Andrey Afanasiev, Victor Makarov, Leonid Lyakishev, Ivan Matvienko, Michail Puchkov, Dmitry Ivanov
|
|
- Clement Jones
- 6 years ago
- Views:
Transcription
1 SEISMIC AND HYDRODYNAMIC TESTS OF FA DUMMY AND SHEM-3 RCCA DRIVE FOR AES-2006 PROJECT IN A LARGE-SCALE TESTING FACILITY Andrey Afanasiev, Victor Makarov, Leonid Lyakishev, Ivan Matvienko, Michail Puchkov, Dmitry Ivanov Joint Stock Company"Experimental and Design Organization "GIDROPRESS", State Atomic Energy Corporation "Rosatom", Podolsk, , Moscow Region, Ordzhonikidze Str., 21, Russia. makarov@grpress.podolsk.ru Introduction The technical and economic indices of VVER reactor safety are largely defined by FA strength and stability under operational loads both under normal operating conditions and under anticipated operational occurrences, in particular, under OBE and SSE. The main requirements imposed on the reactor reactivity channels at NOC and SSE are as follows: - a possibility of a free drop of RCCA absorber rods in FA guide channels for reactor scram; - keeping component integrity; - a possibility of core unloading. The strength and stability of a FA with ShEM-3 RCCA drive is justified in experimental studies and analytical calculations. The results of experimental studies with full-scale dummies at testing facilities are the input data for computer code adjustment. Seismic tests of ShEM-3 RCCA drive were performed at OKB Gidropress seismic test facility in 2004 for the Bushehr NPP. The ShEM-3 RCCA drive was installed in a column on two supports, fastened to the test facility metalworks. The column vessel had two nozzles for water inlet and two nozzles for water outlet. The system of vibration loading for the FA with ShEM-3 RCCA drive comprised four vibrodynamic shakers. One shaker was placed at the bottom of the column to create a vertical dynamic input on AFA fuel assembly with RCCA drive and three shakers that created horizontal impacts were placed in the test facility metalworks at three different elevation marks in one vertical plane: at the level of reactor top head, at the level of nozzle-to-drive housing flange and at the level of PPI flange. Seismic input on reactivity control channel was simulated by applying a seismic signal to each of the shakers the signal being obtained by combining two harmonic signals (11 and 28,9 Hz). IAEA experts who reviewed the justification of strength and stability of a FA with ShEM-3 RCCA drive for the Bushehr NPP made comments to the methods of experimental studies, mainly to the above methods of dynamic impacts. The comments on the methods of dynamic impacts covered: - entire spectrum of seismic loads is to be simulated, not particular harmonics; - FA and drive horizontal vibration shall be two-component. Since the design of the test facility did not make it possible to get rid of the above deficiencies, a new largescale test facility for FA seismic and vibration tests was commissioned at the end of 2008 to perform experimental studies to justify AES-2006 fuel assembly. The new test facility allows seismic testing of FA assembled with ShEM- 3 RCCA drive to an improved methods that consider IAEA expert comments. Along with the seismic and vibration tests of AES-2006 FA assembled with ShEM-3 RCCA drive already implemented at the facility, similar tests of other designs of FAs will be carried out. Brief description of test facility for seismic stability tests of FA assembled with ShEM-3 RCCA drive Test facility for FA seismic and vibration studies is a multi-purpose test facility intended for experimental studies of dynamics and strength of AES-2006 and VVER-1000 FAs with ShEM-3 RCCA drive under the conditions of NOC, NOC+OBE and NOC+SSE to justify FA vibration strength of for VVER reactor safety. The facility contains the following main systems: - hydraulic system; - ShEM-3 RCCA drive with control rods and control system; - FA and drive vibration loading system; - vibration test measurement and control system; - process instrumentation; - framework. Hydraulic system is designed to create coolant flow through FA at a flowrate close to operating. The main hydraulic parameters of the test facility are: - coolant: water; - coolant temperature: up to 55 C;
2 3 - coolant flowrate through the column: up to 1200 mp P/h; - hydraulic circuit pressure: up to 1 MPa. Figure 1 provides the diagram of FA seismic and vibration test facility. The system of vibration loading (Figure 1) is designed to induce FA and drive vibration with amplitudes and at frequencies typical of the conditions of NOC, OBE and SSE. The system comprises six electrodynamic shakers installed in pairs at the angle of 90 at three elevation marks: at the level of top and bottom column flanges and at the level of drive support. Привод СУЗ ShEM-3M RCCA drive ШЭМ-3М Вибратор Shaker Чехол Drive привода housing Опора колонки Column support Проставка Insertion Опорная металлоконструкция Support metalwork Колонка Column Figure 1 FA seismic and vibration test facility
3 FA dummy is installed into the facility column that simulates standard conditions of FA fastening. The column (Figure 2) is a hexahedral prism with width across the flats dimensions (263±3) mm, which provides a possibility for not less than ±10 mm displacement of the middle part of FA. In the bottom and top flanges the facility column is provided with the inlet and outlet nozzles of lateral circulation of coolant. Instrumentation nozzle for dynamic pressure sensors, coolant velocity sensors etc. Laser vibrometer beam Windows FA dummy Figure 2 Column of the FA seismic and vibration test facility (viewed from the bottom) There are 18 transparent observation windows on the opposite facets of the column (9 windows on each one) to measure the vibration response of the fuel assembly and fuel rods with laser vibration meters. Instrumentation nozzles house dynamic pressure sensors, coolant velocity sensors etc. along the column axis. Objective, methods, scope and testing modes The purpose of seismic tests of FA and ShEM-3 drive with RCCA was a study of the correlation of the time and drop velocity versus such controlled factors as coolant pressure differential across the FA, time of scram signal since the beginning of the earthquake and a justification of seismic stability for ShEM-3 drive with RCCA for Novovoronezh NPP-2 site. A specific feature of the completed seismic tests is the methods of a real-time simulation of the calculated seismograms of FA and drive support accelerations. The shakers are controlled and monitored parameters (accelerations, shaker reaction force, fuel rod vibration rate, FA vibration response) are measured by a system that comprises Scadas III system unit, 36 measurement channels and a PC with dedicated computer software of LMS Test.Lab and Cada-X Time Waveform Replication (Belgium). With account for the actual frequency response functions of the facility design and mutual effect of the shakers given system makes it possible to reproduce the assigned time behavior of vibrations (accelerograms) in the assigned points of the structure. Thus, in the course of the tests at three elevation levels (column top and bottom supports, RCCA drive support) in two perpendicular directions calculated seismic loads were simultaneously simulated. The calculated accelerograms were obtained for Novovoronezh NPP-2 power unit. Figure 3 shows an example of calculated dependence of FA top support acceleration in Y-axis direction versus time (target accelerogram for MSK- 64 scale magnitude 7 earthquake). The duration of dynamic loading was 20 s.
