VVER 1000
Fatigue assessment of vver-1000 core baffle
... Core baffle is important part of VVER 1000 reactor internals. Fatigue assessment of the core baffle was performed. At the first step, internal thermal sources due to gamma heating were calculated using TORT ...
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Changes to Irradiation Conditions of VVER-1000 Surveillance Specimens Resulting from Fuel Assemblies with Greater Fuel Height
... The analysis of the data in Table 2 shows that fuel assemblies of the new type with higher fuel rods cause a nearly 1.8-fold increase in the fast neutron flux in containers with surveillance specimens. This value was ...
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Estimation of thermal-hydraulic loading for VVER-1000 under severe accident scenario
... A VVER-1000 is a 3000 MWth pressure vessel type reactor with four-loop system. The reactor core consists of 163 hexahedral Fuel Assemblies (FAs) and each FA comprises 312 fuel elements and 18 control rods. ...
6
Determination of power density in VVER-1000 Mock-Up in LR-0 reactor
... Abstract. The pin power density is an important quantity which has to be monitored during the reactor operation, for two main reasons. Firstly, it is part of the limits and conditions of safe operation and, secondly, it ...
6
LBB Applicability Review and Basic Implementation Engineering for Primary Coolant Loop & Surge Line of VVER-1000/320 NPP: TACIS Project R2.09/96 (G383)
... the VVER 1000-320 Primary Circuit, Main Coolant Pipe (MCP) OD=990mm, thickness=70mm and Surge Line (SL), OD= 426mm, thickness 70mm (both including 5 mm of stainless steel cladding), the most similar Eastern ...
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Precise calculation of neutron-capture reactions contribution in energy release for different types of VVER-1000 fuel assemblies
... According to the results (Table 6) capture energy contribution in effective energy release depends on the fuel assembly’s type and varies starting from 3.35% to 3.79% for serial VVER-1000 fuel assemblies. ...
6
Estimation of material degradation of VVER-1000 baffle
... commercial VVER-1000 units were designed for 30 to 35 ...early VVER plants are now reaching and/or passing the 35-year ...the VVER-1000 mock-up in LR-0 ...
6
Comparative Analysis of VVER 1000 Westinghouse and TVEL Spent Fuel Capability
... on VVER-1000 spent fuel isotope composition caused by the different operational conditions, such as the presence or absence of absorber-rods, oscillating the concentration of boric acid, dissolved in the ...
5
Improvement Of Radiation Embrittlement Dependences For VVER-1000 Pressure Vessel Materials On Lifetime Extension
... Micrographic investigations of temperature SS sets [3-5] prove that on exposure to operation temperatures for up to 200,000 hours, an embrittlement mechanism takes effect in the VVER-1000 RPV material ...
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Fuzzy Automating Strategies of Emergency Operation for SGTR Accident in VVER 1000 Nuclear Reactor
... Abstract Steam generator tube rupture is one of the most important accidents that is focused nowadays. In this work, the automating strategies of emergency operation are developed for SGTR accident in VVER ...
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Validation of 3D Code KATRIN For Fast Neutron Fluence Calculation of VVER-1000 Reactor Pressure Vessel by Ex-Vessel Measurements and Surveillance Specimens Results
... on VVER-1000 reactor pressure vessel (RPV) for prognosis of radiation ...of VVER-1000 have upgraded surveillance ...the VVER-1000 core loading consists of fuel assemblies with ...
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The Effect of Burnup on Reactivity for VVER-1000 with MOXGD and UGD Fuel Assemblies Using MCNPX Code
... for VVER-1000 have been calculated by the Monte Carlo code (version MCNPX ...model VVER-1000 reactors with mixed-oxide (MOX) fuel, comparison is ...
11
Radiation Embrittlement of VVER-1000 RPV Steels
... of VVER-1000 surveillance programs are the most representative for radiation embrittlement evaluation of VVER-1000 RPV ...that VVER-1000 surveillance specimens were irradiated ...
9
Fast Neutron Transport in the Biological Shielding Model and Other Regions of the VVER-1000 Mock-Up on the LR-0 Research Reactor
... scale VVER- 1000 mock-up on the reactor LR-0 in order to validate neutron transport calculation methodologies and to perform the optimization of the shape and locations of neutron flux operation monitors ...
9
Ultimate Capacity Assessment of VVER 1000 Containment Structure
... Many investigators have been working on the subject of containment ultimate capacity assessment and serious progress has been achieved [1, 2, 3, 4]. One significant step forward has been the Cooperative Containment ...
8
Radiation Embrittlement of VVER-1000 Reactor Pressure Vessel Materials
... of VVER-1000 RPV weld metal in order to simplify the form of functional dependence and reduction of the number of adapted coefficients having taken into consideration the limitation of databases of research ...
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Safety Assessment of VVER-1000 PWR Type Containment Foundations
... The results of long-term field investigations and verifying analyses of structures’ beddings allowed to perform a prediction of structural degradation process of VVER-1000 type containments beddings. That ...
6
Assessment of irradiation swelling effects on VVER-1000 core shroud
... VVER-1000 core shroud is significant part of the reactor internals, made of austenitic stainless steel. It was designed to create external shroud of reactor core consisting of fuel assemblies. The ...
9
ON THE DEVELOPMENT OF CT-TYPE SPECIMEN FROM VVER-1000 SURVEILLANCE SPECIMEN MATERIALS RECONSTRUCTION PROCEDURE
... of VVER-1000 pressure vessels lifetime period up to 60 years or more, the methodology for reconstitution and testing the CT specimens out of broken Charpy or SE(B) specimen fragments was developed and ...
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Usage of Possibilistic Methods in Safety Assessment of VVER-1000 Concrete Containments
... The other concern about uncertainty propagation methods is their computational feasibility. The modern approaches based on sampling strategies (such as Monte-Carlo simulation of Latin hypercube sampling) usually require ...
8