Jan Zdebor David Pavlis. ŠKODA JS a.s. and its Cooperation with Czech Universities

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1 Jan Zdebor David Pavlis ŠKODA JS a.s. and its Cooperation with Czech Universities

2 History foundation of the primary ŠKODA company initiation of ŠKODA's nuclear programme start of the VVER reactor programme first VVER 440-type reactor first VVER 1000-type reactor Emil ŠKODA ( ) founder of ŠKODA WORKS starting cask manufacturing privatization and establishment of the parent company ŠKODA a.s. and the subsidiary ŠKODA JADERNÉ STROJÍRENSTVÍ s.r.o transformation to a joint stock company ŠKODA JS a.s sale of ŠKODA JS to the Russian group OMZ (100% owner) today - Czech leader in supplies for nuclear power plants, staff 1200 employees 2

privatization and establishment of the parent company ŠKODA a.s. and the subsidiary ŠKODA JADERNÉ STROJÍRENSTVÍ s.r.o. 1999 - transformation to a joint stock company ŠKODA JS a.

3 Strategic Business Units Engineering Construction of the VVER units Upgrade and renovation of operating VVER units (incl. I&C replacement) Interim spent fuel storage Construction of research and training reactors Services Management of planned outages Maintenance and repairs of reactor equipment Upgrade of reactor components Equipment lifetime management Production Equipment for the VVER and RBMK type NPPs Equipment for the PWR and BWR type NPPs Equipment for spent nuclear fuel storage 3

outages Maintenance and repairs of reactor equipment Upgrade of reactor components Equipment lifetime management

4 Cooperation with Technical Universities on technical issues related to NPPs in developing new equipment in the field of education Participation in lecturing University of West Bohemia Branch of study: Power System Engineering Czech Technical University in Prague Branch of study: Power System Engineering Master s thesis Shop tours and trainee-ships 4

University of West Bohemia Branch of study: Power System Engineering Czech Technical

5 5 Examples of Successful Cooperation

6 Examples of cooperation Replacement of Ni gaskets with gaskets made of expanded graphite for upper block flange joints of VVER 440 and VVER 1000 reactors 20 years of cooperation of ŠKODA JS with the New Technologies Research Centre of the University of West Bohemia Bolt M36x4 25CH1MF Bolt M20x1.5 10CH11N20T3R Stress intensity - joint tightening regime 6

of ŠKODA JS with the New Technologies Research Centre of the University of West Bohemia

7 Calculations of tightening forces and bolt torques; inspection of the tightness of joints (gaskets made of expanded graphite) Nuclear power plants Replacement of Ni gaskets with expanded graphite Experience with nickel gaskets Pressure tests Operation ŠKODA JS a.s. Experience of Calculation Department Design and manufacturing experience Experience from assembly Tests of gaskets made of expanded graphite University of Experimental programme of whole joints West Bohemia Material model of expanded graphite Tightness calculations for upper block flange joints of VVER1000 Others Technical conditions of manufacturer of expanded graphite, DIN standard 7 Complex evaluation Calculations of torques, calculation inspection of tightness of joints (VVER 440, VVER 1000) Methodology and requirements of PNAE G standard Determination of tightening forces and torques Follow-up calculations of strength and service life-time

ets Pressure tests Operation ŠKODA JS a.s. Experience of Calculation Department Design and manufacturing experience Experience from assembly Tests of gaskets made of expanded graphite University of

8 Replacement of Ni gaskets with expanded graphite ŠKODA gasktes made of expanded graphite deliveries implemented For VVER 440 and VVER 1000 reactors Design by ŠKODA JS Customers: Loviisa NPP Mochovce NPP Bohunice NPP Dukovany NPP Paks NPP Temelín NPP South Ukraine NPP Khmelnitsky NPP Zaporozhye NPP Rivne NPP 8 8

Design by ŠKODA JS Customers: Loviisa NPP Mochovce NPP Bohunice NPP Dukovany

9 Examples of successful cooperation Repairs of damaged threaded nests for upper block flange joints of VVER 440 by means of threaded inserts 9