4 t/s Figure 3 Correlation of FA top nozzle overloading coefficient in the direction of Y-axis versus time. Coolant temperature was the main difference between the in-pile conditions and the conditions in the facility. To estimate water temperature as one of the factors that influence the course of RCCA drop, RCCA drop was tested at WWER-1000 hot run-in test facility in the cold and hot conditions of its operation with the same pressure differential across the FA. The water properties in the cold conditions contribute to the drop time, on the average, 0,3 s. Thus, in the cold water tests such factors as Archimedes force and viscous friction contribute to RCCA friction force in comparison with hot water due to higher density and viscosity of coolant, i.e. the tests are conservative. Coolant flowrate in the test facility was assigned to provide pressure differential across FA (176±5) kpa. Pressure differential across the FA, equal to 176 kpa, corresponds to the top calculated value of pressure differential across the core of reactor plant V-392M. The experiment matrix is shown in Table 1. A number of drops were made with a delay of (1-11) seconds after the beginning of seismic impact simulation to consider the effect of the time of scram signal generation. Table 1. Experiment matrix Site NV NPP-2 Earthquake magnitude SSE, magnitude 7 No seismic loading Drop height, m 3,80 3,62 3,80 Pressure differential across FA, kpa Number of drops
5 Experimental results Figure 4 shows an example of a dependence of FA top support acceleration in X-axis direction versus time (target accelerogram) calculated for Novovoronezh NPP-2 power unit and the dependence of accelelration versus time, obtained in the experiment. The difference in the plots of the measured acceleration (shown in red) and the target seismogram (shown in blue) do not exceed 10 % F Time Measurement resp:4_meas_filt F Time Target resp:4 (3) B Time Magnet resp:7current Acceleration, m/sp (m/s2) Real Fixing magnet current, rel. unitsp Amplitude V s Time, s F Time Measurement resp:4_meas_filt 3.00 F Time Target resp:4 (3) Acceleration, m/sp (m/s2) Real Amplitude Time, s Figure 4 Acceleration of FA top support versus time
6 Figure 5 shows the spectrum of FA top support accelerations. In the frequency range up to 400 Hz, in acceleration spectra in the six points of load application a strong harmonic with the frequency of 148,6 Hz is observed, which is close to the circulation pump blade frequency. The fact that the harmonic with the frequency of 148,6 Hz is the pump blade frequency is supported by the decrease of the frequency of this harmonic during the coastdown following the pump trip F Spectrum unfiltresp:3:+y g Vibration acceleration Amplitude amplitude, g Figure 5 Spectrum of FA top support accelerations In the course of the tests the scram signal was sent with a delay from 2 to 10 s with a 2-second step after the beginning of seismogram representation with an error of ±1 s. The tests resulted in defining the total time of RCCA rods drop that is equal to the time interval for rod passage between the upper and lower limit switches, and for some conditions also the time for rod to pass certain areas. All-in-all, there were 15 drops of RCCA rods under different testing conditions and modes. Table 2 shows the effect of earthquake on the RCCA rod drop time. Table 2 The effect of earthquake on RCCA rod drop time Pressure differential, kpa Drop height, m Frequency, Hz Drop time, s No seismic loading SSE, magnitude 7 3,8 1,977 2,925 3,8 1,981 2,459 3,8 1,985 2,726 3,8-2,873 3,8-3,101 3,8-2,799 3,8-2,494 3,8-2,937 3,8-2,901 Average 1,981 2,802 It is seen in the Table that an earthquake increases the RCCA rod drop time, on the average, by 0,82 s. The factor of time between the seismogram start-up and scram signal, in the range of 2-10 s does not make considerable effect on the RCCA rod drop time. It is concluded from Figure 6 that provides the dependence of RCCA rod drop time versus delay time.
7 RCCA rod drop time, s Scram signal delay, s Figure 6 - Dependence of RCCA rod drop time versus scram signal delay time The results of tests to define the natural frequencies, shapes, and damping factors of FAs are shown in Table 4. The tests were performed in the air, in stagnant water and in coolant flow. In the tests in coolant flow the natural oscillations were studied at exciting broadband vibrations (white noise) and at harmonic support vibrations with 2 frequency sweep and at constant amplitude of 0,02 m/sp P. Table 3 Characteristics of natural oscillations the air, in stagnant water and coolant flow Frequency, Hz Damping coefficient, % of critical Shape Stagnant Flowrate, Stagnant Flowrate, Air 3 Air 3 water 300 mp P/h water 300 mp P/h Bending mode 1 5,3 4,3 4,0 1,1 4,7 12,2 Bending mode 2 10,8 9,6 9,2 2,2 3,6 10,9 Bending mode 3 17,5 14,9-1,1 2,9 - Bending mode 4 23,1 20,1-0,7 2,9 - It concluded from a comparison of FA modal characteristics in the air, in stagnant water and in coolant flow that in stagnant water the frequencies of natural oscillations are decreased by % and the damping coefficients 3 increase three times, on the average. In coolant flow with the flowrate through the FA of 300 mp P/h in comparison with stagnant water the natural frequencies further decrease by 0,3-0,4 Hz and the damping factors increase three times, on the average.
