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Sample records for jadrova vyradovacia spolocnost bohunice

  1. JAVYS - Jadrova a vyradovacia spolocnost

    2007-01-01

    This prospectus contains the review about of the joint stock company Jadrova a vyradovacia spolocnost, a.s., (JAVYS). JAVYS established itself in the Slovak power industry in 2005. According to the transaction documents on the privatisation of the Slovenske Elektrarne, a. s. company (SE), on July 6, 2005, the public organisation GovCo, into which the detached SE-VYZ and SE-EBO plants (V1 nuclear power plant) were included, was established. On April 1, 2006, the GovCo company assumed responsibility for the operation of V1 NPP, decommissioning of all nuclear installations in Slovakia, processing, treatment and storage of radioactive waste and care of spent nuclear fuel. The registered at of the company was changed to Jaslovske Bohunice and the company's name changed to Jadrova Vyradovacia Spolocnost, a. s. on August 7, 2006. The company name Jadrova a Vyradovacia Spolocnost, a.s. exists since March, 2007. The history of the company is short; professional activities however have been carried out for several decades. Some facts about the JAVYS are reported

  2. Information letter 10. Information about operation of Jadrova vyradovacia spolocnost, a.s. and plants SE-NPP Bohunice during October 2006

    2006-11-01

    In this leaflet results of exploitation of four units of the Bohunice V1 and V2 NPPs are presented. The electricity and heat production in October 2006 are reviewed. Within a October 2006 the electricity was produced in NPP V1: 313.778 GWh (block 1), 209.838 GWh (block 2), totally 523.616 GWh, and 5125.651 GWh within a January - October 2006. Within a October 2006 the NPP V2: blocks 3 and 4 has worked on nominal power. Processing and storage of radioactive wastes in Jadrova vyradovacia spolocnost (JAVYS) is presented. Seventeen pieces of fibre-concrete containers were processed into fibre-concrete containers in Bohunice processing centre of radioactive wastes (BSC RAO) in October 2006. Thirty-eight fibre-concrete containers were stored into Republic storage of radioactive wastes (RU RAO). Total number in RU RAO reached 1234 pieces of fibre-concrete containers, which represent 17.14 percent of storage capacity (7200 containers)

  3. Information letter 12. Information about operation of Jadrova vyradovacia spolocnost, a.s. and plants SE-NPP Bohunice during December 2006

    2007-01-01

    In this leaflet results of exploitation of four units of the Bohunice V1 and V2 NPPs are presented. The electricity and heat production in December 2006 are reviewed. Within a December 2006 the electricity was produced in NPP V1: 301.221 GWh (block 1), 281.125 GWh (block 2), totally 582.346 GWh, and 6179.205 GWh within a January - December 2006. Within a November 2006 the NPP V2: the block 3 and block 4 has worked in stabile regime according to needs of regulation. Processing and storage of radioactive wastes in Jadrova vyradovacia spolocnost (JAVYS) is presented. Twenty pieces of fibre-concrete containers were processed into fibre-concrete containers in Bohunice processing centre of radioactive wastes (BSC RAO) in December 2006. Eight fibre-concrete containers were stored into Republic storage of radioactive wastes (RU RAO). Total number in RU RAO reached 1260 pieces of fibre-concrete containers, which represent 17.50 per cent of storage capacity (7200 containers)

  4. JAVYS - Jadrova a vyradovacia spolocnost. Annual Report 2006

    2007-01-01

    This Annual Report contains the review of the results of the joint stock company Jadrova a vyradovacia spolocnost, a.s., (JAVYS) in relation to the year 2006. This report contains the following headings: (1) Speech of the General Director; (2) Board of Directors GovCo/JAVYS; (3) Supervisory Board GovCo/JAVYS; (4) Important events; (5) Organization structure of JAVYS; (6) Company strategy; (7) Electricity production; (8) Rad-waste processing and storing; (9) Spent fuel handling; (10) A1 NPP Decommissioning; (11) BIDSF; (12) Trade and services; (13) Investments; (14) Nuclear safety; (15) Radiation protection; (16) Industrial safety, health protection and fire protection; (17) Human resources; (18) Report from the business activities and property balance; (19) Independent Auditors' Report

  5. Eco information 9. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, locality of Bohunice, within September 2014

    2014-10-01

    In this leaflet the results of monitoring of chemical gaseous and liquid effluents into the rivers Vah and Dudvah as well as of radiation monitoring of Bohunice V1 NPP, Interim Spent Fuel Storage (MSVP), Bohunice Radioactive Waste Processing Centre (VK808 - BSC), The Main Production Unit (VK 46A - HVB) and Bitumenation Lines (VK 46B - BL) are presented. The radioactive effluents into atmosphere within January - September 2014 (for NPP V1, MSVP, BSC, HVB and BL, respectively) were: 1.483 MBq (0.002 of AL) for V1, 0.087 MBq (0.029% of AL) for MSVP, 0.084 MBq (0.060% of AL) for BSC, 0.400 MBq (0.061% of AL) for HVB and 0.028 MBq (0.020% of AL) for BL of aero-soles. The radioactive effluents into atmosphere and hydrosphere within a September 2014 for NPP V1, MSVP, and VK 808 BSC, respectively, were: 0.258 MBq (V1), 0.007 MBq (VK MSVP), 0.018 MBq (VK 808 BSC), 0.005 MBq (VK 46A) and 0.002 MBq (VK 46B) of aero-soles into atmosphere; 1.169 MBq (V1 and MSVP) and 0.522 MBq (TSU RAO and NPP A1) of corrosive and fission products, and 0.002 GBq (V1 and MSVP) and 16.740 GBq (TSU RAO and NPP A1) of tritium into the Vah River and 0.000 GBq (V1 and MSVP) and 0.000 MBq (TSU RAO and NPP A1) of corrosive and fission products and 0.000 GBq of tritium (V1) and 0.000 GBq of tritium (TSU RAO and NPP A1) into the Dudvah River). For the period January - September 2014 these radioactive effluents into recipient of Vah River represent for corrosive and fission products 12.402 MBq (0.095% of AL for V1 and MSVP) and 5.010 MBq (0.042% of AL for TSU RAO and MSVP); and for tritium it is 8.382 GBq (0.419% of AL) for V1 and MSVP, and 98.415 GBq (0.984% of AL) for TSU RAO and NPP A1 (into the Vah River) and for corrosive and fission products 0.000 MBq (V1 and MSVP) and 0.000 MBq (TSU RAO and NPP A1) (0.0000 of AL) of tritium (into the Dudvah River). Chemical effluents are reported, too.

  6. Eco information 1. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, locality of Bohunice, within January 2016

    2016-02-01

    In this leaflet the results of monitoring of chemical gaseous and liquid effluents into the rivers Vah and Dudvah as well as of radiation monitoring of Bohunice V1 NPP, Interim Spent Fuel Storage (MSVP), Bohunice Radioactive Waste Processing Centre (VK808 - BSC), The Main Production Unit (VK 46A - HVB) and Bitumenation Lines (VK 46B - BL) are presented. The alpha radioactive effluents into atmosphere within January 2016 (for NPP V1, MSVP, BSC, HVB and BL, respectively) were: 0.051 MBq (0.0001 of AL) for V1, 0.006 MBq (0.002% of AL) for MSVP, 0.007 MBq (0.005% of AL) for BSC, 0.027 MBq (0.004% of AL) for HVB and 0.003 MBq (0.002% of AL) for BL of aero-soles. The radioactive effluents into atmosphere and hydrosphere within a January 2016 for NPP V1, MSVP, and VK 808 BSC, respectively, were: 0.051 MBq (V1), 0.006 MBq (VK MSVP), 0.007 MBq (VK 808 BSC), 0.027 MBq (VK 46A) and 0.003 MBq (VK 46B) of aero-soles into atmosphere; 0.192 MBq (V1 and MSVP) and 0.346 MBq (TSU RAO and NPP A1) of corrosive and fission products, and 0.001 GBq (V1 and MSVP) and 10.991 GBq (TSU RAO and NPP A1) of tritium into the Vah River and 0.000 GBq (V1 and MSVP) and 0.000 MBq (TSU RAO and NPP A1) of corrosive and fission products and 0.000 GBq of tritium (V1) and 0.000 GBq of tritium (TSU RAO and NPP A1) into the Dudvah River). For the period January - January 2016 these radioactive effluents into recipient of Vah River represent for corrosive and fission products 0.192 MBq (0.0015% of AL for V1 and MSVP) and 0.346 MBq (0.003% of AL for TSU RAO and MSVP); and for tritium it is 0.001 GBq (0.00003% of AL) for V1 and MSVP, and 10.991 GBq (0.110% of AL) for TSU RAO and NPP A1 (into the Vah River) and for corrosive and fission products 0.000 MBq (V1 and MSVP) and 0.000 MBq (TSU RAO and NPP A1) (0.0000 of AL) of tritium (into the Dudvah River). Chemical effluents are reported, too.

  7. Eco information 4 Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, locality of Bohunice, within April 2016

    2016-05-01

    In this leaflet the results of monitoring of chemical gaseous and liquid effluents into the rivers Vah and Dudvah as well as of radiation monitoring of Bohunice V1 NPP, Interim Spent Fuel Storage (MSVP), Bohunice Radioactive Waste Processing Centre (VK808 - BSC), The Main Production Unit (VK 46A - HVB) and Bitumenation Lines (VK 46B - BL) are presented. The alpha radioactive effluents into atmosphere within January - April 2016 (for NPP V1, MSVP, BSC, HVB and BL, respectively) were: 0.141 MBq (0.0002 of AL) for V1, 0.027 MBq (0.006% of AL) for MSVP, 0.029 MBq (0.016% of AL) for BSC, 0.127 MBq (0.015% of AL) for HVB and 0.009 MBq (0.006% of AL) for BL of aero-soles. The radioactive effluents into atmosphere and hydrosphere within a April 2016 for NPP V1, MSVP, and VK 808 BSC, respectively, were: 0.017 MBq (V1), 0.008 MBq (VK MSVP), 0.006 MBq (VK 808 BSC), 0.029 MBq (VK 46A) and 0.003 MBq (VK 46B) of aero-soles into atmosphere; 0.880 MBq (V1 and MSVP) and 0.397 MBq (TSU RAO and NPP A1) of corrosive and fission products, and 0.315 GBq (V1 and MSVP) and 7.163 GBq (TSU RAO and NPP A1) of tritium into the Vah River and 0.000 GBq (V1 and MSVP) and 0.000 MBq (TSU RAO and NPP A1) of corrosive and fission products and 0.000 GBq of tritium (V1) and 0.000 GBq of tritium (TSU RAO and NPP A1) into the Dudvah River). For the period January - April 2016 these radioactive effluents into recipient of Vah River represent for corrosive and fission products 2.658 MBq (0.0204% of AL for V1 and MSVP) and 1.744 MBq (0.015% of AL for TSU RAO and MSVP); and for tritium it is 0.736 GBq (0.03679% of AL) for V1 and MSVP, and 31.833 GBq (0.318% of AL) for TSU RAO and NPP A1 (into the Vah River) and for corrosive and fission products 0.000 MBq (V1 and MSVP) and 0.000 MBq (TSU RAO and NPP A1) (0.0000 of AL) of tritium (into the Dudvah River). Chemical effluents are reported, too.

  8. Eco information 2. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, locality of Bohunice, within February 2016

    2016-03-01

    In this leaflet the results of monitoring of chemical gaseous and liquid effluents into the rivers Vah and Dudvah as well as of radiation monitoring of Bohunice V1 NPP, Interim Spent Fuel Storage (MSVP), Bohunice Radioactive Waste Processing Centre (VK808 - BSC), The Main Production Unit (VK 46A - HVB) and Bitumenation Lines (VK 46B - BL) are presented. The alpha radioactive effluents into atmosphere within January - February 2016 (for NPP V1, MSVP, BSC, HVB and BL, respectively) were: 0.100 MBq (0.001 of AL) for V1, 0.013 MBq (0.004% of AL) for MSVP, 0.017 MBq (0.012% of AL) for BSC, 0.048 MBq (0.007% of AL) for HVB and 0.005 MBq (0.003% of AL) for BL of aero-soles. The radioactive effluents into atmosphere and hydrosphere within a February 2016 for NPP V1, MSVP, and VK 808 BSC, respectively, were: 0.049 MBq (V1), 0.007 MBq (VK MSVP), 0.011 MBq (VK 808 BSC), 0.020 MBq (VK 46A) and 0.002 MBq (VK 46B) of aero-soles into atmosphere; 0.706 MBq (V1 and MSVP) and 0.738 MBq (TSU RAO and NPP A1) of corrosive and fission products, and 0.419 GBq (V1 and MSVP) and 7.479 GBq (TSU RAO and NPP A1) of tritium into the Vah River and 0.000 GBq (V1 and MSVP) and 0.000 MBq (TSU RAO and NPP A1) of corrosive and fission products and 0.000 GBq of tritium (V1) and 0.000 GBq of tritium (TSU RAO and NPP A1) into the Dudvah River). For the period January - February 2016 these radioactive effluents into recipient of Vah River represent for corrosive and fission products 0.898 MBq (0.0069% of AL for V1 and MSVP) and 1.084 MBq (0.009% of AL for TSU RAO and MSVP); and for tritium it is 0.420 GBq (0.02098% of AL) for V1 and MSVP, and 18.470 GBq (0.185% of AL) for TSU RAO and NPP A1 (into the Vah River) and for corrosive and fission products 0.000 MBq (V1 and MSVP) and 0.000 MBq (TSU RAO and NPP A1) (0.0000 of AL) of tritium (into the Dudvah River). Chemical effluents are reported, too.

  9. Eco information 12. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment within December 2008

    2009-01-01

    In this leaflet the results of monitoring of chemical gaseous and liquid effluents into the rivers Vah and Dudvah as well as of radiation monitoring of Bohunice V1 NPP and Bohunice Radioactive Waste Processing Centre (MSVP) are presented. The radioactive effluents into atmosphere within January - December 2008 (for NPP V1, A1, and MSVP, respectively) were: 6.834 TBq (0.342% of annually limit (AL)) for V1 of rare gases; 19.956 MBq (0.025% AL) for V1), 18.56 MBq (1.97% of AL) for A1 and 0.545 MBq (0.18% of AL) for MSVP) of aero-soles; 16.754 MBq (0.026% of AL) for V1) of iodine. The radioactive effluents into atmosphere and hydrosphere within a December 2008 for NPP V1, A1 and MSVP, respectively) were: 0.844 TBq (V1) of rare gases; 0.998 MBq (V1), 14.68 MBq (A1) and 0.047 MBq (MSVP) of aero-soles; 0.229 MBq (V1) of iodine; 0.670 MBq (V1) and 7.46 MBq (A1 and MSVP, totally) of corrosive and fission products, and 52.9 GBq (V1) and 12.98 GBq (A1 and MSVP, totally) of tritium. For the period January - December 2008 these radioactive effluents into recipient of Vah River represent for corrosive and fission products 17.704 MBq (0.136% of AL) for V1, 113.23 MBq (0.94% of AL) for A1; and for tritium it is 4330.1 GBq (21.650% of AL) for V1, 212.37 GBq (2.12% of AL) for A1. Chemical effluents are reported, too

  10. Eco information 1. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment within January 2009

    2009-01-01

    In this leaflet the results of monitoring of chemical gaseous and liquid effluents into the rivers Vah and Dudvah as well as of radiation monitoring of Bohunice V1 NPP and Bohunice Radioactive Waste Processing Centre (MSVP) are presented. The radioactive effluents into atmosphere within January - January 2009 (for NPP V1, A1, and MSVP, respectively) were: 0.470 TBq (0.024% of annually limit (AL)) for V1 of rare gases; 0.437 MBq (0.001% AL) for V1), 0.531 MBq (0.06% of AL) for A1 and 0.011 MBq (0.004% of AL) for MSVP) of aero-soles; 4.024 MBq (0.006% of AL) for V1) of iodine. The radioactive effluents into atmosphere and hydrosphere within a January 2009 for NPP V1, A1 and MSVP, respectively) were: 0.470 TBq (V1) of rare gases; 0.437 MBq (V1), 0.531 MBq (A1) and 0.011 MBq (MSVP) of aero-soles; 4.024 MBq (V1) of iodine; 1.358 MBq (V1) and 2.68 MBq (A1 and MSVP, totally) of corrosive and fission products, and 124.4 GBq (V1) and 13.12 GBq (A1 and MSVP, totally) of tritium. For the period January - January 2009 these radioactive effluents into recipient of Vah River represent for corrosive and fission products 1.358 MBq (0.010% of AL) for V1, 2.66 MBq (0.02% of AL) for A1; and for tritium it is 124.4 GBq (0.622% of AL) for V1, 13.12 GBq (0.13% of AL) for A1. Chemical effluents are reported, too

  11. Eco information 4. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within April 2014

    2014-05-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within February 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 1.011 GBq of tritium (1.011 for the period January - April 2014 (0.36% of AL)) and summary of gamma-radionuclides 0.479 GBq (0.944 GBq for the period January - April 2014 (24.21% of AL)). The radioactive effluents into hydrosphere within April 2014 for FS KRAO were: 62 kBq of 90 Sr (62 kBq for the period January - March 2014 (0.003% of AL)), 0.003 kBq of summary alpha (0.003% of AL) and 1847 kBq of 14 C (1847 kBq for the period January - March 2014). The radioactive effluents into hydrosphere within April 2014 for RU RAO were: 0.568 MBq of tritium (4.544 MBq for the period January - April 2014 (0.024% of AL)); 0.004 MBq of 137 Cs (0.033 MBq for the period January - April 2014 (0.145% of AL)); 0.119 MBq of 90 Sr - the value of the quarterly (0.119 MBq for the period January - March 2014 (0.049% of AL)); 0.008 MBq of 60 Co (0.031 MBq for the period January - April 2014 (0.138% of AL)); 0.005 MBq of 239 Pu (0.005 MBq for the period January - March (0.892% of AL)). Volume of liquid effluents in April 2014 was 227 m 3 (186 m 3 for the period January - April 2014). The radioactive effluents into atmosphere within April 2014 for FS KRAO were: 0.0005 MBq of gamma radionuclides (0.0018 MBq for the period January - April 2014, that is 0.0023% of annually limit (AL)); 0.022 MBq of alpha radionuclides (0.022 MBq for the period January - March (0.0022% of AL)), and 0.149 MBq of 89 Sr and 90 Sr - the value of the quarterly (0.149 MBq for the period January - March 2014 (0.0075% of AL)).

  12. Eco information 10. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within October 2014

    2014-11-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within October 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.512 GBq of tritium (8.464 GBq for the period January - October 2014 (2.82% of AL)) and summary of gamma-radionuclides 0.147 GBq (2.904 GBq for the period January - October 2014 (64.13% of AL)). The radioactive effluents into hydrosphere within July - September 2014 for FS KRAO were: 60 kBq of 90 Sr (489 kBq for the period January - September), 0.003 kBq of summary alpha (0.030 kBq of annually value) and 1920 kBq of 14 C for the period July - September (39367 kBq of annually value). The radioactive effluents into hydrosphere within October 2014 for RU RAO were: 0 MBq of tritium (13.064 MBq for the period January - October 2014 (0.069% of AL)); 0 MBq of 137 Cs in October 2014 (0.092 MBq for the period January - August 2014 (0.404% of AL)); 0.128 MBq of 90 Sr - the value within July - September 2014 (0.324 MBq for the period January - September 2014 (0.13% of AL)); 0 MBq of 60 Co in October 2014 (0.093 MBq for the period January - October 2014 (0.415% of AL)); 0.006 MBq of 239 Pu (0.016 MBq for the period April - June 2014 (2.86% of AL)). Volume of liquid effluents in October 2014 was 0 m 3 (5221 m 3 for the period January - October 2014). The radioactive effluents into atmosphere within October 2014 for FS KRAO were: 0.0007 MBq of gamma radionuclides (0.0055 MBq for the period January - October 2014, that is 0.0068% of annually limit (AL)); 0.025 kBq of alpha radionuclides within July - September 2014 (0.071 kBq for the period July - September 2014 (0.0071% of AL)), and 0.161 kBq of 89 Sr and 90 Sr - the value within July - September 2014 (0.465 kBq for the period January - September 2014 (0.0233% of AL)).

  13. Eco information 2. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within February 2014

    2014-03-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within February 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.0000 GBq of tritium (9.0000 for the period January - February 2014 (0.00% of AL)) and summary of gamma-radionuclides 0.0000 GBq (0.0000 GBq for the period January - February 2014 (0.00% of AL)). The radioactive effluents into hydrosphere within February 2014 for FS KRAO were: 0.000 kBq of 90 Sr (0.000% of AL)), 0.000 kBq of summary alpha (0.000% of AL) and 0.000 kBq of 14 C (0.000% of AL). The radioactive effluents into hydrosphere within February 2014 for RU RAO were: 2.272 MBq of tritium (3.976 MBq for the period January - February 2014 (0.021% of AL)); 0.017 MBq of 137 Cs (0.029 MBq for the period January - February 2014 (0.127% of AL)); 0.00 MBq of 90 Sr - the value of the quarterly (0.00 MBq for the period January - March 2013 (0.000% of AL)); 0.014 MBq of 60 Co (0.023 MBq for the period January - February 2014 (0.103% of AL)); 0.000 of 239 Pu (0.000 MBq for the period January - March 2014 (0.000% of AL)). Volume of liquid effluents in February 2014 was 908 m 3 (1589 m 3 for the period January - February 2014). The radioactive effluents into atmosphere within February 2014 for FS KRAO were: 0.0002 MBq of gamma radionuclides (0.0007 MBq for the period January - February 2014, that is 0.0009% of annually limit (AL)); 0.000 MBq of alpha radionuclides (0.000 MBq for the period January - March 2014 (0.000% of AL)), and 0.000 MBq of 89 Sr and 90 Sr - the value of the quarterly (0.000 MBq for the period January - March 2014 (0.000% of AL)).

  14. Eco information 3. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within March 2014

    2014-04-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within March 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.056 GBq of tritium (0.056 for the period January - March 2014 (0.2% of AL)) and summary of gamma-radionuclides 0.465 GBq (0.465 GBq for the period January - March 2014 (11.92% of AL)). The radioactive effluents into hydrosphere within January - March 2014 for FS KRAO were: 0.000 kBq of 90 Sr (0.000% of AL)), 0.000 kBq of summary alpha (0.000% of AL) and 0.000 kBq of 14 C (0.000% of AL). The radioactive effluents into hydrosphere within March 2014 for RU RAO were: 0.000 MBq of tritium (3.976 MBq for the period January - March 2014 (0.021% of AL)); 0.000 MBq of 137 Cs (0.029 MBq for the period January - March 2014 (0.127% of AL)); 0.00 MBq of 90 Sr - the value of the quarterly (0.00 MBq for the period January - March 2014 (0.000% of AL)); 0.000 MBq of 60 Co (0.023 MBq for the period January - March 2014 (0.103% of AL)); 0.000 MBq of 239 Pu (0.000 MBq for the period January - March 2014 (0.000% of AL)). Volume of liquid effluents in March 2014 was 0 m 3 (1589 m 3 for the period January - March 2014). The radioactive effluents into atmosphere within March 2014 for FS KRAO were: 0.0006 MBq of gamma radionuclides (0.0013 MBq for the period January - March 2014, that is 0.0016% of annually limit (AL)); 0.00 MBq of alpha radionuclides (0.000 MBq for the period January - March 2014 (0.000% of AL)), and 0.000 MBq of 89 Sr and 90 Sr - the value of the quarterly (0.000 MBq for the period January - March 2014 (0.000% of AL)).

  15. Eco information 1. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within January 2014

    2014-02-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within January 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.0000 GBq of tritium (0.0000 GBq for the period January - January 2014 (0.000% of AL)) and summary of gamma-radionuclides 0.0000 GBq (0.0000 GBq for the period January - January 2014 (0.000% of AL)). The radioactive effluents into hydrosphere within January 2014 for FS KRAO were: 1,704 kBq of 90 Sr (0.009% of AL)), 0.012 kBq of summary alpha (0.053% of AL) and 0.000 kBq of 14 C (0.000% of AL). The radioactive effluents into hydrosphere within January 2014 for RU RAO were: 0.009 MBq of tritium (1.704 MBq for the period January - January 2014 (1.704% of AL)); 0.012 MBq of 137 Cs (0.012 MBq for the period January - January 2014 (0.053% of AL)); 0.000 MBq of 90 Sr - the value of the quarterly (0.000 MBq for the period January - January 2014 (0.000% of AL)); 0.009 MBq of 60 Co (0.009 MBq for the period January - January 2014 (0.04% of AL)); 0.000 MBq of 239 Pu (0.000 MBq for the period January - January 2014 (0.000% of AL)). Volume of liquid effluents in January 2014 was 681 m 3 (4681m 3 for the period January - January 2014). The radioactive effluents into atmosphere within January 2014 for FS KRAO were: 0.0005 MBq of gamma radionuclides (0.0005 MBq for the period January - January 2014, that is 0.0006% of annually limit (AL)); 0.000 MBq of alpha radionuclides (0.000 MBq for the period January - January 2014 (0.000% of AL)), and 0.000 MBq of 89 Sr and 90 Sr - the value of the quarterly (0.000 MBq for the period January - January 2014 (0.000% of AL)).

  16. Eco information 4. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within April 2016

    2016-05-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within April 2016 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.642 GBq of tritium (0.649 GBq for the period January - April 2016 (0.213% of AL)) and summary of gamma-radionuclides 0.000 GBq (0.000 GBq for the period January - April 2016 (0.0% of AL)). The radioactive effluents into hydrosphere within January - January 2016 for FS KRAO were: 0 kBq of 90 Sr (0 kBq for the period January - March 2016), 0.024 kBq of summary alpha (0.024 kBq of annually value) and 10.817 kBq of 14 C for the period January - March 2016 (01.817 kBq of annually value). The radioactive effluents into hydrosphere within April 2016 for RU RAO were: 0.000 MBq of tritium (2.840 MBq for the period January - April 2016 (0.015% of AL)); 0.000 MBq of 137 Cs in April 2016 (0.026 MBq for the period January - April 2016 (0.114% of AL)); 0.248 MBq of 90 Sr - the value within January - March 2016 (0.248 MBq for the period January - April 2016 (0.102% of AL)); 0.000 MBq of 60 Co in April 2016 (0.018 MBq for the period January - April 2016 (0.080% of AL)); 0.009 MBq of 239 Pu (0.009 MBq for the period January - March 2016 (1.607% of AL)). Volume of liquid effluents in January 2016 was 0 m 3 (1135 m 3 for the period January - April 2016). The radioactive effluents into atmosphere within April 2016 for FS KRAO were: 0.0010 MBq of gamma radionuclides (0.0041 MBq for the period January - April 2016, that is 0.0039% of annually limit (AL)); 0.027 kBq of alpha radionuclides within January - March 2016 (0.027 kBq for the period January - March 2016 (0.0027% of AL)), and 0.179 kBq of 89 Sr and 90 Sr - the value within January - March 2016 (0.179 kBq for the period January - March 2016 (0.0089% of AL)).

  17. Eco information 2 Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within February 2016

    2016-03-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within February 2016 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.007 GBq of tritium (0.000 GBq for the period January - February 2016 (0.02% of AL)) and summary of gamma-radionuclides 0.215 GBq (0.215 GBq for the period January - February 2016 (5.51% of AL)). The radioactive effluents into hydrosphere within January - March 2016 for FS KRAO were: 0 kBq of 90 Sr (0 kBq for the period January - March 2016), 0 kBq of summary alpha (0 kBq of annually value) and 0 kBq of 14 C for the period January - March 2016 (0 kBq of annually value). The radioactive effluents into hydrosphere within January 2016 for RU RAO were: 2.272 MBq of tritium (2.272 MBq for the period January - March 2016 (0.012% of AL)); 0.018 MBq of 137 Cs in February 2016 (0.018 MBq for the period January - March 2016 (0.079% of AL)); 0.000 MBq of 90 Sr - the value within January - March 2016 (0.000 MBq for the period January - March 2016 (0.000% of AL)); 0.013 MBq of 60 Co in February 2016 (0.013 MBq for the period January - March 2016 (0.058% of AL)); 0.000 MBq of 239 Pu (0.000 MBq for the period January - March 2016 (0.00% of AL)). Volume of liquid effluents in February 2016 was 908 m 3 (908 m 3 for the period January - February 2016). . The radioactive effluents into atmosphere within February 2016 for FS KRAO were: 0.0009 MBq of gamma radionuclides (0.002 MBq for the period January - February 2016, that is 0.0025% of annually limit (AL)); 0.000 kBq of alpha radionuclides within January - March 2016 (0.000 kBq for the period January - March 2016 (0.000% of AL)), and 0.000 kBq of 89 Sr and 90 Sr - the value within January - March 2016 (0.000 kBq for the period January - March 2016 (0.000% of AL)).

  18. Report of influence on environment 2006

    2007-01-01

    The joint stock company Jadrova a vyradovacia spolocnost, a. s. (JAVYS) has established in the Slovak power engineering industry just recently. According to transaction documents about privatisation of the joint stock company Slovenske elektrarne, a. s. (SE), on 6-th July 2005 there was established state-owned organisation GovCo from which VYZ plants and V1 power plant were separated. Since 1-st April 2006, the company GovCo assumed responsibility for JE V1 plant, decommissioning of nuclear facilities in Slovakia, processing, treatment and storage of radioactive waste and care for spent nuclear fuel. Seat of the company changed to operation from Jaslovske Bohunice and, on 7-th August, also the company's name changed to Jadrova vyradovacia spolocnost, a.s.. Since March 2007, the company's name is Jadrova a vyradovacia spolocnost, a. s. Starting position of the company in the Slovak power engineering sector developed from achieved results of long- term operation of plants of the company SE, a. s. - VYZ and EBO V1. Apart from operation of currently only one block of V1 nuclear power plant, the company carries out the first phase of the A1 nuclear power plant decommissioning project, operates radioactive waste processing centre in Bohunice (Bohunicke spracovatelske centrum radioaktivnych odpadov), bitumen and vitrification line of radioactive waste processing and fragmentation plant for metal radioactive waste. Currently, new facility - final processing of liquid radioactive waste in Mochovce is being put into operation. This chain is crowned by safe storage of processed low and medium-active waste in Republic's Repository of Radioactive Waste (Republikove ulozisko RAO) in Mochovce. The company also operates spent nuclear fuel in-process store in Jaslovske Bohunice, which is resistant to seismic activity and compacted. This Report contains the results of monitoring of the environment in JAVYS, a.s. in 2006

  19. Treatment and conditioning of solid and liquid raw

    Jakubec, R.

    2015-01-01

    Jadrova a vyradovacia spolocnost, a.s. (JAVYS) implements activities within the processes of treatment and conditioning of radioactive waste (RAW) at two nuclear facilities, one of them located in Bohunice - Technologies for treatment and conditioning of RAW. This nuclear facility includes: Bohunice RAW treatment centre, bituminization lines, waste water purification station and technologies for sorting, fragmentation and decontamination of metallic RAW. The Bohunice RAW treatment centre (BRTC) in Bohunice processes and conditions liquid and solid radioactive waste produced during the A1 NPP and V1 NPP decommissioning, waste from the operation of V2 NPP in Bohunice as well as from the operation of NPP EMO 1,2 in Mochovce. The BRTC includes the following technological facilities: sorting, high-pressure compaction, incineration, concentration and cementation. Treatment of radioactive wastes in the BRTC is described. (authors)

  20. VUEZ. Annual report 2007

    2008-01-01

    A brief account of activities carried out by the Vyskumny ustav energetickych zariadeni, a.s. (VUEZ) in 2008 is presented. These activities are reported under the headings: (1) Introductory address by the Chairman of the Board of Directors; (2) Company profile; (3) Portfolio of products and service 2007; (4) Quality management system; (5) Organisational Structure; (6) Human resources; (7) Financial statements and auditor's report; (8) Basic and contact data; (9) Contact data. The year 2007 was arduous and, with regard to contracts and projects performed and related profits, also successful for VUEZ, a.s. On the domestic market, our principal customers have bee companies such as Slovenske elektrarne - Enel, Bratislava, in its locations of Jaslovske Bohunice and Mochovce, Jadrova vyradovacia spolocnost, Jaslovske Bohunice, and Vodohospodarska vystavba, Bratislava. Equally important customers for our company have been operators of foreign nuclear power plants, namely CEZ, a.s. (Czech Republic) and the Paks NPP (Hungary). In the course of 2007, negotiations and offer proceedings were initiated with WWER nuclear power plants in Ukraine and Russia

  1. Bituminization plant Jaslovske Bohunice

    1999-01-01

    In this leaflet the principle of the bituminization plant for radioactive concentrate (the intermediate liquid radioactive waste generated during the NPP A1, V-1, V-2 operations) solidification used in the Bohunice Radwaste Treatment Centre (BSC RAO) is presented

  2. Internal communication at Bohunice NPPs

    Dobdk, Dobroslav

    1999-01-01

    Communication is the base of everyday existence of a modern person and every company. It is not easy to work in this area in a changing 'eastern' country. Many tools, which are used are in the mind of people connected with 'propaganda'. I would like to share our experience with you. The goal of an internal communication is to spread and provide continuous current of objective information between the management of Bohunice NPPs and its personnel and between the personnel itself. Communication with the Bohunice NPPs employees helps to get acquainted with their opinions and ideas concerning the subsidiary and nuclear power industry

  3. Radwaste Treatment Centre Jaslovske Bohunice

    2000-01-01

    In this leaflet the Bohunice Radwaste Treatment Centre (BSC RAO) is presented. BSC RAO is designed to process and treat liquid and solid radwaste, arising from the NPP A-1 decommissioning, from NPPs V-1, V-2, and Mochovce operations, as well as institutional radwaste of diverse institutional (hospitals, research institutes) in the Slovak Republic. Transport, sorting, incineration, compacting, concentration and cementation of radwaste as well as monitoring of emission are described

  4. Bohunice Nuclear Power Plant Safety Upgrading Program

    Toth, A.; Fagula, L.

    1996-01-01

    Bohunice nuclear Power Plant generation represents almost 50% of the Slovak republic electric power production. Due to such high level of commitment to nuclear power in the power generation system, a special attention is given to safe and reliable operation of NPPs. Safety upgrading and operational reliability improvement of Bohunice V-1 NPP was carried out by the Bohunice staff continuously since the plant commissioning. In the 1990 - 1993 period extensive projects were realised. As a result of 'Small Reconstruction of the Bohunice V-1 NPP', the standards of both the nuclear safety and operational reliability have been significantly improved. The implementation of another modifications that will take place gradually during extended refuelling outages and overhauls in the course of 1996 through 1999, is referred to as the Gradual Reconstruction of the Bohunice V-1 Plant. The general goal of the V-1 NPP safety upgrading is the achievement of internationally acceptable level of nuclear safety. Extensive and financially demanding modification process of Bohunice V-2 NPP is likely to be implemented after a completion of the Gradual Reconstruction of the Bohunice V-1 NPP, since the year 1999. With this in mind, a first draft of the strategy of the Bohunice V-2 NPP upgrading program based on Probabilistic Safety assessment consideration was developed. A number of actions with a general effect on Bohunice site safety is evident. All these activities are aimed at reaching the essential objective of Bohunice NPP Management - to ensure a safe, reliable and effective electric energy and heat generation at the Bohunice site. (author)

  5. Safety upgrading of Bohunice V1 NPP

    2001-01-01

    This CD is multimedia presentation of programme safety upgrading of Bohunice V1 NPP. It consist of next chapters: (1) Introductory speeches; (2) Nuclear power plant WWER 440; (3) Safety improvement; (4) Bohunice Nuclear power plants subsidiary; (5) Siemens; (6) REKON; (7) VUJE Trnava, Inc. - Engineering, Design and Research Organisation; (8) Album

  6. Bohunice V1 NPP upgrading programme

    Kerak, J.

    2001-01-01

    The paper describes whole process of Bohunice V1 NPP nuclear safety and operational reliability level increase which has been performed since units commissioning (1. unit in 1978, 2. unit in 1980), continued Small Reconstruction (1991 -1993) and finished Gradual Upgrading(1994 -2000). The main purpose is to last stage -Gradual upgrading of Bohunice V1 NPP. (author)

  7. Lifetime evaluation of Bohunice NPP components

    Kupca, L.

    2001-01-01

    The paper discuss some aspects of the main primary components lifetime evaluation program in Bohunice NPP which is performed by Nuclear Power Plant Research Institute (NPPRI) Trnava in cooperation with Bohunice and other organizations involved. Facts presented here are based on the NPPRI research report which is regularly issued after each reactor fuel campaign under conditions of project resulted from the contract between NPPRI and Bohunice NPP. For the calculations, there has been used some computer codes adapted (or made) by NPPRI and the results are just the conclusive and very brief, presented here in Tables (Figures). (authors)

  8. Safety enhancement in NPP Bohunice

    Lipar, M.; Mihalik, M.

    1997-01-01

    The upgrading and safety enhancement of both the Bohunice V-1 and V-2 reactors is described in detail. The total estimated cost of the gradual reconstruction of these two units during 1996 to 1999 is 180 mil. US dollars. For the 1995 to 1997 period, the actions common for both units include a quality assurance programme, a personnel training programme, installation of a multifunction simulator, implementation of symptom-oriented operation procedures, installation of diagnostic systems, of a site security system, and of a teledosimetric system. At present, the main maintenance tasks are: to carry out major repair of units, to remedy service interruptions, to enhance equipment service availability, to enhance the technical level of corrective actions at equipment. Investment into maintenance level upgrade has grown from 7.5 mil. Slovak crowns in 1994 to estimated 32 mil. in 2000. The partners of international cooperation are mentioned. (M.D.)

  9. Heat delivery from Bohunice NPP, Slovakia

    Paley, I.

    1998-01-01

    Experience with nuclear district heating in the Slovak Republic is reported. The heating system of the town of Trnava is supplied by the Bohunice NPP and conventional sources. Construction of the hot water heating system from the Bohunice NPP began in 1983. Commercial operation began on 10 December 1987. Heat delivery has gradually increased from 478 TJ in 1988, to 1,104 TJ in 1995. The heat cost is low, resulting in an increasing number of consumers. (author)

  10. Bohunice Simulator Data Collection Project

    Cillik, Ivan; Prochaska, Jan

    2002-01-01

    The paper describes the way and results of human reliability data analysis collected as a part of the Bohunice Simulator Data Collection Project (BSDCP), which was performed by VUJE Trnava, Inc. with funding support from the U.S. DOE, National Nuclear Security Administration. The goal of the project was to create a methodology for simulator data collection and analysis to support activities in probabilistic safety assessment (PSA) and human reliability assessment for Jaslovske Bohunice nuclear power plant consisting of two sets of twin units: two VVER 440/V-230 (V1) and two VVER 440/V-213 (V2) reactors. During the project training of V-2 control room crews was performed at VUJE-Trnava simulator. The simulator training and the data collection were done in parallel. The main goal of BSDCP was to collect suitable data of human errors under simulated conditions requiring the use of symptom-based emergency operating procedures (SBEOPs). The subjects of the data collection were scenario progress time data, operator errors, and real-time technological parameters. The paper contains three main parts. The first part presents preparatory work and semi-automatic computer-based methods used to collect data and to check technological parameters in order to find hidden errors of operators, to be able to retrace the course of each scenario for purposes of further analysis, and to document the whole training process. The first part gives also an overview of collected data scope, human error taxonomy, and state classifications for SBEOP instructions coding. The second part describes analytical work undertaken to describe time distribution necessary for execution of various kinds of instructions performed by operators according to the classification for coding of SBEOP instructions. It also presents the methods used for determination of probability distribution for different operator errors. Results from the data evaluation are presented in the last part of the paper. An overview of

  11. Bohunice Simulator Data Collection Project

    Cillik, I.; Prochaska, J.

    2002-01-01

    The paper describes the way and results of human reliability data analysis collected as a part of the Bohunice Simulator Data Collection Project (BSDCP), which was performed by VUJE Trnava, Inc. with funding support from the U.S. DOE, National Nuclear Security Administration. The goal of the project was to create a methodology for simulator data collection and analysis to support activities in probabilistic safety assessment (PSA) and human reliability assessment for Jaslovske Bohunice nuclear power plant consisting of two sets of twin units: two VVER 440/V-230 (V1) and two VVER 440/V-213 (V2) reactors. During the project, training of V-2 control room crews was performed at VUJE Trnava simulator. The simulator training and the data collection were done in parallel. The main goal of BSDCP was to collect suitable data of human errors under simulated conditions requiring the use of symptom-based emergency operating procedures (SBEOPs). The subjects of the data collection were scenario progress time data, operator errors, and real-time technological parameters. The paper contains three main parts. The first part presents preparatory work and semi-automatic computer-based methods used to collect data and to check technological parameters in order to find hidden errors of operators, to be able to retrace the course of each scenario for purposes of further analysis, and to document the whole training process. The first part gives also an overview of collected data scope, human error taxonomy, and state classifications for SBEOP instructions coding. The second part describes analytical work undertaken to describe time distribution necessary for execution of various kinds of instructions performed by operators according to the classification for coding of SBEOP instructions. It also presents the methods used for determination of probability distribution for various operator errors. Results from the data evaluation are presented in the last part of the paper. An overview of

  12. Operational experiences feedback in Bohunice NPP

    Betak, A [NPP Bohunice (Slovakia)

    1997-10-01

    The presentation reviews the following issues: OEF team in Bohunice NPP - structure; training and qualification: ASSET seminars on Prevention of incidents - INES manual handling, NRA-NRC the training on event investigation methods, NU - the training on HPES; legislation - documentation prepared in the frame of QA programme; results of OEF team activities; ASSET mission Dukovany - Experiences; the perspective activities.

  13. Foreword by the director of Bohunice NPPs

    1998-01-01

    In this foreword the director briefly describes activities of the NPP Bohunice in 1997. Main activities were: electric and heat production , the V-1 NPP Gradual Reconstruction Programme, nuclear safety programmes, environment protection, international co-operation as well as national and international public information

  14. NPP Bohunice experience with ASSET services

    Klimo, J.

    1996-01-01

    The general description of Bohunice NPP ASSET experience history was given at the last annual workshop in 1995. In my short presentation I would like to pay attention to the progress in this area which was achieved at our NPP during the last year. (author)

  15. NPP Bohunice experience with ASSET services

    Klimo, J [Bohunice NPP (Slovakia)

    1997-12-31

    The general description of Bohunice NPP ASSET experience history was given at the last annual workshop in 1995. In my short presentation I would like to pay attention to the progress in this area which was achieved at our NPP during the last year. (author).

  16. Slovak Electric, plc, Bohunice Nuclear Power Plant

    1999-01-01

    A brief account of activities carried out by the Bohunice Nuclear Power Plant in 1998 is presented. These activities are reported under the headings: (1) Operation and electric power generation; (2) Nuclear and radiation safety; (3) Maintenance and scheduled refuelling out-gages; (4) Investment and WWER units upgrading; (5) Power Plants Personnel; (6) Public relations

  17. Personnel education and training at Bohunice NPP

    Malovec, J.

    1998-01-01

    Procedure for education and training of all the personnel employed at Bohunice Nuclear power plant is presented in detail describing the training system structure, kinds of training, staff members qualification development, short term and long term tasks needed to assure attaining the training objectives. The proposed Staff Members Lifetime education implementation project contains basic starting points, measures to be implemented by 1998. It was prepared on the basis of a primary analysis which confirmed the existing need for implementing the lifetime education system

  18. Experience of Bohunice V-1 NPP

    Dobik, Dobroslav

    2000-01-01

    Slovakia remains significantly dependent on imports of primary energy sources, which represent as much as 80% of the demand. Of the total consumption of electricity in Slovakia, 40% was generated in nuclear power plant units in 1998. Slovakia operates 6 units with WWER 440 nuclear reactors. Slovakia is the signatory of all important international agreements and conventions in the field of nuclear energy, and its legislation is in an advanced stage of approximation to European Union law. This is a very important aspect, showing Slovakia's approach to nuclear safety. In 1993 Slovakia accepted the commitments of the UN Convention on Climate Changes, including a reduction of greenhouse gases to 1990 levels by the year 2000. Moreover, as an internal target Slovakia has set the reaching of the 'Toronto Objective', i.e. 20% reduction in CO x , emissions through the year 2005 as compared to 1988. In our opinion, this is not possible without nuclear energy. Time has shown, that the political aspects are more powerful, especially if you underestimate their importance over the than the technical ones. In the case of Bohunice V-1 NPP the political aspects were on the following levels: 1. Slovak republic (Czechoslovakia), political changes, decisions of the government; 2. European Union - Agenda 2000, Accession criteria, nuclear safety criteria, EBRD; 3. Austria as a neighbouring country. Starting with year 1990, 23 expert missions took place at Bohunice V-1 NPP by now. The only criteria for further operation should have been Nuclear safety, which is supervised by NRA SR. It was fully in compliance with EU policy, each country is solely responsible for its energy sector and for nuclear energy use. Our satisfaction lasted not too long. Following negotiation with EU on the highest political level, driven by willingness to be invited for negotiation of accession on the Helsinki Summit, the Slovak government decided on September 14th, on Bohunice V-1 Units shutdown in 2006 and 2008

  19. Optimization of radiation protection at Bohunice NPP

    Dobis, L.; Svitek, J.

    2003-01-01

    Bohunice Nuclear Power Plant is situated in south - western part of Slovakia about 50 km away from Bratislava. There are four PWR reactors 440 MW e each - two units with reactors WWER - 230 (V1 NPP) and two units with WWER - 213 (V2 NPP). requirements for the optimization process are given in the mentioned Code No.12 of Ministry of Health. Code 12 stipulates the technical and organizational requirements for proving the Rational Achievable Level (RAL) of radiation protection. This level can be proved by means of the comparison of the dose distribution to the costs of protection. An example of two figures of dose constraints is: collective dose 20 man mSv for the specific task; individual exposure 1 mSv per day. The values of the financial equivalents of personal exposure - so called the alpha coefficients - are used for the calculation of the benefit of proposed measures. Impact of legislative changes into Bohunice NPP and optimization process are presented. Apparently the new law and the associate code created a base of transparent and understandable policy of radiation protection and optimization in Slovak Republic. The radiation protection legislative was implemented into the praxis and persons became familiar with it. Defining clear and unambiguous terms facilitated the communication between users and the regulatory body - State Health Institute. Optimization was generally accepted by the workers and managers and began to be a part of safety culture of operation at nuclear power plants. (authors)

  20. Backfitting of Nuclear Power Plant Bohunice V1 in Slovakia

    Ferenc, M.

    1999-01-01

    Nuclear power plants in the Slovak Republic generate almost 55 % of electricity. The operating organization and the Nuclear Regulatory Authority of the Slovak Republic pay a great attention to safe and reliable operation of four units with VVER 440 reactors at Bohunices site and one in Mochovce side. Engineering and design organizations in cooperation with well known international companies prepare evaluation of safety conditions, safety analyses and projects for the implementation of modifications to upgrade the nuclear safety of the units in operation. A gradual safety upgrading (reconstruction) of the V-1 Bohunice plant has been in progress, a modernization of the V-2 Bohunice plant is being prepared. Simultaneously the commissioning of Unit 2 at the Mochovce plant is being implemented.(author)

  1. Risk-informed decision making during Bohunice NPP safety upgrading

    Lipar, M.; Muzikova, E.; Kubanyi, J.

    2001-01-01

    The paper summarizes some facts of risk-informed regulation developments within UJD regulatory environment. Based on national as well as international operating experience and indications resulted from PSA, Nuclear Regulatory Authority of the Slovak Republic (UJD) since its constituting in 1993 has devoted an effort to use PSA technology to support the regulatory policy in Slovakia. The PSA is considered a complement, not a substitute, to the deterministic approach. Suchlike integrated approach is used in decision making processes and the final decision on scope and priorities is based on it. The paper outlines risk insights used in the decision making process concerning Bohunice NPP safety upgrading and focuses on the role of PSA results in Gradual Reconstruction of Bohunice VI NPP. Besides, two other examples of the PSA results application to the decision making process are provided: the assessment of proposal of modifications to the main power supply diagram (incorporation of generator switches) and the assessment of licensee request for motor generator AOT (Allowable Outage Time) extension. As an example of improving support of Bohunice V-2 risk-informed operations, concept of AOT calculations and Bohunice V-2 Risk Monitor Project are briefly described. (author)

  2. The Bohunice NPP V-1 units nuclear safety upgrading

    Mlcuch, M.

    2000-01-01

    Safety upgrading and operational reliability improvement was carried out by the Bohunice NPP V-1 staff continuously since the plant commissioning. By now, more than 1200 minor or major modifications have been implemented, either by the NPP maintenance staff or by the contractors. Based on findings of safety assessment missions invited by Bohunice NPP in 1990 - 1991, the Czecho-slovak Nuclear Regulatory Authority (CSKAE) issued the decision No. 5/91 of 81 safety upgrading measures to be taken in different areas. These improvements are referred to as the 'Small Reconstruction of the Bohunice V-1 NPP'. Realization of measures during Small reconstruction of the Bohunice NPP V-1 became a power plant, which further operation is acceptable from safety point of view, but it is also necessary further safety improvement. During the period of the Small Reconstruction the development of a Safety Report for the Gradual reconstruction has been completed. Based on this report the SR Nuclear Regulatory Authority issued the Decision No. 1/94, in which requires 59 upgrading measures in different areas to be addressed. The development of Basic Engineering of the Gradual Reconstruction has been contracted to the Siemens AG. Implementation of safety measures are provided through contract with the consortium REKON (which consists of Siemens AG company and Nuclear Power Plants Research Institute Trnava) and other Czech, Russian and Slovak companies. The Gradual Reconstruction of Bohunice NPP V-1 will be finished in 2000. By implementation of the measures carried out during Gradual Reconstruction achievement of an internationally acceptable nuclear safety level will be reached. (author)

  3. Bohunice V-1 and V-2 approach for achieving high availability, reliability and safety

    Lipar, M.; Kerak, J.; Rohar, S.

    1998-01-01

    Long term operating experience of Bohunice units maintenance activities are overviewed in the paper. Based on common experience of WWER NPP operators, separate maintenance department was established at Bohunice NPP in very early stage of plant operation. Maintenance management, maintenance planning, outage management, diagnostics and monitoring, inspection technologies and backfitting activities are described particularly to demonstrate the capability of Bohunice maintenance department for most complex repairs and maintenance works of nuclear power plant components and equipment, including reactor and turbine itself. (author)

  4. Fuel leak testing performance at NPP Jaslovske Bohunice

    Slugen, V.; Krnac, S.; Smiesko, I.