Examples of successful cooperation Optimalization of Electromagnet Circuit for CRDM VVER 1000 Cooperation with Faculty of Electrical Engineering University of West Bohemia Block of electromagnets The

10 Examples of successful cooperation Optimalization of Electromagnet Circuit for CRDM VVER 1000 Cooperation with Faculty of Electrical Engineering University of West Bohemia Block of electromagnets The sketch of Drive electromagnet F [ratio min/max] 0,98 0,88 0,79 0,70 0,60 0,51 0,42 0, d [mm] Based static char. Minimal tensile force Static char. after optimalization d=20 d=20 3- Drive electromagnet 4- Blocking electromagnet 5- Fixing electromagnet 10

0,98 0,88 0,79 0,70 0,60 0,51 0,42 0,33 20 18 16 14 12 10 8 d [mm] 6 4 2 0 Based static char.

Examples of successful cooperation Optimization of fuel charges for VVER-type reactor cores in cooperation with the Faculty of Applied Sciences of the University of West Bohemia Neutron physical

11 Examples of successful cooperation Optimization of fuel charges for VVER-type reactor cores in cooperation with the Faculty of Applied Sciences of the University of West Bohemia Neutron physical calculations related to VVER-type reactor cores are the basis for evaluating the nuclear safety of nuclear energy systems. The goal is to determine the basic characteristics of the reactor core in the course of the campaigns of normal reactor operation, such as boric acid concentrations, output distribution in a radial and an axial direction, reactivity coefficients, positions of control rods, etc. Analyses are made by a 3D reactor core simulator, MOBY-DICK, which has been developed by ŠKODA JS a.s. The MOBY-DICK macrocode is based on the differential or nodal solution of a multigroup (usually a two-group) equation of neutron diffusion, which is implemented in 3D geometry both at a gross net level and a fine net level (per fuel rods). For common use, the method of reconstructing a detailed output distribution per fuel rods is also applied. Input data in parametrized form is prepared by the WIMS9 spectral programme. The superstructure of the MOBY-DICK macrocode is the ATHENA programme. This programme, which has been developed in cooperation with the University of West Bohemia, is designed to optimize fuel charges for VVER-type reactor cores. The MCNP programme is used for the calculations of the subcriticality of BVP storage racks and packaging sets for transporting and storing spent nuclear fuel.íspektrálním programem WIMS9. Optimum charge 11

The goal is to determine the basic characteristics of the reactor core in the course of the campaigns of normal reactor operation, such as boric acid concentrations, output distribution in a radial

Miroslav Spaniel, Miloš Moravec, Jan Dzugan, Pavel

12 Examples of successful cooperation Identification of Ductile Damage Parameters Antonín Prantl, Jan Růžička, Miroslav Spaniel, Miloš Moravec, Jan Dzugan, Pavel Konopík 12 Identification of Ductile Damage Parameters TIP FR-TI2/279

13 Examples of successful cooperation CANUT Centre of Advanced Nuclear Technologies 13

14 Examples of successful cooperation CANUT Centre of Advanced Nuclear Technologies Strategic consortium in the field of nuclear technologies. Group of internationally renowned research institutions and leading industrial companies created for the purpose of a long-term cooperation in the area of research, development and innovations. The activity of the Centre is supported by the Technological Agency of the Czech Republic from the state budget. 14

Group of internationally renowned research institutions and leading industrial companies created for the purpose

CANUT Centre of Advanced Nuclear Technologies Storage and transport of radioactive waste, especially spent nuclear fuel Members of the consortium participating in this project: University of West

15 CANUT Centre of Advanced Nuclear Technologies Storage and transport of radioactive waste, especially spent nuclear fuel Members of the consortium participating in this project: University of West Bohemia in Plzeň University of Technology in Brno ZAT a.s. Research Centre Řež Basic goal: To develop casks for storing and transporting spent fuel from VVER 440 and VVER 1000 reactors with enrichment exceeding 5% U 235., which in the future will be used in nuclear power plants in the Czech Republic and neighbouring countries. Casks for fuel from VVER 440 and VVER 1000 reactors are being developed. Maximum attention is paid to materials used for cask bodies and internal baskets. 15