8 Conclusions 1. A programme and methods of seismic and hydrodynamic tests of AES-2006 FA with ShEM-3 RCCA drive was developed. 2. Seismic tests were performed for ShEM-3 RCCA drive and AES-2006 FA for seismic stability in a simulated magnitude 7 earthquake calculated for the sites of NVNPP drops of RCCA rods were performed at pressure differential across the FA of 176 kpa, equal to the maximum calculated value of pressure differential across the core of reactor plant V-392M. 2. In the drops with SSE simulation (pressure differential 176 MPa) the RCCA rod drop time was from 2,46 s to 3,10 s (on the average, 2,80 s), which does not exceed the design requirement of 4,0 s for the maximum drop time. SSE simulation (magnitude 7) on FA supports and ShEM-3 RCCA drive support leads to an increase in the average RCCA rod drop time by 0,82 s. 3. Vibration response of FA to the applied seismic impact was determined. FA displacement amplitude was found to be less than the amplitude of support displacement 1,3 3 times. 4. The tests performed have shown that the seismic stability of ShEM-3 RCCA drive and AES-2006 FA is ensured. 5. A study of AES-2006 FA dummy natural oscillations in stagnant water and in coolant flow were performed. 6. Frequencies, shapes and damping coefficients of natural oscillations were determined. The frequencies of natural and forces oscillations of FA as a single structure decease to 23% (for bending mode 1) at transition from air to stagnant water and to 7,5% (in comparison with the stagnant water) as coolant flowrate through the FA increases. The natural oscillation damping factors increase 4,3 times (for bending mode 1) at transition from air to stagnant water and 2,6 times (in comparison with stagnant water) at coolant flowrate increase through the FA. At coolant 3 flowrate through the FA of about 500 mp P/h the damping factors of particular vibration modes are by an order higher than those in the air.
Seismic Non-linear analysis of Polar Crane Alexander Schukin, Maxim Vayndrakh
Seismic Non-linear analysis of Polar Crane Alexander Schukin, Maxim Vayndrakh CKTI Vibroseism, Saint Petersburg, Russia ABSTRACT One of the requirements for Safe Design of NPP is that structures, systems,
More informationResponse Analysis of an RC Cooling Tower Under Seismic and Windstorm Effects D. Makovička
Response Analysis of an RC Cooling Tower Under Seismic and Windstorm Effects D. Makovička The paper compares the RC structure of a cooling tower unit under seismic loads and under strong wind loads. The
More informationProfile LFR-62 SGI RUSSIA. Facility SGI for studies of thermohydraulic characteristics of FACILITY. atomic power plants.
Profile LFR-62 SGI RUSSIA General information NAME OF THE Facility SGI for studies of thermohydraulic characteristics of FACILITY atomic power plants. ACRONYM SGI Coolant technology Water LOCATION (address)
More informationExperimental Structural Mechanics & Piping Vibration issues at Loviisa NPP. Pekka Nurkkala/ Fortum/ Turbine & Generator Solutions
Experimental Structural Mechanics & Piping Vibration issues at Loviisa NPP Pekka Nurkkala/ Fortum/ Turbine & Generator Solutions Loviisa Nuclear Power Plant Loviisa NPP has two reactor units: PWR-type
More informationHeat exchanger equipment of TPPs & NPPs
Heat exchanger equipment of TPPs & NPPs Lecturer: Professor Alexander Korotkikh Department of Atomic and Thermal Power Plants TPPs Thermal power plants NPPs Nuclear power plants Content Steam Generator
More informationVALLIAMMAI ENGINEERING COLLEGE DEPARTMENT OF CIVIL ENGINEERING SUBJECT CODE: CE6701 SUBJECT NAME: STRUCTURAL DYNAMICS AND EARTHQUAKE ENGINEERING YEAR : IV SEM : VII QUESTION BANK (As per Anna University
More information2.15 Tokamak Seismic Analysis
2.15 Tokamak Seismic Analysis 2.15.1 Introduction 1 2.15.2 Input Conditions 3 2.15.2.1 Design Response Spectra 3 2.15.2.2 Damping Coefficients 4 2.15.3 Model Overview 4 2.15.4 Main Results Under SL-2 Seismic
More informationADAPTATION OF HIGH VISCOUS DAMPERS (HVD) FOR ESSENTIAL DECREASING OF IN-STRUCTURE FLOOR RESPONSE SPECTRA
18th International Conference on Structural Mechanics in Reactor Technology (SMiRT 18) Beijing, China, August 7-12, 2005 SMiRT18-K11-6 ADAPTATION OF HIGH VISCOUS DAMPERS (HVD) FOR ESSENTIAL DECREASING
More informationComputerized monitoring system of residual cyclic life of WWER RP equipment
Computerized monitoring system of residual cyclic life of WWER RP equipment The computerized monitoring system of residual cyclic life (SACOR-M) is intended for in-service calculation of cumulative fatigue
More informationRELAP5/MOD3.2 INVESTIGATION OF A VVER-440 STEAM GENERATOR HEADER COVER LIFTING
Science and Technology Journal of BgNS, Vol. 8, 1, September 2003, ISSN 1310-8727 RELAP5/MOD3.2 INVESTIGATION OF A VVER-440 STEAM GENERATOR HEADER COVER LIFTING Pavlin P. Groudev, Rositsa V. Gencheva,
More informationStatus report VVER-1200 (V-491) (VVER-1200 (V-491))
Status report 108 - VVER-1200 (V-491) (VVER-1200 (V-491)) Overview Full name Acronym Reactor type Coolant Moderator Neutron spectrum Thermal capacity Gross Electrical capacity Design status Designers VVER-1200
More informationThe influence of vertical seismic ground motion on structures with uplift
The influence of vertical seismic ground motion on structures with uplift K.D. Makan, Y. Chen, T. Larkin & N. Chouw Department of Civil and Environmental Engineering, The University of Auckland, New Zealand.
More informationSafety Analysis Results of Representative DEC Accidental Transients for the ALFRED Reactor
FR13 - TECHNICAL SESSION 3.5: Fast reactor safety: post-fukushima lessons and goals for next-generation reactors Paper n. IAEA-CN-199/260 Safety Analysis Results of Representative DEC Accidental Transients
More informationDesign, Safety Technology and Operability Features of Advanced VVERs
Technical Cooperation Project INT/4/142 Interregional Workshop on Advanced Nuclear Reactor Technology for Near Term Deployment IAEA Headquarters, Vienna, Austria, 4-8 July 2011 Design, Safety Technology
More informationFloating Type Isolation System Using Earthquake Early Warning
Floating Type Isolation System Using Earthquake Early Warning K. Minagawa Saitama Institute of Technology, Saitama S. Fujita Tokyo Denki University, Tokyo G. Tanaka Oiles Corporation, Tochigi H. Simosaka
More informationDepartment of Civil Engineering, SKP Engg. College, Tiruvanamalai, TN, India
DESIGN AND ANALYSIS OF MULTI- STOREYED BUILDING UNDER STATIC AND DYNAMIC LOADING CONDITIONS USING ETABS Balaji.U. A 1, Mr. Selvarasan M.E. B 2 1 PG Student, 2 Asst.Professor Department of Civil Engineering,
More informationSEISMIC DESIGN OF STRUCTURE
SEISMIC DESIGN OF STRUCTURE PART I TERMINOLOGY EXPLANATION Chapter 1 Earthquake Faults Epicenter Focal Depth Focus Focal Distance Epicenter Distance Tectonic Earthquake Volcanic Earthquake Collapse Earthquake
More informationRosatom Seminar on Russian Nuclear Energy Technologies and Solutions
ROSATOM STATE ATOMIC ENERGY ОАО CORPORATION «ТВЭЛ» - российский ROSATOM производитель ядерного топлива Nuclear fuel for VVER-1200 Rosatom Seminar on Russian Nuclear Energy Technologies and Solutions L.T.