    1995-01-01

    The NPP Bohunice VVER-440 fuel leak testing experience are relatively extensive in comparison with other VVER-440 users. As the first Europe NPP was adapted Siemens (KWU) in core-sipping equipment to VVER-440 units and since this time were have done these tests also for NPP Paks (Hungary) and NPP Dukovany (Czech Republic). The occurrence of leaking fuel assemblies in NPP is in the last 5 years relatively stabilised and low. A significant difference can be observed between type V-230 (31 leaks) and type V-213 (1 leak). None of of the indicated leaking fuel assemblies has been investigated in the hot cell. Therefore cannot be confirm the effective causes of leak occurrence. Nevertheless, the fuel failure rate and the performance of leak testing in NPP Bohunice are comparable to the world standard at PWR's. 1 tab., 2 figs., 3 refs

  5. Fuel leak testing performance at NPP Jaslovske Bohunice

    Slugen, V; Krnac, S [Slovak Technical Univ., Bratislava (Slovakia); Smiesko, I [Nuclear Powr Plant EBO, Jaslovske Bohuce (Slovakia)

    1996-12-31

    The NPP Bohunice VVER-440 fuel leak testing experience are relatively extensive in comparison with other VVER-440 users. As the first Europe NPP was adapted Siemens (KWU) in core-sipping equipment to VVER-440 units and since this time were have done these tests also for NPP Paks (Hungary) and NPP Dukovany (Czech Republic). The occurrence of leaking fuel assemblies in NPP is in the last 5 years relatively stabilised and low. A significant difference can be observed between type V-230 (31 leaks) and type V-213 (1 leak). None of of the indicated leaking fuel assemblies has been investigated in the hot cell. Therefore cannot be confirm the effective causes of leak occurrence. Nevertheless, the fuel failure rate and the performance of leak testing in NPP Bohunice are comparable to the world standard at PWR`s. 1 tab., 2 figs., 3 refs.

  6. Slovak power stations, Nuclear power plants Jaslovske Bohunice. (Annual report 1997)

    1998-01-01

    A brief account of activities carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. These activities are reported under the headings: (1) Foreword by the director of Bohunice NPPs; (2) Management of Bohunice NPPs Subsidiary Plant; (3) The most significant events of the year 1997; (4) Electricity and heat production; (5) Safety; (6) Bohunice NPPs operation impact on environment; (7) The V-1 NPP and V-2 NPP upgrading; (8) Maintenance; (9) Capital construction; (10) Economic balance; (11) International co-operation; (12) Human sources; (12) Public relations

  7. Radiation protection in Bohunice NPP. Description of present status

    Dobis, L.

    2001-01-01

    Radiation protection (RP) at Bohunice NPP has reached the high international standard. The fact was approved by several independent international missions (OSART , WANO, WENRA, ...). A lot of modifications have been done in order to improve the standard of radiation protection. All the BSS requirements have been implemented into the plant regulations before the State Law No 290/1996 and 470/2000 came into the force. Internal audits are regularly performed at NPP in order to reveal potential deficiencies. In 2001 there were 4 such audits focused on quality assurance, software operation, LBB concept and limits and condition of safe operation. State Health Institute, the regulatory body in the radiation protection, performs the inspection at least ones a month. Good relationship with the inspectors of State Health Institute also contributes to the safe operation of the NPP. There were not any radiation accident. All anomalies or radiation events are investigated at a plant level. The results of root cause analysis and proposal of corrective actions are provided to IAEA and WANO databases for the distribution. The Radiation protection department of Bohunice NPP cooperates with the other Czech and Slovak NPPs. Regular meetings on radiation protection and lately also on emergency preparedness are organized. The cooperation is excellent. Occupational exposure is reviewed also with respect of ISOE data. Bohunice NPP (even with high dose burden caused by reconstruction of V1 NPP) can be found in the first half of world PWR speaking about the collective exposure per reactor. V2 NPP itself reaches the lowest collective exposure in the world. All doses are below the limits and kept ALARA. ALARA system has been established already in 1997 at Bohunice NPP and its results are obvious for example looking at dose results during the reconstruction works at V1 NPP. The operation of Bohunice NPP has negligible influence to its surroundings. The values of gas and liquid effluents move

  8. Seismic re-evaluation criteria for Bohunice V1 reconstruction

    Campbell, R.; Schlund, H.; Warnken, L.

    2001-01-01

    Bohunice V1 in Slovakia is a Russian designed two unit WWER 440, Model 230 Pressurized Water Reactor. The plant was not originally designed for earthquake. Subsequent and ongoing reassessments now confirm that the seismic hazard at the site is significant. EBO, the plant owner has contracted with a consortium lead by Siemens AG (REKON) to do major reconstruction of the plant to significantly enhance its safety systems by the addition of new systems and the upgrading of existing systems. As part of the reconstruction, a complete seismic assessment and upgrading is required for existing safety relevant structures, systems and components. It is not practical to conduct this reassessment and upgrading using criteria applied to new design of nuclear power plants. Alternate criteria may be used to achieve adequate safety goals. Utilities in the U.S. have faced several seismic issues with operating NPPs and to resolve these issues, alternate criteria have been developed which are much more cost effective than use of criteria for new design. These alternate criteria incorporate the knowledge obtained from investigation of the performance of equipment in major earthquakes and include provisions for structures and passive equipment to deform beyond the yield point, yet still provide their essential function. IAEA has incorporated features of these alternate criteria into draft Technical Guidelines for application to Bohunice V1 and V2. REKON has developed plant specific criteria and procedures for the Bohunice V1 reconstruction that incorporate major features of the U.S. developed alternate criteria, comply to local codes and which envelop the draft IAEA Technical Guidelines. Included in these criteria and procedures are comprehensive walkdown screening criteria for equipment, piping, HVAC and cable raceways, analytical criteria which include inelastic energy absorption factors defined on an element basis and testing criteria which include specific guidance on interpretation

  9. Fire fighting precautions at Bohunice Atomic Power Plants

    Anon.

    1984-01-01

    Some shortcomings are discussed of the project design of fire protection at the V-1 and V-2 nuclear power plants. The basic shortcoming of the system is insufficient division of the units for fire protection. Fire fighting measures are described for cable areas, switch houses and outside transformers, primary and secondary circuits and auxiliary units. Measures are presented for increasing fire safety in Jaslovske Bohunice proceedi.ng from experience gained with a fire which had occurred at a nuclear power plant in Armenia. (E.S.)

  10. Bohunice V-1. Review of safety upgrading and operating experiences

    Korec, J.; Kuschel, D.

    2000-01-01

    The Bohunice site in the Slovak Republic has two Russian-designed twin-unit nuclear power plants, one equipped with reactors of the WWER 440/230 type, the other with type WWER 440/213 reactors. Two older units (V-1) started commercial operation in late 1978 and 1980 respectively and have been supplying electricity to the national grid since that time without any events that could have degraded plant safety level. In the period prior to 1990 the utility Slovenske Elektrarne (S.E.) performed extensive modifications and upgrades to the original design of the two older units V-1 NPP. Furthermore, significant steps in safety improvement for Bohunice NPP V-1 have been made since 1990. Following the political restructuring of the former Czechoslovakia and the country's new open-door policy towards western organizations, several international expert missions were focused on evaluation of Bohunice NPP safety status level and operational reliability, particularly targeting the two older units. Based on recommendations of individual expert missions and complementary deterministic and probabilistic safety analyses performed by S.E., the Czechoslovak Nuclear Regulatory Authority issued the Resolution No. 5/91 defining 81 measures concerning further safety and reliability improvement of Bohunice V1 .A range of short-term and long-term upgrades was prioritised in terms of importance to plant safety and work to implement these measures commenced in the early nineties. During the 'Small Reconstruction' from 1991 to 1993 some of the short term upgrading measures were realized to eliminate the most serious safety deficits, thus to achieve a significant reduction in core damage frequency and a major improvement in confinement integrity. In this paper and presentation the goals of the gradual reconstruction project, basic engineering, detailed engineering and realization, last major stage of Unit 2 upgrade, as well as final stage of Unit 1 upgrade in early 2000 are presented

  11. Reuse of discharged fuel in Bohunice-1,2 units

    Chrapciak, V.; Majercik, J.; Kacmar, M.

    2003-01-01

    During the reconstruction of Bohunice-1,2 units (1997 - 2001), their cycle lengths dropped to very short values. Because of 4-year limit to fuel residence time, refuelling with fresh 2.4 % enriched assemblies seemed to be a solution of the problem. The paper describes the implementation of a final decision to reuse 3.6 % enriched fuel discharged after 3-year irradiation in previous cycles. This decision led to a large-scale moving of discharged assemblies from spent fuel pools back to reactors (Authors)

  12. New Emergency control center of Slovenske Elektrarne Bohunice NPP

    Pecko, E.

    2012-01-01

    Emergency preparedness of nuclear power plant and operation assurance in case of a possible emergency calls to have devices for emergency response with equipment for rapid detection and continuous evaluation of anticipated events. Chief executive body designated to manage a nuclear power plant during major events is the emergency committee (EC). Emergency Committee is a part of the Emergency Response Organization (ERO). The following centers are on alert to ensure the activities of the ERO - Emergency Response office: - control room (CR) and emergency control room (ECR); - emergency management center (EMC); - Monitoring Centre (MC); - emergency backup control center (EBCC); - congregations of civil protection (CP) and CP shelters; - communications with warning and notification system (VARVYR). From a historical and practical point of view in the vicinity of Jaslovske Bohunice has been set up a joint emergency control center. The center was located on the territory of the former already inoperative V1 NPP. V1 NPP is currently integrated into the organizational structure of JAVYS. Operating Bohunice V2 NPP plant is a designated part of the Slovenske Elektrarne, a. s., whose majority owner is an Italian operator ENEL. In terms of various relevant factors, it was decided to build a new emergency management center on the territory of operating V2 NPP, meet the current standards.

  13. Bohunice NPPs - Part of the Slovak's economy (sustainable) development

    Dobak, Dobroslav

    2001-01-01

    Of the total consumption of electricity in Slovakia, 42% was generated in nuclear power plant units in 1999. Slovakia operates 6 units with a WWER 440 nuclear reactors, 4 of them are at Bohunice site and 2 at Mochovce. The Nuclear Regulatory Authority of SR is not the only regulatory body controlling nuclear activity. Both - the system of nuclear activities regulation in Slovakia as well as the approach to Nuclear Safety enhancement of the operator were positively judged by IAEA and WENRA. In 1993 -Slovakia has accepted the commitments of the UN Convention on Climate Changes, including a reduction of greenhouse gases to 1990 levels by the year 2000. Moreover, as an internal target Slovakia has set the reaching of the ,'Toronto Objective', i.e. 20% reduction in CO x emissions through the year 2005 as compared to 1988. Taking into account the actual situation as well as natural conditions for some renewable sources utilisation, the target won't be reached without nuclear energy. The nuclear energy is free of emissions, does not burn oxygen, and with the share of production in Slovakia will remain significant contributor. To the environment protection it contributes also by replacing fossil heat plants with heat delivery for the region. In case of radiological wastes the environment protection is ensured by very strict system of control, evidence, treatment and repository. To conclude, Bohunice NPPs were, are and will remain very important part of the Slovak's economy, creating conditions for its (sustainable) development

  14. Safety improvement programme of WWER 440/230 units in Jaslovske Bohunice

    Tomek, J.

    2000-01-01

    A brief overview is given of the power sources in Slovakia which include 6 operational reactor units (4 at Jaslovske Bohunice and 2 at Mochovce) and 2 units under construction (at Mochovce). The efforts undertaken in the past 10 years and aimed at upgrading the nuclear safety of the two older (V-230 Soviet type) units at Bohunice are highlighted. The relevant regulatory decisions are dealt with and the measures already carried out are listed. Also characterized are several IAEA international safety assessment missions and safety-aimed meetings which took place in 1998 and 1999 and are of concern to the older Bohunice units. (A.K.)

  15. Monitoring of activity of the persons and vehicles at the exit from the NPP Bohunice

    Dobis, L.; Kaizer, J.; Svitek, J.

    1998-01-01

    In this paper the technical description of the monitoring of activity of the persons and vehicles at the exit from the NPP Bohunice as well as the results of monitoring during last six months are described

  16. REKO - Bohunice V-1. Experience with instrumentation and control system

    Arbet, L.; Ziska, D.; Golan, P.; Karaba, P.; Krupa, S.; Wiening, K.-H.

    2000-01-01

    In this paper and in presentation some results of upgrading of the NPP Bohunice V-1 are presented. For the first time, extensive upgrades are performed in all safety-related areas of both units with VVER 440/230 reactors. These upgrades focused on: - Expansion and upgrading of the process safety systems; - Replacement of the safety I and C system with a TELEPERM XS-based system; - Spatial separation of safety equipment; - Modernisation of the electrical auxiliary power systems; - Seismic upgrading and fire protection; - Improvement of the man-machine interface. This upgrade is considered exemplary around the world. The most extensive stage of gradual reconstruction of Unit 2 was completed according to the schedule in January 1999. For the first time, a reactor which incorporates state-of-the-art digital I and C in its reactor protection system is on-line. (author)

  17. District heating by the Bohunice nuclear power plant

    Metke, E.; Skvarka, P.

    1984-01-01

    Technical and economical aspects of district heating by the electricity generating nuclear plants in Czechoslovakia are discussed. As a first stage of the project, 240 MW thermal power will be supplied using bleeding lines steam from the B-2 nuclear power plant at Jaslovske Bohunice to heat up water at a central station to 130 grad C. The maximal thermal power that can be produced for district heating by WWER type reactors with regular condensation turbines is estimated to be: 465 MW for a WWER-440 reactor with two 220 MWe turbines and 950 MW for a WWER-1000 reactor with a Skoda made 1000 MWe turbine using a three-stage scheme to heat up water from 60 grad C to 150 grad C. The use of satelite heating turbines connected to the steam collector is expected to improve the efficiency. District heating needs will de taken into account for siting of the new power plants

  18. Seismic evaluation and strengthening of Bohunice nuclear power plant structures

    Shipp, J.G.; Short, S.A.; Grief, T.; Borov, V.; Kuzma, J.

    2001-01-01

    A seismic assessment and strengthening investigation is being performed for selected structures at the Bohunice V1 Nuclear Power Plant in Slovakia. Structures covered in this paper include the reactor building complex and the emergency generator station. The emergency generator station is emphasized in the paper as work is nearly complete while work on the reactor building complex is ongoing at this time. Seismic evaluation and strengthening work is being performed by a cooperative effort of Siemens and EQE along with local contractors. Seismic input is the interim Review Level Earthquake (horizontal peak ground acceleration of 0.3 g). The Bohunice V1 reactor building complex is a WWER 4401230 nuclear power plant that was originally built in the mid-1970s but had extensive seismic upgrades in 1991. Siemens has performed three dimensional dynamic analyses of the reactor building complex to develop seismic demand in structural elements. EQE is assessing seismic capacities of structural elements and developing strengthening schemes, where needed. Based on recent seismic response analyses for the interim Review Level Earthquake which account for soil-structure interaction in a rigorous manner, the 1991 seismic upgrade has been found to be inadequate in both member/connection strength and in providing complete load paths to the foundation. Additional strengthening is being developed. The emergency generator station was built in the 1970s and is a two-story unreinforced brick masonry (URM) shear wall building above grade with a one story reinforced concrete shear wall basement below grade. Seismic analyses and testing of the URM walls has been performed to assess the need for building strengthening. Required structural strengthening for in-plane forces consists of revised and additional vertical steel framing and connections, stiffening of horizontal roof bracing, and steel connections between the roof and supporting walls and pointing of two interior transverse URM

  19. Chemistry monitoring and diagnostic system at NPP Jaslovske Bohunice

    Smiesko, Ivan; Figedy, Stefan

    2012-09-01

    This paper provides a description of water chemistry monitoring and diagnostic system installed at Slovak NPP Jaslovske Bohunice. System has complex architecture and covers laboratory data, chemistry and radiochemistry on-line monitoring data, process data acquisition and processing and diagnostics. Pre-filtered data from process computer and chemistry on-line monitors are recorded together with laboratory data in the ORACLE-based information system CHEMIS with many presentation and processing features. Brief information is given about the basic features of a newly developed diagnostic system for early detection and identification of anomalies incoming in the water chemistry regime of the primary and secondary circuit of VVER-440 type unit. This system, called SACHER (System of Analysis of Chemical Regime) has been installed within the major modernization project at the NPP Bohunice in the Slovak Republic. System SACHER has been developed fully in MATLAB environment. Diagnostic system works exclusively with available on-line data as an operation personnel support application allowing effective response to adverse chemistry events/trends. The availability of prompt information about the chemical conditions of the primary and secondary circuit is very important in order to prevent the undue corrosion and deposit build-up processes within the plant systems. The typical chemical information systems that exist and work at the NPPs give the user values of the measured quantities together with their time trends and other derived values. It is then the experienced user's role to recognize the situation the monitored process is in and make the subsequent decisions and take the measures. The SACHER system, based on the computational intelligence techniques, inserts the elements of intelligence into the overall chemical information system. It has the modular structure with the following most important modules: - normality module- its aim is to recognize that the process

  20. Monitoring of Persons at the Exit from Bohunice NPP

    Kaizer, J.; Svitek, J.

    2001-01-01

    Full text: IAEA defines the principal requirement 'defence in depth' as a multilayer system in its authorised document - International Basic Safety Standards for Protection against Ionising Radiation, Safety Series No. 115. The principle of the multilayer system is: a failure at one zone is compensated or corrected at subsequent zones. The main argument why Bohunice NPP modernised its monitoring system at the exit from NPP was the implementation of the principle 'defence in depth'. Several instruments PM7 (Eberline) equipped with the plastic scintillation detectors had been bought because of the modernisation. The instruments had to be integrated into overall security system NPP without any restriction to the number of passing people. The supplier had to modify the basic instrument operation. NPP required a 'dynamic' monitoring version, this means the operation without stopping of a person within the instrument. After the modification the value of the RDA (Reliable Detectable Activity) of the instruments PM7 was within the interval 9.25-10.4 kBq for 137 Cs (dotted source in the middle of the instrument). RDA for the mix of activation products was 2-3 times lower. In conclusion of our paper the results of the monitoring are presented within tree years as well as a discussion about these results. Maximum values of contaminations measured were very low (several kBq) that represented very low risk from potential exposure. (author)

  1. Mitsubishi nuclear technologies and construction of new Bohunice

    Yoshizu, T.

    2009-01-01

    Mitsubishi Heavy Industries (MHI) has setup Generation III+ category power plant technologies both in large and middle size reactors as a key player in the global market of nuclear plant suppliers. MHI has developed 1,700 MWe class Advanced Pressurized Water Reactor for European utilities, EU-APWR, utilizing the APWR technology in Japan. The plant configuration is based on the proven technologies from MHI's ample experiences, but various advanced technologies are adopted to achieve enhanced safety, reliability, and economy. For the regions without large grid capacity, middle-sized nuclear power plant will be an attractive option for the utilities. Joint Venture ATMEA with AREVA NP will serve ATMEA1. The ATMEA1 will offer 1,100 MWe output with superior operation performance based on reliable and proven technologies. Mitsubishi has experience of half century for all of 26 PWR plants in Japan. The latest plant is Tomari Unit 3 of 1,000 MWe, which has completed the construction work and now in the final commissioning test. Tomari Unit 3 applies some advanced technologies such as all digital I and C, which are to be implemented in the EU-APWR. Based on this construction experience, Mitsubishi can contribute any kind of demands for New Bohunice 5 th unit project with the total engineering capability. (author)

  2. Information about environmental effects of Bohunice NPPs V-1 and V-2 within February 2002

    2002-01-01

    In this leaflet the results of monitoring of chemical gaseous and liquid effluents into the rivers Vah and Dudvah as well as of radiation monitoring of Bohunice V-1 and V-2 NPPs are presented. The radioactive effluents within a February 2002 (for NPP V-1 and NPP V-2, respectively) were: 0.571 TBq and 0.664 TBq of rare gases, 0.711 MBq and 0.244 MBq of aero-soles, 2.121 MBq and 0.138 MBq of iodine, 2.022 MBq and 0.564 MBq of corrosive and fission products, and 1.420 TBq and 1.643 TBq of tritium. For the period January - February 2002 these radioactive effluents represent for rare gases 1.286 TBq for NPP V-1 and 1.475 TBq for NPP V-2 (2.761 TBq (0.069% of annually limit (AL) for the locality Bohunice), for aerosols 2.645 MBq for NPP V-1 and 0.542 MBq for NPP V-2 (3.187 MBq (0.002% of AL for the locality Bohunice), for corrosive and fission products 3.848 MBq for NPP V-1 and 1.510 MBq for NPP V-2 (5.358 MBq (0.01% of AL) for the locality Bohunice), and for iodine 2.616 MBq for NPP V-1 and 0.279 MBq (2.894 MBq (0.002% of AL) for the locality Bohunice), and for tritium it is 2.395 TBq for NPP V-1 and 3.532 TBq for NPP V-2 (5.358 TBq (13.56% of AL) for the locality Bohunice

  3. Preliminary results of scoop samples analysis from reactor pressure vessels of Bohunice V-1 NPP

    Kupca, L.

    1997-01-01

    In the paper are presented the main goals and results from the scoop specimen analysis performed on the both RPVs WWER-440/230 in Jaslovske Bohunice V-1 NPPs. Main tasks of this complex activity were: model experiments for analysis procedures optimisation; chemical analysis; hardness measurements on the RPV and bulk samples; microstructure analysis; scanning electron microscope and microprobe analysis; gamma spectrometry; brittle fracture temperature evaluation; trends of brittle fracture temperature growth after annealing procedure. In conclusions and recommendations are discussed the planned activities in the field of both RPVs integrity evaluation for the future operation of the NPP Jaslovske Bohunice V-1. (author)

  4. The common project for completion of Bubbler Condenser Qualification (Bohunice, Mochovce, Dukovany and Paks NPPs)

    Jaroslav, H.; Pavol, B.

    2003-01-01

    Described is the common project for completion of bubbler condenser qualification for nuclear power plants in Bohunice, Mochovice, Dukovany and Paks. Functionality of the bubbler condenser was elaborated during the simulation of the main steam line brake, medium break and small break LOCA. On this basis the appropriate operation of bubbler condenser containment under accident conditions can be positively confirmed

  5. Operation diagnostics of the reactor coolant pumps in the Jaslovske Bohunice nuclear power plant, CSSR

    Bahna, J.; Jaros, I.; Oksa, G.

    1990-01-01

    The state of the art of the materials basis, the diagnostics methods used, organization of data collection and processing, and some results of routine and specific investigations concerned with diagnosis of the reactor coolant pump in the Jaslovske Bohunice NPP V-1 are presented. Some information is given about the reactor coolant pump monitor developed in the VUJE. (author)

  6. Modernization and safety improvement project of the NPP V-2 Jaslovske Bohunice

    Michal, V.; Losonsky, B.; Magdolen, J.

    2000-01-01

    This contribution deals with the form, present state, and results of the Nuclear Power Plants Research Institute (the Slovak acronym is VUJE - Vyskumny Ustav Jadrovych Elektrarni) participation in the NPP V-2 Jaslovske Bohunice Modernization and Safety Improvement Project. A short description of VUJE history, activity, and results is also presented as well as NPPs Jaslovske Bohunice characterization. VUJE was established in 1977 and deals with scientific and research needs of nuclear power plants, such as design, construction, commissioning and operation. The next fields of VUJE activity are, NPP reconstruction, NPP personnel training, radioactive waste management technology, and NPP decommissioning. The nuclear power plant, Jaslovske Bohunice, is situated approximately 15 km from the district town of Trnava in the southwestern region of the Slovak Republic. The construction of the first Czechoslovak NPP A-1 began on this site in 1957 .The construction of the double-unit NPP V-1 with WWER-440 (type V-230) reactor began in 1972. The first unit of NPP V-1 began operation in 1978 and the second in 1980. NPPs construction on the Bohunice site continued with NPP V-2, which has two units with WWER-440 (type V-213) reactors. Unit 1 and Unit 2 of NPP V-2 were commissioned in 1984 and 1985, respectively. Slovak electric utility Slovenske elektrarne (SE) is the owner/commissioner of NPP V-2. This NPP is responsible for more than 20% of the total electrical energy production of SE, making it an essential supporter of the Slovak economy. (authors)

  7. Final results of the gradual reconstruction of Bohunice VI in Slovakia and evaluation of the reconstruction by international missions

    Ferenc, M.

    2001-01-01

    The gradual reconstruction of the Bohunice V1 nuclear power plant (Slovakia) represents the most extensive reconstruction of a nuclear power plant in operation as implemented worldwide up to now. Extensive reconstruction works in both civil construction and process parts, in instrumentation and control part, and in electric part enhanced both nuclear safety and operational reliability of Bohunice V1 in a significant way.(author)

  8. ESTE EMO and ESTE EBO - emergency response system for NPP Mochovce and NPP Bohunice V-2

    Caeny, P.; Chyly, M.; Suchon, D.; Smejkalova, E.; Fabova, V.; Mancikova, M.; Muller, P.

    2009-01-01

    Programs ESTE EMO and ESTE EBO are emergency response systems that help the crisis staff of the NPP in assessing the source term (predicted possible release of radionuclides to the atmosphere ), in assessing the urgent protective measures and sectors under threat, in assessing real release (symptoms of release really detected and observed), in calculating radiological impacts of real release, averted or avertable doses, potential doses and doses during transport or evacuation on specified routes. Both systems serve as instruments in case of severe accident (DBA or BDBA) at NPP Mochovce or NPP Bohunice, accidents with threat of release of radioactivity to the atmosphere. Systems are implemented at emergency centre of Mochovce NPP and Bohunice NPP and connected online to the sources of technological and radiological data from the reactor, primary circuit, confinement, secondary circuit, ventilation stack, from the area of NPP (TDS 1) and from the emergency planning zone (TDS 11). Systems are connected online to the sources of meteorological data, too. (authors)

  9. ESTE EMO and ESTE EBO - emergency response system for NPP Mochovce and NPP Bohunice V-2

    Caeny, P.; Chyly, M.; Suchon, D.; Smejkalova, E.; Fabova, V.; Mancikova, M.; Muller, P.

    2008-01-01

    Programs ESTE EMO and ESTE EBO are emergency response systems that help the crisis staff of the NPP in assessing the source term (predicted possible release of radionuclides to the atmosphere ), in assessing the urgent protective measures and sectors under threat, in assessing real release (symptoms of release really detected and observed), in calculating radiological impacts of real release, averted or avertable doses, potential doses and doses during transport or evacuation on specified routes. Both systems serve as instruments in case of severe accident (DBA or BDBA) at NPP Mochovce or NPP Bohunice, accidents with threat of release of radioactivity to the atmosphere. Systems are implemented at emergency centre of Mochovce NPP and Bohunice NPP and connected online to the sources of technological and radiological data from the reactor, primary circuit, confinement, secondary circuit, ventilation stack, from the area of NPP (TDS 1) and from the emergency planning zone (TDS 11). Systems are connected online to the sources of meteorological data, too. (authors)

  10. Resin intrusion into the primary circuit of NPP Jaslovske Bohunice V-1

    Grezdo, O.; Mraz, V.

    2005-01-01

    During the refueling at the first unit of Bohunice NPP in 2005 a lot of sediment was found on the upper storage rack. This sediment was identification as a filter resin. Resin was found in most of the fuel assemblies, pipes and tanks of the primary circuit and his auxiliary systems. Resin producer and WANO network was contacted in order to get information about similar events. Management of Bohunice NPP made a decision that primary circuit, fuel assemblies and auxiliary systems have to be cleaned. Subsequent cleaning extended outage by 31 days. This paper summarizes causes, existing consequences and corrective actions. Accent was put on the hydraulic characteristics of the primary circuit measurement, power distribution core monitoring and the primary circuit water quality verification (Authors)

  11. Computer modelling the potential benefits of amines in NPP Bohunice secondary circuit

    Fountain, M.J.; Smiesko, I.

    1998-01-01

    The use of computer modelling of PWR and WWER secondary circuit chemistry was already demonstrated in the past. The model was used to illustrate the technical and economic advantages, compared with ammonia, of using an 'advanced', high basicity, low volatility amines to raise the liquid phase pH(T) in the moisture separator and other areas swept by wet steam. Since the 1995, this technique has been successfully applied to a number of power plants and the computer model has been progressively developed. This paper describes the preliminary results of an ongoing assessment being carried out for the VVER 440 plants at Bohunice. The work for Bohunice is being funded by the 'Know How Fund', a department in the British Government's Foreign and Commonwealth Office. (J.P.N.)

  12. Project Management Unit for decommissioning of NPP Bohunice VI (2003-2014)

    Gonzalez Fernandez-conde, A.; Brochet, I.; Ferreira, A.

    2015-01-01

    From October 2003 until december 2014 the Consortium consisting of Iberdrola Engineering and Construction (leader). Empresarios Agrupados Internacional, and Indra Sistemas has carried out the project Project Management Unit ((PMU) for the decommissioning of Bohunice V1 NPP (units 1 and 2), type VVER-440/V-230 in Slovakia. during the first phase (2003-2007) EdF was also part of the Consortium. The project is funded by the Bohunice International Decommissioning Support Fund (BIDSF) administered by the RBRD. The main objective of the project is to provide the necessary engineering and resources of project management for planning, execution, management, coordination and monitoring of all tasks in support of the decommissioning. (Author)

  13. Twenty years of operation of WWER 440/230 units in Jaslovske Bohunice

    Tomek, J.

    1998-01-01

    It is twenty years this year since the first unit WWER 440 of Slovak Nuclear Power Plant Jaslovske Bohunice was commissioned. There are four units WWER 440 in operation Jaslovske Bohunice site. First two units of older soviet PWR design V-230 (also known as V-1) and other two units of newer V-213 type (also known as V-2). The goal of this presentation is to summarize and evaluate the operation of Unit 1 and 2 for this period of time and mainly to describe what has been done and what is planned to be done to increase the nuclear safety and operational reliability of both units. The operating organization and regulatory authority assume that an internationally acceptable level of safety will be reached by accomplishing of the upgrading program.(author)

  14. Programmes design for Bohunice NPP personnel other than control room operators

    Kalincik, L.

    2002-01-01

    This paper deals with project development of training programmes for non-licenced NPP personnel-masters, field operators, maintenance and technical supporting personnel. The programme development focuses on the part stage and on the job training at NPP. Bohunice NPP belongs to plants with higher specific number of personnel per installed power capacity. This factor also influenced the choice of programmes design. Undermentioned procedure is one of various approaches to SAT exploitation for training programmes design. (author)

  15. Forty years of atmospheric radiocarbon monitoring around Bohunice nuclear power plant, Slovakia

    Povinec, P.P.; Chudy, M.; Sivo, A.; Simon, J.; Holy, K.; Richtarikova, M.

    2009-01-01

    Radiocarbon variations in the atmospheric CO 2 with attenuating amplitudes and decreasing mean values with typical maxima in summer and minima in winter have been observed since 1967 in two localities of Slovakia, in Bratislava and Zlkovce, situated about 60 km NE from Bratislava, only 5 km from the Bohunice Nuclear Power Plant (NPP). The 14 C record in Bratislava has been influenced mainly by fossil CO 2 emissions, in contrast to the Zlkovce record which has been more variable, as it has clearly been affected by operation of the Bohunice NPP. However, during specific meteorological conditions with NE transport of air masses to Bratislava, the effect of the Bohunice NPP has been visible in Bratislava as well. Maximum 14 C concentrations (up to 120% above a natural background) were observed around A1 NPP which used CO 2 with admixture of air as a cooling agent. The 14 C concentrations around four pressurized light water reactors were up to 30% above the background. The Δ 14 C values in the heavily polluted atmosphere of Bratislava were up to 10% and at Zlkovce up to 5% lower than the European clean air represented by the Jungfraujoch Δ 14 C data. Later the Δ 14 C values were similar at both sites, and from 2003 they were close to the European clean air levels. The observed Δ 14 C behaviour in the atmosphere provides a unique evidence of decreased fossil fuel CO 2 emissions in the region, as well as the long-term effect of the Bohunice NPP on the Bratislava and Zlkovce stations. The estimated annual radiation doses to the local public due to digestion of radiocarbon contaminated food have been estimated to be around 3 μSv

  16. The Modernization Program and Power Up-rate at NPP V2 Jaslovske Bohunice, Slovak Republic

    Reznik, Vladivoj; Krajmer, Imrich

    2010-01-01

    Slovenske Elektrarne, a.s. is a second largest utility company in the Central and Eastern Europe that owns an optimal production portfolio comprised of nuclear, thermal and hydroelectric power plants. There are two nuclear power plants Bohunice and Mochovce both operate with two units and another two units Mochovce 3 and 4 are currently under construction. Electricity at Nuclear power plant Bohunice V2 is generated by two 440 MW units that had gradually been connected to the power network over the period between 1984 and 1985. In the construction of the nuclear power plant V2 the concept of pressurized water reactors was adopted and the Soviet-era design WWER 440 used. The upgrading of Nuclear Power Plant Bohunice V2 is based on three main points: Modernization, Power up-rate, and Ageing monitoring program. The main targets of the modernization project were: Increasing of the Nuclear Safety and of the Nuclear operational reliability, and Seismic improvement. This modernization program is in full compliance with IAEA requirements and with the decisions from the Nuclear Regulatory Agency of the Slovak Republic (UJD) and achievement of the probabilistic safety criteria in accordance with IAEA recommendations. Except that is ensured a safe, reliable, economical and effective electricity and heat generation. Achieved results are based for further prolongation of the operation life time up to 60 years. (authors)

  17. Commissioning tests at Bohunice NPP V1 unit 2 after reconstruction in 1998

    Pajtinka, A.; Tvaroska, V.; Wiening, K.-H.; Mueller, B.

    2000-01-01

    The last and the most extensive stage in the reconstruction project of the Bohunice NPP started in July 1998. The main activities performed during a 6-month scheduled unit 2 outage included: - Installation of a new emergency core cooling system with an increased capacity according to the defined broader break spectrum for LOCA; - Reconstruction of the existing confinement spray system and installation of a new confinement pressure suppression system; - Completion of upgrading measures to increase the reliability of emergency power supply systems (replacement of low voltage switchgear, installation of new cabling for all loads important to safety, installation of new motor-generators and rectifier sets); - Connection to the plant and commissioning of the new reactor protection system. Comprehensive tests and checks performed on completion of installation work on the modified mechanical, electrical and I and C systems were important reasons for the absence of major problems during restart of the unit after the several project implementation phases. Operating experience at unit 2 since its recommissioning in January 1999 has confirmed that the required safety standards have been met and that operational reliability has been substantially increased at the sometime. Periodic testing is being performed in accordance with the limits and conditions for safe operation of Bohunice NPP. To date all these tests were completed without significant problems. The functions implemented in the new technology met the test program criteria, which were approved with authority, in all essential areas. Through the close cooperation of the partners involved and through the combined efforts of the various engineering and operating disciplines, technical and scheduling problems could be immediately identified and quickly resolved. In general, these kinds of projects require optimum cooperation among the parties involved. Modernization of the NPP Bohunice V1 unit 2 has shown, that all

  18. Current status of LTO licensing programme for Bohunice nuclear power plant

    Borak, J.; Kupca, L.

    2012-01-01

    The objective of long term operation (LTO) licensing programme for Bohunice nuclear power plant is to demonstrate that the relevant structures and components shall perform their functions throughout the entire LTO period during which they shall meet all the relevant safety requirements. All the activities-which should result in utility's request to obtain the licence for LTO-must be performed in line with the relevant legal basis. As of May 2012, the anticipated duration of currently running programme is thirteen months. All relevant documentation, required by the established legal basis, shall be submitted to the licensing authority one year before the Unit 3 design life expiry. (author)

  19. Design of fuel loading for Bohunice V-1 Unit 2 reaktor for fuel cycle No.19

    Majercik, J.

    1998-01-01

    The report contains description of the design of fuel loading for the fuel cycle No. 19 in the V-1 Bohunice Unit 2 reactor. Input data and computer codes used for the development of the design are shown. The fuel loading is characterized by the assortment of the fuel loaded and by the scheme of re shuffling of assemblies in the core. An evaluation of basic neutronic core parameters as relates to the compliance with safety criteria is a part of the report as well

  20. Practical experience with the leaky-fuel monitoring at Bohunice NPP

    Kacmar, M.; Cizek, J.

    2001-01-01

    The first part of this paper describes practical experience with the fuel monitoring in operating reactors from point of view possible leakages. Summarized in the paper are numbers leaky fuel assemblies both for NPP and for particular units. Some failure causes are discussed for operational conditions of Bohunice NPP. In the second part of paper critical power ramps on hot fuel rod of leaky fuel assemblies are analysed to eliminate failures from PCI. The main aim of the paper is the need to understand the mechanism and causes of failures (Authors)

  1. Environment monitoring and residents health condition monitoring of nuclear power plant Bohunice region

    Letkovicova, M.; Rehak, R.; Stehlikova, B.; Celko, M.; Hraska, S.; Klocok, L.; Kostial, J.; Prikazsky, V.; Vidovic, J.; Zirko, M.; Beno, T.; Mitosinka, J.

    1998-01-01

    The report contents final environment evaluation and selected characteristic of residents health physics of nuclear power plant Bohunice region. Evaluated data were elaborated during analytical period 1993-1997.Task solving which results are documented in this final report was going on between 1996- 1998. The report deals in individual stages with the following: Information obtaining and completing which characterize demographic situation of the area for the 1993-1997 period; Datum obtaining and completing which contain selected health physics characteristics of the area residents; Database structures for individual data archiving from monitoring and collection; Brief description of geographic information system for graphic presentation of evaluation results based on topographic base; Digital mapping structure description; Results and evaluation of radionuclide monitoring in environment performed by Environmental radiation measurements laboratory by the nuclear power plant Bohunice for the 1993-1997 period. Demographic situation evaluation and selected health physics characteristics of the area of nuclear power plant residents for the 1993-1997 period are summarized in the final part of the document. Monitoring results and their evaluation is processed in graph, table, text description and map output forms. Map outputs are processed in the geographic information system Arc View GIS 3.0a environment

  2. The preliminary results of the thermal annealing processes performed on the RPVs NPP V-1 in Jaslovske Bohunice

    Kupca, L; Brezina, M; Beno, P [Vyskumny Ustav Jadrovych Elektrarni, Trnava (Slovakia)

    1994-12-31

    Samples of weld and base metal above and below the weld were taken from RPV material in the V-230 type NPP V-1 in Bohunice; hardness measurements were carried out across the weld on the external surface of the RPV under the thermal shielding, before and after annealing. Results are presented and the annealing procedure efficiency is discussed. (authors). 13 refs., 5 figs.

  3. Planning for environmental restoration of the contaminated banks near NPP Bohunice

    Slavik, O.; Moravek, J.; Vladar, M.

    1995-01-01

    The 18 km long banks of the Bohunice NPP waste water recipient are contaminated by cesium-137 as a result of two accidents on the CO 2 cooled NPP A 1 unit in 1976 and 1977. Since 1992, all he contaminated waste waters dumping from NPP Bohunice has been carried out directly to the Vah River through a specially constructed 15 km long pipeline. The final extent of contamination in the Bohunice site is represented. The overall contaminated area in this site with cesium-137 activity above 1 Bq/g of soil is about 67000 m 2 and thus, the corresponding volume of top 20 cm thick soil layer is about 13000 m 3 . For optimizing less costly remedial measures (warning signs...) an agreed scenario with a pre-estimated factor factor collective dose 2.10 -7 man.Sv.y -1 /(m 2 .Bq 137 Cs.g -1 ) was applied. Limitation of individual effective doses according to a site specific stay scenario was also considered for this purposes with a limiting value of 0.25 mSv/y. Cost analysis of available remedial techniques were carried out, too. Two techniques have been selected for the contaminated banks restoration project: 1) removing/disposal of 20 cm soil top layer from steep and unengineered banks, and 2) mechanical dilution/fixation of contamination by clean 15 cm soil cover for the contaminated flat areas. Two-fold reduction of anticipated potential radiation risk were accepted, maximally, for the lastly mentioned technique, however cost saving is considerable (about 10-time lower the cost comparing to removing/disposal technique one). The basic acceptance limits AL for 137 Cs in soil and criteria size of continuously contaminated bank areas were derived as: AL 200 = 6.0 Bq/g and 800 m 2 (300 m) or AL 50 8.0 Bq/g and 200 m 2 (80 m) for removing/disposal of the soil on steep unengineered banks. For clean soil covering technique the resulting limits are in an interval AL 50C = 8 up to 16 Bq/g. According to the criteria developed, it is necessary to subject to restoration about 11000 m 2 of

  4. Planning for environmental restoration of the contaminated banks near NPP Bohunice

    Slavik, O; Moravek, J [Nuclear Power Plants Research Institute, a.s., Trnava (Slovakia); Vladar, M [Inst. of Preventive and Clinical Medicine, Bratislava (Slovakia)

    1996-12-31

    The 18 km long banks of the Bohunice NPP waste water recipient are contaminated by cesium-137 as a result of two accidents on the CO{sub 2} cooled NPP A{sub 1} unit in 1976 and 1977. Since 1992, all he contaminated waste waters dumping from NPP Bohunice has been carried out directly to the Vah River through a specially constructed 15 km long pipeline. The final extent of contamination in the Bohunice site is represented. The overall contaminated area in this site with cesium-137 activity above 1 Bq/g of soil is about 67000 m{sup 2} and thus, the corresponding volume of top 20 cm thick soil layer is about 13000 m{sup 3}. For optimizing less costly remedial measures (warning signs...) an agreed scenario with a pre-estimated factor factor collective dose 2.10{sup -7} man.Sv.y{sup -1}/(m{sup 2}.Bq{sup 137}Cs.g{sup -1}) was applied. Limitation of individual effective doses according to a site specific stay scenario was also considered for this purposes with a limiting value of 0.25 mSv/y. Cost analysis of available remedial techniques were carried out, too. Two techniques have been selected for the contaminated banks restoration project: 1) removing/disposal of 20 cm soil top layer from steep and unengineered banks, and 2) mechanical dilution/fixation of contamination by clean 15 cm soil cover for the contaminated flat areas. Two-fold reduction of anticipated potential radiation risk were accepted, maximally, for the lastly mentioned technique, however cost saving is considerable (about 10-time lower the cost comparing to removing/disposal technique one). The basic acceptance limits AL for {sup 137}Cs in soil and criteria size of continuously contaminated bank areas were derived as: AL{sub 200} = 6.0 Bq/g and 800 m{sup 2} (300 m) or AL{sub 50} 8.0 Bq/g and 200 m{sup 2} (80 m) for removing/disposal of the soil on steep unengineered banks. For clean soil covering technique the resulting limits are in an interval AL{sub 50C} = 8 up to 16 Bq/g. (Abstract Truncated)

  5. Principles and criteria for environmental restoration of the contaminated banks near NPP Bohunice

    Slavik, O.; Moravek, J.

    1995-01-01

    The 18 km long banks of the Bohunice NPP waste water recipient are contaminated by 137 Cs as a result of two accidents on the CO 2 cooled NPP-A1 unit in 1976 and 1977. Contamination acceptance limits 6 or 8 Bq 137 Cslg of soil, depending on contaminated area size, were derived on the basis of developed principles, and approved by the authorities. Removing and safe burial of 1,100 m 3 of contaminated soil from steep area and 15 cm thick clean soil covering on about 1ha of flat area of the contaminated banks is planned in frame of the re-considered restoration project implementation in 1995/96. (author)

  6. IAEA Operational Safety Team Review Bohunice Nuclear Power Plant, Slovak Republic

    2010-01-01

    Full text: An international team of nuclear installation safety experts, led by the International Atomic Energy Agency (IAEA), has reviewed Slovakia's Bohunice Nuclear Power Plant (BNPP) for its safety practices and has noted a series of good practices as well as recommendations to reinforce them. The IAEA assembled an international team of experts at the request of the Government of Slovak Republic to conduct an Operational Safety Review (OSART) of Bohunice NPP. Under the leadership of the IAEA's Division of Nuclear Installation Safety, the OSART team performed an in-depth operational safety review from 1 to 18 November 2010. The team was made up of experts from Belgium, Canada, China, the Czech Republic, France, Sweden, the United Kingdom and the IAEA. An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. The team at BNPP conducted an in-depth review of the aspects essential to the safe operation of the NPP, which largely is under the control of the site management. The conclusions of the review are based on the IAEA's Safety Standards and proven good international practices. The review covered the areas of Management, Organization and Administration; Operations; Maintenance; Technical Support; Operating Experience; Radiation Protection; Chemistry and Emergency Planning and Preparedness. Long Term Operation assessment has been requested by the plant in addition to the standard OSART program. The OSART team has identified good plant practices which will be shared with the rest of the nuclear industry for consideration of their application. Examples include: BNPP has implemented a comprehensive set of technical and organizational measures which have significantly reduced the production of liquid radioactive waste; BNPP has developed an automatic transfer of dosimetry data

  7. Fuel utilization experience in Bohunice NPP and regulatory requirements for implementation of progressive fuel management strategies

    Patenyi, V [Nuclear Regulatory Authority, Bratislava (Slovakia); Darilek, P; Majercik, J [Vyskumny Ustav Jadrovych Elektrarni, Trnava (Slovakia)

    1994-12-31

    The experience gained in fuel utilization and the basic requirements for fuel licensing in the Slovak NPPs is described. The original project of WWER-440 reactors supposes 3-year fuel cycle with cycle length of about 320 full power days (FPD). Since 1984 it was reduced to 290 FPD. Based on the experience of other countries, a 4-year fuel cycle utilization started in 1987. It is illustrated with data from the Bohunice NPP units. Among 504 fuel assemblies left for the fourth burnup cycle no leakage was observed. The mean burnup achieved in the different units varied from 33.1 to 38.5 Mwd/kg U. The new fuel assemblies used are different from the recent ones in construction, thermohydraulics, water-uranium ratio, enrichment and material design. To meet the safety criteria, regulatory requirements for exploitation of new fuel in WWER-440 were formulated by the Nuclear Regulatory Authority of Slovak Republic. 1 tab., 5 refs.

  8. Main features of buildings and structures important to safety of units V1 and V2 of Bohunice NPP

    David, M.

    1993-01-01

    The program of seismic upgrading of Bohunice NPPs has been started in the year 1989 (after finishing of new seismic input). Since that time the seismic upgrading of Main building of NPP V1 has already been realized, structural as well as technological parts. Beside that the designs of seismic upgrading of other structures of NPP V1 and V2 have been completed. It has been proved that the seismic upgrading of NPPs with reactors WWER 440 is very complicated, but still possible, even in the case with high seismic intensity. It would be not possible to fulfill this complicated task without the help of IAEA Missions. The activities of IAEA experts in the program of Bohunice NPPs upgrading are appreciated very much

  9. Evaluation of an external exposure of a worker during manipulation with waste packages stored in Bohunice radioactive waste treatment centre

    Slimak, A.; Hrncir, T.; Necas, V.

    2012-01-01

    The paper briefly describes current state of radioactive waste management as well as radioactive waste treatment and conditioning technologies used in Bohunice Radioactive Waste Treatment Centre. Radioactive Waste management includes pretreatment, treatment, conditioning, storage, transport and disposal of radioactive waste. Presented paper deals with the evaluation of an external exposure of a worker during manipulation with fibre-reinforced concrete container stored under shelter object. The external exposure of a worker was evaluated using VISIPLAN 3D ALARA code. (Authors)

  10. Information letter 2. Information about operation of plants SE-NPP Bohunice and SE-VYZ during February 2005

    2005-03-01

    In this leaflet results of exploitation of four units of the Bohunice V-1 and V-2 NPPs are presented. The electricity and heat production in February 2005 are reviewed. Within a February 2005 the electricity was produced: 217 GWh (block 1), 281 GWh (block 2), 277 GWh (block 3), 282 GWh (block 4), totally 1057 GWh, and 2271 GWh within a January - February 2005. The heat production in February 2005 was 266 506 GJ, and within a January - February 2005 it was produced 531 849 GJ of heat. On February 17 Slovak minister of economy Pavol Rusko and general director of ENEL Paolo Scaroni signed the agreement on acquisition of 66 per cent of Slovenske elektrarne (SE) by Italian ENEL for 840 million Eur. SE has capacity of around 7 GW (83 per cent of total Slovakian capacity). In 2004 SE generated 26 TWh of electricity. Processing and storage of radioactive wastes in Decommissioning of Nuclear Installations and Spent Fuel and Rad-waste Management (SE-VYZ) is presented. Since beginning of this year 58 fibre-concrete containers have been filled up in Bohunice processing centre of radioactive wastes. Twenty-three pieces of fibre-concrete containers were processed into fibre-concrete containers in Bohunice processing centre of radioactive wastes (BSC RAO) in February 2005. Twenty fibre-concrete containers were stored into Republic storage of radioactive wastes (RU RAO). Total number in RU RAO reached 830 pieces of fibre-concrete containers, which represent 11.53 per cent of storage capacity (7200 containers). Bohunice processing centre of radioactive wastes was put into active operation just before five years

  11. Analysis of the mortality development of the population in the surroundings of Bohunice NPP using Fuzzy logic methods

    Letkovicova, M.; Durov, M.; Stehlikova, B.

    2001-01-01

    We pursue the vicinity of Bohunice NPP. The vicinity has cyclic form with radius of 30 km, what represents an area approximately 2 800 km 2 . This area of pursued vicinity is requisite by the security report of Bohunice NPP. To the presumptive calculations we used the complete databases of Register of death, Register of municipalities and of Register of age structure of the inhabitants of the Slovak republic from 1993 to 1999, fully-fashioned in Statistical authority of the Slovak republic. We work with databases, which don't contain personal identifications. We pursue the evolution of the mortality by the indicators of the mortality, calculated by the WHO. By the literary sources and by our experience is necessary the sum at least of three years to calculation of stable demographic and epidemiological parameters. Therefore we work with the method of short time series. The basic observed unit, which is represented by one value of the indicator, is one municipality. All our assessing analyses are calculated from triennial sums of all indicators, so we work with man-years. Advanced report is the adjusted extract from Complex report on situation of environment and health of the inhabitants in vicinity of Bohunice NPP in 1999, which was advanced by our society in March 2001. (authors)

  12. Evaluation of seismic resistance of low voltage switchgear, NPP V1 Jaslovske Bohunice, Slovakia

    Zeman, P.