16 CANUT Centre of Advanced Nuclear Technologies Storage and transport of radioactive waste, especially spent nuclear fuel Master's theses 16

17 CANUT Centre of Advanced Nuclear Technologies Equipment for inspecting components of the primary circuit of pressurized water nuclear reactors Members of the consortium participating in this project: University of West Bohemia in Plzeň ZAT a.s. 17 Basic goal: to develop equipment that will shorten the time of conducting non-destructive tests of components of the primary circuit in nuclear power plants utilizing pressurized water reactors to maintain the extent of testing to increase the probability of non-integrities being detected to determine the dimensions of non-integrities detected more precisely

18 CANUT Centre of Advanced Nuclear Technologies Equipment for inspecting components of the primary circuit of pressurized water nuclear reactors Master's theses 18

19 Examples of successful cooperation Research and Training Reactors 19

20 Research and Training Reactors References Scope of supply Customer Country Year Units Current Status Experimental light water reactor ŠR - 0A Experimental heavy water reactor ŠR - 0B Large critical heavy water experimental reactor TR - 0 ŠKODA Czech Republic Technical University ČVUT Prague Nuclear Research Institute ÚJV Řež 1975 operation cancelled (reconstructed to ŠR-0) Czech Republic operation cancelled Czech Republic operation cancelled (reconstructed to LR-0) Experimental light water reactor ŠR - 0 ŠKODA Czech Republic operation cancelled Large critical ligh water experimental reactor LR - 0 Experimental ligh water research reactor LVR - 15 Research and training light water experimental reactor VR - 1 Innovation of power protection channels at the type VR-1 training reactor Modernization of reacor LR-0 control system Supply and assembly of supercritical water loop Nuclear Research Institute ÚJV Řež Nuclear Research Institute ÚJV Řež Technical University ČVUT Prague Technical University ČVUT Prague Nuclear Research Institute ÚJV Řež Nuclear Research Institute ÚJV Řež Czech Republic Operable Czech Republic Operable Czech Republic Operable Czech Republic Operable Czech Republic Operable Czech Republic Operable 20

1971 1 1978 operation cancelled Czech Republic 1972 1 1980 operation cancelled (reconstructed to LR-0) Experimental light water reactor ŠR - 0 ŠKODA Czech Republic 1975 1 1989 operation cancelled

21 Examples of successful cooperation Research and Training Reactors Total 7 reactors supplied since 1970 Design, manufacture, procurement, supply, erection, setting into operation, service Modernisation of I&C system VR-1 Vrabec (Technical University Prague, Czech Republic) IRT-2000 (INRNE Sofia, Bulgaria) 21

Examples of successful cooperation Research and Training Reactors VR-1 Vrabec (Technical University Prague) Training pool reactor output 1 kw Complete innovation of control and technology

22 Examples of successful cooperation Research and Training Reactors VR-1 Vrabec (Technical University Prague) Training pool reactor output 1 kw Complete innovation of control and technology systems Process control system Neutron flow measurement Voting logic Technology cabinet Circulatory pumps Demineralization station Electric distribution point Cooperation with datapartner and TEDIA 22

23 Examples of successful cooperation Determination of the reliability characteristics of control rod drive mechanisms Cooperation with the Odessa National Polytechnic University in Ukraine Basic goal: Determination of the reliability characteristics of CRDMs operated in Ukrainian nuclear power plants: the characteristics to be determined in compliance with the requirements of ISO 3534 to develop the probability models of operation characteristics 23

24 Contact THANK YOU FOR YOUR ATTENTION ŠKODA JS a.s. Orlík Plzeň Czech Republic Tel.: Fax:

ŠKODA JS a.s. Praha 7.září 2010. Jan Blažek úsek Technika

ŠKODA JS a.s. Praha 7.září 2010 Jan Blažek úsek Technika Content ŠKODA JS company History Manufacturing capabilities Quality assurance Strategic bussines units Development Projects Current projects Finalized