More informationCHAPTER III DYNAMIC BEHAVIOR OF A LABORATORY SPECIMEN
CHAPTER III DYNAMIC BEHAVIOR OF A LABORATORY SPECIMEN To address the vibration response of a long span deck floor system, an experiment using a specimen that resembles the conditions found in the in-situ
More informationDevelopment of 3D Seismic Isolation Technology for Advanced Nuclear Power Plant Application
GENES4/ANP2003, Sep. 15-19, 2003, Kyoto, JAPAN Paper 1110 Development of 3D Seismic Isolation Technology for Advanced Nuclear Power Plant Application Masaki Morishita 1*, Seiji Kitamura 1, Satoshi Moro
More informationDynamic Analysis of Large Steel Tanks
Transactions of the 17 th International Conference on Structural Mechanics in Reactor Technology (SMiRT 17) Prague, Czech Republic, August 17 22, 2003 Paper # K14-1 Dynamic Analysis of Large Steel Tanks
More informationTechnical University of Sofia, Department of Thermal and Nuclear Power Engineering, 8 Kliment Ohridski Blvd., 1000 Sofia, Bulgaria
BgNS TRANSACTIONS volume 20 number 2 (2015) pp. 143 149 Comparative Analysis of Nodalization Effects and Their Influence on the Results of ATHLET Calculations of VVER-1000 Coolant Transient Benchmark Phase
More informationSynopsis - The Comprehensive Vibration Assessment Program (CVAP) for AP1000 Reactor Internals
Synopsis - The Comprehensive Vibration Assessment Program (CVAP) for AP1000 Reactor Internals Gregory A. Banyay Gregory A. Meyer CAV WORKSHOP Wednesday, April 30 th, 2014 1 Outline Background of CVAP AP1000
More informationCONTROL EFFECT OF LARGE TUNED MASS DAMPER APPLIED TO EXISTING HIGH-RISE BUILDING FOR SEISMIC RETROFIT
17th U.S.-Japan-New Zealand Workshop on the Improvement of Structural Engineering and Resilience CONTROL EFFECT OF LARGE TUNED MASS DAMPER APPLIED TO EXISTING HIGH-RISE BUILDING FOR SEISMIC RETROFIT N.
More informationDevelopment of Cylindrical Passive Damper using High Damping Rubber
Development of Cylindrical Passive Damper using High Damping Rubber Nobuyoshi YAMAGUCHI Building Research Institute Japan Masato NAKAO Tomoki FURUTA National University of Yokohama, Daiichi Institute of
More informationModule 05 WWER/ VVER (Russian designed Pressurized Water Reactors)
Module 05 WWER/ VVER (Russian designed Pressurized Water Reactors) 1.3.2016 Prof.Dr. Böck Technical University Vienna Atominstitut Stadionallee 2, 1020 Vienna, Austria ph: ++43-1-58801 141368 boeck@ati.ac.at
More informationDYNAMIC CHARACTERISTICS ASSESSMENT OF STEEL BEAM-COLUMN CONNECTIONS WITH FLOOR SLAB
10NCEE Tenth U.S. National Conference on Earthquake Engineering Frontiers of Earthquake Engineering July 21-25, 2014 Anchorage, Alaska DYNAMIC CHARACTERISTICS ASSESSMENT OF STEEL BEAM-COLUMN CONNECTIONS
More informationLight Water Reactor in Russia
ROSATOM STATE CORPORATION ON NUCLEAR ENERGY ROSATOM Light Water Reactor in Russia Presented M.A.Bykov OKB GIDROPRESS 17 th TWG-LWR Meeting, Vienna, 18-20 June 2012 NPP Electricity Generation in Russia
More informationSeismic Sloshing in a Horizontal Liquid-Storage Tank
To appear in the Journal of Structural Engineering International Seismic Sloshing in a Horizontal Liquid-Storage Tank Praveen K. Malhotra, Parag Nimse and Michael Meekins Summary A horizontal water storage
More informationNEUTRON PHYSICS CALCULATION FOR VVER-1000 ABSORBER ELEMENT LIFETIME DETERMINATION ABSTRACT
NEUTRON PHYSICS CALCULATION FOR VVER-1000 ABSORBER ELEMENT LIFETIME DETERMINATION K.Yu. Kurakin, S.A. Kushmanov OKB GIDRORESS ABSTRACT Absorber element (AE) with compound absorber has been operating in
More informationMETHODS OF CALCULATION OF THE REACTOR BUILDING WITH SEISMIC ISOLATION SYSTEM UNDER DYNAMIC LOADS
Transactions, SMiRT-22 METHODS OF CALCULATION OF THE REACTOR BUILDING WITH SEISMIC ISOLATION SYSTEM UNDER DYNAMIC LOADS Peter Vasilyev 1 1 Principal, CKTI-Vibroseism, Saint Petersburg, Russia (peter@cvs.spb.su)
More informationScenarios of Heavy Beyond-Design-Basis Accidents in HTGRs N.G. Kodochigov, Yu.P. Sukharev
Scenarios of Heavy Beyond-Design-Basis Accidents in HTGRs N.G. Kodochigov, Yu.P. Sukharev IAEA Technical Meeting on the Safety of High Temperature Gas Cooled Reactors in the Light of the Fukushima Daiichi
More informationDESIGN AND SAFETY PRINCIPLES LEONTI CHALOYAN DEPUTY CHIEF ENGINEER ON MODERNIZATION
DESIGN AND SAFETY PRINCIPLES LEONTI CHALOYAN DEPUTY CHIEF ENGINEER ON MODERNIZATION VIENNA OKTOBER 3-6, 2016 1 ANPP * ANPP is located in the western part of Ararat valley 30 km west of Yerevan close to
More informationSEISMIC DESIGN CHARACTERISTICS OF THE NEW BUILDING FOR DIGITAL AUTOMATION EQUIPMENT FOR LOVIISA NUCLEAR POWER PLANT
13 th World Conference on Earthquake Engineering Vancouver, B.C., Canada August 1-6, 2004 Paper No. 2803 SEISMIC DESIGN CHARACTERISTICS OF THE NEW BUILDING FOR DIGITAL AUTOMATION EQUIPMENT FOR LOVIISA
More informationInnovations and Safety Ensuring in WWERs on the Base of Collaboration on the National and International Levels
IAEA INPRO DF9, Vienna 21 November 2014 Innovations and Safety Ensuring in WWERs on the Base of Collaboration on the National and International Levels Grigory Ponomarenko OKB GIDROPRESS Podolsk, Russian
More informationStatus report 85 - VVER-1500 (V-448) (VVER-1500 (V-448))
Status report 85 - VVER-1500 (V-448) (VVER-1500 (V-448)) Overview Full name Acronym Reactor type Coolant Moderator Neutron spectrum Thermal capacity Gross Electrical capacity Design status Designers VVER-1500
More informationLiterature Review of Wood-frame Structure Tests
CHAPTER 2 Literature Review of Wood-frame Structure Tests This dissertation focuses on the investigative process of extracting dynamic characteristics of wood-frame structures from measured seismic response.