    1999-01-01

    During this year, company Stevenson and Associates took part in the project of evaluation of seismic resistance of NPP V-1 Jaslovske Bohunice in Slovakia. It was responsible for a part of electrical equipment, mainly for the evaluation of low voltage switchgears. There were four steps of the evaluation: Detailed Walkdown; Application of GIP-WWER Methodology; Developing, of In Cabinet Response Spectra; and Evaluation of Acceptance of Formerly Performed Relay Tests According to the Russian Standard OEG l-330.00-3). Tests performed according to the Russian Standard OAG are acceptable only if the tested subject shows just one dominant natural frequency in the significant energy frequency range. If there is no knowledge of modal properties of the tested subject (that is a frequent situation because test reports usually contain only generalized Fourier loading spectrum) the enveloping of In Cabinet Response Spectra (ICRS) in all significant energy frequency ranges by Response Spectra (RS) of harmonic signal on one arbitrary frequency. This criteria is usually not satisfied because the shake tables used for the tests are not able to produce the sufficient level of excitation in the low frequency range. It may lead to the demand for test repeating

  13. Analysis of events significant with regard to safety of Bohunice V-1 nuclear power plant

    Suchomel, J.; Maron, V.; Kmosena, J.

    1986-01-01

    An analysis was made of operating safety of the V-1 nuclear power plant in Jaslovske Bohunice for the years 1980 - 1983. Of the total number of 676 reported failures only three were events with special safety significance, namely a complete loss of power supply for own consumption from the power grid, a failure of pins on the collectors of steam generators, and a failure of the heads of heat technology inspection channels. The failures were categorized according to the systems used in the USSR and in the USA and compared with data on failures in nuclear power plants in the two countries. The conclusions show that the operation of the V-1 nuclear power plant achieves results which are fully comparable with those recorded in 9 WWER-440 power plants operating in various countries. The average coefficient of availability is 0.72 and ranks the power plant in the fourth place among the said 9 plants. A comparison of the individual power plant units showed that of the total number of 22, the first unit of the V-1 plant ranks fifth with a coefficient of 0.78 and the second unit with a coefficient of 0.69 ranks 15th. (Z.M.)

  14. Thirtieth anniversary of reactor accident in A-1 Nuclear Power Plant Jaslovske Bohunice

    Kuruc, J.; Matel, L.

    2007-01-01

    The facts about reactor accidents in A-1 Nuclear Power Plant Jaslovske Bohunice, Slovakia are presented. There was the reactor KS150 (HWGCR) cooled with carbon dioxide and moderated with heavy water. A-1 NPP was commissioned on December 25, 1972. The first reactor accident happened on January 5, 1976 during fuel loading. This accident has not been evaluated according to the INES scale up to the present time. The second serious accident in A-1 NPP occurred on February 22, 1977 also during fuel loading. This INES level 4 of reactor accident resulted in damaged fuel integrity with extensive corrosion damage of fuel cladding and release of radioactivity into the plant area. The A-1 NPP was consecutively shut down and is being decommissioned in the present time. Both reactor accidents are described briefly. Some radioecological and radiobiological consequences of accidents and contamination of area of A-1 NPP as well as of Manivier Canal and Dudvah River as result of flooding during the decommissioning are presented (authors)

  15. Chemical composition determination of Bohunice 1 and 2 RPVs and hardness measurements of RPVs material

    Kupca, L.; Brezina, M.; Beno, P.; Kniz, I.

    1994-01-01

    The base informations of all activities concerning the material properties recovery performed before and after annealing procedure on the first two units V-230 type in NPP V-1, are the topic of this paper. The samples of weld and base metal from both RPVs NPP V-1 were prepared by special apparatus in the very narrow gap between the outside surface of the RPV and the reactor thermal shielding in the reactor cavity, from the critical circumferential weld joint no.4. The chemical composition of the samples was analyzed in Nuclear Power Plants Research Institute (VUJE) laboratories. Except these results achieved from the analysis of the irradiated samples are presented the evaluation results of the chemical composition influence on the RPVs materials brittle fracture temperatures. All these results which served as input data for the irradiation embrittlement recovery evaluation of the both RPV NPP V-1 in Jaslovske Bohunice, are presented in the form of the trend curves for both RPVs. (author). 10 refs, 7 figs, 1 tab

  16. Experience in modernization of safety I and C in VVER 440 nuclear power plants Bohunice V1 and Paks

    Martin, M.

    2000-01-01

    For nuclear power plants which have been in operation for more than 15 years, backfitting or even complete replacement of the instrumentation and control (I and C) equipment becomes an increasingly attractive option, motivated not only by the objective to reduce the cost of I and C system maintenance and repair but also to prolong or at least to safeguard the plant life-time: optimized spare-part management through use of standard equipment; reduction of number and variety of different items of equipment by implementing functions stepwise in application software; adding new functionality in the application software which was not possible in the old technology due to lack of space; safeguarding of long-term After-Sales-Service. Some years ago Bohunice V1 NPP, Slovak Republic and Paks NPP, Hungary intended to replace parts of their Safety I and C, mainly the Reactor Trip System, the Reactor Limitation System and the Neutron Flux Excore Instrumentation and Monitoring Systems. After a Basic Engineering Phase in Bohunice V1 and a Feasibility Study in Paks both plants decided to use the Siemens' Digital Safety I and C System TELEPERM XS to modernize their plants. Both Bohunice, Unit 2 and Paks, Unit 1 have been back on line for over six months with the new Digital Safety I and C. At the present time Bohunice, Unit 1 and within the next few months Paks, Unit 2 will be replaced. Trouble-free start-ups and no major problems under operation in the first two plants were based on: thorough understanding of the VVER 440 technology; comprehensive planning together with the plant operators and authorities; the possibility to adapt TELEPERM XS to every plant type; the execution of extensive pre-operational tests. Regarding these modernization measures Siemens, as well as the above Operators, have gained considerable experience in the field of I and C Modernization in VVER 440 NPPs. Important aspects of this experience are: how to transfer the VVER technology to TELEPERM XS; how to

  17. The results of the surveillance specimen program performed in the RPVs NPP V-2 in Jaslovske Bohunice

    Kupca, L; Beno, P [Vyskumny Ustav Jadrovych Elektrarni, Trnava (Slovakia); Cepeek, S [Atomova Elektraren Bohunice, Jaslovske Bohunice (Slovakia); Tomasich, M [Slovak Nuclear Society, Bratislava (Slovakia)

    1994-12-31

    After a description of the mechanical and chemical characteristics of the materials (steels, welded joints) used in the pressure vessels of the WWER-440 V-213 type, the present status of the Bohunice NPP Unit 3 and 4 pressure vessel embrittlement assessment programme is presented: neutron flux monitoring and calculations, detector accuracy, irradiation temperature monitoring, reactor core fuel loading calculation, materials, number and types of surveillance specimens, specimen testing. Results are given for 5 years of irradiation: mechanical properties, transition temperatures, lifetime evaluation. 4 refs., 13 figs., 6 tabs.

  18. Information letter 3. Information about operation of plants SE-NPP Bohunice and SE-VYZ during March 2006

    2006-04-01

    In this leaflet results of exploitation of four units of the Bohunice V-1 and V-2 NPPs are presented. The electricity and heat production in March 2006 are reviewed. Within a March 2006 the electricity was produced: 294.020 GWh (block 1), 287.684 GWh (block 2), 292.636 GWh (block 3), 237.806 GWh (block 4), totally 1112 GWh, and 3330 GWh within a January - March 2005. The heat production in January 2006 was 253 057 GJ, and within a January - March 2006 it was produced 896 226 GJ of heat. Processing and storage of radioactive wastes in Decommissioning of Nuclear Installations and Spent Fuel and Rad-waste Management (SE-VYZ) is presented. Twenty-one pieces of fibre-concrete containers were processed into fibre-concrete containers in Bohunice processing centre of radioactive wastes (BSC RAO) in March 2006. Sixteen fibre-concrete containers were stored into Republic storage of radioactive wastes (RU RAO). Total number in RU RAO reached 1080 pieces of fibre-concrete containers, which represent 15.00 per cent of storage capacity (7200 containers). Celebration of ten years operation of SE-VYZ is described

  19. Information letter 1. Information about operation of plants SE-NPP Bohunice and SE-VYZ during January 2006

    2006-02-01

    In this leaflet results of exploitation of four units of the Bohunice V-1 and V-2 NPPs are presented. The electricity and heat production in January 2006 are reviewed. Within a January 2006 the electricity was produced: 249.149 GWh (block 1), 293.272 GWh (block 2), 305.479 GWh (block 3), 308.378 GWh (block 4), totally 1156 GWh. The heat production in January 2006 was 354 397 GJ. Processing and storage of radioactive wastes in Decommissioning of Nuclear Installations and Spent Fuel and Rad-waste Management (SE-VYZ) is presented. Twenty-two pieces of fibre-concrete containers were processed into fibre-concrete containers in Bohunice processing centre of radioactive wastes (BSC RAO) in January 2006. Sixteen fibre-concrete containers were stored into Republic storage of radioactive wastes (RU RAO). Total number in RU RAO reached 1048 pieces of fibre-concrete containers, which represent 14.55 per cent of storage capacity (7200 containers)

  20. Selective Leaching of aerosol particles collected by cascade impactor in the ventilation stack of NPP V1 in Jaslovske Bohunice

    Rulik, P; Beckova, V; Bucina, I; Foltanova, S; Poliak, R [National Radiation Protection Institute, Prague (Czech Republic)

    1996-12-31

    The study was apart of investigation of the size distribution of aerosol in air effluents from NPP V1 Jaslovske Bohunice. The evaluation the possible relationship between aerodynamic diameter of aerosol particles and chemical forms of radionuclides attached to the discharged aerosol was tried. Selective leaching was used for speciation of radionuclides present in the aerosol particles and for the estimation of their behaviour in the environment and absorption in gastro-intestinal tract. Activity concentrations of the radionuclides in the air, collected on collection substrates taken from individual impact stages and on back-up filter, were determined by sensitive gamma-spectrometric analysis using high purity Ge detectors. For the individual groups seven leaching steps were used. Following 12 radionuclides: silver-110m, cobalt-58, cobalt-60, cesium-134, cesium-137, manganese-54, ruthenium-103, antimony-124, antimony-125, tin-113, zinc-65, zirconium-95. Result shows that the leached fraction of the of the activity concentration does not depend on the size of the aerosol particles. (J.K.) 3 tabs., 3 figs.

  1. Experience from replacement and check of thermocouples during reconstruction of in-reactor temperature measurements at Bohunice V-1 units 1 and 2

    Slanina, M.; Stanc, J.

    2001-01-01

    Replacement of thermocouples in the protection tube blocks was a key phase of the reconstruction of in-reactor temperature measurements at Bohunice V-1 with regard to the success, reliability and impact on safety of unit operation. The replacement consisted of reliable and safe withdrawal of 216 old thermocouples, their disposal and installation of new thermocouples into dry channels. In the material presented, this phase of reconstruction is described in details, with focus on the evaluation of replacement quality and check activities carried out at the new installed thermocouples. (Authors)

  2. Results of physics start-up tests of Mochovce and Bohunice units with 2-nd generation Gd fuel (average enrichment 4.87 %)

    Polakovic, F.

    2015-01-01

    There are presented main features of the fuel and the list of experimental neutron-physical characteristics measured during physics start-up tests.All together there were carried out 14 physics start-ups at Bohunice and Mochovce Units with the new type of fuel. Differences between theoretical and experimental neutron-physical characteristics were statistically processed and compared with the tests acceptance criteria. There are summarized results of reactor physics start-ups with 2-nd generation Gd fuel usage [ru

  3. Post-reconstruction full power and shut down level 2 PSA study for Unit 1 of Bohunice V1 NPP

    Kovacs, Z.

    2003-01-01

    The level 2 PSA model of the J. Bohunice V1 NPP was developed in the RISK SPECTRUM Professional code with the following objectives: to identify the ways in which radioactive releases from the plant can occur following the core damage; to calculate the magnitudes and frequency of the release; to provide insights into the plant behaviour during a severe accident; to provide a framework for understanding containment failure modes; the impact of the phenomena that could occur during and following core damage and have the potential to challenge the integrity of the confinement; to support the severe accident management and development of SAMGs. The magnitudes of release categories are calculated using: the MAAP4/VVER for reactor operation and shutdown mode with closed reactor vessel and the MELCOR code for shutdown mode with open reactor vessel. In this paper an overview of the Level 2 PSA methodology; description of the confinement; the interface between the level 1 and 2 PSA and accident progression analyses are presented. An evaluation of the confinement failure modes and construction of the confinement event trees as well as definition of release categories, source term analysis and sensitivity analyses are also discussed. The presented results indicate that: 1)for the full power operation - there is an 25% probability that the confinement will successfully maintain its integrity and prevent an uncontrolled fission product release; the most likely mode of release from the confinement is a confinement bypass after SGTM with conditional probability of 30%; the conditional probability for the confinement isolation failure probability without spray is 5%, for early confinement failure at the vessel failure is 4%, for other categories 1% or less; 2) for the shutdown operating modes - the shutdown risk is high for the open reactor vessel and open confinement; important severe accident sequences exists for release categories: RC5.1, RC5.2 and RC6.2

  4. Information letter 6. Information about operation of GovCo, a.s. and plant SE-NPP Bohunice during June 2006

    2006-07-01

    In this leaflet results of exploitation of four units of the Bohunice V-1 and V-2 NPPs are presented. The electricity and heat production in June 2006 are reviewed. Within a June 2006 the electricity was produced in GovCo, a.s.: 289.150 GWh (block 1), 262.103 GWh (block 2), totally 551.253 GWh, and 321.515 GWh within a January - June 2006 and in SE-EBO, NPP V2: 278.896 GWh (block 3), 0 GWh (block 4), totally 278.896 GWh, and 2778.249 GWh within a January - June 2006. The heat production in June 2006 was 38 212 GJ, and within a January - June 2006 it was produced 1 098 605 GJ of heat. Processing and storage of radioactive wastes in GovCo, a.s. - Decommissioning of Nuclear Installations and Spent Fuel and Rad-waste Management (VYZ) is presented. Thirty-two pieces of fibre-concrete containers were processed into fibre-concrete containers in Bohunice processing centre of radioactive wastes (BSC RAO) in January 2006. Sixteen fibre-concrete containers were stored into Republic storage of radioactive wastes (RU RAO). Total number in RU RAO reached 1132 pieces of fibre-concrete containers, which represent 15.72 per cent of storage capacity (7200 containers). The technique of SE-VYZ in decommissioning of A1 NPP is described

  5. Calculation of radiation dose rate above water layer of Interim Spent Fuel Storage Jaslovske Bohunice by the point Kernels (VISIPLAN) and Monte Carlo (MCNP4C) methods

    Slavik, O.; Kucharova, D.; Listjak, M.; Fueloep, M.

    2008-01-01

    The aim of this paper is to evaluate maximal dose rate (DR) of gamma radiation above different configurations of reservoirs with spent nuclear fuel with cooling period 1.8 year and to compare by buildup factor method (Visiplan) and Monte Carlo simulations and to appreciate influence of scattered photons in the case of calculation of fully filled fuel transfer storage (FTS). On the ground of performed accounts it was shown, that relative contributions of photons from adjacent reservoirs are in the case buildup factor method (Visiplan) similar to Monte Carlo simulations. It means, that Visiplan can be used also for valuation of contributions of of dose rates from neighbouring reservoirs. It was shown, that calculations of DR by Visiplan are conservatively overestimated for this source of radiation and thickness of shielding approximately 2.6 - 3 times. Also following these calculations resulted, that by storage of reservoirs with cooling period 1.8 years in FTS is not needed any additional protection measures for workers against primal safety report. Calculated DR also above fully filled FTS by these reservoirs in Jaslovske Bohunice is very low on the level 0.03 μSv/h. (authors)

  6. Calculation of radiation dose rate above water layer of Interim Spent Fuel Storage Jaslovske Bohunice by the point Kernels (VISIPLAN) and Monte Carlo (MCNP4C) methods

    Slavik, O.; Kucharova, D.; Listjak, M.; Fueloep, M.

    2009-01-01

    The aim of this paper is to evaluate maximal dose rate (DR) of gamma radiation above different configurations of reservoirs with spent nuclear fuel with cooling period 1.8 year and to compare by buildup factor method (Visiplan) and Monte Carlo simulations and to appreciate influence of scattered photons in the case of calculation of fully filled fuel transfer storage (FTS). On the ground of performed accounts it was shown, that relative contributions of photons from adjacent reservoirs are in the case buildup factor method (Visiplan) similar to Monte Carlo simulations. It means, that Visiplan can be used also for valuation of contributions of of dose rates from neighbouring reservoirs. It was shown, that calculations of DR by Visiplan are conservatively overestimated for this source of radiation and thickness of shielding approximately 2.6 - 3 times. Also following these calculations resulted, that by storage of reservoirs with cooling period 1.8 years in FTS is not needed any additional protection measures for workers against primal safety report. Calculated DR also above fully filled FTS by these reservoirs in Jaslovske Bohunice is very low on the level 0.03 μSv/h. (authors)

  7. Primary system hydraulic characteristics after modification of reactor coolant pumps' impeller wheels at Bohunice NPP executed in 2012 and 2013

    Hermansky, Jozef; Zavodsky, Martin

    2014-01-01

    A coolant flow through the reactor is usually determined after annual outages at Slovak NPP (VVER 440) in two distinct ways. First method is determination on the basis of the secondary system parameters - measurement of thermal balances. The value achieved by this method is used as the input parameter in the Table of allowed reactor operation modes. The second method draws from the primary system parameters - measurement of primary system hydraulic characteristics. Flow nozzles used for the measurement of feed water flow behind high pressure heaters were replaced at both Bohunice Units during outages in 2008. The feed water flow behind high pressure heaters is one of the main parameters used for the determination of coolant flow through the reactor by the first method. Compared to the measurement executed during previous fuel cycles, the calculated coolant flow through the reactor decreased considerably after the change of flow nozzles. The imaginary change of coolant flow through the reactor at Unit 3 was -1,6 %; and at Unit 4 -2,6 %. This change was not proved by the parallel measurement of primary system hydraulic characteristics. Later it was found out that the original flow nozzles used for 25 years were substantially deposited (original inner diameter of the nozzles was reduced by about 0,6-0,9 mm). Therefore feed water flow measurement was untrustworthy within the recent years. On the findings stated above, Bohunice NPP has decided to increase coolant flow through the reactor by changing the reactor coolant pumps impeller wheels. The modification of impellers wheels is planned within years 2012 to 2014. During the outages in 2013 two impeller wheels were replaced at both units. Nowadays Unit 4 is operated with all 6 new impeller wheels and Unit 3 with four new impeller wheels. Modification of last two impeller wheels at Unit 3 will be performed during the outage in 2014. On account of impeller wheels modification, non-standard measurement of PS hydraulic

  8. Report of the IPERS (International Peer Review Service) review mission for the Bohunice-V2 nuclear power plant Level 1 probabilistic safety assessment in the Slovak Republic 17 to 28 January 1995

    1995-01-01

    This report presents the results of the IAEA International Peer Review Services (IPERS) review of the probabilistic safety assessment (PSA) for the Bohunice-V2 NPP. The review was based on the PSA documentation available and on intensive communications with the analysis team and representatives from the utility and the plant operator. The results presented herein reflect the views of the international experts carrying out the review. They are provided for consideration by the responsible authorities of the Slovak Republic. 12 refs, 4 tabs

  9. Report of the ASSET (Assessment of Safety Significant Events Team) follow-up mission to the Bohunice (units 1-2) nuclear power plant in Slovakia 5-9 July 1993. Root cause analysis of operational events with a view to enhancing the prevention of accidents

    1993-01-01

    This Report of the IAEA Assessment of Safety Significant Events Team (ASSET) presents the results of the team's review of the status of implementation of the recommendations made by the 1988 ASSET mission to Bohunice nuclear power plant in Slovakia, and of progress made by plant management in prevention of incidents. The findings, conclusions and suggestions presented herein reflect the views of the ASSET experts. They are provided for consideration by the responsible Slovakian authorities. The ASSET team's views presented in this report are based on review of the documentation made available and on the discussions with plant staff. The report includes the official response of the operating and regulatory organizations of Slovakia to the ASSET findings and conclusions. Figs, tabs

  10. Recent events at Bohunice NPP Slovak Republic

    Lipar, M.

    1996-01-01

    During a filter regeneration in the steam generators (SG) blow down purification system at full power, approximately 900 litres of NaOH penetrated through a condensate collection tank into the main turbine condenser and subsequently into three SGs. The penetration occurred because of a valve left open during the filter regeneration due to a valve configuration error. The water in the tree SGs foamed, causing unexpected behaviour in SG level indicators which led to a reactor scram. By exceeding the pH value of feedwater for 7 minutes, the technical specification were violated, until the unit was brought into hot shut-down mode. Figs

  11. Management of the Bohunice RPVs annealing procedures

    Repka, M.

    1994-01-01

    The program of annealing regeneration procedure of RPVs units 1 and 2 of NPP V-1 (EBO) realization in the year 1993, is the topic of this paper. In the paper the following steps are described in detail: the preparation works, the annealing procedure realization schedule and safety management: starting with zero conditions, assembling of annealing apparatus, annealing procedure, cooling down and disassembling procedure of annealing apparatus. At the end the programs of annealing of both RPVs including the dosimetry measurements are discussed and evaluated. (author). 3 figs

  12. Status of steam generator tubing integrity at Jaslovske Bohunice NPP

    Cepcek, S.

    1997-01-01

    Steam generator represents one of the most important component of nuclear power plants. Especially, loss of tubing integrity of steam generators can lead to the primary coolant leak to secondary circuit and in worse cases to the unit shut down or to the PTS events occurrence. Therefore, to ensure the steam generator tubing integrity and the current knowledge about tube degradation propagation and development is of the highest importance. In this paper the present status of steam generator tubing integrity in operated NPP in Slovak Republic is presented

  13. Production of iron-serpentinite concrete and mortar for Jaslovske Bohunice V-2 nuclear power plant

    Valenta, D.; Oravec, J.

    1982-01-01

    The ideas behind the research and the results of the research of serpentinite concrete with a discontinuous granulometric curve are given. Concrete mixes were experimentally tested; a formula is given for the manufacture of 1 m 3 of fresh concrete. Serpentinite concrete of a density of 2,240 kg/m 3 is satisfactory as shielding material. Time dependence of workability was also tested. It was found that the concrete was well workable as late as 2 hours after manufacture. Serpentinite concrete and mortar were made and used for the biological shielding construction in the shaft of Unit I of the V-2 nuclear power plant. (J.P.)

  14. Application of control computer system TESLA RPP-16 in the Bohunice nuclear power plant

    Spetko, V.

    1976-01-01

    The reasons are given for the installation of a computer at the A-1 nuclear power plant in Czechoslovakia with regard to applied research. The configuration, placement, and software of the computer system is described. The programmes are written in the SAM and FORTRAN-IV languages. The knowledge acquired in the course of tests and the prospect of the future installation of computer control equipment in the A-1 nuclear power plant are described. (J.P.)

  15. Complex nuclear safety evaluation of the Bohunice V-1 nuclear power plant

    Kriz, Z.

    1991-01-01

    The safety concept of V-230 type reactor units dates back to the late 1960s. The units fail to be sufficiently dimensioned for emergency cooling of the reactor core and are fitted with no containment. So far, operating experience is good. The availability factor is 71.5% for unit 1 and 77.8% for unit 2. There occur 1 to 3 unscheduled shutdowns annually. The quality of steam generator tubes is very good. A complex safety assessment of the plant was accomplished in 1990. It concerned the concept and criteria of safety assessment, the earthquake situation, the condition of the primary coolant circuit equipment, the control system, the effect of the human factor, and preparedness of emergency plans. OSART and ASSET missions were accomplished at the plant. Based on the results of the missions as well as of inspections by the State Surveillance over Nuclear Safety, the decision has been adopted to operate the plant not longer than till 1995; the further fate of the plant will be decided on according to a future technical and economic analysis. (M.D.)

  16. Development of decontamination technology for the decommissioned Bohunice A-1 nuclear power plant

    Krejci, F.; Majersky, D.; Solcanyi, M.; Sekely, S.; Kucharik, D.

    1991-01-01

    The main results of investigation into the decontamination technology for the equipment and buildings of the decommissioned A-1 nuclear power plant, achieved by the Nuclear Power Plants Research Institute in Trnava over the 1988-1990 period, are summarized. Mobile decontamination and recirculation equipment has been developed for pre-disassembling decontamination. A solution containing formic acid (19 g/l), EDTA-Na 4 (6 g/l) and thiourea (0.5 g/l) was used for decontamination of low-alloy steels; for materials from the steam generators and turbo-compressors, the decontamination factor (DF) of this solution was 30 to 150 per decontamination cycle. For high-alloy steels, a two-stage process comprising the use of an oxidation solution and a reduction solution appeared suitable. The oxidation solution contained potassium permanganate (0.6 g/l) and nitric acid (0.4 g/l), whereas the reduction solution, viz. Citrox 21, contained citric acid (0.5 g/l), oxalic acid (1.0 g/l) and EDTA-NA 4 (2.5 g/l). The DF is 10 to 50 in one oxidation-reduction cycle and 50-100 in two cycles. For the post-disassembling chemical decontamination, the contaminated material was cut into pieces 70 to 80 cm long, freed from grease and decontaminated chemically by submerging in the solution while applying treatment by ultrasound. A technology of electrochemical decontamination has also been developed. It appeared particularly suitable for structural materials of the primary coolant circuit comprising austenitic stainless steels and low-alloy steels after pre-disassembling chemical decontamination with remainders of the corrosion layer, and for structural materials of the secondary coolant circuit after chemical post-disassembling decontamination. Research in the field of decontamination of the building parts and of the outer surfaces of the structural materials concentrated mainly on the use of decontamination foams. Foaming solutions have been developed for the decontamination of PESL floors and of surfaces of austenitic stainless steels and carbon steels. (Z.S.). 2 figs

  17. Expansion of storage capacity of interim spent fuel storage (MSVP) Bohunice

    Pilat, P.; Fridrich, V.

    2005-01-01

    This article describes modifications of Interim spent fuel storage, performed with aim of storage capacity expansion, seismic stability enhancement, and overall increase of service life as well as assuring of MSVP safe operation. Uniqueness of adopted technical solutions is based upon the fact that mentioned innovations and modifications were performed without any changes, neither in ground plan nor architecture of MSVP structure. It also important to mention that all modifications were performed during continual operation of MSVP without any breaks of limits or operational regulations. Reconstruction and innovation of existing construction and technological systems of MSVP has assured required quality standard comparable with actual trends. (authors)

  18. Liquid concrete mixes for V-2 nuclear power plant at Jaslovske Bohunice

    Valenta, D.; Oravec, J.

    1983-01-01

    The liquid concrete mixes consist of aggregates, cement, water and plastifiers. The main component of aggregates is redeposited dolomite from the Dolinka locality and sand. Cement of the SPC-325 type is used while mixing water is taken from the service water pump station for the V-1 nuclear power plant. All concretes used for the V-2 nuclear power plant construction are treated using plastifier Plastifikator S. In concrete mix development, care was primarily taken to select sand with sufficient amounts of grain of a size up to 0.25 mm. Granularity curves of the sands and the resulting curve of the aggregates granularity of the concrete mix are shown graphically. The method of manufacture and conveying of concrete mixes are briefly described. The mathematical statistical analysis of the quality of the concrete mixes produced showed that the proposed concrete mixes meet the requirements for homogeneity in the controlled parameters and that they can be manufactured in the situation of building production provided suitable components are selected, suitable aggregates are available and the quality of production is systematically checked. (J.P.)

  19. Accident localization system with jet condensers for VVER 440-V 230 NPP at Jaslovske Bohunice

    Murani, J.

    1995-01-01

    The operational safety of the V1 nuclear power plant (NPP) is unsatisfactory and does not correspond to present requirements as to nuclear safety. Further NPP operation after 1995 is conditional on nuclear safety enhancement to a level comparable with that in West European countries. This aim should be achieved by a principal reconstruction involving in addition to others also backfitting the V1 NPP with technical facilities aimed at coping with a design basis accident (DBA).To cope with such an accident the Power Equipment Research Institute (VUEZ) designed an accident localization system with jet condensers. This system consists of (a) an air trap (one for each unit, mutually interconnected) with an expansion bell enclosed within, placed on a plate with 200 pipes of jet condensers passing through, and (b) a connecting duct between the hermetic zone and the air trap. The vertical jet condenser is an essential element of the system designed for steam condensation. Apart from condensation it serves as a water seal separating units 1 and 2.Demonstration tests of the jet condenser (model 1:1) condensing function were carried out at the testing unit of the All-Union Research Institute for NPP Operation (VNIIAES), Moscow in Kashir, 11-22 September 1992. These experiments proved the jet condenser ability to ensure complete condensation of the steam produced. Experimental verification of the sealing function (model 1:1) was carried out at the testing unit of the VUEZ Tlmace. These experiments concerning the dynamics and overpressure in the free space above the pool were close to the conditions in the air trap during DBA. The jet condenser height was proved to be sufficient to ensure the sealing function. Design and experimental work has been implemented in close cooperation with Russian experts Mr. V.N. Bulynin from the VNIIAES, Moscow, and Mr. M.V. Kuznecov from the Scientific and Engineering Center for Nuclear and Radiological Safety, Moscow. (orig.)

  20. Material properties of Bohunice 1 and 2 reactor pressure vessel materials before and after annealing

    Brumovsky, M.; Novosad, P.; Vacek, M.

    1994-01-01

    Six types of experimental RPV materials were studied before and after irradiation in host nuclear power and research reactors. Recovery of RPV materials from radiation hardening and embrittlement after annealing was evaluated including a rate of radiation damage after reirradiation used. (author). 3 refs, 4 figs, 2 tabs

  1. Analytical and experimental verification of confinement upgrading for Bohunice NPP V1

    Tkac, A.

    2000-01-01

    The scope of this paper is to provide a brief description of confinement improvement for NPP V-1 and supporting thermal-hydraulic analyses and experimental results. Series of analyses are performed in the process of the designing of an improved confinement system. Based on the analytical results obtained in the PHARE Project NS01/91 'Confinement and Improved ECCS Evaluation' as well as on additional activities performed after its finishing, additional modifications have been proposed during the designing. It is required to minimize the construction works EWST ceiling, while final solution shall fulfil acceptance criteria set forth in Decision 1/94 of Slovak Regulatory Authority (UJD). The technical requirement of the UJD is related to confinement. IAEA recommendations are taken into account. Due to new definitions of DBA and BDBA first considerations were connected and oriented on possible value of pressure peak increasing. As a result of the structural analysis limiting values for hermetic zone are determined. Some design modifications of the hermetic zone are proposed

  2. Management of very low level waste from decommissioning of the A-1 Jaslovske Bohunice nuclear power plant in Slovakia

    Burclova, J.; Konecny, L.; Mrskova, A.

    2000-01-01

    Efforts were made to accelerate decommissioning, particularly of the nuclear power plant A1 of the HWGCR type. Progress made and current developments in this subject area are reviewed. Radioactive waste categories are described along with release criteria. An overview is provided on contaminated scrap and the sorting of contaminated soil and concrete. (author)

  3. Experience with humidity monitoring and leak detection system SMU-V at the Jaslovske Bohunice V-1 NPP

    Macko, O.

    1996-01-01

    Within the paper a brief technical description of SMU-V system is presented including algorithms for measured data evaluation, assessment of experience acquired the system operation and prospective VUEZ activities aimed at the developed of systems for NPP primary circuit leak detection based on humidity monitoring. System SMU-V is used to diagnose dangerous conditions during which integrity of the pipeline could be impaired resulting in absolute humidity increase in the monitored volume. (author)

  4. The LBB methodology application results performed on the safety related piping of NPP V-1 in Jaslovske Bohunice

    Kupca, L.; Beno, P. [Nuclear Power Plants Research Institute, Trnava (Slovakia)

    1997-04-01

    A broad overview of the leak before break (LBB) application to the Slovakian V-1 nuclear power plant is presented in the paper. LBB was applied to the primary cooling circuit and surge lines of both WWER 440 type units, and also used to assess the integrity of safety related piping in the feed water and main steam systems. Experiments and calculations performed included analyses of stresses, material mechanical properties, corrosion, fatigue damage, stability of heavy component supports, water hammer, and leak rates. A list of analysis results and recommendations are included in the paper.

  5. Design basis and design features of WWER-440 model 213 nuclear power plants. Reference plant: Bohunice V2 (Slovakia)

    1994-05-01

    The prime objective of the IAEA Technical Co-operation Project on Evaluation of Safety Aspects of WWER-440 model 213 NPPs is to co-ordinate and to integrate assistance to national organizations in studying selected aspects of safety for the same type of reactors. Consequently, the study integrated the results generated by national activities carried out in the Czech Republic, Hungary, Slovakia and Ukraine and co-ordinated through the IAEA. Valuable assistance in carrying out the tasks was also provided by Bulgaria and Poland. A set of publications is being prepared to present the results of the project. The publications are intended to facilitate the review and utilization of the results of the project. They are also providing assistance in further refinement and/or extension of plant specific safety evaluation of model 213 NPPs. This Technical Document addressing the design basis and safety related design features of WWER-440 model 213 plants is the first of the series to be published. It is hoped that this document will be useful to anyone working in the field of WWER safety, and in particular to experts planning, executing or reviewing studies related to the subject. Refs, 36 figs, tabs

  6. Outline of the requirements of application of computer based instrumentation and control systems in the systems important to safety on Bohunice NPPs

    Bacurik, J.

    1997-01-01

    The most important regulatory requirements and issues are described related to the review, evaluation and assessment of computer-based safety-related IandC systems, with emphasis on safety instrumentation and control. These aspects include safety classification and categorization of IandC, ranking of applicable codes and standards, design evaluation on the system level, and software assessment. (author)

  7. Radiocarbon in the Atmosphere of the Žlkovce Monitoring Station of the Bohunice NPP: 25 Years of Continuous Monthly Measurements

    Povinec, P.; Sivo, A.; Ješkovský, M.; Světlík, Ivo; Richtáriková, M.; Kaizer, J.

    2015-01-01

    Roč. 57, č. 3 (2015), s. 355-362 ISSN 0033-8222 Institutional support: RVO:61389005 Keywords : nuclear power plant s * C-14 * carbon-14 Subject RIV: BG - Nuclear , Atomic and Molecular Physics, Colliders Impact factor: 4.565, year: 2015

  8. One of the oldest

    Regula, E.

    2006-01-01

    In this paper the oldest hydroelectric power plant in the Slovakia is presented. This hydroelectric power plant belongs to Kremnicka banska spolocnost and it is situated in the shaft number IV at bottom border of Kremnica town and it was commissioned in 1922 year. There are installed 3 Pelton turbines with total power 1500 kVA

  9. VUJE experience with large scale projects and their applicability to the future of the Slovak energy system

    Ferenc, M.

    2004-01-01

    In this presentation author deals with participation of VUJE Trnava, Inc. on the reconstruction of the Bohunice V1 NPP, on modernisation of the Bohunice V2 NPP, and on of the projects in nuclear energy industry including of decommissioning of the Bohunice A1 NPP

  10. We should use nuclear power plants as good as possible

    Kaplanova, J.

    2004-01-01

    In this paper visit of Austrian journalist Christian Hunger (redactor of the Austrian broadcast OE1) on the Jaslovske Bohunice NPP and Mochovce NPP is described. Upgrade of the Jaslovske Bohunice NPP and finishing of a building of the Mochovce NPP as well as shut-down of the first and second blocks of the Jaslovske Bohunice NPP are discussed

  11. National Report

    Lipar, M.

    2001-01-01

    Power production in Slovak Republic is presented. The safety at the NPPs Bohunice V-1, V-2 and Mochovce is discussed. The events - Automatic Reactor Scram at Bohunice 1 and Power Reduction - Home Load at Bohunice 2 due to short circuit in the external grid on 22 May 2001 and Manual Reactor Scram at Mochovce 2 NPP due to Loss of Offsite Power on 30 May 2001 are described

  12. SE-VYZ - Decommissioning of Nuclear Installations, Radioactive Waste and Spent Fuel Management

    Anon

    2004-01-01

    In this presentations processes of radioactive waste treatment in the Bohunice Radioactive Waste Processing Center (SE-VYZ), Jaslovske Bohunice are presented. Decommissioning of the A-1 NPP is also presented. Disposal of conditioned radioactive waste in fibre concrete containers (FCC) are transported to Mochovce from Jaslovske Bohunice by the transport truck where are reposited in the National radioactive waste repository Mochovce. The Interim spent fuel storage facility (ISFSF) is included into this presentation

  13. Public relations

    1998-01-01

    Public relations activities continued in a well-proved form of organizing plant visits and Information Centre off - site activities. Bohunice NPPs were visited by the number of 7294 visitors in 1997. A brief account of activities in public relations carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented

  14. Radwaste management and spent fuel management in JAVYS

    Bozik, M.; Strazovec, R.

    2010-01-01

    In this work authors present radwaste management and spent fuel management in JAVYS, a.s. Processing of radioactive wastes (RAW) in the Bohunice Radioactive Waste Processing Center and surface storage of RAW in National RAW Repository as well as Interim Spent fuel storage in Jaslovske Bohunice are presented.

  15. International co-operation

    1998-01-01

    A brief account of activities in international co-operation carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. Professionality of the Bohunice NPPs staff was highly appreciated by inviting them to be the OSART team members

  16. Monitoring program of surrounding of the NPP SE-EBO

    Dobis, L.; Kostial, J.

    1997-01-01

    The paper dealt with monitoring program of radiation control of surrounding of the NPP Bohunice, which has the aim: (1) to ensure the control of influence of work of the NPP Bohunice on the environment in their surrounding; (2) to ensure the back-ground for regular brief of control and supervisory organs about condition of the environment in surrounding of the NPP Bohunice; (3) to maintain the expected technical level of control of the NPP Bohunice and to exploit optimally the technical means; (4) to solicit permanently the data about the radioactivity of environment in surrounding of the NPP Bohunice for forming of files of the data; (5) to exploit purposefully the technical equipment, technical workers and to maintain their in permanent emergency and technical eligibility for the case of the breakdown; (6) to obtain permanently the files of the values for qualification of the reference levels. This program of monitoring includes the radiation control of surrounding of the NPP Bohunice, in the time of normal work of power-station's blocks, inclusively of all types of trouble-shooting and repairer works in surrounding of the NPP Bohunice, up to distance 20 km from power-station. The monitoring includes: outlets from the NPP Bohunice, monitoring of radiation characteristics in surrounding of the NPP Bohunice, (aerosols, fall-outs, soil), the links of food chains: (grass and fodder, milk, agriculture products), hydrosphere in surrounding (surface waters, drink water, bores of radiation control in complex of the NPP Bohunice, components of the hydrosphere), measurement of radiation from external sources (measurement of the dose rates, measurement of the doses [sk

  17. Symbiosis of human with nucleus - the risk and reality

    Matel, L.

    2009-01-01

    In this presentation author deals with the history of development of nuclear power plants in the world and in the Slovak Republic. Some results of radiation monitoring of the vicinity of Jaslovske Bohunice are presented.

  18. Human sources

    1998-01-01

    Staff preparation and development, preventive medical care, reconditions stays, employees toning-up, complementary pension insurance, and plant boarding carried out by the Nuclear power plants Jaslovske Bohunice in 1997 are presented

  19. VUJE Trnava, Inc. - Engineering, Design and Research Organisation

    2001-01-01

    This CD is multimedia presentation of programme safety upgrading of Bohunice V1 NPP. This chapter contains information about VUJE: It consists of next parts: (1) From VUJE history (1977-2001); (2) Human resources (Development of staff; Structure of employees 1999); (3) VUJE activities: (Diagnostics; Nuclear safety; Radiation safety; Commissioning and operation; Personnel training; Information technology; Electric grids; Conventional power); (4) Significant projects of VUJE are presented: Gradual reconstruction with safety upgrading of the V1 Bohunice nuclear power plant; Modernization of the V2 Bohunice NPP; Completion of the Republic Repository of Radioactive Wastes in Mochovce; Decommissioning of the A1 NPP Bohunice; Development of simulators; Physical and power commissioning of NPPs; Construction of high voltage line Varin - Sucany

  20. From the idea to the power plant. First steps of Czech(oslovak) nuclear power

    Stolár, Jan; Pavlis, David; Říha, Josef

    2016-01-01

    The 60 years' history of the Czechoslovak nuclear machinery company SKODA JS is described with stress on its key role in the construction of the first Czechoslovak nuclear power plant, A-1 at Jaslovske Bohunice.

  1. Metamorphosis of NPP A1, V1, V2

    Dobak, D.; Moncekova, M.

    2005-01-01

    In this book the history of construction, commissioning and exploitation of NPP A1, NPP V1 and NPP V2 in Jaslovske Bohunice is presented on documentary photos. Vicinity around of these NPPs is presented, too

  2. Decommissioning and radioactive waste management. The European Commission overview

    Rehak, M

    2010-01-01

    In this lecture author deals with the European Commission overview on the decommissioning and radioactive waste management. Financial support of European Commission of decommissioning of the Ignalina NPP, Bohunice V1 NPP and Kozloduy Units 1 and 2 is presented.

  3. The NPPR Trnava participation in the NPP V-2 modernisation and safety improvement project

    Michal, V.; Losonsky, B.; Magdolen, J.

    1999-01-01

    The presented contribution deals with form, present state and results of Nuclear Power Plants Research Inst.e participation in the NPP V-2 Jaslovske Bohunice Modernization and Safety Improvement Project.(author)

  4. Increasing of leak-tightness of hermetic zone and other important components in NPPs

    Murani, J.

    2001-01-01

    The performed by VUEZ resealing works in the hermetic compartments/containment of WWER 440 and WWER 1000 NPPs in Slovakia (Jaslovske Bohunice V-1 NPP, Jaslovske Bohunice V-2 NPP, Mochovce NPP), the Czech Republic (Dukovany NPP, Temelin NPP) and Hungary (Pask NPP) are presented. The leakage rate from hermetic compartments at individual NPP reactor units are shown.The VUEZ activities in field of resealing of weld joints in pools and tanks in the Jaslovske Bohunice V-1 NPP and innovation of the seal of reactor pit protective hood (kolpak) are described. The principle of operation and practical experience of the SMU-V system implemented in the Jaslovske Bohunice V-1 NPP (WWER 440 - V 230) for NPP primary circuit leakage monitoring are also given

  5. VVER fuel cycle development at Slovakia

    Darilek, P.; Chrapiak, V.; Majerik, J.

    1995-01-01

    Four VVER-440 units are now under exploitation at Bohunice-site in Slovakia. Fuel cycle development of Unit No.3 and No.4 (type 213) is discussed and compared with equilibrium cycles in this paper. (author)

  6. Safety

    1998-01-01

    A brief account of activities carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. These activities are reported under the headings: (1) Nuclear safety; (2) Industrial and health safety; (3) Radiation safety; and Fire protection

  7. Nuclear installations in Slovakia accords to the convention definition

    1998-01-01

    In this part the nuclear power plants Bohunice - Units V-1 and V-2 and NPP Mochovce (description of units, safety reports and safety improvement programs) are described. Description of Bohunice A-1, history and current status of the NPP A-1 and NPP decommissioning program are included. In next parts interim spent fuel storage, technologies of Raw processing and treatment, and treated and solid Raw storage sites are described

  8. Seismic strengthening of nuclear power plants V1-V2 structures in Slovak Republic

    David, M.

    1993-01-01

    The structural upgrading of main buildings of Bohunice NPP units V1 and V2 is described in this presentation. Design criteria for structural upgrading are included. Since the seismic upgrading of the existing NPP is usually very complicated and expensive task, designer is obliged to find the optimal solution between the economics and reliability of the upgrading. The assistance of IAEA missions during the process of Bohunice seismic upgrading is considered very fruitful

  9. Irradiation temperature measurement of the reactor pressure vessel surveillance specimen in the programmes of radiation degradation monitoring

    Kupca, L.; Stanc, S.; Simor, S.

    2001-01-01

    The information's about the special system of irradiation temperature measurement, used for reactor pressure vessel surveillance specimen, which are placed in reactor thermal shielding canals are presented in the paper. The system was designed and realized in the frame of Extended Surveillance Specimen Programme for NPP V-2 Jaslovske Bohunice and Modern Surveillance Specimen Programme for NPP Mochovce. Base design aspects, technical parameters of realization and results of measurement on the two units in Bohunice and Mochovce NPPs are presented too. (Authors)

  10. Investigation and analysis of SSI effects in seismic response of NPPs EMO and EBO

    Juhasova, E.

    1996-01-01

    This progress report outlines and describes the analysis and investigations of soil-structure interaction effects in seismic response of Bohunice and Mochovce nuclear power plants. The work carries out consists of theoretical-numerical analysis of soil-structure interaction and the description of the experimental results obtained so far. Investigations were performed for different soil conditions and recommendations were elaborated as to prepare and use long-term monitoring of vibration activity at the Bohunice NPP site

  11. The primary circuit materials properties results analysis performed on archive material used in NPP V-1 and Kola NPP Units 1 and 2

    Kupca, L.; Beno, P. [Nuclear Power Plants Research Institute Inc., Trnava (Slovakia)

    1997-04-01

    A very brief summary is provided of a primary circuit piping material properties analysis. The analysis was performed for the Bohunice V-1 reactor and the Kola-1 and -2 reactors. Assessment was performed on Bohunice V-1 archive materials and primary piping material cut from the Kola units after 100,000 hours of operation. Main research program tasks included analysis of mechanical properties, corrosion stability, and microstructural properties. Analysis results are not provided.

  12. Experience from operation of WWER-440 model 213 nuclear power plants. Reference plant: Bohunice V2 (Slovakia). Report of the IAEA technical co-operation project RER/9/004 on evaluation of safety aspects of WWER-440 model 213 nuclear power plants

    1995-07-01

    This TECDOC provides a comprehensive review of the operational experience with WWER-440/213 plants. It is hoped that it will be useful to anyone working in the field of WWER safety, and in particular to experts planning, executing or reviewing studies related to the subject. Refs, figs and tabs

  13. Strength analyses of the bubbler condenser structure of WWER-440 model 213 nuclear power plants. Reference plant: Bohunice V2 (Slovakia). Report of the IAEA Technical Co-operation Project RER/9/004 on evaluation of safety aspects of WWER-440 model 213 nuclear power plants

    1995-06-01

    This publication addresses the topic of mechanical strength of the bubbler condenser applied in the WWER-440 model 213 plants and is intended to assist WWER-440/213 operators in the re-assessment of the bubbler condenser performance. It is hoped that it will also be useful to anyone working in the field of WWER safety, and in particular to experts planning, executing or reviewing studies related to the subject. Refs, figs and tabs

  14. Experience from operation of WWER-440 model 213 nuclear power plants. Reference plant: Bohunice V2 (Slovakia). Report of the IAEA technical co-operation project RER/9/004 on evaluation of safety aspects of WWER-440 model 213 nuclear power plants

    NONE

    1995-07-01

    This TECDOC provides a comprehensive review of the operational experience with WWER-440/213 plants. It is hoped that it will be useful to anyone working in the field of WWER safety, and in particular to experts planning, executing or reviewing studies related to the subject. Refs, figs and tabs.

  15. Experimental design verification of WWER-440 model 213 nuclear power plants. Reference plant: Bohunice V2 (Slovakia). Report of the IAEA technical co-operation project RER/9/004 on evaluation of safety aspects of WWER-440 model 213 nuclear power plants

    NONE

    1995-07-01

    This publication addresses the experimental research supporting the design of WWER-440 model 213 plants. it is hoped that the material presented will be useful for experts working in the field of WWER safety, and in particular to those planning, executing or reviewing studies related to the subject. Refs, figs and tabs.

  16. Experimental design verification of WWER-440 model 213 nuclear power plants. Reference plant: Bohunice V2 (Slovakia). Report of the IAEA technical co-operation project RER/9/004 on evaluation of safety aspects of WWER-440 model 213 nuclear power plants

    1995-07-01

    This publication addresses the experimental research supporting the design of WWER-440 model 213 plants. it is hoped that the material presented will be useful for experts working in the field of WWER safety, and in particular to those planning, executing or reviewing studies related to the subject. Refs, figs and tabs

  17. Strength analyses of the bubbler condenser structure of WWER-440 model 213 nuclear power plants. Reference plant: Bohunice V2 (Slovakia). Report of the IAEA Technical Co-operation Project RER/9/004 on evaluation of safety aspects of WWER-440 model 213 nuclear power plants

    NONE

    1995-06-01

    This publication addresses the topic of mechanical strength of the bubbler condenser applied in the WWER-440 model 213 plants and is intended to assist WWER-440/213 operators in the re-assessment of the bubbler condenser performance. It is hoped that it will also be useful to anyone working in the field of WWER safety, and in particular to experts planning, executing or reviewing studies related to the subject. Refs, figs and tabs.

  18. Chapter No.3. Assessment and inspection of nuclear installations

    2002-01-01

    The assessment activity of UJD in relation to nuclear installation lies in assessment of safety documentation for constructions realised as nuclear installations, or construction through which changes on nuclear installations are realised. The assessment activity of UJD in 2001 was focused on National Repository of Radwaste in Mochovce, on Radwaste conditioning and treatment technology in Jaslovske Bohunice and on the assessment of documentation for the project of modernisation of Bohunice V-2 NPPs which is under preparation. The assessment of the technical condition of equipment, important in terms of nuclear safety, primarily based on results of in-service inspections and surveillance testing of safety related components and systems, is also a part of the safety assessment of nuclear installation operation. The inspectors take part in training courses and participate in other technical meetings and workshops organised by the IAEA and also take part in special training courses organised by the Nuclear Authorities of European countries, USA and Japan. Bohunice V-1 NPP is equipped with two reactors of WWER 440 type V-230 and was put into operation in 1978-1980 as one of the last nuclear power plants with this type of reactor. Both units of NPP V-1 Bohunice operated in 2001 according to the requirements of energy dispatching at nominal power, or in a regime of tertiary regulation. November 2000, a mission of experts invited by UJD and delegated by IAEA took place at the Bohunice NPPs. The mission members together with experts of the plant operator assessed the safety of the units of WWER-440/V-230 of Bohunice V-1 NPP after the reconstruction. The members of the mission prepared the report on the current status of safety of these units for the IAEA. In 2001, UJD by its decision, issued the approval for further operation of both reactor units of Bohunice V-1 NPP. In sense of the relevant decree on operational events, 20 events have been recorded, at Bohunice V-1 NPP in

  19. Planning for Environmental Restoration in Slovak Republic

    Slavik, O.; Moravek, J.

