Type Nuclear Power Plants
... The WWER-440/213 nuclear power plants in Central Europe were designed and constructed at the technical level of late seventies early ...of WWER units had been determined in great extent by the Soviet rules ...
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