More informationSTUDYING THE EFFECT OF EARTHQUAKE EXCITATION ANGLE ON THE INTERNAL FORCES OF STEEL BUILDING S ELEMENTS BY USING NONLINEAR TIME HISTORY ANALYSES
STUDYING THE EFFECT OF EARTHQUAKE EXCITATION ANGLE ON THE INTERNAL FORCES OF STEEL BUILDING S ELEMENTS BY USING NONLINEAR TIME HISTORY ANALYSES Mahmood Hosseini 1 and Ali Salemi 2 1 Associate Professor,
More informationResponse Behaviour of a Three Storied Framed Structure with Tuned Liquid Damper
Response Behaviour of a Three Storied Framed Structure with Tuned Liquid Damper Namrata Yannawar 1, G.R.Patil 2 P.G. Student, Department of Civil Engineering, Rajashri Shahu College of Engineering, Pune,
More informationVerification of VVER-1200 NPP Simulator in Normal Operation and Reactor Coolant Pump Coast-Down Transient
World Journal of Engineering and Technology, 2017, 5, 507-519 http://www.scirp.org/journal/wjet ISSN Online: 2331-4249 ISSN Print: 2331-4222 Verification of VVER-1200 NPP Simulator in Normal Operation
More informationDynamic Design of the Foundation of Reciprocating Machines for Offshore Installations in Persian Gulf
Dynamic Design of the Foundation of Reciprocating Machines for Offshore Installations in Persian Gulf Mohammad AHANGAR Univrsity Of Tehran, Mohammad_ahangar_84@yahoo.com Hesam Sharifian JAZE Univrsity
More informationDesign of buildings using EC8
Design of buildings using EC8 & 1 can be applied to all buildings and is obligatory for buildings which do not satisfy the regularity criteria specified by EC8. The response of all modes of vibration contributing
More informationSeismic Damage-Resistant System for Multi-Storey Modular Light Steel Framed Buildings
Seismic Damage-Resistant System for Multi-Storey Modular Light Steel Framed Buildings John Jing 1 and G. Charles Clifton 2 1. Structural Engineer, BSc., BE Civil (Hons.) and PhD (Civil), Harrison Grierson
More informationSeismic Collapsing Process Analysis of One-story Thatched Roof Wooden Structure under Strong Earthquake Ground Motion
5:2 (216) Journal of Civil Engineering and Construction Seismic Collapsing Process Analysis of One-story Thatched Roof Wooden Structure under Strong Earthquake Ground Motion Tomiya Takatani 1, Hayato Nishikawa
More informationOn the Vibration Mechanism of Historical Menar-Jonban Monument in Iran
On the Vibration Mechanism of Historical Menar-Jonban Monument in Iran Naghdali Hosseinzadeh Structural Engineering Research Center, International Institute of Earthquake Engineering and Seismology (IIEES),
More informationControl of Earthquake Resistant High Rise Steel Frame Structures
Control of Earthquake Resistant High Rise Steel Frame Structures A K Datta a,*, S Sivaprasad a, a CSIR-National Metallurgical Laboratory, Jamshedpur-831007, India e-mail: akd@nmlindia.org P Prasad b b
More informationSeismic Analysis of an SPB Tank Installed in the Offshore GBS LNG Terminal
Vol. 4 No. 2 August 27 Seismic Analysis of an SPB Tank Installed in the Offshore GBS LNG Terminal MANABE Hideo : Manager, Project Engineering Department, Engineering Division, IHI Marine United Inc. SAKURAI
More informationVVER-440/213 - The reactor core
VVER-440/213 - The reactor core The fuel of the reactor is uranium dioxide (UO2), which is compacted to cylindrical pellets of about 9 height and 7.6 mm diameter. In the centreline of the pellets there
More informationdpipe Version 5.26 Calculation sample and recommended sequence for entering input data
dpipe Version 5.26 Calculation sample and recommended sequence for entering input data Россия, Санкт-Петербург, 195220, ул. Гжатская, 9 литер А, www.cvs.spb.ru Тел./факс: +7 (812) 327-85-99. E-mail: cvs@cvs.spb.su
More informationStress analysis of reciprocating pump pipeline system in oil station
Available online www.jocpr.com Journal of Chemical and Pharmaceutical Research, 2014, 6(7):2026-2032 Research Article ISSN : 0975-7384 CODEN(USA) : JCPRC5 Stress analysis of reciprocating pump pipeline
More informationOsamu Takahashi, Hiromasa Aida 1 Junji Suhara, Ryoichiro Matsumoto 2 Yasuo Tsuyuki 3 Takafumi Fujita 4. Kozo Keikaku Engineering 2
The th World Conference on Earthquake Engineering October -7, 8, Beijing, China Construction of Civil Building Using Three Dimensional Seismic Isolation System (Part, Design of Building Using Three Dimensional
More informationTIME HISTORY RESPONSE PREDICTION FOR MULTI-STOREY BUILDINGS UNDER EARTHQUAKE GROUND MOTIONS
Journal of Civil, Structural, Environmental, Water resources and Infrastructure Engineering Research (JCSEWIER)) Vol.2, Issue 2 June 2012 16-23 TJPRC Pvt. Ltd., TIME HISTORY RESPONSE PREDICTION FOR MULTI-STOREY
More informationUp-to-date issues of VVER Technology Development
Up-to-date issues of VVER Technology Development 10 th International Scientific and Technical Conference Safety, Efficiency and Economics of Nuclear Power industry JSC Concern Rosenergoatom May 25-27,
More informationSEISMIC QUALIFICATION OF THE EQUIPMENT FOR LOVIISA PLANT AUTOMATION RENEWAL PROJECT