    1995-01-01

    The restoration in the Slovak Republic concerns to the contaminated banks of the waste water recipient of the Bohunice Nuclear Power Plant. The identified contamination, consisting mainly of 137 Cs, is a result of two accidents on the CO 2 -cooled and heavy water moderated NPP Bohunice-A1 unit of NPP Bohunice complex. Two type of radiation risk scenarios, namely the bank use and contaminated soil (from bank) use scenario were investigated in relation to decision making on the planning for restoration of the contaminated banks. Results of dose assessments and the approach to planning for restoration of contaminated banks are summarized in the paper. Some details from the worked out technical design of the contaminated soil removal from the banks and its safe disposal in a near surface isolated basin are introduced in the paper too

  20. Proceedings of the 9th NUSIM 2000 Conference. Joint Slovak, Czech and German Seminar on Nuclear Power

    2000-01-01

    Scientific conference deals with problems of reactor safety upgrading, mainly of two blocks of the NPP V-1 Bohunice as well as decomissioning of the NPP A-1 Bohunice. Other problems of the nuclear engineering were discussed. Totally, 201 participants from the Slovak Republic, Czech Republic and Germany and from other countries took part in the conference. The Conference included the following sessions: (i): Survey on the situation of nuclear power in the partner countries; (ii) Mochovce design safety enhacement and operational experience; (iii) Bohunice V-1 safety upgrading and operational experience; (iv) Decomissioning, spent fuel and radwaste management; (v) Young Generation Presentation. Proceedings contains thirty one papers dealing with the scope of INIS

  1. Radioactive wastes and their disposal

    Neumann, L.

    1984-01-01

    The classification of radioactive wastes is given and the achievements evaluated in the disposal of radioactive wastes from nuclear power plants. An experimental pilot unit was installed at the Jaslovske Bohunice nuclear power plant for the bituminization of liquid radioactive wastes. UJV has developed a mobile automated high-output unit for cementation. In 1985 the unit will be tested at the Jaslovske Bohunice and the Dukovany nuclear power plants. A prototype press for processing solid wastes was manufactured which is in operation at the Jaslovske Bohunice plant. A solidification process for atypical wastes from long-term storage of spent fuel elements has been developed to be used for the period of nuclear power plant decommissioning. (E.S.)

  2. SIEMENS

    2001-01-01

    This CD is multimedia presentation of programme safety upgrading of Bohunice V1 NPP. This chapter contains information about Siemens and it participation on reconstruction of Bohunice V1 and V1 NPPs. It consists of next parts: (1) FRAMATOME ANP - worldwide activities of the FRAMATOME are presented; (2) Nuclear power engineering - present activities focus on: Upgrading and Backfitting (Siemens WWER activities since 1971); Electrical instrumentation and control systems; Fuel assemblies and related services; Reactor development and construction of new plants; (3) Safety improvement; (4) Siemens in Slovakia (activities of Siemens in Slovakia during 1993-2000 are presented); (5) More than 150-year history

  3. Proceedings of the 14th International Meeting NUSIM 2006. Joint Slovak, Czech and German Seminar on Nuclear Power

    2006-01-01

    During April 26-28, 2006 was carried out The 14 th Annual Nuclear Safety Information Meeting, NUSIM 2006. Scientific conference deals with problems of reactor safety upgrading, mainly of two blocks of the NPP V-1 Bohunice as well as decommissioning of the NPP A-1 Bohunice. Other problems of the nuclear engineering were discussed. The Conference proceeded in the following sessions: (I) Survey on the Situation of Nuclear Power in the Partner Countries; (II) Experiences with WWER operation. Almost 100 participants from the Slovak Republic, Austria, Serbia and Montenegro, Czech Republic and Germany took part in the conference. Thirty-three scientific lectures and three papers were presented.

  4. Cooperation of the SKODA Works in physical starting of the A-1 nuclear power plant

    Zbytovsky, A.

    1974-01-01

    Co-ordinated research and development efforts of the SKODA Works in the construction, commissioning and start-up of the A-1 nuclear power plant at Jaslovske Bohunice are described. The share of the SKODA Works in the cooperation with allied institutions in the USSR and with two Czechoslovak institutions, i.e., the Nuclear Research Institute at Rez and the Nuclear Power Plant at Bohunice, is detailed and documented by a schedule of experiments aimed at verifying the A-1 calculated parameters in actual operation. (L.O.)

  5. Nuclear safety in Slovak Republic. Safety analysis reports for WWER 440 reactors

    Rohar, S.

    1999-01-01

    Implementation of nuclear power program is connected to establishment of regulatory body for safe regulation of siting, construction, operation and decommissioning of nuclear installations. Licensing being one of the most important regulatory surveillance activity is based on independent regulatory review and assessment of information on nuclear safety for particular nuclear facility. Documents required to be submitted to the regulatory body by the licensee in Slovakia for the review and assessment usually named Safety Analysis Report (SAR) are presented in detail in this paper. Current status of Safety Analysis Reports for Bohunice V-1, Bohunice V-2 and Mochovce NPP is shown

  6. Introductory speeches

    2001-01-01

    This CD is multimedia presentation of programme safety upgrading of Bohunice V1 NPP. This chapter consist of introductory commentary and 4 introductory speeches (video records): (1) Introductory speech of Vincent Pillar, Board chairman and director general of Slovak electric, Plc. (SE); (2) Introductory speech of Stefan Schmidt, director of SE - Bohunice Nuclear power plants; (3) Introductory speech of Jan Korec, Board chairman and director general of VUJE Trnava, Inc. - Engineering, Design and Research Organisation, Trnava; Introductory speech of Dietrich Kuschel, Senior vice-president of FRAMATOME ANP Project and Engineering

  7. Nuclear power plant V-2

    1998-01-01

    The nuclear power plant Bohunice V -2 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - December 1976; first controlled reactor power - 7 August 1984, 2 August 1985; connection to the grid - 20 August 1984, 9 August 1985; commercial operation - 14 February 1985, 18 December 1985. This leaflet contains: NPP V-2 construction; Major technological equipment [WWER 440 V230 type reactor; Nuclear Power plant operation safety (Safety barriers; Safety systems [Active safety systems, Passive safety systems]); Centralized heat supply system; Scheme of Bohunice V-2 NPP and technical data

  8. Reconstruction of instrumentation and control system (SKR)

    Wiening, K.-H.

    2001-01-01

    For the first time extensive upgrades have been performed in all safety related areas of units with WWER 440/230 reactors. One of the most important actions was the replacement of the safety and safety related instrumentation and control. The state of the art digital safety instrumentation and control system TELEPERM XS has been implemented in units 1 and 2 of the Bohunice V1 power plant. The requirements as deduced from safety assessments conducted by commissions of international experts have been fulfilled, so that Bohunice V1 after this gradual reconstruction has been upgraded to an internationally accepted safety level for the remainder of its service life. (author)

  9. NPP Mochovce - a project of extraordinay significance

    Chwolik, I.; Debru, M.

    2000-01-01

    In this paper and in this presentation the reactor safety upgrading of two blocks of the NPP V-1 Bohunice, some results of participation on safety upgrading by the German-French consortium EUCOM (Framatome and Siemens-KWU) are presented. (author)

  10. Slovak Electric, plc, Mochovce Nuclear Power Plant

    1999-01-01

    In this popular scientific brochure a brief description of construction scheme of Bohunice Nuclear Power Plant is presented. Electricity generation in a nuclear power plant is described. Instrumentation and control system as well as nuclear safety principles applied on the NPP are presented

  11. Lessons from feedback of safety operating experience for reactor physics

    Suchomel, J.; Rapavy, S.

    1999-01-01

    Analyses of events in WWER operations as a part of safety experience feedback provide a valuable source of lessons for reactor physics. Examples of events from Bohunice operation will be shown such as events with inadequate approach to criticality, positive reactivity insertions, expulsion of a control rod from shut-down reactor, problems with reactor protection system and control rods. (Authors)

  12. Experience with the ASSET service in Slovakia

    Misak, J.

    1996-01-01

    The experience with the ASSET service in Slovakia is described, including the following: ASSET follow-up mission to Bohunice Unit 1-2 NPP; IAEA peer review of the national Incident Reporting System in the Slovak Republic; ASSET seminar on prevention of incidents, Bratislava, January 8-12, 1996

  13. Worldwide WANO biennial in India

    Vrubelova, A.

    2010-01-01

    At the turn of January and February 2010, there was an annual general conference of the World Association of Nuclear Operators - WANO held in Delhi, India. One of the representatives, participating on behalf of Slovenske elektrarne, was also Mr. Robert Guns, a former Director of Bohunice Nuclear Power Plant. After his return from India, he was approached by Anna Vrubelova. (author)

  14. VUJE tasks and activities during gradual upgrading

    Ferenc, M.

    2001-01-01

    The paper describes the organization and management of the Gradual Upgrading of the Bohunice V1 NPP and the principle tasks and scope of activities provided by VUJE Trnava, Inc. It also describes the system of supplies and the system of quality assurance both in the consortium and in subcontractors. (author)

  15. Existing and near future practices of spent fuel storage in Slovak Republic

    Mizov, J.

    1999-01-01

    In this paper existing and near future practices of spent fuel storage in Slovak Republic are discussed: (1) Reactor operation and spent fuel production; (2) Past policy in spent fuel storage; (3) Away-from-reactor (AFR) storage facility at Bohunice NPP site; (4) Present policy in spent fuel storage; (5) Final disposal of spent fuel

  16. EBO feed water distribution system, experience gained from operation

    Matal, O. [Energovyzkum, Brno (Switzerland); Schmidt, S.; Mihalik, M. [Atomove Elektrarne Bohunice, Jaslovske Bohunice (Switzerland)

    1997-12-31

    Advanced feed water distribution systems of the EBO design have been installed into steam generators at Units 3 and 4 of the NPP Jaslovske Bohunice (VVER 440). Experiences gained from the operation of steam generators with the advanced feed water distribution systems are discussed in the paper. (orig.). 4 refs.

  17. Can Slovakia secure reliable electricity supply without nuclear?

    Pnacek, I.

    2004-01-01

    In this presentation author deals with structure of electricity production in the Slovak republic in 2006 and perspectives of electricity supply up to 2020 year. Decommissioning of Unit 1 and Unit 2 of the Bohunice NPP and completion of Unit 3 and 4 of the Mochovce NPP are discussed

  18. Diagnostic and monitoring systems produced in Vuje, Okruzna 5, 918 64 Trnava, Slovak Republic

    Oksa, G.; Bahna, J.; Murin, V.; Kucharek, P.; Smutny, S.

    1996-01-01

    Based on the 20 years experience in on-line vibration diagnostics of mechanical components in the primary circuit of nuclear power plant PWR WWER-440, Vuje, Okruzna 5, 918 64 Trnava produces its own diagnostic and monitoring systems since 1990. The variety of diagnostic systems includes: loose part monitoring system (LPMS), monitoring system of main circulating pumps (MCPMS), vibration monitoring system (LVMS), leakage monitoring system (LMS). The emphasis in the hardware solution is put on the design modularity and versatility so that many subcomponents (circuit boards) are common or highly similar for all systems. Using exclusively digital data for processing enhances the reliability of the measurements and allows the easy data transportation from one computer to another (e.g., for more sophisticated analysis). Trends in the software development follow the similar path as for the hardware solution - namely, the modularity and versatility of software is the imperative goal. The modern operating systems also incorporate the ability of network communication, which is crucial for the integration of stand-alone diagnostic systems into nuclear power plants information system. So far a number of systems have been successfully installed: 6 LPMSs (Jaslovske Bohunice, Dukovany), 4 MCPMs (Jaslovske Bohunice) and 2 LVMSs (Jaslovske Bohunice), all systems operate in PWR WWER-440 environment. Another diagnostic systems are under construction: 2 LPMSs (Temelin, PWR WWER-1000), 2 MCMSs (Mochovce - PWR WWER-440) and 2 LMSs (Jaslovske Bohunice). (author). 1 fig

  19. Slovak Electric, plc, Mochovce Nuclear Power Plant

    2000-01-01

    In this popular scientific brochure a brief description of history construction of Bohunice Nuclear Power Plant is presented. The chart of electricity generation in WWER 440/V-213 nuclear power plant is described. Operation and safety improvements at Mochovce NPP as well as environment protection are presented. Basic data of Mochovce NPP are included

  20. New observations concerning Kulychivka site, Layer IV

    Škrdla, Petr; Sytnyk, O.; Koropets'kyi, R.

    2016-01-01

    Roč. 20, č. 1 (2016), s. 15-25 ISSN 2223-1218 R&D Projects: GA ČR GA15-19170S Keywords : Levallois * Upper Paleolithic * Kulychivka * Bohunice * flint artifacts * refitting * radiocarbon dating Subject RIV: AC - Archeology, Anthropology, Ethnology

  1. Experience with the ASSET service in Slovakia

    Misak, J [Nuclear Regulatory Authority, Bratislava (Slovakia)

    1997-12-31

    The experience with the ASSET service in Slovakia is described, including the following: ASSET follow-up mission to Bohunice Unit 1-2 NPP; IAEA peer review of the national Incident Reporting System in the Slovak Republic; ASSET seminar on prevention of incidents, Bratislava, January 8-12, 1996.

  2. The company's management puts priority on safety

    Tomek, J.

    2006-01-01

    On 29-30 June, 2006, the training for workers of the Slovenske elektrarne, a. s. was organized to explain the most important management safety aspects on leadership awareness (Nuclear Leadership Awareness Course). The course was held at the regional consultation center in Jaslovske Bohunice. (author)

  3. Assessment of spent WWER-440 fuel performance under long-term storage conditions

    Kupca, L [VUJE Inc. (Slovakia)

    2012-07-01

    In the Slovak Republic are under operation 6 units (4 in the Jaslovske Bohunice site, and 2 in the Mochovce), 2 units are under construction in Mochovce site. All units are WWER-440 type. The fresh fuel is imported from the Russian Federation. The spent fuel assemblies are stored in wet conditions in Bohunice Interim Storage Spent Fuel Facility (SFIS). By 15 July 2008, there were 8413 assemblies in SFIS. The objectives are: 1) Wet AR storage of spent fuel from the NPP Bohunice and Mochovce: Surveillance of conditions for spent fuel storage in the at-reactor (AR) storage pools of both NPP's (characteristics of pool water, corrosion product data); Visual control of storage pool components; Evaluation of storage conditions with respect to long-term stability (corrosion of fuel cladding, structural materials); 2) Wet SFIS storage at Bohunice: Measurement of spent fuel conditions during the long-term wet storage, activity data in the storage casks and amount of crud; Surveillance program for SFIS structural materials.

  4. EBO feed water distribution system, experience gained from operation

    Matal, O [Energovyzkum, Brno (Switzerland); Schmidt, S; Mihalik, M [Atomove Elektrarne Bohunice, Jaslovske Bohunice (Switzerland)

    1998-12-31

    Advanced feed water distribution systems of the EBO design have been installed into steam generators at Units 3 and 4 of the NPP Jaslovske Bohunice (VVER 440). Experiences gained from the operation of steam generators with the advanced feed water distribution systems are discussed in the paper. (orig.). 4 refs.

  5. Welding electrode for peripheral welds of A-1 reactor pressure vessel

    Lakatos, L.

    1975-01-01

    The properties are outlined of the VUZ-AC1-52 welding electrode used in welding the Bohunice A-1 reactor pressure vessel. The mechanical properties of welded joints after the final thermal treatment are summed up. (J.K.)

  6. Diagnostic and monitoring systems produced in Vuje, Okruzna 5, 918 64 Trnava, Slovak Republic

    Oksa, G; Bahna, J; Murin, V; Kucharek, P; Smutny, S [Vyskumny Ustav Jadrovych Elektrarni, Trnava (Slovakia)

    1997-12-31

    Based on the 20 years experience in on-line vibration diagnostics of mechanical components in the primary circuit of nuclear power plant PWR WWER-440, Vuje, Okruzna 5, 918 64 Trnava produces its own diagnostic and monitoring systems since 1990. The variety of diagnostic systems includes: loose part monitoring system (LPMS), monitoring system of main circulating pumps (MCPMS), vibration monitoring system (LVMS), leakage monitoring system (LMS). The emphasis in the hardware solution is put on the design modularity and versatility so that many subcomponents (circuit boards) are common or highly similar for all systems. Using exclusively digital data for processing enhances the reliability of the measurements and allows the easy data transportation from one computer to another (e.g., for more sophisticated analysis). Trends in the software development follow the similar path as for the hardware solution - namely, the modularity and versatility of software is the imperative goal. The modern operating systems also incorporate the ability of network communication, which is crucial for the integration of stand-alone diagnostic systems into nuclear power plants information system. So far a number of systems have been successfully installed: 6 LPMSs (Jaslovske Bohunice, Dukovany), 4 MCPMs (Jaslovske Bohunice) and 2 LVMSs (Jaslovske Bohunice), all systems operate in PWR WWER-440 environment. Another diagnostic systems are under construction: 2 LPMSs (Temelin, PWR WWER-1000), 2 MCMSs (Mochovce - PWR WWER-440) and 2 LMSs (Jaslovske Bohunice). (author). 1 fig.

  7. Irradiation Embrittlement Monitoring Programs of RPV's in the Slovak Republic NPP's

    Kupca, Ludovik

    2006-01-01

    Four types of surveillance programs were (are) realized in Slovak NPP's: 'Standard Surveillance Specimen Program' (SSSP) was finished in Jaslovske Bohunice V-2 Nuclear Power Plant (NPP) Units 3 and 4, 'Extended Surveillance Specimen Program' (ESSP), was prepared for Jaslovske Bohunice NPP V-2 with aim to validate the SSSP results, For the Mochovce NPP Unit 1 and 2 was prepared completely new surveillance program 'Modern Surveillance Specimen Program' (MSSP), based on the philosophy that the results of MSSP must be available during all NPP service life, For the Bohunice V-1 NPP was finished 'New Surveillance Specimen Program' (NSSP) coordinated by IAEA, which gave arguments for prolongation of service life these units for minimum 20 years, New Advanced Surveillance Specimen Program (ASSP) for Bohunice V-2 NPP (units 3 and 4) and Mochovce NPP (units 1, 2) is approved now. ASSP is dealing with the irradiation embrittlement of heat affected zone (HAZ) and RPV's austenitic cladding, which were not evaluated till this time in surveillance programs. SSSP started in 1979 and was finished in 1990. ESSP program started in 1995 and will be finished in 2007, was prepared with aim of: increasing of neutron fluence measurement accuracy, substantial improvement the irradiation temperature measurement, fixed orientation of samples to the centre of the reactor core, minimum differences of neutron dose for all the Charpy-V notch and COD specimens, the dose rate effect evaluation. In the year 1996 was started the new surveillance specimen program for the Mochovce RPV's unit-1 and 2, based on the fundamental postulate - to provide the irradiation embrittlement monitoring till the end of units operation. The 'New Surveillance Specimen Program' (NSSP) prepared in the year 1999 for the Bohunice V-1 NPP was finished in the year 2004. Main goal of this program was to evaluate the weld material properties degradation due to the irradiation and recovery efficiency by annealing too. The

  8. Nuclear materials

    1996-01-01

    In 1998, Nuclear Regulatory Authority of the Slovak Republic (NRA SR) performed 38 inspections, 25 of them were performed in co-operation with IAEA inspectors. There is no fresh nuclear fuel at Bohunice A-1 NPP at present. Fresh fuel of Bohunice V-1 and V-2 NPPs is inspected in the fresh fuel storage.There are 327 fresh fuel assemblies in Mochovce NPP fresh fuel storage. In addition to that, are also 71 small users of nuclear materials in Slovakia. In most cases they use: covers made of depleted uranium for non-destructive works, detection of level in production plants, covers for therapeutical sources at medical facilities. In. 1995, NRA SR issued 4 new licences for nuclear material withdrawal. In the next part manipulation with nuclear materials, spent fuel stores and illegal trafficking in nuclear materials are reported

  9. Ten years experience of PR

    Dobak, Dobroslav

    2002-01-01

    This paper is an effort to summarize the way Slovak Bohunice NPP has gone through since the historical change in the Middle and Eastern European countries. Milestones on the way were: 1989 - change of political system; increasing interest of the public appearance; creation of work capacities - personnel and technical; education/exchange with Western countries; 1994 - establishment of Foreign Affairs and PR Department reporting directly to the NPP manager; application of various approaches, some observed from other countries; creation of utility policy - place of PR in the company; establishment of QA system - description of PR activities, goals, interlinks etc.; annual planning process including activities, finance, education (training). Lessons learned are: the NPP managers were not prepared; the public was not (and still is not) prepared to obtain specific information; education is crucial in opinion winning; simple overtake of methods from others is not always applicable; strategy and feedback are necessary. Special case was the early closure Bohunice V1 NPP

  10. Slovak Electric, plc, Environment report 1998

    1999-01-01

    A brief account of activities in environment protection carried out by the Slovenske Elektrarne, a.s. in 1998 is presented. These activities are reported under the headings: (1) The address of general director; (2) Conception of environmental protection in joint stock company SE, a.s.; (3) Air protection; (4) Water management; (5) Waste management; (6) Environmental management system in joint stock company Slovenske Elektrarne, a.s.; (7) Finances spent to protection and setting of environment; (8) Vojany power plant(SE-EVO); (9) Novaky power plant (SE-ENO); (10) Kosice power plant (SE-TEKO); (11) Trencin water power stations (SE-VET); (12) Dobsina water power stations (SE-VED); (13) Bohunice nuclear power plant (SE-EBO); (14) Mochovce nuclear power plant (SE-EMO); (15) Bratislava transmission system plant (SE-PS); (16) Bohunice radioactive waste treatment and conditioning centre

  11. Experience with construction and assembly of V-1 nuclear power plant

    Prochazka, J.; Stepanek, S.; Drahy, J.

    1981-01-01

    The model is discussed of the constructions of the V-1 nuclear power plant at Jaslovske Bohunice with SKODA Trust fulfilling the role of the general supplier of the secondary part technology and the chief and special assembly contractor. The SKODA Trust mediated the Soviet supplies of technology, Soviet assembly and special assembly, and the mounting of the primary part according to Soviet projects. Plant start-up was safeguarded by the investor through Bohunice power plant staff and Soviet experts. The assembly of the primary circuit and the test assembly of reactor parts are described and the experience gained is discussed. The technological requirements are illustrated by the most important characteristics of the individual parts of the primary circuit. Also described are the design specifications of the 220 MW saturated steam turbine and the experience with its assembly and start-up. (B.S.)

  12. Nuclear power plant V-2

    1999-01-01

    In this leaflet the short history of commissioning of Bohunice V-2 NPP is reviewed (beginning of construction December 1976; First controlled reactor power, Reactor Unit 1 (RU1): 7 August 1984, Reactor Unit 2 (RU2): 2 August 1985; Connection to the grid: RU1 20 August 1984, RU2 9 August 1985; Commercial operation: RU1 14 February 1985, RU2 18 December 1985. The scheme of the nuclear reactor WWER 440/V213 is depicted. The major technological equipment are described. Principles of nuclear power plant operation safety (safety barriers, active and passive safety systems, centralized heat supply system, as well as technical data of the Bohunice V-2 NPP are presented

  13. Development of Czechoslovak nuclear power engineering

    Keher, J.

    1985-01-01

    The output of Czechoslovak nuclear power plants is envisaged at 2200 MW by 1985, 4400 MW by 1990 and 10,280 MW by the year 2000. The operation so far is assessed of Bohunice V-1 and Bohunice V-2 power plants as is the construction of the Dukovany nuclear power plant. International cooperation in the fulfilment of the nuclear power programme is based on the General Agreement on Cooperation in the Prospective Development and Interlinkage of CMEA Power Systems to the year 1990, the Agreement on Multilateral International Specialization and Cooperation of Production and on Mutual Deliveries of Nuclear Power Plant Equipment. The most important factor in international cooperation is the Programme of Cooperation between the CSSR and the USSR. The primary target in the coming period is the Temelin nuclear power plant project and the establishment of unified control of the nuclear power complex. (M.D.)

  14. Nuclear energetics as environmentally affable source - present and and future

    Suchomel, J.

    2002-01-01

    In this paper the situation in nuclear energetics in the world in 2000 year is presented. Climatic changes initiated by burning of the fossil fuels an influence of nuclear energetics are discussed. Author informs that European Union and U.S.A. supports developing of nuclear energetics. Nuclear phobia from radiation risk of some inhabitants is compared with risks of other man activities. Possibilities of the electricity production by alternative sources are compared. Liability of the Slovak Republic for decommissioning of two reactor of the V-1 Jaslovske Bohunice NPP in 2006 and 2008, which is compared with the Program of safety improvement of these reactors are discussed. Author and Slovak Nuclear Society accept gladly the suggestion of government of the Slovak Republic that they reassess this liability. The best alternative for decommissioned Jaslovske Bohunice NPP will be the completion of the 3 rd and 4 th blocks of the Mochovce NPP

  15. Nuclear power plant V-1

    1999-01-01

    In this leaflet the short history of commissioning of Bohunice V-1 NPP is reviewed (beginning of construction 24 April 1972; First controlled reactor power, Reactor Unit 1 (RU1): 27 November 1978, Reactor Unit 2 (RU2): 15 March 1980; Connection to the grid: RU1 17 December 1978, RU2 26 March 1980; Commercial operation: RU1 1 April 1980, RU2 7 January 1981. The scheme of the nuclear reactor WWER 440/V230 is depicted. The major technological equipment (primary circuit, nuclear reactor, steam generators, reactor coolant pumps, primary circuit auxiliary systems, secondary circuit, turbine generators, NPP electrical equipment, and power plant control) are described. Technical data of the Bohunice V-1 NPP are presented

  16. Competition to provide heat in Kosice

    Haluza, I.

    2007-01-01

    Replacing political nominees at state-owned companies after each change of the cabinet has become a standard. The consequences are all too well-known. In the best case, the company gets a manager that is an expert in the given area and in the worst case the new manager is a person who does not have the vaguest idea of the business and the only reason he has taken the position is to collect the salary. And in addition to this they might harm the company due to a lack of experience and expertise. These post-election changes often remove capable people from company management that do not have friends in the new cabinet but do not wish to leave the business. Over the years, they gained experience so why not start up a new company in the same business area. And heat supply in Kosice is a good example. For many years, there was only one heat supplier in Kosice, the state-owned joint stock company Teplaren Kosice (TEKO). It uses natural gas and coal from Russia. But at the end of last year, a new private limited liability company, Teplarenska spolocnost, was established. And it plans to build a new heating plant using wooden bio-mass for about 300 mil. Sk (8.82 mil. EUR) to compete with TEKO. The owners and managers of the company include former employees of the state-owned heating plant. (author)

  17. Controversial power station

    Marcan, P.

    2008-01-01

    When information on plans to build a power station in Trebisov first appeared reactions differed. A 40-billion investment in a town with more than 20% unemployment seemed attractive. But some people did not like the idea of having a power plant located in the town. Around one year after the investment was officially announced TREND returned to Trebisov. In the meantime the investor has managed to overcome one of the biggest obstacles on its way to building a new power plant. The ministry responsible gave the environmental study a positive rating. But objectors are still not sure that everything is fine. They claim that the study misinterprets data and that the ministry did not show expertise when evaluating it. 'Is it possible that a coal power plant located in a town would have twice as many positive effects on peoples' health than negative ones? Why don't we build them everywhere?'asked the chairman of the civic society, Trebisov nahlas, Gejza Gore. The developer of the project, Ceskoslovenska energeticka spolocnost (CES), Kosice is fighting back and claims that their counterpart lacks professional arguments. In the meantime it is preparing for area management proceedings. Trebisov is also involved in the discussion and claims that the town planning scheme does not include such a project. The Ministry of Construction has a different opinion. In the opinion of the Ministry the town planning scheme allows a 885-megawatt power plant to be built only a few hundred meters away from housing estates. (author)

  18. Progressive building methods in nuclear power plant construction

    Sikura, V.

    1980-01-01

    A detailed description is given of the new prospective technologies used in the construction of the Bohunice V-1 nuclear power plant. They include the use of steel and large-area forms, the use of profile sheets as a substitute for forms, assembled raw partitions, wall shells consisting of clamped porous concrete slabs, assembled roof shells, special finish of concrete walls, bearing wall deep foundation, the use of modern building machinery for concreting, reinforcing and welding works. (M.S.)

  19. Theoretical parameter histories of dynamic tests during power commissioning of Mochovce units power level up to 100 % Nnom

    Jagrik, J.; Mraz, M.; Rapant, M.; Stefanovic, P.; Kotasek, J.; Gieci, A.; Macko, J.; Mosny, J.

    1998-01-01

    Theoretical histories of selected parameters for dynamic tests carried out in the course of power commissioning of the Mochovce Unit 1 at the power level 100% N nom are shown in the report. The expected histories given were developed based on calculations performed by means of simulator in Nuclear Power Plants Research Institute Trnava, Inc., simulator in EGU Praha and simulator at the Mochovce plant, as well as based on similar tests at both Bohunice and Dukovany plants

  20. Know-how of experts of the VYZ impressed of Japan experts

    Koever, M.

    2003-01-01

    In this paper author give a short review of the course for radiation safety and radioactive waste processing which was organised in the frame of the Program for international co-operation in the scope of management in nuclear energetics. This course proceeds as early as five years and it is covered by Japan Electric Power Information Center, Inc. (JEPIC). Author there has presented know-how of the Bohunice Radioactive Waste Processing Center (VYZ, Slovenske elektrarne, a.s.)

  1. Upgrading of the radiation protection system at the V1 NPP

    Dobis, L.; Kaizer, J.; Svitek, J.

    2003-01-01

    The original radiation protection system at Bohunice V1 NPP from the 1970s was upgraded so as to meet current national as well as international standards. The article describes the upgrading of the radiation control system (teledosimetry, emergency measurement in the hermetic zone, liquid discharges, gaseous discharges, service water, remote measurement, hygiene loop, contamination monitoring at the controlled zone exit and activity monitoring at the NPP exit, special laundry, instrument calibration), dosimetry, software, and personnel contamination inspection/measurement. (author)

  2. Advantages of viscodampers for NPPs upgrading

    Reinsch, K.H.; Schwahn, K.J.; Podrouzek, J.

    1993-01-01

    Viscodampers GERB are the ideal components for seismic upgrading of flexible pipework systems of the existing operating NPPs, of WWER-440 type, namely in primary reactor part. There are cheap, maintenance-free, simple and their installation minimizes the support forces to the structures. The quoted attests are enclosed in this paper. The references for application on Bohunice NPP upgrading are positive, and they are used in Mochovce and Temelin NPP as well

  3. Problems of WWER-440 dynamic changes

    Rydzi, S.

    1986-01-01

    The data processing capability of the DYNAMIKA program is presented and demonstrated for the calculation of coolant parameters and heat transfer variables of the WWER reactor in accident and transient modes of operation. An experimental outage is described of the TG 11 turbogenerator at the V-1 Jaslovske Bohunice nuclear power plant. The measured values were compared with values calculated using the DYNAMIKA program. The graphic representation makes it evident that the mathematical model comes very close to reality. (J.B.)

  4. KS-150 reactor control

    Wagner, K.

    1974-01-01

    A thorough description is presented of the control and protection system of the Bohunice A-1 reactor. The system including auxiliary facilities was developed, manufactured and installed at the reactor by the SKODA Works, Plzen. The system parameters are listed and a brief account is also given of the development efforts and of the physical and power start-up of the A-1 nuclear power plant. (L.O.)

  5. SE-VYZ

    Anon

    2004-01-01

    On this CD compact disc 6 video-films (A-1 NPP; Bituminization; Cementation; Pressing; The Interim spent fuel storage facility; Transport into the National radioactive waste repository Mochovce; Ignition; and Vitrification). In these films process of radioactive waste treatment in the Bohunice Radioactive Waste Processing Center (SE-VYZ) is presented. 2 presentations about radioactive wastes treatment in the SE-VYZ are included

  6. Radiochemical speciation of strontium and cesium in soils and influence of the zeolite on its migration

    Cipakova, A.

    1998-01-01

    The dissertation deals with sorption and desorption characteristics of two significant radionuclides Sr-85 and Cs-137 in selected soil samples as well as from around of NPP Bohunice and NPP Mochovce which were examined. The dissertation consists from next chapters: (1) Introduction; (2) Present state of knowledge; (3) Materials and methods; (4) Results and discussion; (5) Conclusions; (6) Particular conclusions for the realisation in practice and for next development of the science

  7. VUJE capabilities for participation in the development of Slovak power sector

    Liska, P.

    2004-01-01

    In this presentation author deals with VUJE Trnava, Inc. capabilities for participation in the development of Slovak power sector. It is concluded that VUJE supports the completion of Mochovce units 3 and 4 as the most effective option; VUJE calls of the Slovak government to revive negotiations on a revision of a commitment to close V1 units Bohunice NPP in 2006 or 2008 respectively; VUJE is prepared to be an important participant in supply system for Mochovce NPP Units 3 and 4

  8. Experience with quality of training of personnel in start-up, operation and maintenance of nuclear power plants

    Ziman, V.; Alaxin, E.

    1983-01-01

    The theoretical education of personnel takes place in the branch training centre in Jaslovske Bohunice and in the concern training centre of the Slovak Power Plants. Practical training takes place in the Bohunice V-1 power plant. Selected specialists are trained in the training centre of the Novo Voronezh nuclear power plant, at the Paks nuclear plant and in the training centre of the Tusimice power plant. The recruitment, selection, schooling, practical training and placement of personnel and their assignment to posts is done in such a manner as to make sure that the complexly trained personnel is available 6 months to 3 years prior to the physical start-up of the nuclear power plant. The training of university graduates for the post of reactor operator takes 18 months or more. Trained personnel attend in-service training courses in form of complementary courses whose content includes such problems as the elimination of typified possible accidents, on the basis of the analysis of all failures which occurred in the previous period. The rising quality of personnel training at the Bohunice V-1 nuclear power plant is reflected in the decreasing number of failures caused by the human factor and in the increased availability of the power units. (M.D.)

  9. Quality assurance

    1996-01-01

    The main efforts of Nuclear Regulatory Authority of the Slovak Republic (NRA SR) was focused on support of quality assurance programmes development at responsible organizations Bohunice V-1 and V-v and Mochovce NPPs and their inspection. Development of the level two documentation of a partial quality assurance programme for NPP operation continued at Mochovce NPP. Most of documentation has been submitted to NRA SR for comments and approval. NRA SR invited a mission of French experts to Mochovce NPP to review preparation and performance of internal audits that would be beneficial for improvement in this kind activities at the NPP. Bohunice NPP continued in development of a partial quality assurance programme for operation. The Quality Assurance Programme submitted to NRA SR for approval. Based on a request of Bohunice NPPs, NRA SR consulted the draft quality assurance programme developed by Siemens for stage of the 'Basic Design' of V-1 NPP upgrading. The programme had not been submitted for approval to NRA SR prior to completion of works by Siemens. Based on an internal audit that had been performed, corrective measures were proposed to meet requirements on review and approval of suppliers quality assurance programmes. Requirements related to the quality assurance at nuclear installations were prepared to be incorporated into principles of a act on peaceful use of nuclear power in Slovak Republic

  10. Chapter 9. Personnel qualification and training

    2000-01-01

    In 1999 the Nuclear Regulatory Authority of the Slovak Republic (UJD) focused on the overall training system and on developing programmes for individual categories for NPP V-1 Bohunice, NPP V-2 Bohunice, NPP Mochovce and SE-VYZ. The fundamental theoretical and periodical training for both Bohunice and Mochovce NPPs personnel, simulator training for NPP Bohunice, and periodical simulator training for Bohunice personnel is carried out by the VUJE Training center in Trnava, whereas the simulator training and periodical training for NPP Mochovce is carried at Mochovce plant. Based on a successful passing of examination before the examining committee, UJD issues, a certificate on special professional skills of selected staff of nuclear installations for specific activity for the given type of nuclear installation and for the following positions: (a)Shift manager for scientific start up with the right of manipulation; (b) Shift supervisor; (c) Unit supervisor; (d) Primary circuit operator; (e) Secondary circuit operator; (f) Reactor physicist; (g) Shift manager for scientific start up without the right of manipulation. Examination of selected personnel is described. Last year the examining committee held twelve session for oral theoretical examination. The number of licenses issued in 1999 and the total number of valid licenses is given.Conclusions from inspections carried out by UJD and inspections and tests carried out by the NPP operators in 1999, as well as results from operation and start up of nuclear units confirm that the standard of professional skills of the staff at nuclear installations a high standard of operational safety is being achieved on a permanent basis. Increasing the qualification of UJD staff was done in a form of training and courses scheduled in the plan of training for the staff for 1999. These training, composed of specialized qualification study, functional study, as well as study aimed at maintaining qualification. Training courses organized

  11. Chapter No.8. Personnel qualification and training

    2002-01-01

    The overall training system and the development projects of training the staff of all categories from NPP V-1, NPP V-2 Bohunice, SE-VYZ and NPP Mochovce were the subject of UJD's attention. During 2001 following inspections were carried out on nuclear personnel training: - PP's Bohunice: an inspection focused on compliance with requirements for staff qualifications and compliance with the prescribed training of Bohunice plant staff; - Mochovce NPP: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of NPP Mochovce staff; - SE-VYZ: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of SE-VYZ staff. Training the staff of the NPP's Bohunice: - The fundamental and periodical theoretical training as sure as the fundamental and periodical simulator training is carried out by the VUJE Training centre in Trnava. - The fundamental practical training in the workplace and training for the change work- rank is carried at Bohunice plant. Training of the staff of the NPP Mochovce: - The fundamental and periodical theoretical training is carried out by the VUJE Training centre in Trnava. The fundamental practical training in the workplace and training for the change work- rank as well as the fundamental and periodical simulator training is carried at Mochovce plant. Based on a successful passing of examination before the examining committee, UJD issues a certificate on special professional skills of selected staff members of nuclear installations for specific activity for the given type of nuclear installation and for the following positions: 1. Scientific shift manager for start up with the right of manipulation; 2. Shift supervisor; 3. Unit supervisor; 4. Primary circuit operator; 5. Secondary circuit operator; 6. Reactor physicist; 7. Scientific shift manager for start up without the right of manipulation. Examinations of

  12. VUEZ. Annual report 2004

    2005-01-01

    A brief account of activities carried out by the Vyskumny ustav energetickych zariadeni, a.s. (VUEZ) in 2004 is presented. These activities are reported under the headings: (1) Introductory address by the Chairman of the Board of Directors; (2) Mission and vision; (3) Basic data; (4) Product portfolio and customer services; (5) VUEZ - Quality policy; (6) Human resources; (7) Economic data; (8) Auditor's certificate; (8) Adving, s.r.o.; (9) Contact persons and addresses. In 2004, the decisive domestic market capacities of VUEZ were focused on its main business partner SE, a.s., particularly on the Jaslovske Bohunice NPP. VUEZ was one of the major contractors participating in investment projects such as the Upgrading of the Jaslovske Bohunice V2 NPP. In addition, sealing work and periodical integrated leakage rate tests in nuclear power plants were resumed. In the field of fossil-fuel power plants, a substantial increase in services provided by VUEZ Emission Measurement Laboratory was recorded. In the field of experimental research, another bilateral project was implemented with IRSN Paris - an extensive programme aimed at verifying the operational reliability of emergency core cooling systems for PWR reactors. In 2004, experimental tests in this field were performed also for Westinghouse. In the process of preparation for the Jaslovske Bohunice V1 NPP decommissioning, intensive work was performed for the Project Management Unit Consultant - an international consortium consisting of Electricite de France, Empresarios Agrupados Internacional S.A., Iberdrola Ingenieria y Consultoria S.A., and Soluziona Ingenieria S.A. In the field of leak-tightness improvement in nuclear power plants, work was executed in foreign plants such as the Dukovany NPP, Czech Republic, and the Paks NPP, Hungary. In the field of investment deliveries, hermetic doors designed for the RAW Repository in the Paks NPP were manufactured for and delivered to OLAJTERV R.t. Company, Budapest, Hungary

  13. Mathematical simulation of gas pressure in fibre-reinforced concrete container at radiation and biological decomposition of cellulose, bituminized and concrete radwastes

    Kuruc, J.; Kvito, P.

    2005-01-01

    Fibre-reinforced concrete container (FRCC) are used for long-time repository of radioactive wastes. Low- and middle-active radwastes from operation of the NPPs V-1, V-2 Jaslovske Bohunice, Mochovce NPP and from decommissioned NPP A-1 (Jaslovske Bohunice) are treated in the plant SE-VYZ in Jaslovske Bohunice and after immobilisation are deposited in National Radwaste Repository Mochovce (RU RAO). After filling of the RU RAO, FRCC will be stored during 300 years. During this time the integrity of the FRCC must be guaranteed. By the influence of autoradiolysis of the cellulose and bituminized radwastes as well as in cement grout the gases are formed, mainly the hydrogen, methane and carbon dioxide. In the case of presence of available water (a w ≥ 0.63) and in presence of microbes and moulds at appropriate conditions the biological decomposition of cellulose materials may proceed with formation of H 2 , CH 4 a CO 2 . With increasing of developed gases may increase pressure in FRCC, that may initiate the loss of integrity of the FRCC with following endangering of radiation safety of the RU RAO, respectively of the territory over the repository.Authors developed the new mathematical model of pressure of gases in FRCC and in deposited barrels with cellulose and bituminized radwastes. The mathematical model is based on biological decomposition of cellulose materials as well as on radiation decomposition of cellulose, bitumen and concrete. In this mathematical model the diffusion through the walls of FRCC is the main process responsible for decreasing of the pressure. This model was developed in two basic variants: (1) Mathematical model of gas pressure in FRCC as function of dose; (2) Mathematical model of gas pressure in FRCC as function of mass of cellulose

  14. Application of Moessbauer spectroscopy on corrosion products of NPP

    Dekan, J., E-mail: julius.dekan@stuba.sk; Lipka, J.; Slugen, V. [Institute of Nuclear and Physical Engineering, Faculty of Electrical Engineering and Information Technology, SUT (Slovakia)

    2013-04-15

    Steam generator (SG) is generally one of the most important components at all nuclear power plants (NPP) with close impact to safe and long-term operation. Material degradation and corrosion/erosion processes are serious risks for long-term reliable operation. Steam generators of four VVER-440 units at nuclear power plants V-1 and V-2 in Jaslovske Bohunice (Slovakia) were gradually changed by new original 'Bohunice' design in period 1994-1998, in order to improve corrosion resistance of SGs. Corrosion processes before and after these design and material changes in Bohunice secondary circuit were studied using Moessbauer spectroscopy during last 25 years. Innovations in the feed water pipeline design as well as material composition improvements were evaluated positively. Moessbauer spectroscopy studies of phase composition of corrosion products were performed on real specimens scrapped from water pipelines or in form of filters deposits. Newest results in our long-term corrosion study confirm good operational experiences and suitable chemical regimes (reduction environment) which results mostly in creation of magnetite (on the level 70 % or higher) and small portions of hematite, goethite or hydrooxides. Regular observation of corrosion/erosion processes is essential for keeping NPP operation on high safety level. The output from performed material analyses influences the optimisation of operating chemical regimes and it can be used in optimisation of regimes at decontamination and passivation of pipelines or secondary circuit components. It can be concluded that a longer passivation time leads more to magnetite fraction in the corrosion products composition.

  15. Strengthening of the nuclear safety regulatory body. Field evaluation review

    1996-10-01

    As a result of a request from the Preparation Committee of the Nuclear Regulatory Authority (NRA) in 1992, and as recommended by the CEC/RAMG (Commission of European Communities/Regulatory Assistance Management Group) and the Agency mission in July 1993 to the Slovak Republic, the project SLR/9/005 was approved in 1993 as a model project for the period 1994-1996. Current budge is $401,340 and disbursements to date amount to $312,873. The project time schedule has been extended to 1997. The major conclusions of this evaluation are as follows: The project responded to an urgent national need, as well as to a statutory mandate of the Agency, and was adequately co-ordinated with other international assistance programmes to NRA. The project was designed as a structured programme of assistance by means of expert missions, scientific visits and a limited amount of equipment, acting upon several key areas of NRA regulatory responsibilities. Agency assistance was provided in a timely manner. A high concentration of expert missions was noticed at the initial stages of the project, which posed some managements problems. This was corrected to some extent in the course of implementation. Additionally, some overlapping of expert mission recommendations suggests that improvements are needed in the design of such missions. The exposure to international regulatory practice and expertise has resulted in substantial developments of NRA, both in organizational and operational terms. The project can claim to have contributed to NRA having gained governmental and international confidence. NRA's role in the safety assessment of Bohunice V1 reconstruction, as well as in Bohunice V2 safety review, Bohunice A1 decommissioning and in informing the public, also points at the success achieved by the project. The institutional and financial support of the Government contributed decisively to the project achievements. (author). Figs, tabs

  16. Evaluation of doses during the handling and transport of radioactive wastes containers

    Kubik, I.; Kusovska, Z.; Hanusik, V.; Mrskova, A.; Kapisovsky, V.

    2000-01-01

    Radioactive waste products from the nuclear power plants (NPPs) must be isolated from contact with people for very long period of time. Low and intermediate-level waste will be disposed of in Slovakia in specially licensed Regional disposal facility which is located near the NPP Mochovce site. Radioactive waste accumulated in the Jaslovsk. Bohunice site, during the decommissioning process of the NPP A-1 and arising from the NPP V-1 and NPP V-2 operation, will be processed and shipped in standard concrete containers to the Mochovce Regional disposal facility. The treatment centre was build at the NPP Jaslovsk? Bohunice site which is in the trial operation now. It is supposed that radioactive waste containers will be transported by train from the treatment centre Jaslovsk? Bohunice to the site of Radioactive Waste Repository at Mochovce and by truck in the area of repository. To estimate the occupational radiation exposure during the transport the calculations of dose rates from the containers are necessary. The national regulations allow low level of radiation to emanate from the casks and containers. The maximum permissible volume radioactivity of wastes inside the container is limited in such a way that irradiation level should not exceed 2 mGy/h for the contact irradiation level and 0,1 mGy/h at 2-meter distance. MicroShield code was used to analyse shielding and assessing exposure from gamma radiation of containers to people. A radioactive source was conservatively modelled by homogenous mixture of radionuclides with concrete. Standard rectangular volume source and shield geometry is used in model calculations. The activities of the personnel during the transport and storage of containers are analysed and results of the evaluation of external dose rates and effective doses are described. (author)

  17. Slovenske elektrarne has fulfilled the plan of electric power production at 101 %

    Anon

    2004-01-01

    Slovenske elektrarne, a. s., produced in 2003 year the electric power in capacity 26,047.6 GWh, whereby they fulfilled business plan at 101 %. In compare with the last year it is a reduction in production by 1,397.3 GWh. The biggest share of production - till 68.6 % of overall production of the Slovenske elektrarne, was provided by nuclear sources. Nuclear power plants fulfilled business plan at 104 %, when Jaslovske Bohunice NPP has produced 11,625 GWh and Mochovce NPP 6,238 GWh. The share of other power plants on the electricity production is presented

  18. Chapter 17. Electric schema and its changes

    Feik, K.; Kmosena, J.

    2010-01-01

    In this chapter an electric schema and its changes of the A1 nuclear power plant in Jaslovske Bohunice (the Slovak Republic) are described. Three turbogenerators with power 50 MW were installed in the A1 NPP. Basic description of electrical equipment installed according authentic project and authentic conception of accidental cooling are presented in detail. New conception and equipment of accidental and super-accidental after-cooling of the A1 NPP as well as final solution of electrical part with new functions of accidental and super-accidental after-cooling are presented. Shortcomings of electrical equipment, which originated and were eliminated during construction and operation, are also described.

  19. Jevgenij V. Doc: We do not want to build a monument at Mochovce

    Janoska, J.

    2004-01-01

    In this paper the interview with the General Manager of Inter RAO JES - Jevgenij V. Doc is published. Inter RAO JES applies for the privatisation of Slovenske elektrarne (Slovak Electric - SE). According to the General Manager of Inter RAO JES, the company does not need a foreign partner to provide financial support after the privatisation of SE, but rather it requires a political support. Plans about Bohunice NPP and of completion of the Mochovce NPP as well as of privatisation of the SE by the Inter RAO JES are presented

  20. Contributions of Modranska potrubni a.s. to the safety improvement of piping systems and valves of NPS type VVER 440 and VVER 1000

    Slach, J.

    2004-01-01

    The following activities are described: (i) Installation of pipe whip restraints on piping for high pressure and temperature steam and feed piping; (ii) Installation of air receivers for quick-acting valves with air actuator on VVER 440 units at the Jaslovske Bohunice V2 NPP; (iii) Replacement of the technical water distribution system material in the reactor hall of the Temelin VVER 1000 units; Installation of measuring nozzles on main steam piping DN 600 at the Temelin VVER 1000 units. (P.A.)

  1. Emergency preparedness

    1998-01-01

    According the conception of the Emergency Response Centre (ERC) of the Nuclear Regulatory Authority of the Slovak Republic (NRA), and the obtained experience from exercises, and as well as on the basis of recommendations of international missions, the NRA SR started, in 1997 the ERC extension. The new room enable the work for radiation protection group, reactor safety and logistic group separately. At the same time special room was build for work of the NECRA Technical Support Group of the Emergency Commission for Radiation Accidents of the SR.This group co-operates closely with ERC while evaluation the situation, and by using the information system of the NRA and database of ERC to generate the conditions of nuclear facilities in once of emergency. Extension of the mentioned rooms was carried out. The financing by the European Union helped to build the project RAMG. In this way the NRA gained a working site which, with its equipment and parameters belongs to the top working sites of regulatory bodies of developed European countries. The NRA preparation of exercise and special staff education was carried out in 1997, for employees of the NRA and members of Emergency Headquarters (EH) for work in ERC in case of nuclear installation accident. The task of education of member of EH was their preparation for carrying out three exercises. These exercises are described. In the area of emergency preparedness, in accordance with inspection plan of the Office, 7 team inspections were carried out in individual localities; in NPP Bohunice, two in NPP Mochovce and one in Bohunice Conditioning Centre for radioactive wastes. Solution of the task of development of science and technology in the area of 'Development of technical and programme means for analyses of accidents and solutions of crisis situations'continued in 1997. Another regulations were elaborated for activity of members of EH of the NRA. The following was was carried out: selection of data for transfer and the

  2. Energy and environment

    Spurny, Z.

    1987-01-01

    The objectives and the proceedings are presented of the conference ''Energy and the environment'' held in Pardubice, Czechoslovakia, on 9-10 June, 1987. A total of 31 papers were presented; 4 papers were centred on nuclear power: an assessment of the impact of ionizing radiation from power generation on the health of the population and on the environment; an assessment of the impact of the nuclear power plant complex in the Jaslovske Bohunice locality on the environment; an assessment of the impact of the Vychodni Cechy (Eastern Bohemia) plant on the environment; and a paper on the ecological optimization of the landscape during the development of the uranium industry. (J.B.)

  3. Assessment of the integrity of WWER type reactor pressure vessels

    Brumovsky, M.

    1995-01-01

    Procedures are given for the assessment of the residual lifetime of reactor pressure vessels with respect to a sudden failure, the lifetime of vessels with defects disclosed during in-service inspections, and the fatigue or corrosion-mechanical lifetime. Also outlined are the ways of assessing the effects of major degradation mechanisms, i.e. radiation embrittlement, thermal aging, and fatigue damage, including the use of calculated values and experimental examination, by means of surveillance specimens in particular. All results of assessment performed so far indicate that the life of reactor pressure vessels at the Dukovany, Jaslovske Bohunice, and Temelin nuclear power plants is well secured. 7 figs., 3 refs

  4. Education and training of experts for the nuclear power sector at the Faculty of Electrical Engineering and Information Technologies, Slovak University of Technology in Bratislava

    Lipka, J.; Slugen, V.; Miglierini, M.; Necas, V.; Hascik, J.; Pavlovic, M.

    2003-01-01

    The Faculty of Electrical Engineering and Information Technologies, Slovak University of Technology in Bratislava has been training experts for the nuclear sector for over 40 years now. Current status and trends in nuclear education within the faculty's educational system, encompassing BSc, MSc and PhD studies, are highlighted. Dedicated training courses in the safety aspects of operation of the nuclear power installations are also organized for NPP staff. Periodical training is also provided to supervising physicists at the Jaslovske Bohunice and Mochovce nuclear power plants. Major international projects aimed at nuclear knowledge management and preservation are highlighted and the ENEN - European Nuclear Education Network project is described. (P.A.)

  5. SEJV2 software package for radiation monitoring system of WWER 440 NPP

    Kapisovsky, V.; Jancik, O.; Kubik, I.; Bena, J.

    1993-01-01

    The main part of the radiation monitoring system at a WWER-440 (213 reactor type) nuclear power plant is the centralized 400-channel monitoring system 'SEJVAL' servicing twin reactor units. The SEJV2 software package is described developed to run on a PC with an IFS2 interface to the SEJVAL radiation monitoring system. It provides enhanced data presentation, record keeping and report generation, thus improving the efficiency of the health physics shift. The system was for the first time implemented at the Jaslovske Bohunice V-2 nuclear power plant with encouraging results. (Z.S.) 3 refs

  6. Operating experience with KRAFTWERK UNION cementation line

    Podmaka, L.; Tomik, L.

    1988-01-01

    A facility is described designed for fixation in a cement matrix of the radioactive concentrate produced by thickening waste water from the Bohunice nuclear power plant. The cementation line output is 0.6 m 3 concentrate/h. The concentrate is put in 200 l drums. The individual operating units, cement management, air conditioning, dosimetric monitoring and the building part are described. The requirements for the operators and the assessment of the quality of raw materials and the product are discussed. (M.D.). 3 figs., 4 refs

  7. The application of gamma and isotopic correlation techniques for safeguards identification and verification purposes

    Valovic, J.

    1976-05-01

    The report contains the method of measurement of burn-up and isotopic composition of spent fuel by the non-destructive gamma spectrometry method developed for the fuel elements of the Bohunice A-1 power plant. Results obtained for samples of spent fuel as well as fuel assemblies are shown. The method of measuring the radial distribution of the radioactive fission products is briefly described and examples demonstrating its use are given. In-core neutron flux mapping with self-powered detectors and burn-up determination by detector signal integration are also described

  8. Progress in Investigation of WWER-440 Reactor Pressure Vessel Steel by Gamma and Moessbauer Spectroscopy

    Hascik, J.; Slugen, V.; Lipka, J.; Hinca, R.; Toth, I.; Groene, R.; Uvacik, P.; Kupca, L.

    1998-01-01

    Gamma spectroscopic analyse and first experimental results of original irradiated reactor pressure vessel surveillance specimens are discussed in. In 1994, the new ''Extended Surveillance Specimen Program for nuclear Reactor Material Study'' was started in collaboration with the nuclear power plants (NPP) V-2 Bohunice (Slovakia). The first batch of MS samples (after 1 year, which is equivalent to 5 years of loading RPV-steel) was measured and interpreted using the new four components approach with the aim to observe microstructural changes due to thermal and neutron treatment resulting from operating conditions in NPP. The systematic changes in the relative areas of Moessbauer spectra components were observed. (author)

  9. Operational inspections

    Bystersky, M.

    1997-01-01

    Special equipment is described, designed for inspection of reactor pressure vessels performed from the inside. Central shaft manipulator ZMM-5 is available for crack detection control using ultrasound and eddy currents, for visual check of surfaces, repair works at the reactor pressure vessel, and hardness measurements. The manipulator consists of the manipulator bridge, a cable container, shaft segments, a control mechanism and auxiliary parts. Eight inspections were performed at the Bohunice nuclear power plant and two at the Paks nuclear power plant. (M.D.)

  10. Reuse of contaminated material from nuclear-power plants

    Melichar, Z.

    1988-01-01

    Some building structures of decommissioned nuclear power plants are contaminated to a very low extent. Little experience is so far available concerning the recycling and furher exploitation of such materials, the majority of which is constituted by concrete and steel. The mass and activities of the metal parts of the Bohunice A-1 nuclear power plant are estimated and the major contaminant radionuclides are listed. Czechoslovak as well as foreign regulations concerning radioactive material handling are cited and criteria for releasing such materials for further use are discussed. (M.D.). 7 tabs., 3 figs, 28 refs

  11. Concept and experiences with LLW and MLW handling in Czech and Slovak Republic

    Neumann, L.; Holan, K.; Tomik, L.; Kulovany, J.; Seifert, P.

    1993-01-01

    Czechoslovak policy of safe management of low and intermediate level radioactive waste from nuclear power plants has been formed gradually and was approved by the decision of Czechoslovak Government in 1977. It consists of a comprehensive treatment from the volume reduction through solidification to the disposal. Characteristics of the main types of solid, liquid and gaseous waste produced in Czechoslovak nuclear power plants with VVER type reactors are given. Systems for the collection and treatment of radioactive waste operated in Bohunice and Dukovany nuclear power plants as well as the system developed for the nuclear power plant under construction in Temelin are briefly described

  12. Internal flooding analyses results of Slovak NPPs

    Sopira, Vladimir

    2000-01-01

    The assessment of the flood risk was the objective of the internal flooding analysis for NPPs Bohunice V1, V2 and Mochovce. All important flooding sources were identified. The rooms containing safety important components were analyzed from the point of view of: Integrity of flood boundaries; Capability for drainage; Flood signalisation; Flood localization and liquidation; Vulnerability of safety system component. The redundancies of safety systems are located mostly separately and no flood can endanger more than single train. It can be concluded that NPPs with WWER-440 are very safe against the flooding initiating event

  13. Safety of nuclear installations in Slovakia

    1998-01-01

    In this part next aspects are described: (1) Site selection (Legislation related to site selection; Meeting criteria at Bohunice and Mochovce sites; International agreements); (2) Design preparation and construction (Designing and construction-relevant legislation; Nuclear installation project preparation of nuclear installation at Mochovce site); (3) Operation (Operator licensing procedure; Operation limits and conditions; Maintenance testing and control documentation for management and operation; Technical support of operation; Analysis of events at nuclear installations and Radioactive waste production); (4) Planned safety upgrading activities at nuclear installations

  14. Sorption study of system soil/water solution of CsCl using 137Cs as a radio-indicator

    Varga, R.; Krajnakova, M.; Lesny, J.; Matusek, I.

    2003-01-01

    Mobility of the radiocesium in natural environment is a function of all scale of variables, including the time. The important factor that influences on the mobility is quality and quantity of loamy minerals in soils. This paper represents a study of sorption characteristics of soils of the object No. 41, which is in the area of the Jaslovske Bohunice NPP, for radiocesium, examined experimentally appointed adsorption isotherms according to Langmuir and Freundlich. The identical experiments with the montmorillonite K-10 were realized simultaneously for a comparison of the results. (authors)

  15. Radioactive waste handling at the Mochovce NPP, 1998-2008

    Vasickova, Gabriela

    2009-01-01

    The radioactive waste management system at the Mochovce NPP is described. The system addresses technical aspects as well as administrative provisions related to radioactive waste generated within the controlled area, from the waste generation phase to waste sorting, packaging, storage, recording, measurement, and transportation to the Bohunice waste processing facility or transfer to the Mochovce liquid radioactive waste treatment facility. The article also addresses conditions for release from the controlled area to the environment for radioactive waste which can be exempt from the institutional administrative control system or released to the environment on the basis of a valid permission issued by the relevant regulatory authority

  16. Working environment in power generation

    1989-05-01

    The proceedings contain 21 papers, of which 7 are devoted to nuclear power generation. They are concerned with the working environment in the controlled areas of the Bohunice nuclear power plant, the unsuitable design of the control rooms with respect to reliability and safety of operation of the nuclear power plant, optimization of the man-working conditions relation, operation of transport facilities, refuelling and fuel element inspection, the human factor and the probabilityy assessment of the nuclear power plant operating safety, a proposal to establish a universal ergonometric programme for the electric power distribution system, and physical factors in the ergonometric analysis of the working environment. (J.B.)

  17. Problems and possibilities of establishing greenery within nuclear power plant areas

    Supuka, J.

    1987-01-01

    The environmental impacts of nuclear power plants are briefly discussed. The arrangement of the green in the area of nuclear power plants is illustrated by an example of the territorial plans of the Bohunice nuclear power plants. The green must fullfil multiple functions, such as architectonical, aesthetical, wind protection, dust protection, noise and radioactivity protection, soil improvement, psychological, soil reclamation, renaturalization, and social functions. The green zones are differentiated into the actual plant zone, the hygiene protection zone, the accompanying green zone, and the peripheral housing development green zone. (M.D.). 6 figs., 1 tab., 7 refs

  18. Analysis and testing of model worm type tanks on shaking table

    Ma, D.

    1996-01-01

    This report contains the summary of the lectures, notes and discussions at the IAEA workshop on Benchmark studies for seismic analysis of WWER NPPs, held in 1995 at St. Petersburg. The specific subject of main interest at the meeting was the testing of unanchored worm-type tanks in the emergency cooling systems of WWER-440/213 NPPs such as Paks and Bohunice. Seismic forces were not considered in the original design, therefore this is one of the important tasks in the assessment of seismic vulnerabilities of the WWER NPPs

  19. Modeling of radiocesium transport kinetics in system water-aquatic plants

    Svadlenkova, M.

    1988-01-01

    Compartment models were used to describe the kinetics of the transport of radionuclides in the system water-biomass of aquatic plants. Briefly described are linear models and models with time variable parameters. The model was tested using data from a locality in the environs of the Bohunice nuclear power plant. Cladophora glomerata algae were the monitored plants, 137 Cs the monitored radionuclide. The models may be used when aquatic plants serve as bioindicators of the radioactive contamination of surface waters, for monitoring the transport of radionuclides in food chains. (M.D.). 10 refs

  20. Retention of radionuclides by some types of flora in the aquatic system in the vicinity of a nuclear facility

    Csupka, S.

    1982-01-01

    In the years 1974 to 1981 the impacts were monitored of 90 Sr and 137 Cs discharged in liquid wastes from the Bohunice nuclear power plant on aquatic plants in the recipient. The highest values of the said monitored radionuclides were found in 1977 in Fontinalis antipyretica and Cladophora glomerata in the waste water discharge channel. The content of 137 Cs in plants is higher than the content of 90 Sr. The average values of concentration coefficients in the individual plants ranged from 750 to 3200 for 90 Sr and from 1600 to 3300 for 137 Cs. (author)

  1. Retention of radionuclides by some types of flora in the aquatic system in the vicinity of a nuclear facility

    Csupka, S. (Krajska Hygienicka Stanica, Bratislava (Czechoslovakia))

    1982-01-01

    In the years 1974 to 1981 the impacts were monitored of /sup 90/Sr and /sup 137/Cs discharged in liquid wastes from the Bohunice nuclear power plant on aquatic plants in the recipient. The highest values of the said monitored radionuclides were found in 1977 in Fontinalis antipyretica and Cladophora glomerata in the waste water discharge channel. The content of /sup 137/Cs in plants is higher than the content of /sup 90/Sr. The average values of concentration coefficients in the individual plants ranged from 750 to 3200 for /sup 90/Sr and from 1600 to 3300 for /sup 137/Cs.

  2. Containment leak-tightness enhancement at VVER 440 NPPs

    Prandorfy, M.

    2001-01-01

    The hermetic compartments of VVER 440 NPPs fulfil the function of the containment used at NPPs all over the word. The purpose of the containment is to protect the NPP personal against radioactive impact as well as to prevent radioactive leakage to the environment during a lost of coolant accident. Leak-tightness enhancement in NPPs with VVER 440/213 and VVER 440/230 reactors is an important safety issue. New procedures, measures and methods were adopted at NPPs in Mochovce, J. Bohunice, Dukovany and Paks for leak identification and sealing works performed by VUEZ Levice. (authors)

  3. Assessment of environmental impacts of nuclear power plants

    Horacek, P.

    1990-01-01

    The effects of normal operation and of accidents are analyzed. It is pointed out that the public is insufficiently informed, which bears anxiety and prejudice. The effective dose equivalents for the population and for the individual, measured during operation of the Bohunice nuclear power plants are listed and compared with those from natural background and from medical applications. The possible radioactive contamination of a large area of agricultural soil is the highest specific risk of nuclear power plant operation. Problems are growing related to spent fuel disposal and eventually to the decommissioning of the power plant itself. (M.D.). 1 tab., 8 refs

  4. Chapter No.5. Nuclear materials and physical protection of nuclear installations

    2002-01-01

    The State System of Accounting for and Control of Nuclear Material (SSAC) is based on requirements resulting from the Safeguards Agreement between the Government of the Slovak Republic and the IAEA. UJD performs this activity according to the 'Atomic Act' and relevant decree. The purpose of the SSAC is also to prevent unauthorised use of nuclear materials, to detect loses of nuclear materials and provide information that could lead to the recovery of missing material. The main part of nuclear materials under jurisdiction of the Slovak Republic is located at NPP Jaslovske Bohunice, NPP Mochovce and at interim storage in Jaslovske Bohunice. Even though that there are located more then 99% of nuclear materials in these nuclear facilities, there are not any significant problems with their accountancy and control due to very simply identification of accountancy units - fuel assemblies, and due to stability of legal subjects responsible for operation and for keeping of information continuity, which is necessary for fulfilling requirements of the Agreement. The nuclear material located outside nuclear facilities is a special category. There are 81 such subjects of different types and orientations on the territory of the Slovak Republic. These subjects use mainly depleted uranium as a shielding and small quantity of natural uranium, low enrichment uranium and thorium for experimental purposes and education. Frequent changes of these subjects, their transformations into the other subjects, extinction and very high fluctuation of employees causes loss of information about nuclear materials and creates problems with fulfilling requirements resulting from the Agreement. In 2001, the UJD carried out 51 inspections of nuclear materials, of which 31 inspections were performed at nuclear installations in co-operation with the IAEA inspectors. No discrepancies concerning the management of nuclear materials were found out during inspections and safeguards goals in year 2001 were

  5. Nuclear power plant V-1

    1998-01-01

    The nuclear power plant Bohunice V -1 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - 24 April 1972; first controlled reactor power - 27 November 1978, 15 March 1980; connection to the grid - 17 December 1978, 26 March 1980; commercial operation - 1 April 1980, 7 January 1981. This leaflet contains: NPP V-1 construction; Major technological equipment (Primary circuit: Nuclear reactor [WWER 440 V230 type reactor];Steam generator; Reactor Coolant Pumps; Primary Circuit Auxiliary Systems. Secondary circuit: Turbine generators, Nuclear power plant electrical equipment; power plant control) and technical data

  6. Experiences from start-up and use of fail-safe reactor level meter with KNITU probes

    Badiar, S.; Sipka, J.; Vanco, P.; Slanina, Marek; Liska, L.; Gavora, D.

    2001-01-01

    Within the framework of the reconstruction of both V1 Bohunice units with WWER-440/V-230 reactors, the VUJE-SIEMENS consortium implemented measurement systems for coolant level monitoring in reactor pressure vessels with 1E qualification, resp. with the qualification of category 1 according to NUSS RG1.97. The solution uses KNITU 11 probes made by Russian POZIT company. In operating plants, the installation causes problems in relation to the existing technology and quality assurance system. In the phase of implementation, the most important tasks were to resolve component quality, to commission the system, and to check its performance. (Authors)

  7. SCORPIO-VVER core monitoring and surveillance system with advanced capabilities

    Molnar, J.; Vocka, R.

    2010-01-01

    In this work authors present 12 years of operation experience of core monitoring and surveillance system with advanced capabilities on nuclear power plants on 6 unit of VVER-440 type of reactors at two different NPPs. The original version of the SCORPIO (Surveillance of reactor CORe by PIcture On-line display) system was developed for the western type of PWR reactors. The first version of the SCORPIO-VVER Core Monitoring System for Dukovany NPP (VVER-440 type of reactor, Czech Republic) was developed in 1998. For SCORPIO-VVER implementation at Bohunice NPP in Slovakia (2001) the system was enhanced with startup module KRITEX.

  8. Radiation supervision - NPPs A-1, V-1, V-2

    2000-01-01

    In this leaflet the radiation supervision of the nuclear power plants A-1, V-1, V-2 is presented. Off-site radiation supervision laboratory is a part of monitoring scheme of the NPPs. More than 1150 samples are taken from the environment annually. The tele-dosimetric system was constructed to improve the quality of the Bohunice NPPs operation impacts supervision. It has been running in a continuous operation from 1992 and providing supervision of the nuclear power plant off-site area within 25 kilometres. The tele-dosimetric system is described

  9. Extraordinary repair in Madunice Hydro Power Plant

    Vrablik, R.; Zacik, P.

    2007-01-01

    A New Year did not begin very well for Madunice hydroelectric power plant. On 3 January, 2007 during operation, the TG 1 turbine set suffered sudden large impacts and inadmissible vibration of the machine while in the secondary regulation regime. The attending personnel had to shut down the turbine and discover the cause of the failure. The reinstatement of the TG 1 turbine was realised during 15 days in continual regime because TG 1 turbine is back-up power supply for the Bohunice NPP. (author)

  10. Evaluation of fatigue crack growth in the primary circuit pipeline of a WWER 440/213c type nuclear power plant

    Samohyl, P.

    1993-07-01

    The fatigue damage of the primary circuit of WWER-440/213c reactors was evaluated proceeding from actual and design operating data of units 3 and 4 of the Bohunice V-2 nuclear power plant. A complex computation model was set up, encompassing the main circulation pipeline, pressurizer pipeline, emergency core aftercooling system pipeline, steam pipeline, and feedwater pipeline. The standardized STATIC code was applied to the stress analysis, and the FATLBB code was used to determine the crack increment for all operating states and primary circuit sections. The probability of fatigue failure of the pipelines was found to be low. (J.B.). 55 tabs., 3 figs., 9 refs

  11. Containment leak-tightness enhancement at VVER 440 NPPs

    Prandorfy, M.

    2000-01-01

    The hermetic compartments of WWER 440 NPPs fulfil the function of the containment used at NPPs all over the world. The purpose of the containment is to protect the NPP personnel against radioactive impact as well as to prevent radioactive leakage to the. environ ent during a lost of coolant accident. Leak-tightness enhancement in NPPs with WWER 440/213 and WWER 440/230 reactors is an important safety issue. New procedures, measures and methods were adopted at NPPs in Mochovce, Jaslovske Bohunice, Dukovany and PAKS for leak identification and sealing works performed by VUEZ Levice. (authors)

  12. European Decommissioning Academy

    Slugen, V. S.; Hornacek, M.

    2016-01-01

    Full text: Experiences from the first run of the European Decommissioning Academy (EDA) are reported in details. EDA was created at the Slovak University of Technology in Bratislava Slovakia, based on discussion and expressed needs declared at many international meetings including ECED2013. The first run successfully passed 15 participants during 7–26 June 2015. Academy was focused on decommissioning issues via lessons, practical exercises in laboratories, on-site training prepared at NPP V-1 in Jaslovské Bohunice, Slovakia as well as four day technical tour to other European decommissioning facilities in Switzerland and Italy. Detailed information can be found at http://kome.snus.sk/inpe/. (author

  13. European Decommissioning Academy (EDA) - successful 1. run in june 2015

    Slugen, V.; Hornacek, M.

    2015-01-01

    Experiences from the first run of the European Decommissioning Academy (EDA) are reported in details. EDA was created at the Slovak University of Technology in Bratislava Slovakia, based on discussion and expressed needs declared at many international meetings including ECED2013. The first run successfully passed 14 participants during 7.-20.6. 2015. Academy was focused on decommissioning issues via lessons, practical exercises in laboratories, on-site training prepared at NPP V-1 in Jaslovske Bohunice, Slovakia as well as 4 days technical tour to other European decommissioning facilities (Swiss, Italy), respectively. Detailed information can be found at http://kome.snus.sk/inpe/. (authors)

  14. Sequential determination of {sup 239,240}Pu, {sup 238} Pu, {sup 241} Am and {sup 90}Sr in radioactive wastes using SPE sorbents Analig Pu02, AnaLig Sr01 and TRU Resin; Sekvencne stanovenie {sup 239,240}Pu, {sup 238} Pu, {sup 241} Am a {sup 90}Sr v radioaktivnych odpadoch pouzitim SPE sorbentov Analig Pu02, AnaLig Sr01 a TRU Resin

    Durkot, E; Dulanska, S [Univerzita Komenskeho v Bratislave, Prirodovedecka fakulta, Katedra jadrovej chemie, 84215 Bratislava (Slovakia)

    2012-04-25

    A simple and rapid method of the sequential determination of radionuclides {sup 239,240}Pu, {sup 238} Pu, {sup 241} Am and {sup 90}Sr in radioactive sludge from the NPP Bohunice A1 with high radiochemical yields and efficient removal of interfering components from a matrix was developed. Separation method combines SPE sorbents Analig Pu02, AnaLig Sr01 made by IBC Advanced Technologies and TRU Resin (Eichrom Technologies) placed in tandem. Advantage of a single-stage column located on the vacuum box with a rapid flow is an effective pre-concentration and separation of radionuclides and minimization of sample separation time. (authors)

  15. Developing new serious games tools to improve radiation protection

    Majersky, T.; Rapant, T.; Bayer, M.; Majersky, D.

    2008-01-01

    In this paper, novel software technologies for simulation and training of workers in radiologically dangerous conditions are presented. Such new software tools enable the radiation protection managers and workers to better evaluate, visualize and intuitively understand the radiation situation. In the first part of the paper, virtual reality planning tool ALPLANNER is introduced. ALPLANNER enables computation of worker's doses and 3D simulation of planned activities in the environment. In the second part of the paper , a software technology SP ACEVISION for real-time interactive 3D visualization of radioactivity is presented. Radiation fields can be spatially and dynamically visualized in the environment using computer games technologies. Such real-time visualization can be used by RP staff to compute and visualize direct responses of the radiation field to the effects of shielding. Another presented application is determination and visualization of activity sources in inhomogeneous radiation fields. Practical example of how the mentioned software technologies are used during the decommissioning of NPP A-1 Jaslovske Bohunice is provided. Practical example of how the mentioned software technologies are used during the decommissioning of NPP A-1 Jaslovske Bohunice is provided. (authors)

  16. Developing new serious games tools to improve radiation protection

    Majersky, T.; Rapant, T.; Bayer, M.; Majersky, D.

    2009-01-01

    In this paper, novel software technologies for simulation and training of workers in radiologically dangerous conditions are presented. Such new software tools enable the radiation protection managers and workers to better evaluate, visualize and intuitively understand the radiation situation. In the first part of the paper, virtual reality planning tool ALPLANNER is introduced. ALPLANNER enables computation of worker's doses and 3D simulation of planned activities in the environment. In the second part of the paper , a software technology SP ACEVISION for real-time interactive 3D visualization of radioactivity is presented. Radiation fields can be spatially and dynamically visualized in the environment using computer games technologies. Such real-time visualization can be used by RP staff to compute and visualize direct responses of the radiation field to the effects of shielding. Another presented application is determination and visualization of activity sources in inhomogeneous radiation fields. Practical example of how the mentioned software technologies are used during the decommissioning of NPP A-1 Jaslovske Bohunice is provided. Practical example of how the mentioned software technologies are used during the decommissioning of NPP A-1 Jaslovske Bohunice is provided. (authors)

  17. Feasibility studies for decommissioning

    Hladky, E.

    2000-01-01

    In this presentation author deals with planning of decommission of the NPPs A1, V1 and V2 Bohunice and Mochovce. It was concluded that: Used model for decommissioning parameters assessment has been suitable for elaboration of initial decommissioning plans (feasibility studies); Basic assessment of main decommissioning parameters and basic comparison of various decommissioning options have been possible; Improvement of the model and corresponding software is desirable and works on software improvement began one year ago; V1-NPP initial decommissioning plan should be actualized, because initial decommissioning plan does not correspond by its content and structure to requirements of Act No. 130/98 and Nuclear Regulatory Authority Degree No. 246/99; Strategy of radioactive wastes treatment and conditioning together with technical provisions at Jaslovske Bohunice site was changed in comparison with the assumptions in 1991-92; Considered V1 NPP decommissioning options are necessary to be re-evaluated in accordance with latest development of knowledge and approaches to NPP decommissioning in the world; Specific unit costs are substantially and differentially changed in comparison with the assumptions in 1991-92; Necessity to take into account technical changes resulted from V1 NPP reconstruction. (author)

  18. Nuclear safety in Slovak Republic. Status of safety improvements

    Toth, A.

    1999-01-01

    Status of the safety improvements at Bohunice V-1 units concerning WWER-440/V-230 design upgrading were as follows: supplementing of steam generator super-emergency feed water system; higher capacity of emergency core cooling system; supplementing of automatic links between primary and secondary circuit systems; higher level of secondary system automation. The goal of the modernization program for Bohunice V-1 units WWER-440/V-230 was to increase nuclear safety to the level of the proposals and IAEA recommendations and to reach probability goals of the reactor concerning active zone damage, leak of radioactive materials, failures of safety systems and damage shields. Upgrading program for Mochovce NPP - WWER-440/V-213 is concerned with improving the integrity of the reactor pressure vessel, steam generators 'leak before break' methods applied for the NPP, instrumentation and control of safety systems, diagnostic systems, replacement of in-core monitoring system, emergency analyses, pressurizers safety relief valves, hydrogen removal system, seismic evaluations, non-destructive testing, fire protection. Implementation of quality assurance has a special role in improvement of operational safety activities as well as safety management and safety culture, radiation protection, decommissioning and waste management and training. The Year 2000 problem is mentioned as well

  19. Radon in outdoor air at various sites in Slovakia

    Bulko, Martin; Holy, Karol; Muellerova, Monika; Polaskova, Anna; Hola, Olga

    2010-01-01

    Radon 222 was continuously monitored at four sites of Slovakia, viz. at the campus of the Faculty of Mathematics, Physics and Informatics, Comenius University in Bratislava (FMPI CU), at the Slovak Metrological Institute in Bratislava (SMI), at Jaslovske Bohunice (with its nuclear power plant), and at Novaky (coal mining area). The minima and maxima of the daily radon waves occurred at different periods of the day. The average radon activity concentration (RAC) in Novaky was more than twice as high as at the remaining sites, presumably due to a higher rate of radon exhalation from soil. By using the 'box' model, the exhalation rate at Novaky was estimated to be 40 mBq.m -2 .s -1 , which is about 2.5 times that at the FMPI CU in Bratislava. This higher exhalation rate in Novaky is probably caused by a different bedrock in this area. The average annual effective dose from radon and its daughters estimated by the UNSCEAR methodology is 0.06 mSv in the atmosphere of Bratislava and Jaslovske Bohunice and 0.13 mSv in the atmosphere of Novaky

  20. Radon in the atmosphere in two different localities of Slovakia

    Bulko, M.; Holy, K.; Polaskova, A.; Simon, J.; Muellerova, M.; Melicherova, T.; Hola, O.

    2006-01-01

    Radon activity concentration in the atmosphere can vary more or less according to the locality of the measurement. In this paper there are compared radon activity concentration (RAC) and equilibrium equivalent concentration (EEC) obtained in two different localities of Slovakia (Bratislava and Jaslovske Bohunice, respectively). The localities are about 55 km apart from each other. Data analyses for 5 months of the year 2005 are presented. A surprisingly good agreement between the localities was found on the variations and mean values. These results imply that the turbulent mixing of air in the atmosphere of both localities is very similar. Various EEC/RAC ratios were found for different months, which might indicate a change in equilibrium factor F during the year. There was also found out that the mean daily courses observed in the two localities are slightly shifted apart. This is probably caused by different orography of the area where the measurement devices are installed and because of an earlier incidence of solar radiation on the measurement area in Jaslovske Bohunice. (authors)

  1. Radioactivity in the environment

    2006-01-01

    In this report different aspects of the radioactivity in the environment of the Slovak Republic for the period of 2004 - 2006 years are reported. This report is published only on the Enviroportal.sk. The following aspects of the radioactivity in the environment are reviewed there: Electricity production in nuclear power plants and their consumption; Natural sources of ionisation radiation; Man-made sources of ionisation radiation; Safety of exploitation of the nuclear power plants on the territory of the Slovak Republic; International Nuclear Event Scale; Basic information about influence of radiation on health of population and about evaluation methods; Influence of physical risk factors (including of ionisation radiation) in the working environment on formation of occupation diseases; Collective doses of occupation in NPPs; Health state of population in the locality of the NPP Mochovce; Food contamination by ionisation radiation; Radiation monitoring network; Legislative directives about population health protection against ionisation radiation action; Decommissioning of the NPP Jaslovske Bohunice (EBO V-1); Conception of the back fuel cycle and treatment of spent fuels and high-level radioactive wastes; Project of territorial-economic development of the Trnava region after decommissioning of the Jaslovske Bohunice NPP

  2. Feasibility study for NPP Mochovce Units 3 and 4 completion

    Tomik, L.; Chakraborty, S.; Hoffelner, W.; Stoian, A.

    2004-01-01

    The system dynamic approach presented in this study by modelling the behaviour of Slovak market on the basis of system dynamic model (Forrester model), enables real mix in the extend of 12 years and helps understanding of the market limits. In addition this tool can be used for sensitivity calculations depending on many parameters to develop possible trends in the economic development of the Slovak Republic. If both nuclear power options are maintained then it becomes obvious that electric excess energy is produced and could be exported. This export option remains for the situation that a strong growth of the gross national product is assumed without any increase in energy efficiency. Between these extremes is the scenario that Bohunice 1, 2 off is balanced by Mochovce 3, 4 on and increasing demand this will lead to more moderate but still not negligible potential of CO 2 increase. Switching off Bohunice 1, 2 and not switching on Mochovce 3, 4 leads to energy need which must be counterbalanced either by investments in other power plants or by import energy. As far as domestic production is concerned even assuming 50 % CHP production leads to partly remarkable additional CO 2 -production which might infringe on a long term basis with the Kyoto goals. Assuming additional CO 2 -emissions from increasing traffic real problems can be expected in such a case. To maintain national nuclear capabilities in Slovakia is very important for today and for future of nuclear energy option in enlarged European Union. (authors)

  3. A model study of cost estimates of decontamination and decommissioning with an emphasis to derive cost functions for alpha contaminated material using OMEGA code

    Kristofova, Kristina; Daniska, Vladimir; Ondra, Frantisek; Rehak, Ivan; Vasko, Marek [DECOM SLOVAKIA spol. s.r.o., Trnava (Slovakia)

    2004-12-01

    The presented study is focused on model decommissioning cost calculations for primary circuit of A-1 nuclear power plant in Jaslovske Bohunice. In addition, the survey of advanced decommissioning costing is included together with impact analyses of contamination on particular decommissioning parameters. OMEGA code decommissioning cost calculations for primary circuit of A-1 NPP presented in the study are performed and evaluated under the following conditions: different contamination level of inner and outer surfaces; different waste management scenarios; application and non-application of pre-dismantling decontamination; different start of decommissioning: 2004, 2010, 2020, 2030, 2040; radionuclide composition of primary circuit contamination in A-1 NPP with occurrence of alpha radionuclides and fission products as a consequence of operational accident with damaged fuel cladding; radionuclide composition of primary circuit contamination in V-2 NPP in Jaslovske Bohunice as a representative NPP with an operation without accidents and therefore neither non-alpha contaminants nor fission products are included. The results of all the above mentioned conditions impacts on calculated costs, manpower, exposure and distribution of materials arisen from decommissioning are evaluated in detail within the calculation sensitivity analysis.

  4. Computation code TEP 1 for automated evaluation of technical and economic parameters of operation of WWER-440 nuclear power plant units

    Zadrazil, J.; Cvan, M.; Strimelsky, V.

    1987-01-01

    The TEP 1 program is used for automated evaluation of the technical and economic parameters of nuclear power plant units with WWER-440 reactors. This is an application program developed by the Research Institute for Nuclear Power Plants in Jaslovske Bohunice for the KOMPLEX-URAN 2M information system, delivered by the USSR to the V-2 nuclear power plants in Jaslovske Bohunice and in Dukovany. The TEP 1 program is written in FORTRAN IV and its operation has two parts. First the evaluation of technical and economic parameters of operation for a calculation interval of 10 mins and second, the control of the calculation procedure, follow-up on input data, determination of technical and economic parameters for a lengthy time interval, and data printout and storage. The TEP 1 program was tested at the first unit of the V-2 power plant and no serious faults appeared in the process of the evaluation of technical and economic parameters. A modification of the TEP 1 programme for the Dukovany nuclear power plant is now being tested on the first unit of the plant. (Z.M.)

  5. VUEZ. Annual report 2005

    2006-01-01

    A brief account of activities carried out by the Vyskumny ustav energetickych zariadeni, a.s. (VUEZ) in 2005 is presented. These activities are reported under the headings: (1) Introductory address by the Chairman of the Board of Directors; (2) On the company; (3) Basic data; (4) Product portfolio and customer services; (5) Quality management system; (6) Human resources; (7) Economic data; (7) Adving, s.r.o.; (8) Basic data and company management; (9) Line of business; (10) Activities performed in the past year; (11) Economic data; (12) Contact persons and addresses. In 2005, a number of important events took place in VUEZ. On the home market, our main business partner was SE a.s. Company. The key works were performed at SE nuclear power plant sites in Jaslovske Bohunice and Mochovce. A considerable volume of works co-ordinated by our company was executed also for Vodohospodarska vystavba Bratislava at the Gabcikovo Dam. On the foreign market, VUEZ kept on carrying out ongoing projects of preparation for the Jaslovske Bohunice V1 NPP decommissioning in co-operation with a consortium of foreign companies. In the field of experimental research, another project was launched in co-operation with IRSN Paris. As to leak tightness improvement of hermetic compartments and integrated leakage rate tests in nuclear power plants, works were continued in foreign plants such as the Dukovany NPP, Czech Republic, and the Paks NPP, Hungary

  6. The most extensive reconstruction of nuclear power plant with VVER 440/V230 reactor

    Ferenc, M.

    2000-01-01

    The nuclear power plant V-1 Bohunice consists of two VVER-440 units with V-230 reactors. Unit 1 was commissioned in 1978 and Unit 2 in 1980. Large experience and knowledge from the operation of previous units with V-230 reactors were incorporated into the V-1 design, which resulted in a higher level of safety and operational reliability of these units. The Siemens company which won an international bidding process developed these basic goals for the Gradual Upgrading into the so called Basic Engineering (BE). For the implementation of the Gradual Upgrading in line with the BE, Rekon consortium was established consisting of Siemens and VUJE. The implementation of the Gradual Upgrading is scheduled for the time period of 1996 - 2000. Siemens was responsible for the upgrading strategy - based on the approved results of the basic engineering phase and the PSAR, the engineering and realization of all I and C improvements, and also for the seismic upgrade. VUJE's responsibility covered the detailed engineering and implementation of mechanical, electrical and civil part of upgrading measures as well as overall organisation and evaluation of verification tests. The consortium awarded contracts for final planning and design, installation services and commissioning to other Slovakian subcontractors in order to ensure the largest possible local content. The gradual reconstruction of the V-1 Bohunice with V230 reactors represents a comprehensive reconstruction of safety-related systems and equipment. Following its completion, the units will be operated with a safety level accepted internationally. (author)

  7. Modeling of detection efficiency of HPGe semiconductor detector by Monte Carlo method

    Rapant, T.

    2003-01-01

    Over the past ten years following the gradual adoption of new legislative standards for protection against ionizing radiation was significant penetration of gamma-spectrometry between standard radioanalytical methods. In terms of nuclear power plant gamma-spectrometry has shown as the most effective method of determining of the activity of individual radionuclides. Spectrometric laboratories were gradually equipped with the most modern technical equipment. Nevertheless, due to the use of costly and time intensive experimental calibration methods, the possibilities of gamma-spectrometry were partially limited. Mainly in late 90-ies during substantial renovation and modernization works. For this reason, in spectrometric laboratory in Nuclear Power Plants Bohunice in cooperation with the Department of Nuclear Physics FMPI in Bratislava were developed and tested several calibration procedures based on computer simulations using GEANT program. In presented thesis the calibration method for measuring of bulk samples based on auto-absorption factors is described. The accuracy of the proposed method is at least comparable with other used methods, but it surpasses them significantly in terms of efficiency and financial time and simplicity. The described method has been used successfully almost for two years in laboratory spectrometric Radiation Protection Division in Bohunice nuclear power. It is shown by the results of international comparison measurements and repeated validation measurements performed by Slovak Institute of Metrology in Bratislava.

  8. A model study of cost estimates of decontamination and decommissioning with an emphasis to derive cost functions for alpha-contaminated material using OMEGA code

    Kristofova, Kristina; Daniska, Vladimir; Ondra, Frantisek; Rehak, Ivan; Vasko, Marek

    2004-12-01

    The presented study is focused on model decommissioning cost calculations for primary circuit of A-1 nuclear power plant in Jaslovske Bohunice. In addition, the survey of advanced decommissioning costing is included together with impact analyses of contamination on particular decommissioning parameters. OMEGA code decommissioning cost calculations for primary circuit of A-1 NPP presented in the study are performed and evaluated under the following conditions: different contamination level of inner and outer surfaces; different waste management scenarios; application and non-application of pre-dismantling decontamination; different start of decommissioning: 2004, 2010, 2020, 2030, 2040; radionuclide composition of primary circuit contamination in A-1 NPP with occurrence of alpha radionuclides and fission products as a consequence of operational accident with damaged fuel cladding; radionuclide composition of primary circuit contamination in V-2 NPP in Jaslovske Bohunice as a representative NPP with an operation without accidents and therefore neither non-alpha contaminants nor fission products are included. The results of all the above mentioned conditions impacts on calculated costs, manpower, exposure and distribution of materials arisen from decommissioning are evaluated in detail within the calculation sensitivity analysis

  9. Chapter 9. Personnel qualification and training

    2001-01-01

    The overall training system and the development of projects for training of all categories of NPP V-1, NPP V-2 Bohunice, SE-VYZ and NPP Mochovce staff were the subject of Nuclear Regulatory Authority of the Slovak Republic (UJD) attention. During 2000, the following inspections were carried out on nuclear personnel training: (a) NPP Bohunice: an inspection focused on compliance with requirements for staff qualifications and compliance with the prescribed training of Bohunice plant staff ; (b) NPP Mochovce: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of NPP Mochovce staff; an inspection focused on verifying the simulator aided training; an inspection focused on checking the preparedness of NPP Mochovce operation and technical personnel for NPP Mochovce Unit 2 operation; (c) Technology for treatment and conditioning of radioactive waste Bohunice (BSC): an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of SE-VYZ staff; VUJE Trnava: verification of technical equipment and professional skills of VUJE Trnava staff and tasks arising out of the 'Authorisation on nuclear installation staff training'. Examinations of selected personnel were scheduled according to the plan of examining committee meetings. For each examined person written tests are generated by the computer from the database of test questions at the Training Centre of VUJE Trnava for individual positions - categories of selected staff of NPP V-1 and NPP V-2 Bohunice and NPP Mochovce so that the examination questions both in written and oral part equally cover individual facilities and regimes of operation of NPP. The database is continuously updated, thereby containing new questions resulting from the recent changes carried out at NPPs. A part of the examination in case of promotion to a higher position is the practical part, which is conducted under

  10. Chapter 4. Assessment and inspection of nuclear installations

    2001-01-01

    Supervisory activity of Nuclear Regulatory Authority of the Slovak Republic (UJD) upon the safety of nuclear installations in compliance with the 'Atomic Act' and other legal regulations includes also inspection and assessment activities of UJD. Assessment activity of UJD in relation to nuclear installations lies in assessment of safety documentation for constructions realised as nuclear installations, or constructions through which changes are realised on nuclear installations. The scope of safety documentation required for the assessment is stipulated in the Atomic Act. In 2000 the assessment activity focused first of all on Unit 1 of NPP Bohunice after completing its Gradual Reconstruction Programme, on National Repository of Radioactive waste in Mochovce and on radioactive waste conditioning and treatment technology in Jaslovske Bohunice. Activities of UJD in assessment focused mainly on control of compliance with requirements for nuclear safety, assessment of commissioning programmes, operating procedures, limits and conditions, etc. The assessment of changes, which influence nuclear safety of nuclear installations in operation, realisation of which is conditioned by the approval from UJD, is a significant part of the assessment activity of UJD. Mainly it is the assessment of design changes, changes in limits and conditions, operating procedures, changes in programmes of periodical testing of equipment important in terms of nuclear safety, changes in physical protection of nuclear equipment, etc. The assessment of nuclear installations operational safety, based on assessment of operational events, on maintaining limits and conditions of safe operation, on operational safety performance indicators and on inspection results is a separate category in the assessment activity of UJD. Inspection activity specified in the 'Atomic Act' is governed by an internal guideline, an important part of which is an annual inspection plan that considers the following types of

  11. Chapter No.6. Radioactive waste (RAW)

    2002-01-01

    UJD SR supervises all phases of radioactive waste management at nuclear installations and final phases of institutional radioactive waste management. Total concentrates generation and minimisation trends during recent period (for NPP V1, NPP V2 Bohunice and NPP Mochovce) as well as increasing of their conditioning are presented. So nearly 8000 m3 of concentrates were stored at the end of year 2001, representing 75.5% of storage capacity at Bohunice site. Total amount of solid waste stored at VVER NPPs reached 3500 m3 at December 2001. The solid waste storage capacity of NPP V1 Bohunice is spent. NPP A1 Bohunice with a heterogeneous reactor using natural uranium, moderated by heavy water and cooled by CO 2 had been in operation for 4 years. It was finally shut down in February 1977 after an accident (INES level 4). Main activities in 2001 were focused on an increasing of radwaste management safety by the waste solidification or storage improvement, especially in the case of inorganic spent fuel coolant. The total solid radwaste inventory in 2001 (including filters) represents cca 700 m3 of soft and pre-pressed not sorted waste, 700 m3 of sorted waste, more then 1 000 t of scrap and next 260 m3 of scrap in drums. The total volume of contaminated soils and concrete is more than 7200 m3. The volume of solid radwaste depends on the extent of dismantling works and following treatment, conditioning and disposal. The total volume is also increased by products of bituminization and cementation facilities in drums stored before conditioning at NPP A1 Bohunice site. The facilities focused only on treatment of radwaste from NPP A1 decommissioning are operated by the same operator as a part of this decommissioned nuclear installation. Experimental and research treatment plants are operated by VUJE. A facility for the treatment and conditioning of operational liquid radwaste from NPP Mochovce is under preparation and a start of construction is foreseen in 2004. The nuclear

  12. Nuclear business worth billions begins

    Beer, G.; Marcan, P.; Slovak, K.

    2005-01-01

    The first V1 unit of Bohunice nuclear power station is to be shutdown by the end of next year. However, its decommissioning can only start in 2011 as before the decommissioning can start the second unit must be shutdown and the nuclear fuel to be stored in a basin must cool down. But in spite of these limitations, the decommissioning process has already started. Various analyses and projects have been put out to tender, work on the technical division of the decommissioned V1 units from the V2 units, which will remain in service, has also began. The state owned company, GovCo, a.s., will be in charge of the decommissioning of the V1 units. The method to be applied to the decommissioning of the V1 units has not yet been selected. The project management unit of Slovak Electric favours immediate decommissioning. 'Not only will decommissioning start immediately following the removal of the nuclear fuel, but it will also be done continuously,'explained unit director, Peter Hlbocky. Using this procedure, decommissioned could be complete by 2026. The question as to whether the power plant will be completely decommissioned to create a green field site will, according to P. Hlbocky, depend on Slovakia's future plans regarding nuclear energy generation at Jaslovske Bohunice, which could be a suitable location for building a new nuclear power station. In such a case, a part of the infrastructure would remain in place. 'Should Slovakia decide to continue its nuclear program, it would be a waste not to take advantage of the existing infrastructure,' said P. Hlbocky. The cabinet is to decide on the method to be used for decommissioning of the V1 reactor and the time frame for the process by the end of next year. The cabinet will decide mainly on the basis of cost estimates to be prepared together with decommissioning concept that is currently under preparation. The decommissioning concept financed by the Bohunice International Decommissioning Support Fund should provide more

  13. Annual Report 2007 VUJE

    Anon

    2008-01-01

    VUJE foundation is closely connected with the history of Bohunice nuclear power plant. The team of research and development employees in Bohunice nuclear power plant formed the basis for foundation of the Vyskumny ustav jadrovych elektrarni (Nuclear Power Plant Research Institute - hereinafter referred to as VUJE or Company). Institute started its operations on January 1, 1977 as a concern company of Slovenske energeticke podniky (Slovak Power Enterprises). One year later VUJE became an independent organization controlled directly by the Federal Ministry of Fuels and Power. Excellent results were the impulse for the federal government to accredit VUJE in 1983 to lead the scientific commissioning of all nuclear power plants in Czechoslovakia. In 1983 started VUJE the branch education and training centre, which was in the next year equipped with a full-range simulator of WWER 440/213 reaktor unit. This centre gradually achieved international recognition. The international Atomic Energy Agency in Vienna also carried out training courses here. VUJE moved its headquarters to Trnava in 1985, however multiple experimental facilities, development workshops and some laboratories stayed in the area of nuclear power plants in Jaslovske Bohunice. At the end of the eighties VUJE counted 759 employees and gained an important position not only in Czechoslovakia, but also within international nuclear power industry. Important changes in the whole society in 1989 also influenced the future in the institute. Management developed a new organizational model of VUJE and step-by- step also the institute's strategy and line of business. Company retained its focus and was transformed in to a state company. In the following privatisation the joint-stock company established by the institute's employees bought the state research institute. The institute was transformed into a private joint-stock company Vyskumny ustav jadrovych elektrarni Trnava, a.s as of November f 1, 1994. A The

  14. Annual report 2006 VUJE

    Anon

    2006-01-01

    VUJE foundation is closely connected with the history of Bohunice nuclear power plant. The team of research and development employees in Bohunice nuclear power plant formed the basis for foundation of the Vyskumny ustav jadrovych elektrarni (Nuclear Power Plant Research Institute - hereinafter referred to as VUJE or Company). Institute started its operations on January 1, 1977 as a concern company of Slovenske energeticke podniky (Slovak Power Enterprises). One year later VUJE became an independent organization controlled directly by the Federal Ministry of Fuels and Power. Excellent results were the impulse for the federal government to accredit VUJE in 1983 to lead the scientific commissioning of all nuclear power plants in Czechoslovakia. In 1983 started VUJE the branch education and training centre, which was in the next year equipped with a full-range simulator of WWER 440/213 reaktor unit. This centre gradually achieved international recognition. The international Atomic Energy Agency in Vienna also carried out training courses here. VUJE moved its headquarters to Trnava in 1985, however multiple experimental facilities, development workshops and some laboratories stayed in the area of nuclear power plants in Jaslovske Bohunice. At the end of the eighties VUJE counted 759 employees and gained an important position not only in Czechoslovakia, but also within international nuclear power industry. Important changes in the whole society in 1989 also influenced the future in the institute. Management developed a new organizational model of VUJE and step-by- step also the institute's strategy and line of business. Company retained its focus and was transformed in to a state company. In the following privatisation the joint-stock company established by the institute's employees bought the state research institute. The institute was transformed into a private joint-stock company Vyskumny ustav jadrovych elektrarni Trnava, a.s as of November f 1, 1994. A The

  15. Chapter 8: Quality assurance

    2001-01-01

    The main efforts of Nuclear Regulatory Authority of the Slovak Republic (UJD) have been focused on inspection of quality assurance programmes of Slovak Power Stations, plc. and its daughter companies at Bohunice and Mochovce. Two quality assurance inspections in the area of periodical in service inspections (V-2 units) and tests of selected equipment (NPP V-2 units) and operation control (V-1 units) has been performed at NPPs Bohunice. One violation of decree on quality assurance of selected equipment has been found in the area of documentation archiving. The inspection concerning the implementation of quality assurance programme for operation of NPP Mochovce in the area of operation control has been performed focused on safety aspects of operation, operational procedures, control of operational events and feedback from operational experience. The results of this inspection were positive. Inspection of implementation of quality assurance programme for operation of radioactive waste repository (RU RAW) at the Mochovce location has been performed focused on receiving of containers, with radioactive wastes, containers handling, radiation monitoring, activities of documentation control and radiation protection at the repository site. No serious deficiencies have been found out. Also one inspection of experimental nuclear installations of VUJE Trnava at Jaslovske Bohunice site has been performed focused on procurement control, quality audits, documentation and quality records control when performing activities at experimental nuclear installations. The activity on development of internal quality assurance system continued. The implementation of this system will assure quality and effective fulfilment enlarged tasks of UJD with limited resources for its activity. The analyses of possible use of existing internal administrative control documentation as a basis for future quality system procedures was performed in co-operation with an external specialised organisation. The

  16. ESTE AI (Annual Impacts) - the program for calculation of radiation doses caused by effluents in routine releases to the atmosphere and to the hydrosphere

    Carny, P.; Suchon, D.; Smejkalova, E.; Fabova, V.

    2009-01-01

    ESTE AI is a program for calculation of radiation doses caused by effluents in routine releases to the atmosphere and to the hydrosphere. Doses to the members of critical groups of inhabitants in the vicinity of NPP are calculated and as a result, critical group is determined. The program enables to calculate collective doses as well. Collective doses to the inhabitants living in the vicinity of the NPP are calculated. ESTE AI calculates doses to the whole population of Slovakia from the effluents of the specific plant. In this calculation, global nuclides are included and assumed, as well. The program enables to calculate and to document beyond-border radiological impacts of effluents caused by routine operation of NPP. ESTE AI was approved by the 'Public Health Authority of the Slovak Republic' and is used as legal instrument by Slovenske elektrarne a.s., NPP Bohunice. (authors)

  17. Actual status of project Mochovce NPP units 3 and 4 completion

    Niznan, S.