SEISMIC QUALIFICATION OF THE EQUIPMENT FOR LOVIISA PLANT AUTOMATION RENEWAL PROJECT P. Varpasuo Fortum Nuclear Services Ltd., Espoo, Finland ABSTRACT This paper describes the seismic qualification methods
More informationEffect of plastic hinge, soil nonlinearity and uplift on earthquake energy in structures
Effect of plastic hinge, soil nonlinearity and uplift on earthquake energy in structures M. Sarrafzadeh, E. Lim, X. Qin & N. Chouw Department of Civil and Environmental Engineering, the University of Auckland,
More informationnuclear science and technology
EUROPEAN COMMISSION nuclear science and technology Fast-Acting Boron Injection System (FABIS) Contract No: FIKS-CT-2001-00195 Final report (short version) Work performed as part of the European Atomic
More informationPerformance Improvement on Water-cooled Cold-Plate
Proceedings of the 4th WSEAS International Conference on Heat and Mass Transfer, Gold Coast, Queensland, Australia, January 17-19, 2007 104 Performance Improvement on Water-cooled Cold-Plate SHYAN-FU CHOU,
More informationModal-spectral analysis of a gas storage tank.
Modal-spectral analysis of a gas storage tank. Description of the structure: A Spherical tank gas storage is formed by: 1.- S-355 steel sphere plate elements of 1.5 cm thickness. 2.- Eight vertical posts
More informationIMPLEMENTATION AND OPERATION EXPERIENCE OF URANIUM FUEL ASSEMBLIES WITH BURNABLE ABSORBER AND CLUSTER CONTROL RODS AT THE IGNALINA NPP
IMPLEMENTATION AND OPERATION EXPERIENCE OF URANIUM FUEL ASSEMBLIES WITH BURNABLE ABSORBER AND CLUSTER CONTROL RODS AT THE IGNALINA NPP Saulius Stravinskas, Nikolajus Lebedevichius, Aleksej Tarasov, Georgy
More informationSEISMIC COLLAPSING BEHAVIOUR OF ONE-STORY WOODEN STRUCTURE WITH THATCHED ROOF UNDER STRONG EARTHQUAKE GROUND MOTION
SEISMIC COLLAPSING BEHAVIOUR OF ONE-STORY WOODEN STRUCTURE WITH THATCHED ROOF UNDER STRONG EARTHQUAKE GROUND MOTION Tomiya Takatani 1, * and Hayato Nishikawa 2 1 National Institute of Technology (NIT),
More informationSpecific Design Consideration of ACP100 for Application in the Middle East and North Africa Region
Specific Design Consideration of ACP100 for Application in the Middle East and North Africa Region IAEA Technical Meeting on Technology Assessment of Small Modular Reactors for Near Term Deployment 2 5
More informationIn Vessel Retention Strategy VVER 1000/320 VVER 2013 Conference
ÚJV Řež, a. s. In Vessel Retention Strategy VVER 1000/320 VVER 2013 Conference J. Zdarek Presentation content Background of SA issues VVER 1000/320 Containment and RPV Cavity Configuration IVR Strategy
More informationSERIES SEISMIC ENGINEERING RESEARCH INFRASTRUCTURES FOR EUROPEAN SYNERGIES
SEVENTH FRAMEWORK PROGRAMME Capacities Specific Programme Research Infrastructures Project No.: 227887 SERIES SEISMIC ENGINEERING RESEARCH INFRASTRUCTURES FOR EUROPEAN SYNERGIES Work package [WP8 TA4 EQUALS]
More informationSeismic Considerations of Circuit Breakers
Seismic Considerations of Circuit Breakers Willie Freeman, IEEE 693 Working Group ABB Inc, Mt. Pleasant PA, USA IEEE Tutorial - 2008 Abstract: The tutorial covers the seismic qualification of high voltage
More informationPipe Stress Analysis Where Do I Start?
Pipe Stress Analysis Where Do I Start? This is a step-by-step logic guideline for the data collection effort that should occur prior to beginning to model a piping system for a stress analysis: TRIFLEX
More informationAbstract. 1. Introduction
Building monitoring during the partial implosion stage J. Garcés 1, J.C. Botero 1, D. Murià-Vila 2 (1) Universidad EAFIT - Colombia, (2) Instituto de Ingeniería- UNAM México Abstract The partial collapse
More informationTURBO GENERATOR MACHINE FOUNDATIONS SUBJECTED TO EARTHQUAKE LOADINGS
TURBO GENERATOR MACHINE FOUNDATIONS SUBJECTED TO EARTHQUAKE LOADINGS P.St. Fleischer 1 and P.G. Trombik 2 1 Trombik Engineers Ltd. Zurich, Switzerland, Email: p.fleischer@trombik.ch 2 Trombik Engineers
More informationDYNAMIC CHARACTERISTICS OF A R/C BUILDING OF FIVE STORIES BASED ON MICROTREMOR MEASUREMENTS AND EARTHQUAKE OBSERVATIONS
DYNAMIC CHARACTERISTICS OF A R/C BUILDING OF FIVE STORIES BASED ON MICROTREMOR MEASUREMENTS AND EARTHQUAKE OBSERVATIO 5 Yasutaka IRIE And Kazuya NAKAMURA SUMMARY This paper describes the dynamic characteristics
More informationCOMPONENTS DISMANTLING AT NOVOVORONEZH UNITS 1, 2 SHUT DOWN FOR DECOMMISSIONING
COMPONENTS DISMANTLING AT NOVOVORONEZH UNITS 1, 2 SHUT DOWN FOR DECOMMISSIONING Filatov Alexey Engineer, Decommissioning Department Novovoronezh NPP, Russia INTRODUCTION The first phase of Novovoronezh
More informationPVP2006-ICPVT
Proceedings of PVP2006-ICPVT-11 2006 ASME Pressure Vessels and Piping Division Conference July 23-27, 2006, Vancouver, BC, Canada PVP2006-ICPVT-11-93732 SEISMIC ANALYSIS OF A PRESSURE VESSEL Mike Porter
More informationCHAPTER 4. 1:6-Scale Frame: Stiffness and Modal Testing 4.1 OVERVIEW
CHAPTER 4 1:6-Scale Frame: Stiffness and Modal Testing 4.1 OVERVIEW A 1:6-scale steel moment frame was designed for shaking-table experiments described in Chapter 5 based on Drain-2DX (DRAIN) analyses.