    2005-01-01

    In this presentation author deals with actual status of project Mochovce NPP units 3 and 4 completion. Present state of Mochovce NPP, Units 3 and 4 enables real assumption to completion. It is expected that such supplier companies can be used which are experienced in field of nuclear projects. Based on budget of 2002, it seems that completion costs of 45 billions SKK are real. These figures were confirmed by study performed by TRACTEBEL in 2004. Based on experience from Bohunice NPP completion as well as from Mochovce NPP, Units 1 and 2 completion and if decision milestone and project start up deadlines will be observed according to modified preliminary schedule of Mochovce NPP Units 3 and 4 completion, it seems as real that Unit 3 will be completed till 06/2011 and Unit 4 - till 12/2011.

  18. Fire protection of nuclear power plant cable ducts

    Kandrac, J.; Lukac, L.

    1987-01-01

    Fire protection of cable ducts in the Bohunice and Dukovany V-2 nuclear power plants is of a fourtier type. The first level consists in preventive measures incorporated in the power plant design and layout. The second level consists in early detection and a quick repressive action provided by an electric fire alarm system and a stationary spray system, respectively. Fire partitions and glands represent the third level while special spray, paint and lining materials represent the fourth level of the protection. Briefly discussed are the results of an analysis of the stationary spray system and the effects reducing the efficiency of a fire-fighting action using this system. The analysis showed the need of putting off cable duct fires using mobile facilities in case the stationary spray system cannot cope any longer. (Z.M.). 3 figs., 2 refs

  19. Calculation of external exposure during transport and disposal of radioactive waste arisen from dismantling of steam generator

    Hornacek, M.; Necas, V.

    2014-01-01

    The dismantling of large components (reactor pressure vessel, reactor internals, steam generator) represents complex of processes involving preparation, dismantling, waste treatment and conditioning, transport and final disposal. To optimise all of these activities in accordance with the ALARA principle the prediction of the exposure of workers is an essential prerequisite. The paper deals with the calculation of external exposure of workers during transport and final disposal of heat exchange tubes of steam generator used in Slovak nuclear power plant V1 in Jaslovske Bohunice. The type of waste packages, the calculation models of truck and National Radioactive Waste Repository in Mochovce are presented. The detailed methodology of radioactive waste disposal is showed and the degree of influence of time decay (0, 5 and 10 years) on the radiological conditions during transport and disposal is studied. All of the results do not exceed the limits given in Slovak and international regulatory documents. (authors)

  20. Radioiodine in soils

    Szabova, T.

    1981-01-01

    Behaviour was studied of radioiodine in different soil subtypes sampled in the vicinity of the A-1 nuclear power plant at Jaslovske Bohunice. Radioiodine sorption is mainly affected by the amount of humus and by the clay fraction of soil. The highest sorption was recorded for meadow chernozem and the lowest for rendzina soils. At the same pH, soils with a higher level of organic matter adsorb more radioiodine. Upon applying radioiodate in soil samples, reduction to iodide takes place. Under the action of anions, radioiodine sorption decreases, the effect decreasing as follows: H 2 PO 4 - >SO 2- >Cl - >NO 3 - . The highest desorption was caused by 0.1 N NaOH solution. (author)

  1. Preparation for and building of V-1 nuclear power plant

    Smatlak, S.; Spirko, M.

    1981-01-01

    Some findings and problems encountered during the construction of the V-1 nuclear power plant at Jaslovske Bohunice are discussed from the point of view of the investor, mainly problems associated with project preparation and relations between suppliers and the customer. The progress of construction is described and the dates are shown of the main stages of construction and tests. The construction proceeded according to a net diagram and was controlled by the construction management and a coordination group headed by the investor. An international start-up commission was established for the start-up stage. The fields are outlined of the participation and co-operation of Soviet organizations during project preparation, supplies, assembly, start-up, and fuel supplies for the V-1 nuclear power plant. (B.S.)

  2. Slovak Chernobyl /1976/

    Sveda, R.

    2007-01-01

    In this video-film history of Bohunice A-1 NPP is presented. The A-1 reactor was an experimental reactor, which during 1973 - 1977 this NPP produced electricity. In January 5, 1976 during refuelling of fuel elements one of them was hurled and carbon dioxide leaks into reactor hall. The operator Viliam Paces packed the hole with refuelling machine. In this film process of refuelling and this reactor accident are reconstructed and reasons are analysed. Two workers were killed outside the premises of the reactor hall. Direct participants as well as one son of the victim recall about this accident. After repairing of the reactor this nuclear power plant was again put into operation. But in February 22, 1977 the second accident (level 4 of the INES scale) occurred after which the nuclear power plant has been closed.

  3. Use of fixation techniques in processing radioactive wastes from nuclear power plants in Czechoslovakia

    Seliga, M.

    1977-01-01

    The current state of radioactive waste disposal from the Bohunice nuclear power plant is described. The method of vacuum cementation was chosen for solidifying liquid radioactive wastes. This method makes it possible to obtain a product whose properties, namely strength, leachability, and radiation stability allow for the production of blocks without packing material. Also solved was the fixation of liquid radioactive waste using bituminization based on mixing liquid radioactive waste with aqueous bitumen emulsion in a film evaporator in which the mixture of liquid radioactive wastes and bitumen emulsion evaporate producing solid bitumen. The parameters are given of the cementation and bituminization lines which are designed for use in nuclear power plants with WWER type reactors. (J.B.)

  4. Optimization of determination of 126Sn by ion exchange chromatography method (presentation)

    Pasteka, L.; Dulanska, S.

    2013-01-01

    The aim of the work is to optimize the uptake of tin on anion exchange resins and application of this knowledge for the analysis of samples of radioactive waste from the device of Jaslovske Bohunice and Mochovce in determining of 126 Sn. First to be optimized a method for the separation of tin on ion exchange sorbent Anion Exchange Resin (1-X8, Chloride Form) from Eichrom Technologies. Model sample was prepared in 7 mol dm -3 HCl, because in that environment a sorbent effectively captures the tin, which is bounded complexly with chloride anions as SnCl 6 2- . The radiochemical separation yield was monitored by gamma spectrometric measurements on high purity germanium detector HPGe (E = 391 keV) by adding isotope 113 Sn to each model solution. The method of tin separation was optimized on model samples.

  5. The dilatations with the balloon catheter in treatment of the patients with the benign oesophageal stenoses

    Valek, V.; Benda, K.; Hrobar, P.; Mrazova, J.; Prasek, J.; Bilicky, J.; Vomela, J.; Hep, A.; Muenzova, H.

    1996-01-01

    Between January 1989 and June 1995 the authors dilated in the Department of Radiology in University Hospital Bohunice the benign stenosis of the oesophagus with balloon dilatation catheter in 76 of other patients. The aetiology of the stenosis was long-term reflux oesophagitis in the 39 patients (51%), achalasia 14 patients, 18%) postoperative benign stenosis in anastomosis (7 patients, 9%), corrosive stricture (5 patients, 6,5%), post-radiation stricture (5 patients, 6,5%) and epidermolysis bulosa oesophagi (2 patients, 3%). In four patients (5%) the aetiology of the stenosis was unknown. The standing of the dilatation was from 15 second to 6 minutes and dilatation was technically successful in all cases. First the authors used Owman Oesophageal Dilatation Kit (William COOK), before three years they started to used Rigiflex ORW Dilators Kit (Microvasive). In the patients with achalasia the authors currently used Rigiflex ABD Achalasia Balloon Dilator (Microvasive). (authors). 2 tabs., 3 figs., 14 refs

  6. Calculational experimental examination and ensuring of equipment and pipelines seismic resistance at starting and operating water-cooled and moderated reactor WWER-type NPPs. Final report

    1999-01-01

    The results of testing of equipment at Bohunice NPP and pipeline systems at Unit 3 of Kozloduy NPP (WWER-440 type reactors) are presented in this Final Report. These results side by side with experimental values of natural frequencies and decrements also include experimental data about vibration modes of tested equipment and pipelines. For the first time the results of new calculational-experimental examination of equipment seismic resistance at Unit 2 of Armenian NPP are presented. At Kozloduy NPP direction's request the planed additional tests of some selected items were put off on 1997. Instead of postponed tests we carried out detailed analysis of our past inspections of numerous equipment seismic resistance at the Unit 5 of Kozloduy NPP. Experimental data with results of additional analysis are presented

  7. Support calculations for management of PRISE leakage accidents

    Matejovic, P.; Vranka, L. [Nuclear Power Plants Research Inst. Vuje, Trnava (Slovakia)

    1997-12-31

    Accidents involving primary-to-secondary leakage (PRISE) caused by rupture of one or a few tubes are well known design basis events in both, western and VVER NPPs. Operating experience and in-service inspections of VVER-440 units have demonstrated also the potential for large PRISE leaks in the case of the steam generator (SG) primary collector cover lift-up (Rovno NPP). Without performing any countermeasure for limitation of SG collector cover lift-up, a full opening results in PRISE leak with an equivalent diameter 107 mm. Although this accident was not considered in the original design, this event is usually analysed as DBA too. Different means are available for detection and mitigation of PRISE leakage in NPPs currently in operation (J.Bohunice V-1 and V-2) or under construction (Mochovce) in Slovakia. 8 refs.

  8. Project investigation and analysis of soil-structure interaction effects in seismic response of NPPs EBO, EMO, Slovakia. Final report

    Juhasova, E.

    1999-01-01

    The work described in this report was devoted to investigation of expected seismic response of the structures of WWER-440/213 type NPPs, namely Mochovce and Bohunice. Special attention was devoted to the properties of subsoil materials and the transfer of seismic waves from the bedrock to the foundation structures. Theoretical background was elaborated and discussed for wave propagation of surface waves. Alternative procedure was derived for non-linear media accounting for complex modulus theory. Material characteristics of subsoils were investigated for both NPPs. The obtained results were used as a basis for forecasting and calculation of expected seismic response when the time history records from Paks explosion were used an input. It was pointed out that the used procedure, together with previous calculation of subsoil transfer characteristics completed well the comparison with experimental results

  9. Cooperation of nuclear reactor controller ARM-5S and turbine TVER-02

    Wagner, K.; Lnenicka, B.; Pokorny, F.; Prochazka, F.

    1985-01-01

    Turbines of Czechoslovak make provided with controllers TVER-02 are installed in WWER-440 nuclear power plants under construction in Czechoslovakia. Reactor output is controlled using Soviet-made controllers ARM-5S which already comprise turbine controllers. The problems are analyzed of cooperation of both controllers, especially their parameters and transient processes in typical operating situations. The analysis uses the results of measurements performed during the power start-up of Unit 1 of the V-2 nuclear power plant at Jaslovske Bohunice. The results show that two types of control modes can be selected for the operation of the entire unit: the control to constant unit output, and control of unit output varying with turbine load selected on the TVER-02 controller or given by the demand of the power network. (Z.M.)

  10. VVER-440 training simulators upgrades - Experience of CORYS T.E.S.S

    Bartak, J.; Fallon, B.

    2006-01-01

    The paper presents recent projects of upgrading screen operated simulators of VVER-440 nuclear power plants to full scale replica simulators, implemented by CORYS TESS. Control room replica full scope simulators were built for the Bohunice NPP in Slovakia and the Novovoronezh NPP in Russia. The scope of simulation was extended to reflect the current status of the units, which have undergone significant modernization programs over the last few years. The paper describes the software and hardware adaptations and evolutions of the existing simulators, the implementation in the simulator of modern supervision systems as well as of systems and equipment designed in the seventies and still used on the reference units. The training benefits of parallel use of control room replica and screen-operated simulators in the training process are discussed. (author)

  11. ESTE AI (Annual Impacts) - the program for calculation of radiation doses caused by effluents in routine releases to the atmosphere and to the hydrosphere

    Carny, P.; Suchon, D.; Smejkalova, E.; Fabova, V.

    2008-01-01

    ESTE AI is a program for calculation of radiation doses caused by effluents in routine releases to the atmosphere and to the hydrosphere. Doses to the members of critical groups of inhabitants in the vicinity of NPP are calculated and as a result, critical group is determined. The program enables to calculate collective doses as well. Collective doses to the inhabitants living in the vicinity of the NPP are calculated. ESTE AI calculates doses to the whole population of Slovakia from the effluents of the specific plant. In this calculation, global nuclides are included and assumed, as well. The program enables to calculate and to document beyond-border radiological impacts of effluents caused by routine operation of NPP. ESTE AI was approved by the 'Public Health Authority of the Slovak Republic' and is used as legal instrument by Slovenske elektrarne a.s., NPP Bohunice. (authors)

  12. V-1 nuclear power plant standby RPP-16S computer software

    Suchy, R.

    1988-01-01

    The software structure of the function of program modules of the RPP-16S standby computer which is part of the information system of the V-1 Bohunice nuclear power plant are described. The multitasking AMOS operational system is used for the organization of programs in the computer. The program modules are classified in five groups by function, i.e., in modules for the periodical collection of values and for the measurement of process quantities for both nuclear power plant units; for the primary processing of the values; for the monitoring of exceedance of preset limits; for unit operators' communication with the computer. The fifth group consists of users program modules. The standby computer software was tested in the actual operating conditions of the V-1 power plant. The results showed it operated correctly; minor shortcomings were removed. (Z.M.). 1 fig

  13. The numerical benchmark CB2-S

    Chrapciak, Vladimir

    2000-01-01

    In this paper are activity, neutron and gamma source strength of 1 kg WWER-440 spent fuel (enrichment 3.6%, burnup 40 MWd/kg U) for short (Is up to 2 500 000 s(=1 month) and long period (l y up to 100 000 years) published. In the first period (up to 100 years) dominates activity from fission products. After 100 years main sources are actinides (mainly Pu). Gamma is produced first 100 years from fission products and later from actinides. Neutrons ((α,n) and spontaneous fission) are from various isotopes Np, Pu, Am and Cm. In second part is neutron measurement (dependence neutron sources on burnup for WWER-440 3.6% fuel) in NPP Jaslovske Bohunice described. (Author)

  14. Chemical mode control in nuclear power plant decommissioning during operation of technologies in individual radioactive waste processing plants

    Horvath, J.; Dugovic, L.

    1999-01-01

    Sewage treatment of nuclear power plant decommissioning is performed by system of sewage concentration in evaporator with formation of condensed rest, it means radioactive waste concentrate and breeding steam. During sewage treatment plant operation department of chemical mode performs chemical and radiochemical analysis of sewage set for treatment, chemical and radiochemical analysis of breeding steam condensate which is after final cleaning on ionization filter and fulfilling the limiting conditions released to environment; chemical and radiochemical analysis of heating steam condensate which is also after fulfilling the limiting conditions released to environment. Condensed radioactive concentrate is stored in stainless tanks and later converted into easy transportable and chemically stable matrix from the long term storage point of view in republic storage Mochovce. The article also refer to bituminous plant, vitrification plant, swimming pool decontamination plant of long term storage and operation of waste processing plant Bohunice

  15. Experience-based teaching of acute medicine for extra motivated medical students and young physicians – 4th Emergency Medicine Course and 6th AKUTNĚ.CZ Congress

    Petr Štourač

    2014-12-01

    Full Text Available Faculty of Medicine of the Masaryk University (MU, and especially its departments focusing on acute medicine, make an active effort to find and to support extra motivated students by organising courses and congresses with simulation-based learning sessions for them. 4th Emergency Medicine Course (EMC and 6th AKUTNĚ.CZ Congress were organised during 2014. EMC was held during a weekend in mid-April for 80 medical students. The congress was held on 22nd November 2014. A group of more than 700 enthusiastic professionals including physicians, nursing staff and medical students interested in acute medicine met again in Brno at the University Campus Bohunice. We also report the evaluation of effectiveness of different types of sessions, as well as its influence on practical skills and the fixation of memory footprint. The website AKUTNĚ.CZ (www.akutne.cz is freely accessible, and anyone can find and watch all the videos and presentations there.

  16. Scenarios for dealing with large components in the process of decommissioning nuclear power plants and the possibility of their implementation in the Slovak Republic

    Hornacek, M.; Necas, V.

    2014-01-01

    The subject of this presentation is a general assessment of the strategies of dismantling of large components in view of the experience gained from projects implemented as well as the identification of the factors determining the choice of the appropriate disassembly procedure. The paper also deals with the possibilities of removing the steam generator used in nuclear power plant Bohunice V1, which is currently in the process of decommissioning. Different scenarios for dismantling, storage respectively storing into the repository are analyzed. The is also studied the impact of declining of the activity of natural decay and application of decontamination technologies (before or dismantling decontamination) on quantities of materials releasable into the environment respectively leviable in the corresponding storage system. (authors)

  17. Termination of exploitation of V 1 NPP - BIDSF projects

    Pnackova, L.

    2004-01-01

    In this paper the interview with engineer Peter Hlbocky, director of division of the Project of decommissioning of V 1 Nuclear Power Plant in Jaslovske Bohunice is presented. Project Manager Unit (PMU) was formed on the basis of directive of the General Director of the Slovenske elektrarne, a.s. The Director of the Division of decommissioning of the V 1 NPP and at the same time the Main manager of the PMU is engineer Peter Hlbocky. On this project participate 19 employees of the Slovenske elektrarne, a. s. (SE), 6 abroad employees of the consortium IBERINCO, 15 employees of the VUEZ and 25 abroad employees on the detached place of work in the Spain and France

  18. Microcomputer network for technological equipment monitoring and control

    Segec, O.

    1990-01-01

    The properties and purpose are characterized of a microcomputer network developed for monitoring and controlling the nuclear power plant chemistry. In the development, emphasis was put on simplicity of the components, reliability, ease of operation and availability of the components on the domestic market. So far, these criteria are only met by the DIAMO L(S) system equipped with an MH 8080 (Z80) processor. Its assets include simplicity and ruggedness, owing to which it is well suited to heavy-duty performance, whereas its drawbacks comprise a narrow extent of addressable memory and absence of any supporting software. Until now, 5 types of automated stations have been developed and submitted for test operation at the Bohunice V-2 nuclear power plant. Virtually any personal computer can be attached to the network. The system can also be installed in conventional power plants as well as beyond the power generation field. (Z.M.)

  19. In sustainable way with nuclear energy

    Kopriva, J.; Svolik, S.; Placek, V.

    2009-01-01

    Company, which wants to be successful in an open market, must continuously improve its existing production capacities taking into account competitiveness - by improving safety and reliability, minimising the risk of damages and losses due to unplanned outages.. At the same time the company has to optimise operation, e.g. by shortening of the planned outages, decreasing emissions and waste, water and fuel consumption, automatisation as well as using the reserves of existing production equipment. Based on the last mentioned example the company Slovenske elektrarne is an excellent company, which after the shut down of unit 1 in the state-owned V1 Bohunice NPP, was able to deliver 150 MWe of new capacity to the grid in the period 2008- 2009 (or 180 MWe by 2010), and thus increase energy security in Slovakia. (authors)

  20. Selection of a new nuclear unit for Slovakia: possibilities and key technical issues

    Misak, J.

    2009-01-01

    Plans for construction of new nuclear unit at Jaslovske Bohunice brings forward the issue of selection of reactor design. This paper compares technical characteristics (safety and operational) of pressurized water reactors that are at present available in the market, such as AP 1000 (WEC), EPR (AREVA), AES 2006 (ASE), APWR 1700 (Mitsubishi) and APR 1400 (Korea Hydro and Nuclear). Selected parameters that require close attention in future negotiations with potential suppliers are discussed in detail. Compared are parameters as type of the reactor, reactor output power, quantified level of safety, compliance with national legislature and international safety requirements, operational flexibility in meeting requirements of the grid, using of verified technology, measures for coping with severe accidents, resistance against extreme external conditions etc. (authors)

  1. Introducing a European Partnership. First issue of 'European Nuclear Features'. A joint publication of atw, Nuclear Espana, Revue Generale Nucleare (2004)

    2004-01-01

    'European Nuclear Features' is a joint publication of the three specialized technical journals, Nuclear Espana (Spain), Revue Generale Nucleaire (France), and atw - International Journal for Nuclear Power (Germany), planned for six issues annually. ENF is to further greatly the international European exchange of information and news about energy and nuclear power. News items, comments, and scientific and technical contributions will cover important aspects of the field. The first issue of ENF contains contributions about these topics, among others: - European Nuclear Society and Foratom: Strengthening the Nuclear Network. - Report: EPR - the European Pressurized Water Reactor. - Finland: Starting Construction of the Fifth Nuclear Power Plant. - Czech Republic: Nuclear Power Report for 2003/2004. - The Decommissioning Project of the Bohunice-1 and -2 Units. - FRM-II: TUM Research Neutron Source Generates Its First Neutrons. (orig.)

  2. A potention of renewable energy sources in Slovakia in term of production of electricity

    Štefan Kuzevič

    2005-11-01

    Full Text Available Electro-energetics of Slovak Republic is in this time in state of re-structuralization consequent from responsibilities which SR has with integration to the EU and on the other hand with actual status of production capacities of fossil fuels using in heat power stations and heat stations also the utilization of nuclear energy in nuclear power stations Jaslovské Bohunice and Mochovce. Paradoxically slim representation in production capacities have renewable energy sources, while only one relevant one is utilization of water in small hydro power stations. According to fact, that to the year 2010, the share of renewable sources of energy using in comparing with electric energy has to achieve 21,7% (direction of EU 77/2001. It is necessary to evaluate possibilities of utilization and to specify potential of utilization from technical and economical aspect.

  3. Siemens tasks and activities during gradual upgrading

    Kuehne, B.

    2001-01-01

    The gradual upgrading of NPP V1 Bohunice constitutes the most extensive reconstruction project to be performed in an operational WWER plant to date. It constitutes a milestone in Siemens co-operation on projects for WWERs to date and is an encouraging example for the successful combination of western and eastern safety cultures. During the runtime of this project Siemens learnt very much about the 'complete function' as well as the details of this WWER plant type. In contrast the Slovakian partners really gained a much better understanding for the western approach to ensure safety, for the most modern safety technology, in particular for instrumentation and control, and last but not least or advanced project management. (author)

  4. Heat supply of the town of Trnava from EBO nuclear plant

    Kovarik, Z.

    4 variants of central heat supply from the V-2 Bohunice nuclear power plant were considered. Three included the supply of hot water while the fourth envisaged the supply of steam. The variants of hot water supply differed in the proportion of heat supply during load peak, the range being from 75% to 88% to 100%. The system suggested considers hot water with a maximum overpressure of 2.5 MPa and temperature of 150/70 degC, with possible temporary decrease to 130/70 degC. The estimated power of heat exchange stations is 240 MW at a temperature gradient of 150/70 degC and 180 MW at a temperature gradient 130/70 degC. The location, design and control of the heat supply system and the specifications of heat generation facilities are given. (J.P.)

  5. Economic assessment of nuclear power plant operation with regard to effective use of nuclear fuel

    Svec, P.; Raninec, S.; Mizov, J.

    1988-01-01

    The essential preconditions are discussed for the better utilization of fuel in nuclear power plants. The MORNAP program which models the operation of the reactor is used for assessing the consequences of various fuel utilization strategies on technical and economic parameters of WWER-440 nuclear power plant operation. Some results of model calculation are given for the third and fourth units of the Jaslovske Bohunice nuclear power plant. The calculations have served for the economic assessment of the transition of part of the nuclear fuel from a three-campaign to a four-campaign cycle. This transition reduces fuel costs by 1.7%. The implementation of this strategy on a larger scale is expected to save 7 to 9% of fuel costs. (Z.M.). 2 tabs., 7 refs

  6. Conditions for selection, training and placement of personnel

    Chrkavy, L.

    1983-01-01

    Methods applied in the choice of personnel include: the assessment of personnel files, references, interviews, examinations, long-term observation of the respective person. Investment intents go hand in hand with the concept of labour demands. The planned employment of personnel takes place from the very beginning of the construction of the power plant. At the Bohunice V-1 nuclear power plant 23 university graduates, 29 secondary school graduates and 64 graduates of vocational schools were employed every year. Social measures and complex care are being implemented. Personnel is being selected also on the basis of an assessment of their psychic qualities which are very important in view of the high personal and social responsibility of nuclear power plant personnel. The high technical standard of the equipment places high demands on the education level of all personnel, high demands on training, high remuneration and high level of allround care of personnel. (M.D.)

  7. Experience with modular steam generator production and application of new testing methods

    Olesovsky

    Experience is reviewed gained at the Trebic IBZKG plant with the production of modular steam generators. The plant started producing steam generators for the Jaslovske Bohunice nuclear power plant in 1965. In addition to the steam generator for the A-1, the plant also produced a loop for the Melekess power plant and a steam generator for the BOR-60 reactor. Operating experience gained so far allowed improving the quality of the BOR steam generator, especially in the tube-tube plate joint. A double tube plate was used and the welded joint shape was changed. As a result of high requirements on the quality of welded joints, the steam generator has successfully been in operation for more then 10,000 hours. The existing experience was utilized in designing a new steam generator named Nadya. Many design and technological requirements were presented concerning the Nadya generator and many new checking operations have been included in technology. (Kr)

  8. Meteorological safeguarding of nuclear power plant operation in Czechoslovakia

    Rak, J.; Skulec, S.

    1976-01-01

    A meteorological tower 200 m high has to be built for meteorological control of the operation of the A-1 nuclear power plant at Jaslovske Bohunice. This meteorological station will measure the physical properties of the lower layers of the atmosphere, carry out experimental verifications of the models of air pollution, investigate the effects of waste heat and waste water from the nuclear power plant on the microclimate, provide the theoretical processing of measured data with the aim of selecting the most favourable model for conditions prevailing in the Czechoslovak Socialist Republic, perform basic research of the physical properties of the ground and boundary layers of the atmosphere and the coordination of state-wide plans in the field of securing the operation of nuclear power plants with regard to meteorology. (Z.M.)

  9. SE and ENEL - One Year Together One Year after Privatization

    Anon

    2007-01-01

    In Bratislava, one year ago, exactly in April 28, the privatization deal of a 66% stake in Slovenske elektrarne (SE) was finally closed. The Slovak government and the Italian company ENEL signed final documents and ENEL thus definitely entered into SE. In May 2006, Miroslav Pikus, a former CEO, was replaced by Marco Arcelli, who, as a regional manager for Slovakia, had been preparing the entry of ENEL into SE since March 2005. Not only did he sometimes cook for us, in his 'kitchen' but also there were prepared 160 investment projects, e.g the improvement of nuclear safety and resistance of the Bohunice power plant, electricity sale through the so-called 'virtual power plant', ensuring a non-attended operation in hydro power plants, reconstruction and modernization of the Orava and Dobsina hydro power plants. (author)

  10. Experiences with mobile units for liquid raw management in slovak and czech nuclear power plants

    Rapant, T.; Tatransky, P.; Vasko, M.; Hlavacka, R.

    2015-01-01

    Text describes the experience from multiple projects of retrieval, pre-treatment and final treatment of liquid radioactive waste in Slovak and Czech NPPs during last 20 years. The purpose of these projects was to retrieve RAW (sludge, used resins, crystalline sediments, other types of liquid RAW) from operational tanks or technological systems, its pre-treatment and its solidification into 200 l or 60 l drums. Slovak and Czech NPPs are WWER 440 type (except Bohunice A1 NPP) where operational liquid RAW should be stored in large capacity tanks during the whole operational period. Volume of tanks placed in auxiliary buildings is from 460 to 550 m 3 , usually they are situated in rooms with limited access and minimal handling space. The liquid RAW management process is described. (authors)

  11. Some aspects of experimental investigation of the RPV material properties

    Lipka, J.; Hascik, J.; Groene, R.; Slugen, V.; Vitazek, K.; Hinca, R.; Toth, I.; Kupca, L.

    1996-01-01

    Moessbauer spectra (MS) and Electron-Positron Annihilation (EPA) spectra at room temperature have been measured on the samples from Reactor Pressure Vessel (RPV). Both types of measurements showed that the changes associated with the effects of neutron irradiation, as well as thermal treatment, can be detected by Moessbauer and Electron-Positron Annihilation spectroscopy. On base of a positive results achieved in MS and EPA measurements the complementary surveillance specimen program for the Reactor Pressure Vessel Materials Study of the third and fourth units NPP Jaslovske Bohunice has been prepared. The complementary surveillance specimen program has started in May 1995. The samples with proper design from basic and welded RPV materials were measured by MS and EPA before placing into the reactor. After neutron irradiation the samples become radioactive because of 59 Co content. To eliminate the influence of 60 Co gamma radiation on the EPA angular correlation and time spectra a three detectors spectrometer has been introduced. (author)

  12. Nuclear power plant diagnostic system

    Prokop, K.; Volavy, J.

    1982-01-01

    Basic information is presented on diagnostic systems used at nuclear power plants with PWR reactors. They include systems used at the Novovoronezh nuclear power plant in the USSR, at the Nord power plant in the GDR, the system developed at the Hungarian VEIKI institute, the system used at the V-1 nuclear power plant at Jaslovske Bohunice in Czechoslovakia and systems of the Rockwell International company used in US nuclear power plants. These diagnostic systems are basically founded on monitoring vibrations and noise, loose parts, pressure pulsations, neutron noise, coolant leaks and acoustic emissions. The Rockwell International system represents a complex unit whose advantage is the on-line evaluation of signals which gives certain instructions for the given situation directly to the operator. The other described systems process signals using similar methods. Digitized signals only serve off-line computer analyses. (Z.M.)

  13. Behaviour of Aluminosilicate Inorganic Matrix Sial During and After Solidification of Radioactive Sludge And Radioactive Spent Resins and Their Mixtures

    Lichvar, P.; Rozloznik, M.; Sekely, S.

    2013-01-01

    SIAL matrix is the product of inorganic compounds by polycondensation. The inorganic SIAL matrix was subject of study from the atomic level to the level of technological application. Infrared spectroscopy measurement and X-ray analysis confirmed that SIAL matrix is mostly formed by amorphous phase. This satisfies the required criteria for disposal of immobilized radioactive waste of appropriate properties into surface repository (Slovak and Czech Republic). First of all, leaching of radioactive nuclide Cs-137 and compressive strength of the final product were found. Various remotely operated devices have been designed, manufactured and successfully used for the radioactive sludge and sludge/resins mixture solidification at the Nuclear power plant (NPP) A-1, V-2 in Jaslovske Bohunice, at Mochovce NPP (Slovak Republic), at Dukovany NPP and at Temelin NPP (Czech Republic). The SIAL matrix was approved for waste package for sludge/resins mixture by the Slovak and Czech Nuclear Regulatory Authorities. (author)

  14. Support calculations for management of PRISE leakage accidents

    Matejovic, P; Vranka, L [Nuclear Power Plants Research Inst. Vuje, Trnava (Slovakia)

    1998-12-31

    Accidents involving primary-to-secondary leakage (PRISE) caused by rupture of one or a few tubes are well known design basis events in both, western and VVER NPPs. Operating experience and in-service inspections of VVER-440 units have demonstrated also the potential for large PRISE leaks in the case of the steam generator (SG) primary collector cover lift-up (Rovno NPP). Without performing any countermeasure for limitation of SG collector cover lift-up, a full opening results in PRISE leak with an equivalent diameter 107 mm. Although this accident was not considered in the original design, this event is usually analysed as DBA too. Different means are available for detection and mitigation of PRISE leakage in NPPs currently in operation (J.Bohunice V-1 and V-2) or under construction (Mochovce) in Slovakia. 8 refs.

  15. Seismic margin assessment and earthquake experience based methods for WWER-440/213 type NPPs

    Masopust, R.

    1996-01-01

    This report covers the review of the already completed studies, namely, safe shutdown system identification and classification for Bohunice NPP and the comparative study of standards and criteria. It contains a report on currently ongoing studies concerning seismic margin assessment and earthquake experience based methods in application for seismic evaluation and verification of structures and equipment components of the operating WWER-440/213 type NPPs. This is based on experiences obtained from Paks NPP. The work plan for the remaining period of Benchmark CRP and the new proposals are included. These are concerned with seismic evaluation of selected safety related mechanical equipment and pipes of Paks NPP, and the actual seismic issues of the Temelin WWER-1000 type NPP

  16. Determination of 90Sr by liquid scintillation spectrometry in samples of contaminated water

    Ometakova, J.; Dulanska, S.

    2009-01-01

    On a model sample we optimized conditions of SPE separation of 90 Sr on Empore Sr Rad Disk in term of use eluent reagent and its appropriate concentration. Also the possibility of multiple use of both sorbents Empore Sr Rad Disk and AnaLig Sr-01 was confirmed. Not even after 8 separations radiochemical yield fall below 87%. For separation of 90 Sr from real sample of percolating water of controlled area of Bohunice NPP three commercially available products were used: 3M Empore Strontium Rad Disk, sorbents AnaLig (with different grain size) and Sr-Resin. The aim of this work was to compare the selected products in term of strontium extracts, the time demandingness and the possibility of multiple use of sorbents. For separation of strontium were also used two classical methods, namely liquid extraction with tributyl phosphate and carbonate precipitation due to the exclusion of interferents. (author)

  17. Chapter 15. Attachments

    2001-01-01

    In this chapter used abbreviations and radiation safety of NPPs in Slovak Republic are presented. Results of monitoring of NPP Bohunice V-1 and V-2 as well as NPP Mochovce are presented. A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2000 is presented. The collective dose is one of the fundamental indicators to assess the level of nuclear safety and safety culture. This is the total dose of both external and internal exposure of the whole of the body measured with a personal dosimeter and a calculated internal exposure over a certain period of time. Measured doses to the utility personnel, the staff of supplier organisations and official working visits are included

  18. Behaviour of Aluminosilicate Inorganic Matrix Sial During and After Solidification of Radioactive Sludge And Radioactive Spent Resins and Their Mixtures

    Lichvar, P.; Rozloznik, M.; Sekely, S. [Amec Nuclear Slovakia, 919 31 Jaslovske Bohunice (Slovakia)

    2013-09-15

    SIAL matrix is the product of inorganic compounds by polycondensation. The inorganic SIAL matrix was subject of study from the atomic level to the level of technological application. Infrared spectroscopy measurement and X-ray analysis confirmed that SIAL matrix is mostly formed by amorphous phase. This satisfies the required criteria for disposal of immobilized radioactive waste of appropriate properties into surface repository (Slovak and Czech Republic). First of all, leaching of radioactive nuclide Cs-137 and compressive strength of the final product were found. Various remotely operated devices have been designed, manufactured and successfully used for the radioactive sludge and sludge/resins mixture solidification at the Nuclear power plant (NPP) A-1, V-2 in Jaslovske Bohunice, at Mochovce NPP (Slovak Republic), at Dukovany NPP and at Temelin NPP (Czech Republic). The SIAL matrix was approved for waste package for sludge/resins mixture by the Slovak and Czech Nuclear Regulatory Authorities. (author)

  19. Hermetic compartments leak-tightness enhancement

    Murani, J.

    2000-01-01

    In connection with the enhancement of the nuclear safety of the Jaslovske Bohunice V-1 NPP actions for the increase of the leak tightness are performed. The reconstruction has been done in the following directions: hermetic compartments leak tightness enhancement; air lock installation; installation of air lock in SP 4 vent system; integrated leakage rate test to hermetic compartments with leak detection. After 'major' leaks on the hermetic boundary components had been eliminated, since 1994 works on a higher qualitative level began. The essence of the works consists in the detection and identification of leaks in the structural component of the hermetic boundary during the planned refueling outages. The results of the Small Reconstruction and gradual enhancement of leak tightness are presented

  20. Results and discussion

    1998-01-01

    The author deals with the experimental study of sorption, desorption and vertical migration of radionuclides in Sr-85 and Cs-137 in selected soil samples from around of NPP Bohunice and NPP Mochovce and other localities of the Slovakia. The influence of different materials [concurrent ions (K + , Ca 2+ , NH 4 + , pH), organic matter (peat) and zeolite, humidity] on kinetic of sorption and desorption of strontium and cesium as well as distribution coefficient (K D ) and transfer coefficients in followed samples of soils were followed. Obtained adsorption isotherm are presented and discussed. Using the Tessiere's sequential extraction analysis a gross variability in binding of radionuclides on soils was found. The obtained results were processed with the correlation analysis and the compartment model

  1. What were we like in 2008

    Hroch, A.

    2009-01-01

    Slovenske elektrarne, a. s. (SE) entered the year 2008 with a determination to achieve the best possible profit from power production. During the process of production optimization were taken into account external conditions, which were mentioned in the last issue. The result is SE supply reaching 22 251 GWh. Very satisfactory for us is the fact that high fulfillments by nuclear power plants have exceeded the expectations. Bohunice V1 NPP up to 103%, Bohunice V2 NPP up to 104,5% and Mochovce NPP up to 102, 9%. Nonfulfillment of hydroelectric and thermal power plants is a result of objective reasons- as for thermal power plants due to market conditions and in case of hydroelectric power plants this has been a result of hydrological reasons. Just a few words to a crisis that appeared in January 2009. When we look back, we have to divide the issue into two periods (crises). The first one is an economic crisis the consequences of which were apparent already in December, where the providers of supporting services among industrial customers were unable to guarantee those services (the service is activated by reduction of consumption and since then there was no sale of their products, they cut off their production, i.e. power production, and as a consequence, no reserve for Ss remained.) Missing supporting services have been purchased by a transmission system provider on both daily and monthly basis. There was a demand for SRV, TRV30MIN, + TRV3MIN+, however, there were no extreme values. (author)

  2. Energy liberalization should not scare anyone

    Slova, K.; Marcan, P.

    2006-01-01

    In this interview, the Energy commissioner of the European Union, Andris Piebalgs, is aware of the fact that natural monopolies try to hinder market liberalization of the internal market. But he does not see an alternative to opening the market. The European directive clearly stipulates the tasks of the regulator as well as the fact that it has to be independent. The Commission also plans to increase the independence and competencies of the regulator. His some answers are following: the concerns interventions the Slovak cabinet has regarding the situation on the energy market. This issue is about the interests of the citizens as regards prices and the opportunity to create new jobs in the sector. From what I have heard prices in this sector increased dramatically and not all the increases were transparent. If suppliers want to increase their prices they have to be able to justify the increase. In Germany, some cases are already the subject of court cases. It is important that Slovakia keeps full control over the company. We, of course, support the government's aim to obtain full control over the company (Transpetrol). It is important that the state has 100-percent control over the company, not a 100-percent ownership. And whether the Slovak cabinet will achieve this alone or with partners depends on its decisions. But it certainly will need a partner that can get the oil into the pipelines. Europe will lack lack energy sources. Nuclear power stations in Germany are closing down and within two years Slovakia will close down Jaslovske Bohunice. The decommissioning of Jaslovske Bohunice will not result in Slovakia remaining in darkness. Although it will certainly change the supply and demand situation. But I believe that there will be investments in power plants. There are sufficient funds on the market. (authors)

  3. Financial groups charmed by energy sector

    Haluza, I.; Marcan, P.

    2006-01-01

    The Slovak power industry is no longer the domain of big state-controlled and international companies. Local financial groups that grew up on equity deals, revitalisation of industry, real estate and receivables business have developed an interest in the field as well. They are contemplating the possibility of investing a part of their gains into energy sources. They can see the gap that the closure of the V1 power plant in Jaslovske Bohunice will create in Slovakian's power capacity. Although the new owner of Slovenske elektrarne, Italian Enel, will attend to filling the gap, local market players also sense an opportunity. Apart from the closure of V1 there is also rising energy demand driven by growing industry and growing energy prices. What is more, the state supports renewable energy sources like wind and biomass though subsidies, tax allowances or higher purchase prices. According to standard economic formulas at least, increased competition should exert pressure on prices. However, renewable energy sources are more expensive then traditional ones and new gas or coal driven power plants will certainly not push prices down. The electricity produced by power plants in Jaslovske Bohunice, which is to be closed, is the cheapest we have. So nobody dares to predict with 100-percent certainty what energy prices will look like in two years. Investment director of private equity group Penta, Vladimir Brodnan, says that new investors are not entering the energy business because of guaranteed profit. Utility regulator URSO only sets fixed prices for distribution companies but, on the other hand, the draft amendment to the regulation act indicates that the government would like to change this status. In future the powers of the regulator should also cover the prices of electricity as a commodity. In addition, the possibility of the regulator being able to interfere with the liberalised market concerns investors. (authors)

  4. VUEZ. Annual report 2006

    2007-01-01

    A brief account of activities carried out by the Vyskumny ustav energetickych zariadeni, a.s. (VUEZ) in 2006 is presented. These activities are reported under the headings: (1) Introductory address by the Chairman of the Board of Directors; (2) Company profile; (3) Organisational structure; (4) Portfolio of products and services in 2006; (5) Quality management system; (6) Human resources; (7) Financial statements and auditor's report; (8) Auditor's certificate; (9) Basic and contact data. The year 2006 was a year of changes in the Slovak energy sector what, in a certain degree, became evident also in the related sphere of supplies. In the course of the year, Slovenske elektrarne a.s. Company was divided into two entities and its proprietary structure was changed. At the same time, the number of capital investment projects was reduced and the related procedure of procurement was changed. VUEZ, as a supplier to the energy sector, had to promptly respond to the changes. That was why in the first half of 2006, the organisational structure of VUEZ was modified. In the course of the year, also the structure of customers on the domestic market was partly changed. To stable partners such as Slovenske elektrarne (and its successors after the company splitting), another important partner was added - Vodohospodarska vystavba s.p. Bratislava. As to Slovenske elektrarne, our supplies were oriented mainly on nuclear reactor units in the Jaslovske Bohunice and Mochovce NPPs. At the end of the year, a joint convention was agreed and concluded on application of the results of the joint research at third parties. In the preparation for the decommissioning of the Jaslovske Bohunice V1 NPP, VUEZ continued its participation in on-going projects of an international consortium of companies. Similarly important were the customers such as CEZ a.s., Czech Republic (in particular its Dukovany NPP), and the Paks NPP (Hungary)

  5. Regulatory Aspect of Periodic Safety Review Performed in Nuclear Power Plants in the Slovak Republic

    Baszo, Z.

    2010-01-01

    The paper deals with the regulatory aspect of Nuclear Power Plant (NPP) Periodic Safety Review (PSR) as a part of license renewal process in the Slovak Republic. It summarizes the history of activities similar to PSR performed in the past for NPPs operated in the Slovak Republic. Furthermore, it describes both the requirements involved in the current Slovak legislation to be met by licensee in the Slovak Republic in this field and the procedures concerning the PSR as well. The objective and rules of PSR to be performed for NPPs in the Slovak Republic were derived from the internationally accepted International Atomic Energy Agency (IAEA) document and have been implemented into national legislation. PSR of two twin units located in Bohunice NPP and Mochovce NPP, respectively, has been initiated in the Slovak Republic based on evaluation of each area to be reviewed (safety factors) using recent methodology and practice. Other significant factors, such as ageing, modifications of NPP and the safe operation for a specified future period, have to be assessed in the frame of PSR. Report on performed PSR outlines the results of review for each area, the corrective plan, which considering mutual relations between assessed areas specifies the issues to be solved with the aim to eliminate shortcomings identified in the frame of PSR and to adopt safety improvements. The findings from PSR in the evaluated areas also serve as a source of information for updating of all documents to be attached to the written application of licensee for renewal of a nuclear power plant operating license. The presented procedure describes how the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) has reviewed the documents submitted during PSR. Based on results of submitted documents evaluation and licensee application for license renewal the license for next 10 years operation has been issued for Bohunice NPP. At present, similar procedure for Mochovce NPP unit 1 and 2 is underway.(author).

  6. Radiation monitoring network of the Slovak Hydrometeorological Institute

    Melicherova, T.

    2005-01-01

    In 2000 Centre of Partial monitoring system 'Radioactivity of environment' was established on Slovak Hydrometeorology Institute (SHMI). Radiation monitoring network is one part of Radiation monitoring network of the Slovak Republic. At present SHMI operates in its monitoring network 23 detectors GammaTracer fy Genitron, one mobile detector and one stan by detector. All active detectors are placed in the professional meteorological stations in the selected parts of Slovakia. First one of these detectors was installed in 1999 and they replaced former type of detector (FAG). Last two detectors were installed in 2002. Detector GammaTracer has range of measurement from 20 nSv/h to 10 Sv/h. The detectors are calibrated every 2 years in the Slovak Institute of Metrology in compliance with the calibration plan. SHMI operates 4 aerosol monitors in Hurbanovo, Lucenec, Stropkov and Liesek. Filter 8 from these monitors are analysed in the Institute of Public Health (Cs-137, Be-7). On the base of bilateral agreement between the Austrian Ministry of Agriculture, Forestry, Environment and Water-Management and the Slovak Ministry of Environment Austrian side gave into the ownership of the Slovak side an automatic aerosol monitor AMS-02 including container and weather station. This monitor was installed in meteorological station Jaslovske Bohunice on 4-th October 2001. The Slovak Ministry of Environment provides the Austrian Ministry of Agriculture, Forestry, Environment and Water-Management with the readings of this monitor, free of charge, for at least 3 years and vice versa, the Austrian side gives the readings of the Austrian aerosol monitors to the Slovak Ministry of Environment free of charge. At present national monitoring center in Bratislava-Koliba is connected via ISDN line with Jaslovske Bohunice and Austrian center providing the data exchange. Radiation data (dose rate in the unit nSv/h) are collected via the Institute network to the MSS (message switch system) in the

  7. Radiological characterisation on V1 NPP technological systems and buildings - Contamination

    Hanzel, Richard; Rapant, Tibor; Svitek, Jaroslav

    2012-01-01

    Since 2001, the preparation of V1 NPP practical decommissioning has been supported and partly financed by the Bohunice International Decommissioning Support Fund, under the administration of the European bank for Reconstruction and development. AMEC Nuclear Slovakia, together with partners STM Power and EWN GmbH, performed BIDSF B.4 project - Decommissioning database development. The main purpose of the B6.4 project was to develop a comprehensive physical and radiological inventory database to support RAW management development of the decommissioning studies and decommissioning project of Bohunice V1 NPP. AMEC Nuclear Slovakia was responsible mainly for DDB design, planning documents and physical and radiological characterization including sampling and analyses of the plant controlled area. The objective of V1 NPP radiological characterization was summarisation of sampling and analyses results, description of methodology used for radiological characterization and determination of the V1 NPP radiological inventory. Results of the characterization survey included the identification and distribution of contamination in buildings, structures, and other site facilities or other impacted media. The characterization survey clearly identified those portions of the site that have been affected by site activities and are contaminated. The survey also identified the portions of the site that have not been affected by these activities and can be marked as 'not impacted'. Radiological data have been presented also on the basis of index RAI level, where 5 radiological classes have been defined. On the basis of sampling and analyses results following radiological parameters have been assigned to all impacted components and civil structures included in DDB: dose rate in contact, dose rate in distance 1 m, external surface contamination, internal surface contamination and volume/mass contamination. Each room in controlled area has been described by following radiological parameters

  8. Radiological characterisation of V1 NPP technological systems and buildings - Activation

    Kristofova, Kristina; Rapant, Tibor; Svitek, Jaroslav

    2012-01-01

    V1 NPP at Jaslovske Bohunice site has been finally shutdown after 28 years of successful operation in 2006 (Unit 1) and 2008 (Unit 2). At present, both units are finally shutdown and since July 2011 under decommissioning license. The preparation of V1 NPP decommissioning has been supported and partly financed by the Bohunice International Decommissioning Support Fund (BIDSF), under the administration of the European Bank for Reconstruction and Development. From 06/2008 to 12/2011 AMEC Nuclear Slovakia, together with partners STM Power and EWN GmbH, carried out BIDSF B6.4 project - Decommissioning database development (DDB). The main purpose of the B6.4 project was to develop a physical and radiological inventory database to support V1 NPP decommissioning process planning and performance. One of the specific deliverable tasks within the B6.4 project was deliverable D12 - Characterization of activated equipment and civil structures based on measurement, sampling and analyses performed on the samples. The scope of deliverable services within D12 task consisted of: 1. Categorization of activated components ; 2. Development of single working programs for their radiological monitoring and sampling ; 3. Preparation of sampling device and revision of all handling equipment; 4. Dose rate monitoring and sampling of: - Civil structures from reactors shaft on both units ; - Components placed in HLW storage, (so called 'Mogilnik') - connection rods, absorbers ; of control rod assemblies and neutron flux measurement channels ; - Reactor pressure vessel and shielding assemblies at both units of V1 NPP, reactor; internals from Unit 2 of V1 NPP; 5. Analysis of samples ; 6. Determination of radiological inventory ; 7. Import of radiological data for activated components into DDB. During sampling, mainly remotely controlled sampling device and radiation resistant camera with LED lightening for visual checking of all performed activities was used. In total, 125 samples have been taken

  9. Bituminization of low- and intermediate-level radioactive concentrates

    Breza, M.; Krejci, F.; Timulak, J.; Tibensky, L.

    1985-01-01

    The results and experiences are summed up from the research and development of the technology of bituminization of low- and intermediate-level radioactive concentrates generated in the operation of nuclear power plants with WWER-440 reactors. The experiments took place on a pilot plant bituminization line with various model solutions at an evaporator capacity of 70, 100 and 140 litres per hour. The composition of the solutions changed in dependence on the knowledge of the composition of actual concentrates in the V-1 nuclear power plant at Jaslovske Bohunice. The following factors were studied in the concentrate: the effect of its pH, its borate content and content of metal carbonates, the content of organic acid salts, the content of detergents, etc., on the process of bituminization. Physico-chemical conditions are described under which the operation of the evaporator was fail-safe and filling of the bituminization product with salts homogeneous. A low water content of up to 1% was achieved. The properties of the bituminization product were negatively affected by a high level of heavy metal oxides, surfactants, oxalates and citrates. In order to improve the properties of the product it will be necessary to replace bitumen emulsion Silembit-60 used as reinforcement matrix, by a different type of bitumen. (Z.M.)

  10. Restructuring of the Slovenske elektrarne, p.l.s. and their influence on economy of the Slovak Republic

    Horvat, J.

    2003-01-01

    In this paper author deals with privatization of Slovenske elektrarne (SE), a.s. Bratislava and their influence on economy of the Slovak Republic. Country made the first step in privatization in the case of SE at the beginning of 90's by transformation of state enterprise to a. s. with state dominant position (95.8% of stocks was held by Fond narodneho majetku (National Property Fund), the rest was divided between SPP, a.s. and Restitucny investicny fond (Restitution capital fund). In the next phase two newly founded separate a.s. TEKO, a.s. (Teplaren Kosice) and SEPS, a.s. (Slovenska elektrizacna prenosova sustava) were set aside from a.s. Government adopted two basic variants of sale of SE, a.s. stocks by resolution N. 700/2002. Possible variants of SE privatisation are discussed. Energy position of Slovak Republic in European context is relatively favourable in present time because production capacities exceed domestic consumption and part of energy (up to 600 MWh) is exported. Future of thermal power plants Novaky and Vojany is interrogative because of tightened ecological norms, besides Slovak Republic undertook to lay up both blocks of Bohunice NPP V1. Forecasts show that Slovak Republic will stop to be self-sufficient in electric power production about 2010. (Author)

  11. Clean-up levels for recovery of a 137Cs contaminated site in the Slovak Republic

    Slavik, O.; Moravek, J.

    2003-01-01

    The 19 km long banks of the Bohunice NPP waste water recipient (Manivier canal (0.3 m 3 /s) and Dudvah River (0.8 m 3 /s)) has been identified as contaminated by 137 Cs as a result of two accidents on the CO 2 cooled and heavy water moderated NPP-A1 unit in 1976 and 1977. Until 1992, NPP waste water had been derived through a 5 km-long canal to the Dudvah River (Q a 1.8 m 3 /s) conducting with the Vah River (150 m 3 /s) after 13 km downstream at 90 km from Vah's mouth into the Danube River. Between 1976 and 1978, when both accidents happened, construction of a flood control project on Dudvah River had just been being implemented in the length of 8 km upstream of its mouth. In the next upstream part of the River with about 5 km long river section, affected by NPP, the flood control conditions are insufficient and has, hitherto, caused permanent concern of the public. In this paper authors deals with the radiological characterization of the contaminated banks, re-consideration of the restoration project, criteria dose assessments and cleanup level developments, as well as present conditions for implementation of planned bank restoration

  12. Measuring techniques for the characterisation of 137Cs contaminated river banks, Slovakia

    Slavik, O.; Moravek, J.

    2000-01-01

    In 1990, 137 Cs contaminated areas were discovered along 19 km of the banks of the rivers receiving discharged waste waters from the Bohunice NPP. The contamination was the result of uncontrolled releases of drainage water from the radioactive waste treatment unit and two accidents on the CO 2 cooled and heavy water moderated NPP-A1 unit in 1976 and 1977. In total, more than 67.000 m 2 of bank surfaces (the lower and middle parts of their slopes) have been found to be contaminated with 137 Cs at levels exceeding 1 kBq/kg of soil. This paper describes the planning for restoration of these river banks with emphasis on site characterization techniques used for these purposes. The general strategy and application of monitoring techniques for the purposes of characterisation of contaminated river banks is the main topic of the work performed in the context of the IAEA CRP on 'Site Characterisation Techniques for Environmental Restoration'. First results in developing new and more sophisticated measuring techniques, needed for the characterization of discontinuous and spot-contamination found on parts of the banks are given. The technique described is based on a dose rate measurement approach, using ratio of two detector readings at two different distances above ground and Monte-Carlo simulations of the plastic scintillation detector responses. The method will also be useful, for the final, post-remediation survey of residual spots of 137 Cs contamination. (author)

  13. Long-term investigation of biosphere contamination by tritium

    Trnovec, T.; Kollar, J.; Tatara, M.; Chorvat, D.

    1974-03-01

    An apparatus was designed and built for isotope enrichment by electrolysis of water samples (taken in several localities in the vicinity of the Jaslovske Bohunice nuclear power plant) and a method was elaborated of measuring tritium using liquid scintillators, serving the determination of natural tritium concentrations. Operating experience showed that the degree of enrichment may easily be controlled and that the reproducibility of the enrichment coefficient value is conditional on the skill of personnel handling the apparatus. The apparatus constraints include a limited capacity of isotope enrichment (given by the number of electrolytic columns), demands on time, and sensitivity to secondary contamination. In addition to isotope enrichment of samples prior to measurement, also the feasibility of direct determination of natural tritium concentration without previous enrichment was tested. Tests were carried out of commercial products by Packard, INSTA-GEL and MONOPHASE-40. It was verified that the above method may be used in direct measuring tritium levels of several hundred TU. The preparation of a representative background sample was found to be the main problem involved in the type of determination described. The detection limit was mainly determined by the measurement statistics. (B.S.)

  14. Rapid nuclear reaction

    Marcan, P.; Beer, G.

    2008-01-01

    Whereas the completion of blocks 3 and 4 in Mochovce were subject to some discussion, the building of a new unit at Jaslovske Bohunice has remained unnoticed. Not even environmentalists objected. And so far the plans to build a new power plant seem to have been approved without any major discussion about whether Slovakia really needs or does not need a new nuclear power unit. Political statements about a possible future shortage of electricity were enough. The plans of private companies to build their own power plants or the possibility of decreasing the use of energy by savings were disregarded. But a clear answer to the question whether this new power unit will generate electricity for export to other countries has not yet been given. But by the end of this year the government wants to decide whether the new power plant which will cost an estimated 100 billion Slovak crowns (3.3 billions EUR) will be built from public funds in tandem with a private investor or fully financed by private capital. The name of the private investor should become known by the end of this year. (authors)

  15. Assessing radioactive concentrates and waste vapor condensate in solidifying radioactive wastes by bituminization

    Tibensky, L.; Krejci, F.; Breza, M.; Timulak, J.; Hladky, E.

    1986-01-01

    A brief overview is presented of chemical and radiochemical methods used in the world for the analysis of the concentrate of liquid radioactive wastes from nuclear power plants destined for bituminization. Most methods are also suitable for an analysis of the condensate of waste vapors produced in bituminization. The methods of analysis of the radioactive concentrate from the V-1 nuclear power plant in Jaslovske Bohunice and of the waste vapors condensate were developed and tested in practice. Gross gamma activity was measured using a well-type Na(Tl) scintillation detector, the content of radionuclides was determined using semiconductor Ge(Li) spectrometry. The concentration of boric acid in the concentrate was determined by titration with mannite; in the condensate, using spectrophotometry with curcumine. The content of nitrates in both the concentrate and the condensate was determined spectrophotometrically using salicylic acid, the content of nitrites was determined by spectrophotometry using sulfanilic acid and α-naphthylamine. Carbonates and chlorides were determined by titration, sodium and potassium by flame photometry. The content of organic acids was measured by gravimetry of extracted methyl esters, the content of surfactants by spectrophotometry. Infrared spectrophotometry was used in determining hydrocarbons in the waste vapor condensate. The measured value range and the measurement errors are shown for each method. (A.K.)

  16. Metal stents insertion in the treatment of the patients with benign oesophageal strictures

    Valek, V.; Benda, K.; Hrobar, P.; Mrazova, J.; Prasek, J.; Vomela, J.; Muenzova, H.; Hep, A.; Stefl, M.

    1996-01-01

    Between October 1993 and June 1995 the authors inserted in the Department of Radiology in University Hospital Bohunice in 16 of their patients with benign stenosis of the oesophagus an expandable metals stent. the aetiology of the stenosis was long-term reflux oesophagitis (6x), postoperative benign stenosis in anastomosis (3x), corrosive structure (2x), epidermolysis bulosa oesophagi (2x) and post-radiation structure (1x). In two patients the aetiology of the stenosis was unknown. All the patients suffered at the the of the stent insertion from marked dysphagia (stage 3 and/or 4). The indication for oesophageal stent implantation was always carefully considered by an interdisciplinary indication committee. Before the stent insertion all the stenoses have been repeatedly unsuccessfully dilated with balloon dilatation catheter. In total, 25 stents were used. In seven patients were inserted more as one stent. The intervention itself was preceded by a double contrast X-ray examination of oesophagus, oesophagoscopy with biopsy to verify the stricture aetiology, computed tomography and endosonography. No complications associated with the intervention have been encountered and stent insertions have always been well tolerated. (authors). 1 tab., 3 figs., 9 refs

  17. RODOS System in the Slovak Republic - its Implementation and Adaptation

    Duranova, T.; Bohun, L; Metke, E.; Janko, K.

    2003-01-01

    With support of the European Commission's (EC) ECHO programme 'Implementation of the RODOS Decision Support System for Off-Site Emergency Preparation and response in the Emergency centres in Poland and the Slovak Republic', RODOS system version 3.13 was implemented in the Slovak Republic with main objective to accelerate the implementation of the system within national emergency preparedness arrangements. Within the ECHO project, the National Centre of RODOS was established at the Nuclear Regulatory Authority of the Slovak Republic (NRA SR). VUJE was established as technical support organization and interactive user. As a data supplier and passive user were established the Slovak Centre for Radiation Monitoring, Slovak Hydro-Meteorological Institute (SHMI), Jaslovske Bohunice and Mochovce NPP's. As RODOS could become a standard tool for emergency preparedness in the European Union and CEE region lessons learned within projects mentioned in the paper were valuable contribution to other similar international and national projects. Effective working arrangements and links have been established between some institutes having competence in various aspects of emergency preparedness and response in about 20 European countries, with Forschungszentrum Karlsruhe as main responsible institute for system development and DSSNET project co-ordination. This network contributes to the more cost-effective use of resources for the further improvement of decision support for nuclear emergencies. More importantly, it will enhance trust and confidence between people, which is essential for responding effectively and coherently to any future nuclear accident that may have implications on a European scale. (authors)

  18. Scaling model for prediction of radionuclide activity in cooling water using a regression triplet technique

    Silvia Dulanska; Lubomir Matel; Milan Meloun

    2010-01-01

    The decommissioning of the nuclear power plant (NPP) A1 Jaslovske Bohunice (Slovakia) is a complicated set of problems that is highly demanding both technically and financially. The basic goal of the decommissioning process is the total elimination of radioactive materials from the nuclear power plant area, and radwaste treatment to a form suitable for its safe disposal. The initial conditions of decommissioning also include elimination of the operational events, preparation and transport of the fuel from the plant territory, radiochemical and physical-chemical characterization of the radioactive wastes. One of the problems was and still is the processing of the liquid radioactive wastes. Such media is also the cooling water of the long-term storage of spent fuel. A suitable scaling model for predicting the activity of hard-to-detect radionuclides 239,240 Pu, 90 Sr and summary beta in cooling water using a regression triplet technique has been built using the regression triplet analysis and regression diagnostics. (author)

  19. Mochovce NPP safety measures evaluation from point of view of operational safety enhancement

    Cillik, I.; Vrtik, L.

    2000-01-01

    Mochovce NPP consists of four reactor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present first unit operated and the second one under the construction finishing. As these units represent second generation of WWER reactor design, the additional safety measures (SM) were implemented to enhance operational and nuclear safety according to the recommendations of performed international audits and operational experience based on exploitation of other similar units (as Dukovany and J. Bohunice NPPs). These requirements result into a number of SMs grouped according to their purpose to reach recent international requirements on nuclear and operational safety. The paper presents the bases used for safety measures establishing including their grouping into the comprehensive tasks covering different areas of safety goals as well as structural organization of a project management of including participating companies and work performance. More, results are given regarding contribution of selected SMs to the total core damage frequency decreasing. (author)

  20. Modernized accurate methods for processing of in-core measurement signals in WWER reactors

    Polak, T.

    1996-01-01

    Utilization of the new accurate WIMS-KAERI library (WIMKAL-88) to generate the following characteristics for Rhodium SPND: Sensitivity depletion law by high (approx= 75%) burnup of emitter; influence of burnup-history on depletion law course; influence of neutron spectrum change on Rh-SPND sensitivity caused by change of fuel enrichment, fuel burnup, moderator temperature, concentration of boracid, central pin power rate and concentration of Xe 135 ; generating and experimental testing of Rh-SPND signal to linear pin power rate and signal to neutron flux conversion factors. Rh-SPND instrumentation optimization (reduction) related to safety and operational aspects as needed for 3D power surveillance in WWER-1000 reactors. Analysis of SPND reduction from 64x7 to 46x7 by method of Shannon information entropy optimization. Influence of reduction on accuracy of 3D power distribution reconstruction. Physical methods of 3D power distribution unfolding in new modernized on-line I and C system in NPP J. Bohunice with in-core measurements according to 210 thermocouples and 36x7 Rh-SPNDs. Program system TOPRE under QNX operating system network in FORTRAN 77, neutronic background calculations by macrocode MOBY-DICK. (author). 10 refs, 6 figs, 7 tabs

  1. Neutron flux control systems validation

    Hascik, R.

    2003-01-01

    In nuclear installations main requirement is to obtain corresponding nuclear safety in all operation conditions. From the nuclear safety point of view is commissioning and start-up after reactor refuelling appropriate period for safety systems verification. In this paper, methodology, performance and results of neutron flux measurements systems validation is presented. Standard neutron flux measuring chains incorporated into the reactor protection and control system are used. Standard neutron flux measuring chain contains detector, preamplifier, wiring to data acquisition unit, data acquisition unit, wiring to display at control room and display at control room. During reactor outage only data acquisition unit and wiring and displaying at reactor control room is verified. It is impossible to verify detector, preamplifier and wiring to data acquisition recording unit during reactor refuelling according to low power. Adjustment and accurate functionality of these chains is confirmed by start-up rate (SUR) measurement during start-up tests after refuelling of the reactors. This measurement has direct impact to nuclear safety and increase operational nuclear safety level. Briefly description of each measuring system is given. Results are illustrated on measurements performed at Bohunice NPP during reactor start-up tests. Main failures and their elimination are described (Authors)

  2. Investigation of internal contamination by tritium in A-1 nuclear power plant personnel in 1974

    Ondris, D.; Herchl, M.; Homolova, E.

    1977-01-01

    The results are presented of the 1974 personnel monitoring of the Bohunice A-1 nuclear power plant staff for internal contamination with tritium. Totally, 650 urine samples taken from 103 workers were analyzed using the recommended ICRP procedure. In routine examinations, the highest dose equivalent value of tritium incorporated within two weeks did not exceed 10 mrem, i.e., the maximum annual dose equivalent did not exceed 260 mrem. 8.5 μCi tritium per 1 litre urine was considered to be an alarm value. In a selected group of 21 high-risk persons analyses were conducted before and after each operation associated with tritium hazards. The limit dose was set to 5.8 μCi.l -1 , i.e., the tritium concentration equivalent to 10% of the maximum permissible annual intake. In 18 workers where tritium risk was of a more serious nature the biological half-life was followed up, with the average biological half-life being 8.5 days, with 5 days for the minimum and 12 days for the maximum values. The results show that in 1974 the tritium burden did not exceed 1/10 of the maximum permissible dose for any of the A-1 nuclear power plant workers. (L.O.)

  3. Safety of nuclear power plants in Slovak Republic in the context of integration into the European Union

    Pillar, V.

    2001-01-01

    A review of the construction and operation of nuclear power plants in Slovak Republic which belong within Slovenske Elektrarne is made. Since 1993 with the applying of the Least Cost Planning Methods and Financial Feasibility Analysis the optimal variant, considering construction completion of the two units at Mochovce NPP, has been adopted and a project for safety enhancement has been implemented. Some changes have been made in siting project in order to meet the seismic requirements, following by change of the control system design and supplier. The most important result of the safety enhancement program, important not only for NPP Mochovce, but also for all NPPs of WWER 440/213 type, is the fact, that operability of containment with passive bubbler-condenser system for pressure suppression and its acceptability from safety point of view, has been fully confirmed. Results of safety enhancement program have been re-evaluated not only by International Atomic Energy Agency, but also by other international authorities and professional organisations with positive result. Especially significant is the conclusion of RISKAUDIT, which has carried out repeated evaluation of safety level of NPP Mochovce based on PHARE project and which is accepted by European Commission. A similar approach for enhancing the safety has been applied for the NPP V-1 units at Jaslovske Bohunice

  4. Geological aspects of radioactive waste disposal

    Kobera, P.

    1985-01-01

    Geological formations suitable for burying various types of radioactive wastes are characterized applying criteria for the evaluation and selection of geological formations for building disposal sites for radioactive wastes issued in IAEA technical recommendations. They are surface disposal sites, disposal sites in medium depths and deep disposal sites. Attention is focused on geological formations usable for injecting self-hardening mixtures into cracks prepared by hydraulic decomposition and for injecting liquid radioactive wastes into permeable rocks. Briefly outlined are current trends of the disposal of radioactive wastes in Czechoslovakia and the possibilities are assessed from the geological point of view of building disposal sites for radioactive wastes on the sites of Czechoslovak nuclear power plants at Jaslovske Bohunice, Mochovce, Dukovany, Temelin, Holice (eastern Bohemia), Blahoutovice (northern Moravia) and Zehna (eastern Slovakia). It is stated that in order to design an optimal method of the burial of radioactive waste it will be necessary to improve knowledge of geological conditions in the potential disposal sites at the said nuclear plants. There is usually no detailed knowledge of geological and hydrological conditions at greater depths than 100 m. (Z.M.)

  5. Replacement of nickel sealing rings by expanded graphite sealing rings -upgrading of SG primary collector flange connection

    Cikryt, F.; Bednarek, L.; Kusyn, L. [Vitkovice, Ostrava (Switzerland)

    1997-12-31

    One of the most loaded parts of a steam generator of VVER 440 MW type are the bolts and thread holes of the primary collector cover sealing set. The strength calculations and tensometric measurings performed during operation proved the high degree of a load on the bolts. The conditions of the stress limitation are not met in some cases according to the pertinent standards. The untightnesses at nickel rings occurred during putting the units of Jaslovske Bohunice and Dukovany nuclear power stations into operation. With regard to improve the reliability, the producer has taken measures to improve the quality of the rings and users have introduced more strict regulations for bolts tightening. Due to these measures the high reliability of the set has been obtained from point of view of the tightness, but substantial reduction of bolts and holes threads loading have not been obtained. Several years operation experience proved relatively low service of bolts, damage of thread holes and sealing grooves. As the degree of mechanical load is one of the vital parameters influencing the damage of sealing set, in 1996 we started with the works aimed at a possibility of nickel sealing rings replacement for a more modern type of sealing which assure the higher reliability and service life of the individual part of sealing set under the reduced load.

  6. Application of routine methods for the inspector fuel burn-up determination and identification of displacement of spent fuel elements by dummy elements

    Rohar, S.

    1979-08-01

    14 irradiated assemblies were analyzed using nondestructive high resolution gamma spectrometry (HRGS). Measured and calculated (on the basis of calorimetric data) axial burnup profiles and average burnup values were compared. The measurements of spent fuel were performed in the Bohunice A-1 dry hot cell by using a proper collimating system and the standard Agency equipment, consisting of PGT intrinsic Ge detectors and Silena MCA with 1024 channels. The method of 134 Cs/ 137 Cs fission product activity ratio was used for burnup determination. It was found that the burnup values for 14 measured assemblies determined by HRGS were systematically lower than the calculated values with about 4-5%. The difference between the nondestructively determined burnup value of the 2N0053 assembly (average over 11 measured points) and destructively determined burnup (average over 19 measured points) was less than 2%. Passive neutron measurements of the irradiated assembly showed that the neutron counting rate was high enough for practical use and that the neutron and gamma profiles were similar and close to the burnup profile. Some calculations of gamma ray activity angular distribution were made for different numbers of dummy elements inside the irradiated assemblies. The results show that, by using gamma spectrometry transversal method, it is possible to find a significant number of dummy elements in different types of assemblies

  7. Radiation Load of Children by Chest Radiodiagnostic Measurements

    Nikodemova, D.; Vladar, M.; Ranogajec-Komor, M.; Horvathova, M.

    1998-01-01

    Radiodiagnostic examinations of children present particular importance from the radiation hygiene point of view. The estimation of the radiation load of pediatric patient is not easy, because of the lack of information about organ weighting factors for various ages of patients, as well as due to the differences in applied X-ray examination parameters. In the district of Slovak Republic, in which also the working Nuclear Power Plant Jaslovske Bohunice is included, efforts were done to estimate the radiation load of children to 15 years by chest radiodiagnostic examinations. The data of entrance surface doses were collected using measurements with TLD for 100 patients divided in 5 age categories at six radiodiagnostic departments. The calculations of the total absorbed dose were performed using the measured ESD values (entrance surface dose in mGy) integrated over the X-ray beam area, the conversion factors between the imparted energy and the dose-area product and the known irradiation parameters (kV, HVL, mass, etc.). The analysis of the obtained absorbed doses (E a ) as a function of age for chest PA radiodiagnostic examinations has shown, that the investigated Slovak radiodiagnostic centres use rather lower voltage techniques and the entrance surface doses are much higher than the proposed value of European Communities. (author)

  8. Training of personnel

    1997-01-01

    Selected staffs (in the area of NPPs) are examined by the State Examining Committee established by Nuclear Regulatory Authority of the Slovak Republic (NRA SR's) chairman. The committee consists of representatives of NRA SR , Bohunice NPPs, Mochovce NPP, Research Institute of Nuclear Energy and experts from the Faculty of Electrical Engineering and Information Technology of the Slovak Technical University. The review of selected personnel of NPP V-1, V-2 and Mochovce NPP which passed exams in 1996 is given. NRA SR paid attention to the upgrading training process of individual categories of staff for V-1, V-2 and Mochovce NPPs, simulator training and training with computerized simulation system according to the United criteria of nuclear installation personnel training that started in 1992. During the year, an inspection was performed focused on examination of technical equipment of the simulator of Mochovce NPP, professional eligibility and overall preparation of simulator training including simulator software. Throughout the year launching works continued at the simulator with the deadline of commissioning to trial use operation in the first half of 1997

  9. Standard model of WWER-440 fuel rod for Transuranus and its application for RELAP5 hot channel validation

    Hatala, B.; Cvan, M.

    2001-01-01

    Within the PECO European Commission project of 'Extension of the validation matrix of the TRANSURANUS code' is developed a generic model of WWER-440 fuel rod. The model is intended to be applied for both realistic and licensing, conservative analysis. For such an application the TRANSURANUS code would be complementary tool to generally used system codes, e.g. RELAP5, providing realistic, more detailed insight into processes and safety criteria, relevant to the fuel rod. The paper presents general description of the model for TRANSURANUS code, brief discussion of approaches used in TRANSURANUS and RELAP5 code safety analysis, accompanied with information about RELAP5 model (whole scope unit model, used for licensing analysis). The existing model for RELAP5 code for WWER-440/V-213 Bohunice V2 unit is checked and modified in hot channel part to allow transparent comparison with the TRANSURANUS code. The results from comparison calculations of the both codes are presented for fresh fuel and quasi steady state scenario and are in good agreement, almost identical. These results might be used as a basis for transient analysis

  10. Statistical analysis of the vibration loading of the reactor internals and fuel assemblies of reactor units type WWER-440 from deferent projects

    Ovcharov, O.; Pavelko, V.; Usanov, A.; Arkadov, G.; Dolgov, A.; Molchanov, V.; Anikeev, J.; Pljush, A.

    2006-01-01

    In this paper the following items have been presented: 1) Vibration noise instrument channels; 2) Vibration loading characteristics of control assemblies, internals and design peculiarities of internals of WWER-440 deferent projects; 3) Coolant flow rate through the reactor, reactor core, fuel assemblies and control assemblies for different projects WWER-440 and 4) Noise measurements of coolant speed per channel. The change of auto power spectrum density of absolute displacement detector signal for the last 12 years of SUS monitoring of the Kola NPP unit 2; the coherence functions groups between two SPND of the same level for the Kola NPP unit 1; the measured coolant flow rate at Paks NPP and the auto power spectrum density group of SPND signals from 11 neutron measuring channels of the Kola NPP unit 1 are given. The main factors of vibration loading of internals and fuel assemblies for Kola NPP units 1-4, Bohunice NPP units 1 and 2 and Novovoronezh NPP units 3 and 4 are also discussed

  11. Vessel annealing. Will it become a routine procedure?

    Davies, M.

    1995-01-01

    The effect of neutron radiation on the reactor pressure vessel and the influence of annealing performed to eliminate this effect are explained. Some practical examples are given. A simple heat treatment at 450 degC for 168 h is sufficient to eliminate a major fraction of the radiation effect in the displacement of the transition temperature from the brittle state to the tough state. Some observations indicate that at this temperature, excessive energy recovery takes place at the upper toughness limit in the Charpy diagram. The annealing furnace manufactured by the SKODA company is described. The furnace consists of heating elements in 13 zones and 5 heating sections. The maximum power of each element is 75 kW, the total power of the furnace is 975 kW. The annealing procedure and its results are briefly outlined for the reactor pressure vessel at unit 2 of the Jaslovske Bohunice NPP. Reactor pressure vessel annealing is proposed for the Marble Hill NPP which has been shut down. Preparatory activities for annealing are also under way at the Loviisa NPP. (J.B.)

  12. Czech interim spent fuel storage facility: operation experience, inspections and future plans

    Fajman, V.; Bartak, L.; Coufal, J.; Brzobohaty, K.; Kuba, S.

    1999-01-01

    The paper describes the situation in the spent fuel management in the Czech Republic. The interim Spent Fuel Storage Facility (ISFSF) at Dukovany, which was commissioned in January 1997 and is using dual transport and storage CASTOR - 440/84 casks, is briefly described. The authors deal with their experience in operating and inspecting the ISFSF Dukovany. The structure of the basic safety document 'Limits and Conditions of Normal Operation' is also mentioned, including the experience of the performance. The inspection activities focused on permanent checking of the leak tightness of the CASTOR 440/84 casks, the maximum cask temperature and inspections monitoring both the neutron and gamma dose rate as well as the surface contamination. The results of the inspections are mentioned in the presentation as well. The operator's experience with re-opening partly loaded and already dried CASTOR-440/84 cask, after its transport from NPP Jaslovske Bohunice to the NPP Dukovany is also described. The paper introduces briefly the concept of future spent fuel storage both from the NPP Dukovany and the NPP Temelin, as prepared by the CEZ. The preparatory work for the Central Interim Spent Nuclear Fuel Storage Facility (CISFSF) in the Czech Republic and the information concerning the planned storage technology for this facility is discussed in the paper as well. The authors describe the site selection process and the preparatory steps concerning new spent fuel facility construction including the Environmental Impact Assessment studies. (author)

  13. Approach to the safety culture in the Slovak Republic

    Kuchta, L.; Sladek, V.

    2002-01-01

    The Nuclear Regulatory Authority of the Slovak Republic was established on January 1st, 1993, after division of former Czech and Slovak Federation Republic to two independent states - Czech Republic and Slovak Republic. As there were inherited four units on the site Jaslovske Bohunice and Interim Spent Fuel Storage on the same site under operation and four units under construction on site Mochovce it was necessary to keep on regulatory activities from very beginning of regulatory authority existence. The new regulator has been all time co-operating closely with IAEA and countries with developed nuclear power to cover all nuclear safety related areas including the safety culture. It is, however, to be said, that the issue of safety culture begun to be an object of considerations of Czechoslovak NPPs as early as in 1986 after issue of IAEA INSAG 1. Since that time the NPPs try to enforce the safety culture principles as a part of nuclear safety into their daily work in consensus with an utility Slovenske elektrarne, nuclear power plants and Nuclear Regulatory Authority. A purpose of the article is to provide an overview on safety culture practices at nuclear installations in the Slovak Republic. (author)

  14. Diagnostic systems developed in NPPRI (VUJE) Trnava Inc. for NPPs

    Kucharek, P.

    1998-01-01

    Since foundation of Nuclear Power Plant Research Institute (NPPRI) in 1977, the department of diagnostics has been dealt with problems related to the theoretical, practical and organizatory questions of operational diagnostics connected with PWR type nuclear components. This department acts directly in locality of NPP Jaslovske Bohunice, but there are performances for all NPP in Slovak or Czech Republic (Dukovany, Mochovce, and Temelin). Besides direct services and achievements for NPP there exist advisory, experts and research activities for the government and supervising authorities, too. In 1985, NPPRI began systematically construct and verify technical means for operational diagnostics of main circulating pumps (MCP) with good results, based on own rich practical experiences and contacts with organisations abroad. In recent years NPPRI as one of recognised qualified and authorised institutions in Slovak Republic has begun to develop a new generation of diagnostic systems for NPP on high technical level but with lower procuring costs in comparison with western countries products. This contribution deals with four following types of diagnostic systems which were not only developed but also delivered and installed on Slovak and Czech nuclear units: - Loose part monitoring system (LPMS), - Humidity monitoring system (HUMON), - Reactor coolant pumps monitoring system (RCPMS), - Primary circuit vibration monitoring system (VMS). Main features of new generation from middle of 1990's of these systems are described in this paper and operational experiences with them too. (author)

  15. Decommissioning of VUJE's nuclear facilities

    Bosnak, M.; Holicka, Z.; Svitokova, M.; Listjak, M.

    2015-01-01

    Technology for the incineration of soft combustible waste (VUJE experimental incineration (VEI), building 76/B, A-1) was constructed by VUJE workers in collaboration with cooperating organizations in 1985. The research activity carried out in the second half of the 80s was focused to optimize the incineration process. Implemented experiments led to the optimization of operating parameters of the incineration technology to achieve the best quality of the final incineration product by achieving high reduction factors (volume 100, weight 16), a high degree of purification of combustion products (HEPA filter 99.995%) with minimal effect on the environment and operating personnel radiation load. In the years 1992 - 2000 VEI combusted soft solid radioactive waste from A-1, V-1, V-2 in the amount of 12 to 20 tons a year. Incineration unit in the Bohunice treatment centre was put into operation in 2001, and from that time VEI was operated only sporadically, approximately once per 3-4 months for incineration of soft radioactive waste from VUJE laboratories. VEI stopped its operation at the beginning of 2004, and passed through the phase of safety deposit (2005-2010) to the phase of the physical disposal of technological components (2011 -2014). Disposal of the building 76/B which started in 2015 within the NPP A-1 Project is described. (authors)

  16. Thermal-deformation effect of welding on A 1 reactor pressure vessel weld joints properties and state of stress

    Becka, J.; Kupka, I.

    1976-01-01

    The methods are compared of electroslag welding and of arc welding with a view to their possible application in welding the Bohunice A-1 reactor pressure vessel. Considered are the thermal deformation effects of welding on the physical properties and the stress present in welded joints. For testing, plates were used having the dimensions of 1100x2300x200 mm and rings with 4820 mm outer diameter, 1800 mm height and 170 mm thickness made of steel CSN 413O30 modified with Ni, Al+Ti. The deformation effect of welding on the residual surface and triaxial stress, the specific stored energy, the initiation temperature of brittle crack and the critical size of the initiation defect corresponding to the thermal deformation effect of welding were determined. It was found that for electroslag welding, there is a low probability of crack formation in the joints, a low level of residual stress and a low level of specific stored energy in a relatively wide joint zone. For arc welding there is a considerable probability of defect formation in the vicinity of the sharp boundary of the joint, a high level of the triaxial state of stress in the tensile region, and a high level of specific stored energy concentrated in the narrow zone of weld joints. The recommended thermal process is given for welding pressure vessels made of the CSN 413030 steel modified with Ni, Al+Ti, and 150 to 200 mm in thickness. (J.P.)

  17. Chapter 2. The production units

    1998-01-01

    In the second chapter of this CD ROM the production units of the Slovak Electric, Plc. (Slovenske elektrarne, a.s.), are presented. It consist of next paragraphs: (1) Nuclear power plants (A-1 Nuclear Power Plant (History, Technological scheme, basic data are presented); V-1, V-2 Bohunice Nuclear Power Plant (History 1972-1985, technological scheme; nuclear safety, radiation protection, heat supply, international co-operation and basic data are presented); Mochovce Nuclear Power Plant (History 1980-1998, technological scheme, construction completion, milestones of commissioning, safety and environmental protection as well as basic data are included). (2) Conventional sources of energy (Vojany fossil power plant (History 1959-1992, Technological units of power plant, Impact of operation on the environment, Plant of Vojany FPP Renewal and Reconstruction, Basic data are listed), Novaky fossil power plant (History 1949-1998, Technological scheme, current investment construction, basic data, Handlova heating plant). Kosice Combined Heat Power Plant (History 1960-1995, technological scheme, State metrology centre, acredited chemical laboratory, basic data). (3) Hydroelectric power plants (Trencin HPPs: Cierny Vah pumped storage HPP, Liptovska Mara HPP, Orava HPP, Sucany HPP, Miksova HPP, Nosice HPP, Velke Kozmalovce HPP, Gabcikovo HPP, Dubnica HPP, Nove Mesto n/V HPP, Madunice HPP, Kralova HPP) and Dobsina HPPs: (Dobsina HPP, Ruzin HPP, Domasa HPP, small HPPs) are presented

  18. Heat extraction from turbines of Czechoslovak nuclear power plants for district heating

    Drahy, J.

    1985-01-01

    Two design are described of SKODA extraction turbines for Czechoslovak nuclear power plants with WWER-440 and WWER-1000 reactors. 220 MW steam turbines were originally designed as pure condensation turbines with uncontrolled steam extraction. Optimal ways are now being sought for their use for heating hot water for district heating. For district heating of the town of Trnava, the nuclear power plant at Jaslovske Bohunice will provide a two-step heating of water from 70 to 120 degC with a heat supply of 60 MW th from one turbine unit. The ratio of obtained heat power to lost electric power is 5.08. Investigations showed the possibility of extracting 85 MW th of heat from uncontrolled steam extraction, this at three-step water heating from 60 to 145 degC, the ratio of gained and lost power being 7.14. Information is presented on the SKODA 220 MW turbine with steam extraction for heat supply purposes and on the 1000 MW turbine with 893 MW th heat extraction. The specifications of both types are given. (Pu)

  19. Forgotten research institute makes money from ideas

    Sobinkovic, B.

    2008-01-01

    Robots that stack magnets weighing several tons in the world's biggest nuclear laboratory with a millimetre precision. Small machines that can destroy bombs, detect bombs in trains, planes or cars. A leading position in an expert group that, with NATO funds, tests how robotic systems can be used in the fight against terrorism. This summary indicates that ideas are an integral part of the work done at the ZTS Vyskumno-vyvojovy ustav (ZTS VVU) research institute in Kosice. This is nothing special for a research institute. But this is a joint stock company. And so it needed one additional vision: producing goods that sell from the research. ZTS VVU has delivered robotic system for accurate positioning of cryo-magnets for the CERN. Cryo-magnet is 16 m long and weights 34 tonnes. For the CERN five robotic systems were delivered. The value of the contract with the CERN was about 60 millions slovak crowns (≅ 2 million EUR). Transport containers, manipulators for decontamination and manipulators with radioactive wastes were manufactured for the Bohunicke spracovatelske centrum (Bohunice Radioactive Waste Processing Center). (authors)

  20. Research of thermal stability of ion exchangers

    Stuchlik, S.; Srnkova, J.

    1983-01-01

    Prior to the fixation of radioactive ion exchangers into bitumen these exchangers have to be dried. The resulting gaseous products may generate explosive mixtures. An analysis was made of the thermal stability of two types of ion exchangers, the cation exchanger KU-2-8 cS and the anion exchanger AV-17-8 cS which are used in the V-1 nuclear power plant at Jaslovske Bohunice. The thermal stability of the anion exchangers was monitored using gas chromatography at temperatures of 100, 120, 140, 160 and 180 degC and by measuring weight loss by kiln-drying at temperatures of 120, 140, 160 and 180 degC. The ion exchanger was heated for 6 hours and samples were taken continuously at one hour intervals. The thermal stability of the cation exchanger was monitored by measuring the weight loss. Gas chromatography showed the release of trimethylamine from the anion exchanger in direct dependence on temperature. The measurement of weight losses, however, only showed higher losses of released products which are explained by the release of other thermally unstable products. The analysis of the thermal stability of the cation exchanger showed the release of SO 2 and the weight loss (following correction for water content) was found only after the fourth hour of decomposition. The experiment showed that the drying of anion exchanger AV-17-8 cS may cause the formation of explosive mixtures. (J.P.)

  1. Determination of 129I in radioactive wastes

    Horvathova, B.; Dulanska, S.; Matel, L.; Remenec, B.; Gardonova, V.

    2015-01-01

    The goal of this work was to develop and optimize the conditions for the distillation of iodine and its use for determination of 129 I on liquid scintillation spectrometer (LSC). An appropriate distillation apparatus for distillation of iodine was proposed by testing distillation apparatus. A method of cleaning of 129 I from present interferents , e.g. 14 C, 137 Cs, was tested on proposed simple distillation apparatus. High-purity fraction needed for the determination of 129 I was achieved by distillation on liquid scintillation spectrometer TRI CARB 2900TR from Perkin Elmer Company. Optimal energy window (0 - 80) keV was chosen to measure 129 I on liquid scintillation spectrometer. Ultima Gold TM AB was chosen as more appropriate scintillator by testing of two scintillation solutions. Optimized method for determining the 129 I was applied to real samples coming from Bohunice NPP. The combination of precipitation method and method of 129 I purification by distillation is easy and less time consuming separation method for the determination of 129 I compared to conventional methods of separation of 129 I, e.g. by liquid extraction. Measuring method on the LSC spectrometer represents a measurement with a higher detection efficiency (95%) as compared to measurement of low-energy X-ray radiation 129 I (29.6 keV) with X-ray detector Si (Li) 12155 SL with detection efficiency only (1-2)%.

  2. Long-term measurement with calorimetric probes at unit 1 of V-1 nuclear power plant

    Erben, O.; Szasz, Z.; Jirousek, V.; Teren, S.

    1989-01-01

    Two calorimetric probes were tested at the first unit of the Bohunice V-1 nuclear power plant in long-term operation, i.e., during one whole reactor duty time. Each probe consisted of five fission calorimeters and one compensation calorimeter with a tungsten body. The actual calorimeters were provided with jacketed thermocouples 0.5 mm indiameter and 19 m in length. A detailed description is presented of the measuring chains and measurement techniques. Also described is the method of the disposal of the irradiated probes. The method is presented of the evaluation of measured data and the results are discussed of the analysis of these data. The measurements, including measurements during reactor shut-down and the results of the analysis of the measured data proved good viability and stability of the used calorimetres. The method of measuring the thermocouple signals is simple and the in-service evaluation of required data is quick. In order to increase measurement efficiency it would be appropriate to complete the measuring chain and to automate it. Reliability is a affected merely by protecting the thermocouples against mechanical damage during measurement probe handling and on the reactor. (Z.M.). 5 figs., 5 tabs., 5 refs

  3. Selection of optimal treatment procedures for non-standard radioactive waste arising from decommissioning of NPP after accident

    Strážovec, Roman, E-mail: strazovec.roman@javys.sk [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia); JAVYS, a.s., Tomášikova 22, 821 02 Bratislava (Slovakia); Hrnčíř, Tomáš [DECOM, a.s., Sibírska 1, 917 01 Trnava (Slovakia); Lištjak, Martin [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia); VUJE, a.s., Okružná 5, 918 64 Trnava (Slovakia); Nečas, Vladimír [Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovičova 3, 812 19 Bratislava (Slovakia)

    2016-05-15

    The decommissioning of nuclear power plants is becoming a standard industrial activity where the optimization processes of partial activities are inevitable mainly for technical and economic reasons. In Slovakia, the decommissioning of A1 NPP is very specific case because A1 NPP is rare type of NPP (prototype) and furthermore its operation was affected by the accident. A large number of specific non-standard radioactive waste, such as long-time storage cases (hereinafter LSC), that is not usually present within the decommissioning projects of NPP with a regular termination of operation, represent one of the significant consequences of the accident and issues arisen from follow-up activities. The presented article describes the proposal of processing and conditioning of non-standard radioactive waste (such as LSC), together with description of methodology applied in the proposal for update of waste acceptance criteria for the processing and conditioning of radioactive waste (hereinafter RAW) within Bohunice Radioactive waste Treatment and Conditioning Centre (hereinafter RWTC). The results of performed detailed analysis are summarized into new waste acceptance criteria for technological lines keeping in mind safety principles and requirements for protection of operating personnel, the public and the environment.

  4. PSA analysis focused on Mochovce NPP safety measures evaluation from operational safety point of view

    Cillik, I.; Vrtik, L.

    2001-01-01

    Mochovce NPP consists of four reactor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present first unit operated and the second one under the construction finishing. As these units represent second generation of WWER reactor design, the additional safety measures (SM) were implemented to enhance operational and nuclear safety according to the recommendations of performed international audits and operational experience based on exploitation of other similar units (as Dukovany and J. Bohunice NPPs). These requirements result into a number of SMs grouped according to their purpose to reach recent international requirements on nuclear and operational safety. The paper presents the bases used for safety measures establishing including their grouping into the comprehensive tasks covering different areas of safety goals as well as structural organization of a project management of including participating companies and work performance. More, results are given regarding contribution of selected SMs to the total core damage frequency decreasing.(author)

  5. Comparison of Planning, Management and Organizational Aspects of Nuclear Power Plants A1 and V1 Decommissioning

    Stubna, M.; Michal, V., E-mail: Marian.Stubna@vuje.sk, E-mail: V.Michal@iaea.org [VUJE, Inc. Trnava (Slovakia); Daniska, V., E-mail: Daniska@decom.sk [DECOM, Inc. Trnava (Slovakia); Sirota, J., E-mail: Sirota.Jan@javys.sk [JAVYS, Inc. Bratislava, (Slovakia)

    2013-08-15

    This contribution deals with planning, management and organizational aspects of decommissioning of NPP shut down due to the accident (prototype NPP A1) and NPP shut down after normal operation (NPP V1). The A1 and V1 NPPs are located very close in Bohunice nuclear site however both plants have very different technology and operational history. The preparation of A1 NPP decommissioning strategy and relevant decommissioning plans was long term process, because the plant was shut down after the accident in 1977 and decommissioning was implemented first time in Slovakia with many specific difficulties. The decommissioning planning of V1 NPP was shorter and easier, because the plant was shut down after normal operation, there were lessons learned from the A1 NPP decommissioning planning, available legislation, available financing etc. Development of decommissioning strategies, preparation and planning for decommissioning, development of legislation for decommissioning, management of decommissioning projects and other aspects are described and compared. Lessons learned are formulated on the basis of analysis of past, ongoing and planned decommissioning activities in Slovakia. (author)

  6. Geomorphologic specificities of selected sites for nuclear power plants in Czechoslovakia

    Kalvoda, J.; Demek, J.

    1991-01-01

    The contribution of geomorphology to the complex evaluation of properties of sites for the construction and operation of nuclear facilities is demonstrated. The unique manifestation of the present geodynamics at the Jaslovske Bohunice nuclear power plant locality and the spatial correlations of annals of the specific morphotectonic development of georeliefs of that nuclear power plant with the location of the epicentral earthquake zones are shown. The results of the geomorphological survey in the surroundings of the Temelin nuclear power plant construction site are described and a drawing is reproduced showing how the georelief of this locality divides into areas with different categories of occurrence of morpho-structural formations. For the Tetov locality, where the construction of a nuclear power plant is planned, the changes in the course of the Labe (Elbe) river which occurred in the Pleistocene are of importance in the assessment of the intensity of geodynamic processes. The geomorphological and geotectonic complexity of the planned Blahutovice nuclear power plant construction site is demonstrated. A drawing shows the morphotectonic situation in the surroundings of that construction site. (Z.S.). 4 figs

  7. Enel waiting for the state to act first

    Anon

    2005-01-01

    Enel will only answer the basic question whether Slovenske elektrarne will complete the reactors 3 and 4 in nuclear power plant in Mochovce next year. Initial analyses made by Enel indicate that the completion of Mochovce would cost over 60 billions Sk (1,54 billions EUR). Since National Property Fund has approved the strategic investment plan two more conditions have to be met before Enel can acquire Slovenske elektrarne. The first condition is that a part of the company assets has to taken over by state owned joint stock company GovCo. This regards reactor V-1 in nuclear power plant Jaslovske Bohunice that should be made ready for closure by end of 2008, damaged reactor A-1, nuclear equipment decommissioning and disposal unit VYZ and hydroelectric power plant in Gabcikovo. The other condition that still has to be fulfilled is passing of a new act on disposal of nuclear power generating equipment. The new act should distribute the fund's resources amongst the individual nuclear energy sources. M. Arcelli (regional manager of Enel for Slovakia) stresses that the money nuclear power station in Mochovce and V-2 earned and will earn during their time in operation will have to remain in the fund to cover their later liquidation i.e. should not be used on liquidation of reactors V-1 or A-1. (authors)

  8. Toxicity and biodegradation of PCBs in contaminated sediments

    Dercova, K.; Cicmanova, J.; Lovecka, P.; Demnerova, K.; Mackova, M.; Hucko, P.; Kusnir, P.

    2006-01-01

    PCBs represent a serious ecological problem due to their low degradability, high toxicity, and strong bioaccumulation. Because of many environmental and economical problems, there are efforts to develop bio-remediation technologies for decontamination of the PCB-polluted areas. PCB were used by storage of spent nuclear fuel in nuclear power plants Jaslovske Bohunice. In the locality of the former producer of PCB - Chemko Strazske a. s. - big amount of these substances is still persisting in sediments and soil. The goal of this study was to analyze the contaminated sediments from Strazsky canal and Zemplinska Sirava water reservoir from several points of view. The study of eco-toxicity confirmed that both sediments were toxic for various tested organisms. The genotoxicity test has not proved the mutagenic effect. The subsequent step included microbiological analysis of the contaminated sediments and isolation of pure bacterial cultures capable of degrading PCBs. In order to determine the genetic potential for their biodegradability, the gene bphA1 was identified using PCR technique in their genomes. This gene codes the enzyme biphenyl-dioxygenase, which is responsible for PCB degradation. The final goal was to perform aerobic biodegradation of PCBs in the sediments. The bacteria present in both sediments are able to degrade certain low chlorinated congeners. The issue of biodiversity is still open and has to be studied to reveal the real cooperation between bacteria. (authors)

  9. A successful approach for the implementation of symptom-based emergency operating procedures for VVER reactors

    Lhoest, V.; Prior, R.; Pascal, G.

    2000-01-01

    The paper provides an overview of the organization, the progress and the results of the various Emergence Operating Procedure (EOP) development programs for VVER type reactors conducted by Westinghouse so far. The detailed working process is presented through the solutions to some major plant issues. The EOPs have been developed for the Temelin, Dukovany, Bohunice, Mochovce and Paks VVER nuclear power plants. The procedures are developed in working teams of experts from the utility and Westinghouse. The completion of the programs constitute an indication of the overall success of this approach. This is further reinforced by the general acceptance of the new procedures by the plant personnel, together with the good results obtained so far from procedure testing. This is also confirmed by a new PSA-level 1 analysis for Dukovany plant, which shows a significant improvement in the overall plant safety. This means a 20% reduction in the Core Damage Frequency due to the introduction of the new EOPs. The fact that some modifications have been implemented to the plants to solve design weaknesses identified in the course of this programs also constitute a positive result

  10. The ethical implications of nuclear power in Czechoslovakia

    Komarek, A.

    1991-01-01

    Editor of the journal, the Czechoslovak Atomic Energy Commission (CSAEC) is opening up a discussion on the basic problems of nuclear power in Czechoslovakia. Renowned authorities from the Czechoslovak political and professional community have been invited to contribute. Initiator of the discussion, the author of the paper formulated 5 principal tasks of Czechoslovak nuclear industry for the nearest period to come. CSAEC should only retain the function of State Surveillance over Nuclear Safety; the lowest permissible degree of nuclear safety should be defined for Czechoslovakia; Czechoslovak nuclear law should be modified so as to be compatible with the EC and not only with the IAEA; after completing the first two units of the Temelin nuclear power plant, links of the Czechoslovak nuclear industry should be established to some Western firm; and attitude to the feasibility of further operation of the Bohunice V-1 nuclear power plant and to the conditions of operation of the V-2 nuclear power plant should be formulated. (Z.M.)

  11. Use of computer codes to improve nuclear power plant operation

    Misak, J.; Polak, V.; Filo, J.; Gatas, J.

    1985-01-01

    For safety and economic reasons, the scope for carrying out experiments on operational nuclear power plants (NPPs) is very limited and any changes in technical equipment and operating parameters or conditions have to be supported by theoretical calculations. In the Nuclear Power Plant Scientific Research Institute (NIIAEhS), computer codes are systematically used to analyse actual operating events, assess safety aspects of changes in equipment and operating conditions, optimize the conditions, preparation and analysis of NPP startup trials and review and amend operating instructions. In addition, calculation codes are gradually being introduced into power plant computer systems to perform real time processing of the parameters being measured. The paper describes a number of specific examples of the use of calculation codes for the thermohydraulic analysis of operating and accident conditions aimed at improving the operation of WWER-440 units at the Jaslovske Bohunice V-1 and V-2 nuclear power plants. These examples confirm that computer calculations are an effective way of solving operating problems and of further increasing the level of safety and economic efficiency of NPP operation. (author)

  12. Improving of spent fuel monitoring in condition of Slovak wet interim spent fuel storage facility

    Miklos, M.; Krsjak, V.; Bozik, M.; Vasina, D.

    2008-01-01

    Monitoring of WWER fuel assemblies condition in Slovakia is presented in the paper. The leak tightness results of fuel assemblies used in Slovak WWER units in last 20 years are analyzed. Good experiences with the 'Sipping system' are described. The Slovak wet interim spent fuel storage facility in NPP Jaslovske Bohunice was build and put in operation in 1986. Since 1999, leak tests of WWER-440 fuel assemblies are provided by special leak tightness detection system 'Sipping in Pool' delivered by Framatome-ANP facility with external heating for the precise detection of active specimens. Another system for monitoring of fuel assemblies condition was implemented in December 2006 under the name 'SVYPP-440'. First non-active tests started at February 2007 and are described in the paper. Although those systems seems to be very effective, the detection time of all fuel assemblies in one storage pool is too long (several months). Therefore, a new 'on-line' detection system, based on new sorbent KNiFC-PAN for effective 134 Cs and 137 Cs activity was developed. This sorbent was compared with another type of sorbent NIFSIL and results are presented. The design of this detection system and its possible application in the Slovak wet spent fuel storage facility is discussed. For completeness, the initial results of the new system are also presented. (authors)

  13. Replacement of nickel sealing rings by expanded graphite sealing rings -upgrading of SG primary collector flange connection

    Cikryt, F; Bednarek, L; Kusyn, L [Vitkovice, Ostrava (Switzerland)

    1998-12-31

    One of the most loaded parts of a steam generator of VVER 440 MW type are the bolts and thread holes of the primary collector cover sealing set. The strength calculations and tensometric measurings performed during operation proved the high degree of a load on the bolts. The conditions of the stress limitation are not met in some cases according to the pertinent standards. The untightnesses at nickel rings occurred during putting the units of Jaslovske Bohunice and Dukovany nuclear power stations into operation. With regard to improve the reliability, the producer has taken measures to improve the quality of the rings and users have introduced more strict regulations for bolts tightening. Due to these measures the high reliability of the set has been obtained from point of view of the tightness, but substantial reduction of bolts and holes threads loading have not been obtained. Several years operation experience proved relatively low service of bolts, damage of thread holes and sealing grooves. As the degree of mechanical load is one of the vital parameters influencing the damage of sealing set, in 1996 we started with the works aimed at a possibility of nickel sealing rings replacement for a more modern type of sealing which assure the higher reliability and service life of the individual part of sealing set under the reduced load.

  14. Annealing of the RPV of unit 1 in Loviisa 1996

    Ahlstrand, R.; Kohopaeae, J.