More informationCOMPARISON OF SEISMIC PERFORMANCE OF BASE-ISOLATED HOUSE WITH VARIOUS DEVICES
COMPARISON OF SEISMIC PERFORMANCE OF BASE-ISOLATED HOUSE WITH VARIOUS DEVICES SHINJI NAKATA ) TSUTOMU HANAI ) SHIN-ICHI KIRIYAMA ) and NOBUO FUKUWA ) ) Asahi Kasei Homes Co., TOKYO 6-845, Japan Email:
More informationFULL-SCALE VERIFICATION TEST OF DYNAMIC RESPONSE CONTOROL TECHNIQUES FOR STRONG EARTHQUAKES
FULL-SCALE VERIFICATION TEST OF DYNAMIC RESPONSE CONTOROL TECHNIQUES FOR STRONG EARTHQUAKES Hirokazu IEMURA 1, Akira IGARASHI 2, Torajiro FUJIWARA 3 And Akihiro TOYOOKA 4 SUMMARY In order to verify the
More informationFrictional Properties of Non-Metallic Materials for Use in Sliding Bearings: An Experimental Study
19 Frictional Properties of Non-Metallic Materials for Use in Sliding Bearings: An Experimental Study Daniel Fenz Department of Civil, Structural & Environmental Engineering, University at Buffalo Research
More informationSeismic isolation of LFR Reactor Buildings
EC Collaborative Project SILER: Seismic-Initiated events risk mitigation in LEad-cooled Reactors International Workshop 2013 Seismic isolation of LFR Reactor Buildings Ing. Giuseppe Moretti Ing. Ulisse
More informationEVALUATION OF SEISMIC BEHAVIOR OF IRREGULAR STEEL STRUCTURES IN PLAN WITH BRB AND EBF BRACES UNDER NEAR-FAULT EARTHQUAKE
IJBPAS, January, 2015, 5(1), Special Issue: 572-581 ISSN: 2277 4998 EVALUATION OF SEISMIC BEHAVIOR OF IRREGULAR STEEL STRUCTURES IN PLAN WITH BRB AND EBF BRACES UNDER NEAR-FAULT EARTHQUAKE HOSSEIN NASERI
More informationComparative Analysis and Design of Flat and Grid Slab System with Conventional Slab System
Comparative Analysis and Design of Flat and Grid Slab System with Conventional Slab System Syed Abdul Qavi 1, Syed Khaleelullah Shah Quadri 2 Syed Farrukh Anwar 3 1 PG Student, M.tech in Structural engineering,
More informationMETHODS OF QUALIFYING ELECTRICAL CABINETS FOR THE LOAD CASE EARTHQUAKE
18th International Conference on Structural Mechanics in Reactor Technology (SMiRT 18) Beijing, China, August 7-12, 2005 SMiRT18-K14-1 METHODS OF QUALIFYING ELECTRICAL CABINETS FOR THE LOAD CASE EARTHQUAKE
More informationNUMERICAL MODELING OF CONCRETE FACE ROCKFILL DAM AT SEISMIC IMPACT
NUMERICAL MODELING OF CONCRETE FACE ROCKFILL DAM AT SEISMIC IMPACT V.B. Glagovsky 1 and E.V. Kourneva 2 1 Deputy Director, The B.E.Vedeneev Research Institute of Hydraulic Engineering (VNIIG), Saint Petersburg,
More informationSEISMIC ANALYSIS OF NUCLEAR POWER PLANT CANNED MOTOR PUMP UNIT BASED ON INTEGRAL CALCULATION METHOD
SEISMIC ANALYSIS OF NUCLEAR POWER PLANT CANNED MOTOR PUMP UNIT BASED ON INTEGRAL CALCULATION METHOD Li Zhenggui 1,Li Muyu 1, Zhang Jiarong 1,Li Bo 1,Liu Xiaobing 1,Yang Fengyu 1,2 1 Key Laboratory of Fluid
More informationSEISMIC EVENTS AND NUCLEAR POWER PLANTS
GUIDE YVL 2.6 / 19 DECEMBER 2001 SEISMIC EVENTS AND NUCLEAR POWER PLANTS 1 GENERAL 3 2 DESIGN BASIS EARTHQUAKE 3 3 SEISMIC CLASSIFICATION 4 3.1 General 4 3.2 Seismic category S1 4 3.3 Seismic category
More information0306 SEISMIC LOADS GENERAL
0306 SEISMIC LOADS 0306.1 GENERAL Every structure, and portion thereof, including nonstructural components such as architectural, mechanical, and electrical components, shall be designed and constructed
More information4.2 DEVELOPMENT OF FUEL TEST LOOP IN HANARO
4.2 DEVELOPMENT OF FUEL TEST LOOP IN HANARO Sungho Ahn a, Jongmin Lee a, Suki Park a, Daeyoung Chi a, Bongsik Sim a, Chungyoung Lee a, Youngki Kim a and Kyehong Lee b a Research Reactor Engineering Division,
More informationJoint Stock Company St. Petersburg Research and Design Institute ATOMENERGOPROEKT (JSC SPbAEP) Baltic NPP project in the Kaliningrad region
Joint Stock Company St. Petersburg Research and Design Institute ATOMENERGOPROEKT (JSC SPbAEP) Baltic NPP project in the Kaliningrad region 2011 The Baltic NPP will be constructed in the north-east of
More informationFEM Analyses on Seismic Responses of Rocking Structural Systems with Yielding Base Plates
FEM Analyses on Seismic Responses of Rocking Structural Systems with Yielding Base Plates by Mitsumasa Midorikawa 1, Tatsuya Azuhata 2, Tadashi Ishihara 2, Akira Wada 3 and Izuru Okawa 4 ABSTRACT The seismic
More informationEVALUATION OF PERFORMANCE OF A SKEW BRIDGE IN WENCHUAN 2008 EARTHQUAKE
Proceedings of the International Symposium on Engineering Lessons Learned from the 2011 Great East Japan Earthquake, March 1-4, 2012, Tokyo, Japan EVALUATION OF PERFORMANCE OF A SKEW BRIDGE IN WENCHUAN
More informationRELAP 5 ANALYSIS OF PACTEL PRIMARY-TO-SECONDARY LEAKAGE EXPERIMENT PSL-07
Fifth International Seminar on Horizontal Steam Generators 22 March 21, Lappeenranta, Finland. 5 ANALYSIS OF PACTEL PRIMARY-TO-SECONDARY LEAKAGE EXPERIMENT PSL-7 József Bánáti Lappeenranta University of
More informationFloor Response Spectra Generation for Seismic Design of Buildings
Page1 Floor Response Spectra Generation for Seismic Design of Buildings Mathews Wilson*& Dr.S. Elavenil** * P.G. Student, School of Mechanical and Building Sciences, VIT University, Chennai. ** Professor,
More informationChapter 13 SEISMICALLY ISOLATED STRUCTURE DESIGN REQUIREMENTS
Chapter 13 SEISMICALLY ISOLATE STRUCTURE ESIGN REQUIREMENTS 13.1 GENERAL 13.1.1 Scope. Every seismically isolated structure and every portion thereof shall be designed and constructed in accordance with
More informationSTABLE SYSTEMS IN UNSTABLE CONDITIONS: EARTHQUAKE TESTING CONFORM THE IBC
STABLE SYSTEMS IN UNSTABLE CONDITIONS: EARTHQUAKE TESTING CONFORM THE IBC Paul SCHOTEN Eaton Holec The Netherlands holec-info@eaton.com Bob TOWNE Eaton Cutler-Hammer United States of America Mostafa AHMED
More informationSEISMIC ANALYSIS OF THE SAFETY RELATED PIPING AND PCLS OF THE WWER-440 NPP
SEISMIC ANALYSIS OF THE SAFETY RELATED PIPING AND PCLS OF THE WWER-440 NPP A.M. BERKOVSKI, V.V. KOSTAREV, A.J. SCHUKIN CKTI-VIBROSEISM, Russian Federation XAoioO52? Z. BOIADJIEV KNPP, Bulgaria M.KOSTOV
More informationPERFORMANCE OF DEFICIENT STEEL HOLLOW SQUARE SECTION SHORT COLUMN STRENGTHENED WITH CFRP
PERFORMANCE OF DEFICIENT STEEL HOLLOW SQUARE SECTION SHORT COLUMN STRENGTHENED WITH CFRP Mohammed J. Hamood, Maha Ghalib Gaddar and Zinah Asaad Abdul Husain Department of Building and Construction Engineering,
More informationSeismic Motion Incoherency Effects on Structure
Proceedings Third UJNR Workshop on Soil-Structure Interaction, March 29-30, 2004, Menlo Park, California, USA. Seismic Motion Incoherency Effects on Structure Dan M. Ghiocel * and Letian Wang * The paper
More informationIJSRD - International Journal for Scientific Research & Development Vol. 4, Issue 05, 2016 ISSN (online):
IJSRD - International Journal for Scientific Research & Development Vol. 4, Issue 05, 2016 ISSN (online): 2321-0613 Experimental Investigation of Effect of Tuned Mass Damper in the Structure using Shake
More informationANALYSIS OF 3-D VIBRATIONS OF THE BASE ISOLATED SCHOOL BUILDING "PESTALOZZI" BY ANALYTICAL AND EXPERIMENTAL APPROACH
ANALYSIS OF 3-D VIBRATIONS OF THE BASE ISOLATED SCHOOL BUILDING "PESTALOZZI" BY ANALYTICAL AND EXPERIMENTAL APPROACH Mihail A GAREVSKI 1, James M KELLY 2 And Nikola V ZISI 3 SUMMARY The results obtained
More informationTransactions, SMiRT-22 San Francisco, California, USA - August 18-23, 2013 Division V
Transactions, SMiRT- San Francisco, California, USA - August 8-, SIMPLIFIED MODELING OF EFFECTS OF CONCRETE CRACKING ON OUT-OF-PLANE VIBRATIONS OF FLOORS Luben Todorovski, Mahmoud Khoncarly, Dan M Ghiocel,
More informationTERMO-HYDRAULICS AND TERMO-MECHANICAL LOADING OF VVER-440 REACTOR PRESSURE VESSEL
TERMO-HYDRAULICS AND TERMO-MECHANICAL LOADING OF VVER-440 REACTOR PRESSURE VESSEL G. Gálik 1, V. Kutiš 2, J. Paulech 3, V. Goga 4 Abstract: This article describes a pressure thermal shock simulation methodology
More informationPumping System Vibration
Pumping System Vibration Understanding the Fundamentals Eric J. Olson Mechanical Solutions, Inc. (MSI) ejo@mechsol.com Agenda 1. Vibration testing and analysis fundamentals 2. Structural and acoustic resonance
More informationBN-1200 Reactor Power Unit Design Development
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) BN-1200 Reactor Power Unit Design Development B.A. Vasilyev a, S.F. Shepelev a, M.R.
More informationSeismic-Resistant Switchboards Conforming to New Regulatory Standards Concerning Commercial Nuclear Reactors
Seismic-Resistant Switchboards Conforming to New Regulatory Standards Concerning Commercial Nuclear Reactors KONNO, Masayuki * FUJIMOTO, Yoshio NAGASAWA, Takenori A B S T R A C T Nuclear power plants and
More information