    1997-01-01

    The critical circumferential core area weld of Loviisa 1 reactor pressure vessel was successfully annealed during the refueling and maintenance outage in August 1996. The weld was heated up to the annealing temperature of 475 deg.C and this temperature was maintained for 100 hours. The work was implemented by Skoda Nuclear Machinery Ltd as a main supplier representing consortium of Skoda Nuclear machinery Ltd from Czech Republic and Bohunice Nuclear Power Plant from Slovak Republic. Comprehensive material testing programs have been carried out to ensure the licensing of the annealing. Part of these programs have not yet been finished and are still going on. In the domestic programs sophisticated testing techniques including electric discharge machining and reconstitution techniques were used. Thus already tested surveillance specimens halves could be used as authentic material. The licensing work has been carried out mainly by VTT in Finland and Moht Otjig RM in Russia. A new comprehensive surveillance program has started to follow the embrittlement of the RPV after annealing. (author)

  15. Early detection and identification of anomalies in chemical regime based on computational intelligence techniques

    Figedy, Stefan; Smiesko, Ivan

    2012-01-01

    This article provides brief information about the fundamental features of a newly-developed diagnostic system for early detection and identification of anomalies being generated in water chemistry regime of the primary and secondary circuit of the VVER-440 reactor. This system, which is called SACHER (System of Analysis of CHEmical Regime), was installed within the major modernization project at the NPP-V2 Bohunice in the Slovak Republic. The SACHER system has been fully developed on MATLAB environment. It is based on computational intelligence techniques and inserts various elements of intelligent data processing modules for clustering, diagnosing, future prediction, signal validation, etc, into the overall chemical information system. The application of SACHER would essentially assist chemists to identify the current situation regarding anomalies being generated in the primary and secondary circuit water chemistry. This system is to be used for diagnostics and data handling, however it is not intended to fully replace the presence of experienced chemists to decide upon corrective actions. (author)

  16. A PC based multi-CPU severe accident simulation trainer

    Jankowski, M.W.; Bienarz, P.P.; Sartmadjiev, A.D.

    2004-01-01

    MELSIM Severe Accident Simulation Trainer is a personal computer based system being developed by the International Atomic Energy Agency and Risk Management Associates, Inc. for the purpose of training the operators of nuclear power stations. It also serves for evaluating accident management strategies as well as assessing complex interfaces between emergency operating procedures and accident management guidelines. The system is being developed for the Soviet designed WWER-440/Model 213 reactor and it is plant specific. The Bohunice V2 power station in the Slovak Republic has been selected for trial operation of the system. The trainer utilizes several CPUs working simultaneously on different areas of simulation. Detailed plant operation displays are provided on colour monitor mimic screens which show changing plant conditions in approximate real-time. Up to 28 000 curves can be plotted on a separate monitor as the MELSIM program proceeds. These plots proceed concurrently with the program, and time specific segments can be recalled for review. A benchmarking (limited in scope) against well validated thermal-hydraulic codes and selected plant accident data (WWER-440/213 Rovno NPP, Ukraine) has been initiated. Preliminary results are presented and discussed. (author)

  17. 222Rn and 14CO2 concentrations in the surface layer of the atmosphere

    Holy, K.; Chudy, M.; Sivo, A.; Richtarikova, M.; Boehm, R.; Polaskova, A.; Vojtyla, P.; Bosa, I.; Hola, O.

    2002-01-01

    Long-term monitoring of the Δ 14 C in the atmospheric near-ground CO 2 has been realized in Bratislava and Zlkovce, situated near the nuclear power plant Jaslovske Bohunice. Until 1993, the monthly mean Δ 14 C values showed a high variability. The annual means of Δ 14 C were about 30 per mille higher at Zlkovce than in highly industrialised Bratislava. An important change in the behaviour of the 14 C data has occurred since 1993. The records from both stations show the similar course, mainly due to the fact that there do not occur deep winter minima in Bratislava. This behaviour corresponds to the lower values of the total fossil fuel CO 2 emissions in the years after 1993 when compared to the previous years. At present, both sets of data show that the 14 C concentration is about 10% above the natural level. Since 1987 also the 222 Rn concentration in the surface layer of the atmosphere has been measured in Bratislava. These measurements provided an extensive set of the 222 Rn data characteristic for the inland environment with high level of atmospheric pollution. The seasonal and daily variations of the 222 Rn concentration were observed. The investigation of the relation between the monthly mean diurnal courses of the 222 Rn concentration and the atmospheric stability proved a high correlation between them. The 222 Rn data were used to interpret the anomalous Δ 14 C values in the surface layer of the atmosphere. (author)

  18. Activities of the Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear facilities in the Slovak Republic in 1994

    1995-01-01

    The report summarizes activities of the Nuclear Regulatory Authority of the Slovak Republic (NRA SR) in 1994 and briefly presents results of the national expert supervision over nuclear safety facilities in the SR in 1994. In 1994, the NRA SR have performed a national supervision of following organizations: SE, a.s. - Jaslovske Bohunice Nuclear Power Plant (V-1 Nuclear Power Plant (V-1 NPP), V-2 Nuclear Power Plant (V-2 NPP), A-1 Nuclear Power Plant (A-1 NPP)); Mochovce Nuclear Power Plant; Radioactive waste repository, Mochovce); Organizations providing a specialized training of NPP personnel; Organizations providing specific deliveries and activities for the nuclear power industry; Organizations having an owner of nuclear materials; Organizations providing activities related to import of radioactive sources; Organizations using radioactive sources. Organization structure of the NRA SR is explained. In the presented Chapter 1 - Safety of nuclear power plants in the Slovak Republic - safety aspects of the Slovak NPPs are reported. The next activities are reported: nuclear materials and safeguards; radioactive waste; emergency planning and NRA SR's control and crisis centre; international activities to improve the national surveillance quality; other activities

  19. European Decommissioning Academy (EDA). Ready to start

    Slugen, Vladimir

    2015-01-01

    According to analyses presented at EC meeting focused on decommissioning organized at 11 September 2012 in Brussels, it was stated that at least 2,000 new international experts for decommissioning will be needed in Europe up to 2025, which means about 150 each year. The article describes the European Decommissioning Academy (EDA) which is prepared for the first term in June 2015 in Slovakia. The main goal is a creation of new nuclear experts generation for decommissioning via the Academy, which will include lessons, practical exercises in laboratories as well as 2 days on-site training at NPP V-1 in Jaslovske Bohunice (Slovakia). Four days technical tour via most interesting European decommissioning facilities in Switzerland and Italy are planned as well. After the final exam, there is the option to continue in knowledge collection via participation at the 2nd Eastern and Central European Decommissioning (ECED) conference in Trnava (Slovakia). We would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future.

  20. Determination methods of the 90Sr in a sample of contaminated water

    Ometakova, J.; Silvia Dulanska, S.

    2009-01-01

    The aim of this work was a comparison of selected products from the point of view of the amount of strontium yields, time needed and possibility of multiple use of sorbents. Three commercial products: 3M Empore Stroncium Rad Disk, AnaLig , Sr-Resin and two classical methods: liquid-liquid extraction with tributylphosphate and carbonate coprecipitation (to eliminate interferents) were used for separation of 90 Sr. The model sample was used in radiochemical analysis to check multiple use of 3M Em-pore Stroncium Rad Disk a AnaLig. A radiochemical strontium yield was traced by using radionuclide 85 Sr. The model sample was also used to optimize conditions of strontium separation. The results were used for 90 Sr determination from a sample of permeating groundwater from a supervised zone of a Nuclear Power Plant Jaslovske Bohunice. We have found out that 90 Sr separation with sorbents AnaLig Sr-01, 3M Empore Sr Rad Disk is as effective as with sorbent Sr-Resin in matrices of contaminated water. (authors)

  1. Redevelopment drawing off of underground waters - a tool for lowering of environmental influences of the decommissioned A-1 NPP on the environment

    Kostolansky, M.; Benko, J.; Plsko, J.; Machyniak, P.

    2003-01-01

    Decommissioned A-1 NPP is the main source of radioactive contamination of the underground waters in the locality of nuclear energetic facilities in Jaslovske Bohunice. This situation is the consequence of historical as well as present leaks of the radioactive contamination into geological surroundings of the locality. The tritium is the determining radionuclide. The remedial measures were accepted for solution of this negative influence on the environment. The aim of these measures was the minimisation of influence of the underground waters. One of instruments, which supply the decreasing of environmental influence of the decommissioned A-1 NPP on underground waters, is the also redevelopment drawing off of underground waters. In this paper is briefly said the process of planning of the optimal technology and of the parameters of redevelopment drawing off of underground waters in the area of the A-1 NPP and its realisation. The main part of the paper is dedicated to the evaluation of results of realisation of the redevelopment drawing off of underground waters and to the total evaluation of this measure for assigning of protection of underground waters, their resources and right function of water divisions of this locality in the meaning of applicable legislation. (authors)

  2. VUJE's experience in the field of thermal-hydraulic behaviour of WWER

    Klepach, J.

    1995-01-01

    The thermal-hydraulic behavior (THB) of NPP coolant system and its consequences to nuclear safety of WWER reactors in previous Czechoslovakia has been studied in the VUJE (Nuclear Power Plants Research Institute, Trnava, SK). The institute takes part in the development and verification of its own (SLAP, LENKA, PUMKO, SICHTA, TRACO etc.) and international (DYNAMIKA5) codes for thermal-hydraulic analysis. The verification efforts are concentrated on the WWER specific features such as horizontal steam generators, control and safety system functioning, etc. The whole range of NPP accident analyses is covered by the VUJe staff. The author outlined briefly the WWER specific features as design and implemented improvements in Bohunice V-1 and Mochovce V-1 (WWER 230 model). The pros and cons of the WWER design compared against western type PWR are described. It is believed that although the WWERs are designed under the rules and standards of 1960s, their safety and operational performance can be improved to acceptable level by thorough analysis and appropriate measures. 5 figs

  3. Practical results of the MESA 1 line calcinator trial operation

    Napravnik, J.; Sazavsky, P.; Skaba, V.; Zahalka, F.; Vild, J.; Kulovany, J.

    1987-01-01

    Mobile calcination and cementation unit MESA 1 was designed and built by UJV Rez in cooperation with many enterprises, mainly with the Kralovopolske Strojirny Brno. This facility for direct fixation of liquid radioactive wastes was experimentally tested using model non-radioactive solutions and model and actual wastes from the Jaslovske Bohunice nuclear power plant. The calciner was run in trial operation at the Kralovopolske SAtrojirny Brno. A total of 1.3 m 3 of model solutions was processed into 180 kg of calcinate. The fixation of the calcinate in cement, the times of solidification and of hardening and the moisture content of concrete blocks were studied. The application was also tested of the calciner in drying ion exchangers from WWER-440 prior to their bituminization. Following the despatch of the cementation module to the Chernobyl nuclear power plant, the direct calcination module was tested at Dukovany together with an auxiliary module which makes possible self-contained calciner operation. Model non-radioactive solutions from the Dukovany nuclear power plant were treated containing H 3 BO 3 and NaNO 3 as main components. The usability in actual conditions of the mobile calcination and cementation unit for radioactive wastes was tested in a total of about 70 operating hours. (E.S.). 2 figs., 2 refs

  4. Statement of participants at the International Conference on Can Slovakia secure energy supply and sustainable development without nuclear?

    Mikus, T.; Suchomel, J.

    2004-01-01

    completion as possible. The Slovak participants at the Conference stated with deep concern that the commitment of the Slovak government to close V1 Bohunice, accepted during EU pre-entry negotiations and reminding e nergy imperialism , as warned by the former Finnish premier Paavo Lipponen, is not fair as it is based on a political appraisal from G7 summit in Munich in 1992 that VVER-440/V230 reactors cannot be upgraded with reasonable costs, which had been disproved by the Slovak evidence. The participants called on the Slovak government and the future Slovak members of the European Parliament to revive negotiations on a revision of this groundless commitment. The participants called on the European nuclear community to support the Slovak demand to revise the commitment to close the two V1 Bohunice units and to complete the construction of the Mochovce units 3 and 4. So the major message from the Conference is: Go Nuke Slovakia!

  5. Early Detection and Identification of Anomalies in Chemical Regime

    Figedy, Stefan; Smiesko, Ivan

    2011-01-01

    This paper provides a brief information about the basic features of a newly developed diagnostic system for early detection and identification of anomalies incoming in the water chemistry regime of the primary and secondary circuit of VVER-440 reactor. This system, called SACHER (System of Analysis of CHEmical Regime) is being installed within the major modernization project at the NPP-V2 Bohunice in the Slovak Republic. System SACHER has been developed fully in MATLAB environment. The availability of prompt information about the chemical conditions of the primary and secondary circuit is very important to prevent the undue corrosion and deposit build-up. The typical chemical information systems that exist and work at the NPPs give the user values of the measured quantities together with their time trends and other derived values. It is then the experienced user's role to recognize the situation the monitored process is in and make the subsequent decisions and take the measures. The SACHER system, based on the computational intelligence techniques, inserts the elements of intelligence into the overall chemical information system. It has the modular structure with the following most important modules: normality module- its aim is to recognize that the process starts to deviate from the normal one and serves as the early warning to the staff to take the adequate measures, fuzzy identification module- its aim is to identify the anomaly on the basis of a set of fuzzy rules, time-prediction module- its aim is to predict the behavior/trend of selected chemical quantities 8 hours ahead in 15 min step from the moment of request, validation module- its aim is to validate the measured quantities, trend module- this module serves for showing the trends of the acquired quantities

  6. Monitoring of arched sched ground layer

    Listjak, M.; Slaninka, A.; Rau, L.; Pajersky, P.

    2015-01-01

    Arched Shed was a part of controlled area of NPP A1 site in Jaslovske Bohunice (Slovakia). It had been used for temporary storage of loose radioactive waste (RAW) which has been characterized within the BIDSF project C13, Characterisation of Loose Radioactive Waste'. Stored RAW has been treated and sorted within the project ',Realization of the 2 nd stage of Decommissioning Project of NPP A1'. Area of Arched Shed represents approximately 270 m 2 (45 m x 6 m). Ground layer of the AS consists mostly of soil with solid elements (stones and gravel). The aim of monitoring was to remove the contaminated soil up to 1 m below ground level. Requirement for detail monitoring of the Arched Shed ground layer resulted from conclusions of the BIDSF project C13 which has proved that massic activity 137 Cs of soil was up to few thousands Bq·kg -1 in underground layer. Dominant easy to measure radionuclide in the soil is 137 Cs which has been used as a key radionuclide for methodology of in-situ soil monitoring. Following methods has been applied during characterization: dose rate survey, sampling from defined ground layer followed by laboratory gamma spectrometry analysis by the accredited testing laboratory of radiation dosimetry VUJE (S-219) and in-situ scintillation gamma spectrometry by 1.5''x1.5'' LaBr detector. Massic activity of the remaining soil (not excavated) comply the criteria for free release into the environment (Government Regulation of Slovak Republic 345/2006 Coll.). Area was filled up by non-contaminated soil up to the ground level of surroundings. Afterward the area was covered with geotextile and concrete panels and nowadays it is ready for further usage within the NPP A1 decommissioning project as a place for treatment, conditioning and disposal of contaminated soil and concrete. (authors)

  7. Prophylactic and thermovision measurements of electric machines and equipment

    Jedlicka, R; Brestovansky, L [Atomova Elektraren Bohunice, Jaslovske Bohunice (Slovakia)

    1997-12-31

    High-voltage measurements of generators, unit and service transformers and some significant motor drives used at a nuclear power plant are described in this paper. Thermovision measurements of electric machines and distribution systems are dealt with in the second part of the paper. Power electric equipment represent one of the most significant components of a nuclear power plant. Turbine mechanical energy is converted into the electrical energy within these equipment. Power generated by generators is transformed by transformers so that it can achieve appropriate parameters for both the transmission over the distribution system and the power plant service power supply. The service power supply switchboards and cables provide supply to motors and other consumers necessary for the nuclear power plant technological process. The whole complex of equipment has to be maintained in good technical conditions. It is necessary to make thermovision and prophylactic measurements to identify and verify the electric equipment technical condition. The mentioned measurements warn the operation staff in advance against both gradual deterioration of power connection contact resistances, i.e. power connections overheating, and the machine insulation systems condition deterioration. The operation staff try to prevent the electric equipment operation accidents by early removing the detected failures, thus, improving the nuclear safety. In order to provide the above-mentioned activities a special prophylactic measurement group was established at the NPP Bohunice in 1983. The group specialists make following types of measurements. 1. Prophylactic measurements of electric machines. Prophylactics of 220 MW generators and 6 MW service power generators; Prophylactics of both unit and service transformers and VHV bushings; Prophylactics of major 6 kV motor drives. 2. Thermovision measurements of current connections. (Abstract Truncated)

  8. Atoms in Slovakia

    Danis, D.; Feik, K.; Florek, M.; Kmosena, J.; Chrapan, J.; Morovic, M.; Slugen, V.; Seliga, M.; Valovic, J.

    2006-01-01

    In this book the history of development of using of nuclear energy in the Slovak Republic as well as in the Czechoslovakia (before 1993 year) is presented. The aim of the book is to preserve the memory of the period when the creation and development of nuclear physics, technology, nuclear medicine, radioecology and energetics in Slovakia occurred - as witnessed by people who experienced this period and to adapt it to future generations. The Editorial board of the SNUS collected the views of 60 contributors and distinguished workers - Slovakian experts in nuclear science, education and technology. Calling upon a wide spectrum of experts ensured an objective historical description of the period. A huge amount of subjective views on recent decades were collected and supported by a wealth of photographic documentation. This created a synthesised reflection on the history of the 'atoms' in Slovakia. The book contains 15 tables, 192 black and white and 119 colour pictures from around the world and from places involved in the compilation of the study and with the study of atomic science in Slovakia. The main chapters are as follows: Atoms in the world, Atoms in Slovakia, Atoms in the educational system, Atoms in health services (Radiology, Nuclear medicine, Radiation protection, the Cyclotron centre of the Slovak Republic), Radioecology, Other applications of irradiation, Nuclear energetics (Electric energy in the second half of the 20 th century, NPP Bohunice, NPP Mochovce, the back-end of Nuclear energetics, Big names in Nuclear energetics in Slovakia), Chronology and an Appendix entitled 'Slovak companies in nuclear energetics'

  9. New radiochemical methods for determination of 237Np a 241Pu using extraction chromatography (Presentation)

    Strisovska, J.

    2013-01-01

    Thesis was focused on the development of a new methodology for the separation of anthropogenic transuranium radionuclides 237 Np a 241 Pu from different kinds of matrices. The analytical methods used in this study were based on extraction chromatography and were optimized according to the sample type. The proposed radiochemical procedure is a combination of two algorithms, which represent the separation of radionuclides by using extraction chromatographic sorbents TEVA resin and TRU resin supplied by Eichrom Technologies LLC. 239 Np a 237 Np were selectively captured on sorbent TEVA resin in oxidation state 4+. TRU resin was used for purification of plutonium fraction from interfering americium radionuclide. 242 Pu and 239 Np radionuclides as tracers have been used to monitor the radiochemical yields of separation. Before every radiochemical separation tracer radionuclide 239 Np was obtained by separation from the parent radionuclide 2 43 Am, which is in radioactive equilibrium to 239 Np. The average yield of chemical separation was 69,3% for 239 Np at 277 keV energy line and 65,9% at 228 keV energy line. The NPL AH-B08069 (2008) samples which consist of the mixture of alpha-radionuclides were used for the modification and optimization of separation method used for separation of Np and Pu in model samples. This method provided high radiochemical yields of 239,240 Pu (95,0 ± 3,5)% and 237 Np (87,9 ± 3,0)%.. Reliability of the method was verified by applying our modified separation procedures on reference materials IAEA-375 and IAEA-414 supplied by International Atomic Energy Agency. A good agreement between the results is obtained by this procedure and the certified values were found. Samples of contaminated soils from the area of Nuclear power plant A-1 Jaslovske Bohunice which is stored temporarily before disposal were analyzed using developed separation procedure. Specific activity of investigated radionuclides was determined in these samples. (author)

  10. Monopolist requires totally liberalization

    Janoska, J.

    2003-01-01

    Slovenske elektrarne (SE), a.s, Bratislava in present time operates some sources, which would be off at normal conditions. It was caused by high electricity price on European markets. It is possible to sell 1 MWh for 12 thousands Slovak crowns abroad in last months. It is also advantageous to initialise thermal sources for power plant, where variable expenses are higher - from 1200 to 1300 Slovak crowns per MWh. SE are mainly trying to sell most of electricity on domestic market because returnability of dominant nuclear power plants was projected for this market. Utilizing capacities profit via domestic market covers fixed costs of power plants. Besides, power plant can demand regulated price 1272 Slovak crowns per 1 MWh. SE sources have capacity of 6800 MW, but maximal daily load uses for example in December approximately 4000 MW. Overflows are more higher in the summer - load dropped to 2200 MW in the beginning of September in last year. It is noted in issue that price increase in Europe is noticed. Price of primary power electricity will remain at liquid markets at 28 Euro (1176 Slovak crowns) in the following year prices fluctuate from 38 to 40 Euro (to 1700 Slovak crowns) per 1 MW at load peaks. Price increase is caused by lack of sources - it does not keep up to satisfy demand increase. Sources are gradually laid up and no new sources are built. Production capacities will decrease also in SE - by laying up of two 440 MW blocks of Bohunice NPP V-1. Price increase trend will continue according to SE businessmen till it is advantageous to build new source. Present price trend can be accelerated by decision about completing of Mochovce NPP 3-4

  11. The LA-10 Project for complex testing of nuclear incineration systems

    Hron, M.; Chochlovsky, I.; Lelek, V.; Peka, I.; Valenta, V.

    1997-01-01

    The current proposals for high-active long-lived (more then 10''4 years) waste from spent nuclear fuel disposal call forth an increasing mistrust of society towards nuclear power at all. These problems are highly topical even in the Czech Republic. In 1993, the Czech Republic and the Slovak Republic were constituted instead of the former Czechoslovakia. The first of two operated Czechoslovakian NNPs, the NNP Bohunice together with the only one in that time intermediate storage of spent fuel, remains on the territory of Slovakia and the NPP Dukovany as well as the NPP Temelian (designed with totally 4 x VVER-1000, 2 x VVER-1000 of which are ready for start up in the next few years) are located in the Czech Republic. As a consequence of this political step, the decision was accepted to build up an intermediate storage in the Czech Republic (to put it into operation in 2005) and to store all Dukovany's fuel in transport casks (84 complete fuel assemblies per one cask) on the Dukovany's site territory up to the 600 tons of heavy metal and the move it into the new intermediate storage, which should be designed for the lifetime of about 50-60 years. At about 2030 as a main variant, the final disposal of all spent fuel should be prepared. There is an opinion of a rational part of the Czech nuclear community that the final disposal of spent fuel is only something like fairy-tale for public and that a real technical solution should be found definitely. (Author) 13 refs

  12. Chapter 12. Public information

    2000-01-01

    In 1999 there were 83 contributions on both national and foreign activities of the Nuclear Regulatory Authority of the Slovak Republic (UJD) send to the Press agencies of Slovakia, dailies and electronic media. UJD, together with State Office for Nuclear Safety of the Czech Republic, is a publisher of a professional journal 'Safety of Nuclear Energy', which publishes principal articles about main activities of UJD. The double issue 3/4 (1999) was dedicated to the process of start up of Unit 1 of Mochovce. In 'Public administration' there were 2 principal articles published in 1999 on legislative activities of UJD. Contributions about the regulatory activities and the international co-operation of UJD are regularly published in the 'SE Newsletter', and in company journals of 'Mochovce' and 'Bohunice'. National and foreign activities of UJD were published in 3 issues of 'Bulletin of the Slovak Nuclear Society (SNUS)'. This year also the report on safety of nuclear installations of SR was published in the journal of 'European Nuclear Society - Nuclear Europe Worldscan'. For the world information agency, NucNet, there were 4 contributions prepared focusing on both national and foreign activity of UJD. Information material on INES was was prepared and published for the public. In 1999 there were 4 press conferences held at UJD with a follow up presentation of the management of UJD on television and in the radio broadcasting. Officials of UJD had 7 presentations on television and gave 6 interviews for Slovak Radio Broadcasting and for magazines and daily 5 significant interviews. In 1999 a vide-clip was produced for public purposes on the SWISSSLOVAK project. In Bern, Switzerland a very successful press conference was held with the participation of the UJD chairman. The UJD 3 Bulletins prepared and published on national and foreign activities of UJD

  13. Modifications of Probabilistic Safety Assessment-1 Nuclear Power Plant Dukovany based upon new version of Emergency Operating Procedures

    Aldorf, R.

    1997-01-01

    In the frame of 'living Probabilistic Safety Assessment-1 Nuclear Power Plant Dukovany Project' being performed by Nuclear Research Institute Rez during 1997 is planned to reflect on Probabilistic Safety Assessment-1 basis on impact of Emergency Response Guidelines (as one particular event from the list of other modifications) on Plant Safety. Following highlights help to orient the reader in main general aspects, findings and issues of the work that currently continues on. Older results of Probabilistic Safety Assessment-1 Nuclear Power Plant Dukovany have revealed that human behaviour during accident progression scenarios represent one of the most important aspects in plant safety. Current effort of Nuclear Power Plants Dukovany (Czech Republic) and Bohunice (Slovak Republic) is focussed on development of qualitatively new symptom-based Emergency Operating Procedures called Emergency Response Guidelines Supplier - Westinghouse Energy Systems Europe, Brussels works in cooperation with teams of specialist from both Nuclear Power Plants. In the frame of 'living Probabilistic Safety Assessment-1 Nuclear Power Plant Dukovany Project' being performed by Nuclear Research Institute Rez during 1997 is planned to prove on Probabilistic Safety Assessment -1 basis an expected - positive impact of Emergency Response Guidelines on Plant Safety, Since this contract is currently still in progress, it is possible to release only preliminary conclusions and observations. Emergency Response Guidelines compare to original Emergency Operating Procedures substantially reduce uncertainty of general human behaviour during plant response to an accident process. It is possible to conclude that from the current scope Probabilistic Safety Assessment Dukovany point of view (until core damage), Emergency Response Guidelines represent adequately wide basis for mitigating any initiating event

  14. VUJE experience with cementation of liquid and wet radioactive waste

    Kravarik, Kamil; Holicka, Zuzana; Pekar, Anton; Zatkulak, Milan

    2011-01-01

    Liquid and wet LLW generated during operation as well as decommissioning of NPPs is treated with different methods and fixed in a suitable fixation matrix so that a final product meets required criteria for its disposal in a final repository. Cementation is an important process used for fixation of liquid and wet radioactive waste such as concentrate, spent resins and sludge. Active cement grout is also used for fixation of low level solid radioactive waste loaded in final packing containers. VUJE Inc. has been engaged in research of cementation for long. The laboratory for analyzing radioactive waste properties, prescription of cementation formulation and estimation of final cement product properties has been established. Experimental, semi-production cementation plant has been built to optimize operation parameters of cementation. VUJE experience with cementation of liquid and wet LLW is described in the presented paper. VUJE has assisted in commissioning of Jaslovske Bohunice Treatment Centre. Cement formulations for treatment of concentrate, spent resins and sludge have been developed. Research studies on the stability of a final concrete packaging container for disposal in repository have been performed. Gained experience has been further utilized for design and manufacture of several cementation plants for treatment of various liquid and wet LLW. Their main technological and technical parameters as well as characterization of treated waste are described in the paper. Applications include the Mochovce Final Treatment Centre, Movable Cementation Facility utilizing in-drum mixing for treatment of sludge, Cementation Facility for treatment of tritiated water in Latvia and Cementation Facility for fixation of liquid and solid institutional radioactive waste in Bulgaria, which utilizes lost stirrer mixer. (author)

  15. Equipment for RAW handling, packaging, transport and storage from ZTS VVU KOSICE a.s

    Vargovcik, L.

    2004-01-01

    Since 1988, the company ZTS VVU KOSICE has devoted a great part of its activities to the development of equipment for RAW handling, packaging, transport and storage, mainly for application in the decommissioning of NPP A1 at Jaslovske Bohunice in Slovakia. This is a HWGCR NPP shut down following a breakdown in 1977. This incident was caused by disruption of the technological channel serving as a barrier between heavy water moderator and fuel assembly. Damage of this barrier enabled heavy water leakage into the primary circuit with partial fuel elements cladding damage and subsequent additional contamination of the primary circuit. During two consecutive years after the incident main effort was focused on activities related to personnel and environment protection, moderator draining, reactor defuelling, dry cleaning of the primary circuit, repair and maintenance of equipment. The next step was the preparation of the concept of NPP A-1 introduction into dry safe state. The order of importance of RAW liquidation was as follows: 1. Spent fuel - spent fuel assemblies from NPP A-1 were, after short cooling, stored temporarily in storage pipe containers filled at the beginning of NPP operation with ''chrompik'' (an aqueous solution of K 2 Cr 2 O 7 with concentration of 3-5%), later with ''dowtherm'' (mixture of bi-phenyl oxide and bi-phenyl). The containers were placed in a storage pond filled with water. 2. Liquid RAW - combustible (dowtherm, oils) and non-combustible (chrompik, Demi water, decontaminating solutions, sludge, sorbents, etc.) 3. Solid RAW - metallic and non-metallic For this purpose, it was necessary to build RAW processing lines, intermediate storage facilities and systems for manipulation and transport of RAW

  16. Borate compound content reduction in liquid radioactive waste from nuclear power plants with VVER reactor

    Szalo, A.; Zatkulak, M.

    2000-01-01

    This paper describes the current status of liquid waste (evaporator concentrates) inventory at V-1 and V-2 NPPs in Jaslovske Bohunice and the intention to separate boron from them with respect to waste minimisation and improvement of physical and chemical properties for further waste treatment and conditioning. Preliminary results of laboratory experiments concerned to borate crystallisation after pH adjustment with nitric or formic acid performed in the 1998 are given. At the present time laboratory experiments continuing - next acids, coagulation with carbon oxide, electrolytic process, ion exchange resin, study of decontamination factors, immobilization of boric acid, decrease radioactivity, purification of boron-contained compounds. Slovenske Elektrarne have accumulated 7,000 m 3 of evaporator concentrates containing 100-180 g/l borate. In order to make more storage space available, it is proposed to remove some of the borate in the liquor by precipitation as sodium tetraborate and immobilise in either cement of bitumen. The supernate can be further volume reduced by evaporation and returned to the tanks. Slovenske Elektrarne are currently evaluating acid addition to the pH 12-13 concentrate to reduce the borate solubility. However, this adds to the salt burden of the waste through this chemical addition -thus creating future increases in conditioning and disposal costs. Boric acid is used in pressurized water as a soluble neutron poison to control reactivity and also to assure a safety margin in the spent fuel pool and during refuelling operations. Boric acid is also present in the water reserved for injection into the reactor in the event of postulated accidents. (author)

  17. Fast and effective determination of strontium-90 in high volumes water samples

    Basarabova, B.; Dulanska, S.

    2014-01-01

    A simple and fast method was developed for determination of 90 Sr in high volumes of water samples from vicinity of nuclear power facilities. Samples were taken from the environment near Nuclear Power Plants in Jaslovske Bohunice and Mochovce in Slovakia. For determination of 90 Sr was used solid phase extraction using commercial sorbent Analig R Sr-01 from company IBC Advanced Technologies, Inc.. Determination of 90 Sr was performed with dilute solution of HNO 3 (1.5-2 M) and also tested in base medium with NaOH. For elution of 90 Sr was used eluent EDTA with pH in range 8-9. To achieve fast determination, automation was applied, which brings significant reduction of separation time. Concentration of water samples with evaporation was not necessary. Separation was performed immediately after filtration of analyzed samples. The aim of this study was development of less expensive, time unlimited and energy saving method for determination of 90 Sr in comparison with conventional methods. Separation time for fast-flow with volume of 10 dm 3 of water samples was 3.5 hours (flow-rate approximately 3.2 dm 3 / 1 hour). Radiochemical strontium yield was traced by using radionuclide 85 Sr. Samples were measured with HPGe detector (High-purity Germanium detector) at energy E φ = 514 keV. By using Analig R Sr-01 yields in range 72 - 96 % were achieved. Separation based on solid phase extraction using Analig R Sr-01 employing utilization of automation offers new, fast and effective method for determination of 90 Sr in water matrix. After ingrowth of yttrium samples were measured by Liquid Scintillation Spectrometer Packard Tricarb 2900 TR with software Quanta Smart. (authors)

  18. SCORPIO-VVER core monitoring and surveillance system with advanced capabilities

    Molnar, Jozef; Vocka, Radim

    2010-01-01

    The SCORPIO (SCORPIO-VVER) core monitoring system, its basic features and history of implementation at Czech NPPs are described. The most important improvements in the area of neutron physics, core thermal analysis and operation support are as follows: Moving to the 42 axial nodes across the whole system (2004); Implementation of new cross section library to support mixed reactor core with differences in axial geometry of used fuel types and enhancement of Core Simulator boundary conditions model, to properly address the 'wild' geometry in axial direction; Adjusting the thermohydraulic and neutron-physical models regarding to the Gd2 fuel needs; Support up to 5 types of FAs and 2 types of SPND (Posit, IST); Extension of form functions for pin-wise reconstruction to improve pin-power prediction in control rod coupler region; System adaptation to the new upgraded digital I and C unit system; Integration of the SCORPIO-VVER system and its workstation into the plant redundant in-core system; Implementation of new On-Line form function generation to module RECON; New design of the Strategy Generator with advanced predictions; Adaptation of the system to support the new up-rated reactor thermal power; Adding new online SDM calculation function into to system; Implementation of the new 3D power reconstruction with SPND interpretation; Extending the limit checking to the 'full core' checking. The control of margins to the technical specification: Extended to full core - all FA is controlled individually in core; The limits are definable up to 59 FA (1/6 symmetry); 4 limited parameters are controlled - Kr, qlin, Tout-fa, dTfa; 2 additional parameters are monitored - dTsat, DNBR; New MMI are developed to present the limited and controlled parameters in core. Upgrade 3 is planned for the Slovak Bohunice NPP in 2011-2012. (P.A.)

  19. Plant uptake of radiocesium from contaminated soils

    Pipiska, M.; Lesny, J.; Hornik, M.; Augustin, J.

    2004-01-01

    Phytoextraction field experiments were conducted on soil contaminated with radiocesium to determine the capacity of autochthonous grasses and weeds to accumulate 137 Cs. The aim of the study was to evaluate the potential of spontaneously growing vegetation as a tool for decontamination of non-agricultural contaminated land. As a test field, the closed monitored area of the radioactive wastewater treatment plant of the Nuclear Power Plant in Jaslovskie Bohunice, Slovakia was used. contamination was irregularly distributed from the level of background to spots with maximal activity up to 900 Bq/g soil. Sequential extraction analysis of soil samples showed the following extractability of radiocesium (as percent of total): water 2 = 0.3-1.1%; 1M CH 3 COONa = 0.3-0.9%; 0.04 M NH 4 Cl (in 25% CH 3 COOH) = 0.9-1.4% and 30% H 2 O 2 - 0.02 M HNO 3 = 4.5-9.0%.Specific radioactivity of the most efficiently bioaccumulating plant species did not exceed 4.0 BqKg -1 (dry weight biomass). These correspond to the soil-to-plant transfer factor (TF) values up to 44.4x10 -4 BqKg -1 crop, d.w.)/(BqKg -1 soil d.w). Aggregated transfer factor (T ag ) of the average sample of the whole crop harvested from defined area was 0.5x10 -5 (Bqkg -1 d.w. crop)/(Bqm -2 soil). It can be concluded that low mobility of radiocesium in analysed soil type, confirmed by sequential extraction analyses, is the main hindrance for practical application for autochthonous plants as a phytoremediation tool for aged contaminated area of non-cultivated sites. Plant cover can efficiently serve only as a soil surface-stabilising layer, mitigating the migration of radiocesium into the surrounding environment. (author)

  20. Experiences Gained from Independent Assessment in Licensing of Advanced I and C Systems in Nuclear Power Plants

    Lindner, Arndt B.; Wach, Dieter H.

    2003-01-01

    Operational benefits and enlarged functionality of modern technology, but also the physical and the technological aging of conventional instrumentation and control (I and C) systems, are motivations for modernization of I and C systems in nuclear power plants (NPPs). In case of safety-relevant I and C systems, the licensing authorities require the demonstration of sufficient safety of the systems.In several countries ongoing research and development projects are directed to provide a scientific basis and engineering solutions for cost-effective assessment of software-based I and C systems important to safety in NPPs. International initiatives have been started to develop a harmonized safety assessment methodology. The Institute for Safety Technology (ISTec) has been engaged in national and international programs as well as in establishing a two-phase qualification approach, which comprises a generic plant-independent qualification of hardware and software components and a plant-specific system qualification phase.In both generic qualification and plant-specific system qualification, ISTec has been involved as an independent third-party assessor for the relevant state authority. This paper reports experiences from the ISTec involvement in the assessment projects, e.g., in the assessment of the I and C important to safety in the new German High-Flux Research Reactor (FRM-2) in Munich and in the assessments of I and C modernization in NPPs of foreign countries (Bohunice, Slovak Republic; Paks, Hungary; and others). Conclusions are drawn from the experiences with respect to the practicability of the two-phase qualification concept and from the major findings in the plant-specific I and C assessments

  1. Regulation of radioactive waste management

    2002-01-01

    This bulletin contains information about activities of the Nuclear Regulatory Authority of the Slovak Republic (UJD). In this leaflet the regulation of radioactive waste management of the UJD are presented. Radioactive waste (RAW) is the gaseous, liquid or solid material that contains or is contaminated with radionuclides at concentrations or activities greater than clearance levels and for which no use is foreseen. The classification of radioactive waste on the basis of type and activity level is: - transition waste; - short lived low and intermediate level waste (LlLW-SL); - long lived low and intermediate level waste (LlLW-LL); - high level waste. Waste management (in accordance with Act 130/98 Coll.) involves collection, sorting, treatment, conditioning, transport and disposal of radioactive waste originated by nuclear facilities and conditioning, transport to repository and disposal of other radioactive waste (originated during medical, research and industrial use of radioactive sources). The final goal of radioactive waste management is RAW isolation using a system of engineered and natural barriers to protect population and environment. Nuclear Regulatory Authority of the Slovak Republic regulates radioactive waste management in accordance with Act 130/98 Coll. Inspectors regularly inspect and evaluate how the requirements for nuclear safety at nuclear facilities are fulfilled. On the basis of safety documentation evaluation, UJD issued permission for operation of four radioactive waste management facilities. Nuclear facility 'Technologies for treatment and conditioning contains bituminization plants and Bohunice conditioning centre with sorting, fragmentation, evaporation, incineration, supercompaction and cementation. Final product is waste package (Fibre reinforced container with solidified waste) acceptable for near surface repository in Mochovce. Republic repository in Mochovce is built for disposal of short lived low and intermediate level waste. Next

  2. Monitoring of primary circuit and reactor of NPP A-1

    Prazska, M.; Majersky, M.; Rezbarik, J.; Sekely, S.; Vozarik, P.; Walthery, R.; Stuller, P.

    2005-01-01

    Nuclear Power Plant A-1 in Jaslovske Bohunice was commissioned in 1972. Heavy water moderated, carbon dioxide cooled channel type reactor was shut down after two accidents in 1977. During more serious second accident, the reduced coolant flow caused local overheating of the fuel and consequent damage/melting of the fuel channel. Both accidents had led to the damage of several fuel assemblies with extensive local damage of fuel claddings. As a consequence, the main cooling circuit was significantly contaminated by fission products and long-life alpha nuclides. The detailed monitoring of dose rates, smearable contamination and sampling of contamination was performed. Extended monitoring in reacto vessel, primary circuit pipes, turbo-compressors, steam generators, main valves, gas tanks and also heavy water system with collectors, coolers, distilling and purification station, pumps and valves was done. Appropriate devices and procedures for the monitoring and examination of the installations were prepared and applied. Obtained results will serve for the future planning of the decontamination and decommissioning works. The 3-D model of the reactor that had been developed as part of this Project proved invaluable for orientation, visualisation, planning and analysis of results. Dose rates were measured in the technological channels from the reactor hall floor to the bottom of the hot gas chamber in decrements of 1 m and 0.5 m. The highest absolute values of dose rates were found in channels located in the middle of the reactor (up to 1900 mGy/h in the active zone region). It is estimated that the total contaminated area of primary circuit equipment (pipework, steam generators and turbo-compressors) is some 48 000 m 2 . It follows that the total gamma contamination is of the order of 10 14 to 10 15 Bq and total alpha contamination 10 11 to 10 13 Bq. The total amount of deposits in the gas circuit is about 14.3 tons. (authors)

  3. VUEZ. Annual report 2003

    2005-01-01

    A brief account of activities carried out by the Vyskumny ustav energetickych zariadeni, a.s. (VUEZ) in 2003 is presented. These activities are reported under the headings: (1) Introductory address by the Chairman of the Board of Directors; (2) Mission and vision; (3) Basic data; (4) Product portfolio and customer services; (5) VUEZ - Quality mark; (6) Economic data; (7) Auditor's certificate; (8) Contact persons and addresses. In 2003, a number of important events took place in VUEZ. From the standpoint of international activities, a significant event was VUEZ involvement in the process or the preparation for the V-1 NPP decommissioning. VUEZ company became a subcontractor to the Consultant to the Project Management Unit who is an international Consortium consisting of Iberdrola Ingenieria Y Consultoria S.A., Electricite de France, Empresarios Agrupados Intemacional S.A. and Soluziona Ingenierfa S.A. In the field of experimental research, activities within the research and development project with IRSN Paris were successfully continuing. As to increasing the leak-tightness of NPP hermetic compartments, relevant works were executed at the Dukovany and Paks NPPs. For a business partner from Hungary, a project was initiated related to the manufacture and delivery of air locks. Predominant VUEZ capacities concentrated on Slovenske elektrarne, a.s. (SE) a.s. Company in the Jaslovske Bohunice and Mochovce sites. In addition to major sealing works and periodical integrated leakage rate tests at individual reactor units, VUEZ participated also in the upgrading of the V-2 NPP. Design work was implemented through ADVING, a daughter company of VUEZ; erection and installation works within the project were performed by relevant VUEZ departments during refuelling outages at the V-2 NPP

  4. Composite ion-exchangers and their possible use in treatment of low/intermediate level liquid radioactive wastes

    Sebesta, F.; Motl, A.; John, J.

    1993-01-01

    A new method of preparation of composite inorganic-organic ion exchangers using modified polyacrylonitrile (PAN) as a binding polymer for the inorganic active component is described. This method enables incorporation of very fine to colloidal particles of active component in the binding polymer which increases the capacity and improves the kinetics of ion exchange of the resulting absorber. The proposed method can be applied on most of the inorganic ion exchangers known. Results of tests of some absorbers for treatment of radioactive wastes produced in the nuclear industry are given. For the removal of radiocesium from Long Term Fuel Storage Pond water at NPP Jaslovske Bohunice (Slovakia) NiFC-PAN composite ion exchanger has been tested. Excellent results have been achieved both at low and high (floating bed) flow rates in the course of treatment of up to 45,000 BV of pond water. The possibility of decreasing the total activity of the Biological Shield water from the same NPP below the 37 Bq/l discharge limit has been proved using NiFC-PAN and NaTiO-PAN composite ion exchangers. NiFC-PAN, NaTiO-PAN, MnO-PAN, M315-PAN and Na-Y-PAN composite ion exchangers were tested for removal of radiocesium, radiocobalt and radiomanganese from standard liquid radioactive wastes and concentrates from NPP Krsko, Croatia. Different combinations of absorbers have been tested for the treatment of Boron Recycle Hold-up, Waste Condensate and Waste Hold-up Tanks. Radium could be quantitatively removed from highly saline acid waste water from uranium underground leaching on Ba(Ca)SO 4 -PAN absorber

  5. Review of decommissioning, spent fuel and radwaste management in Slovakia

    Jamrich, J.

    2000-01-01

    Two nuclear power plants with two WWER reactors are currently under operation in Jaslovske Bohunice and NPP A-1 is under decommissioning on the same site. At the second nuclear site in the Slovak Republic in Mochovce third nuclear power plant with two units is in operation. In accordance with the basic Slovak legislation (Act on Peaceful Utilisation of Nuclear Energy) defining the responsibilities, roles and authorities for all organisations involved in the decommissioning of nuclear installations Nuclear Regulatory Authority requires submission of conceptual decommissioning plans by the licensee. The term 'decommissioning' is used to describe the set of actions to be taken at the end of the useful life of a facility, in order to retire the facility from service while, simultaneously, ensuring proper protection of the workers, the general public and the environment. This set of activities is in principle comprised of planning and organisation of decommissioning inclusive strategy development, post-operational activities, implementation of decommissioning (physical and radiological characterisation, decontamination, dismantling and demolition, waste and spent fuel management), radiological, aspects, completion of decommissioning as well as ensuring of funding for these activities. Responsibility for nuclear installations decommissioning, radwaste and spent fuel, management in Slovakia is with a subsidiary of Slovak Electric called Nuclear Installations Decommissioning Radwaste and Spent Fuel Management (acronym SE VYZ), established on January 1, 1996. This paper provides description of an approach to planning of the NPP A-1 and NPPs with WWER reactors decommissioning, realisation of treatment, conditioning and disposal of radwaste, as well as spent fuel management in Slovakia. It takes into account that detail papers on all these issues will follow later during this meeting. (author)

  6. Prophylactic and thermovision measurements of electric machines and equipment

    Jedlicka, R.; Brestovansky, L.

    1996-01-01

    High-voltage measurements of generators, unit and service transformers and some significant motor drives used at a nuclear power plant are described in this paper. Thermovision measurements of electric machines and distribution systems are dealt with in the second part of the paper. Power electric equipment represent one of the most significant components of a nuclear power plant. Turbine mechanical energy is converted into the electrical energy within these equipment. Power generated by generators is transformed by transformers so that it can achieve appropriate parameters for both the transmission over the distribution system and the power plant service power supply. The service power supply switchboards and cables provide supply to motors and other consumers necessary for the nuclear power plant technological process. The whole complex of equipment has to be maintained in good technical conditions. It is necessary to make thermovision and prophylactic measurements to identify and verify the electric equipment technical condition. The mentioned measurements warn the operation staff in advance against both gradual deterioration of power connection contact resistances, i.e. power connections overheating, and the machine insulation systems condition deterioration. The operation staff try to prevent the electric equipment operation accidents by early removing the detected failures, thus, improving the nuclear safety. In order to provide the above-mentioned activities a special prophylactic measurement group was established at the NPP Bohunice in 1983. The group specialists make following types of measurements. 1. Prophylactic measurements of electric machines. Prophylactics of 220 MW generators and 6 MW service power generators; Prophylactics of both unit and service transformers and VHV bushings; Prophylactics of major 6 kV motor drives. 2. Thermovision measurements of current connections. Measurements enumarated in paragraph 1 are made on disconnected electric

  7. Living near a nuclear power station

    Marcan, P.; Slovak, K.

    2007-01-01

    The need to expand nuclear power and its advantages are discussed publicly nearly each week. According to politicians and the nuclear lobby investing tens of billions Sk at Mochovce will bring Slovakia the often cited 'independence and energy self-sufficiency'. It will also mean profit for Slovenske elektrarne and the company's shareholders - the state and Italian company, Enel. In addition to the lively discussion on the pros and cons of nuclear energy, TREND was also interested in the living conditions around the concrete and strictly guarded, potentially dangerous plants and in the opinion of the people most affected by Mochovce and Jaslovske Bohunice on expansion of the existing and the building of new nuclear power plants. The construction of nuclear powers stations in these regions was not only about new jobs. The state 'prescribed' iodine pills and did not allow any construction in the region and, in the case of Mochovce, ordered the complete demolition of a village. The only thing that remained from Mochovce village was the church. 'And when it was found that the power plant would not reach it, it was even given a new roof. Former inhabitants, especially the older ones that had problems accepting the evacuation, used to visit it often,' explained Jan Foldy, the head of the local municipality in Kalna nad Hronom. After many years, life in the neighbouring villages is not bad. Their budgets are overflowing and so they can afford to spoil their inhabitants with free cable TV and high standard sport facilities, which should partly compensate for the fact that the people are living so close to a nuclear facility. (authors)

  8. Experimental lysimetric device NPP A-1

    Matusek, I.; Plsko, J.

    2002-01-01

    In the frame of decommissioning of the NPP A-1 in the locality Jaslovske Bohunice the problem of remedial measures in scope of radioactive contaminated soils is also studied. These soils have originated in the area of the NPP A-1 by different mechanisms as the result of leakages from technology and in the present time they represent the secondary source of contamination of underground waters. Contaminated soils represent the particularity, because we can characterize them as voluminous radioactive contaminated residues with low-level or very low-level activity. EKOSUR Company in the frame of active underground water protection suggested more remedial measures. Two basic tasks are solved in the field of the contaminated soils: rehabilitation of contaminated soils or temporary immobilisation of radionuclides in the contaminated volumes, deposition of rehabilitated soils in the storage of landfill type. In the frame of engineering solution of the landfill storage the question of technology of own deposition of contaminated soils into storage area is important from the safety viewpoint. Therefore the Experimental lysimetric device was built for half-operational test of suggested technologies. This device contains 6 pieces of lysimeters with 6 active volumes of approximately 1 cubic meter. The aim of suggested and in the present time realised experiments is the practical modelling of influence of filtering of waters into storage of contaminated soils in configurational and qualitative different conditions of deposition of soils (for example exploitation of sorption materials). Also the structure of un-rehabilitated soils by the influence of natural downfalls activity is modelled in one lysimeter. In this issue the authors deal with the construction of lysimetric device, proposed experiments as like as gained results of observations. (authors)

  9. The V-1 NPP and V-2 NPP upgrading

    1998-01-01

    A brief account of activities in the V-1 NPP and V-2 NPP upgrading as well as maintenance carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. The V-1 NPP applied the so called 'Small Backfitting Programme'covering 81 points of the Czechoslovak Atomic energy Commission Decree No 5/91. Continual upgrading continued after the Backfitting Programme completion with the Safety Report and following Nuclear Regulatory Authority of Slovak Republic (NRA SR) Decrees No 1/94 and 110/94 setting spheres and procedure for adopting and implementation of measures enabling the units to operate further on. Results of expert missions, analyses and assessments of components identified by Basic Engineering became the basis for the development of the Gradual Reconstruction Programme. The Programme outputs underwent economic and probabilistic assessing their contribution to nuclear safety. This process resulted in finalizing the Gradual Reconstruction Programme which started to be implemented in 1996 and will be completed in 1999. It is implemented by the REKON consortium and covers 17 areas including Instrumentation and Control, self-consumption emergency supply, leakage monitoring, emergency core cooling system, seismic reinforcement and radioactivity localisation. Both units will reach internationally acceptable safety standards for the remaining life-time period. The V-2 NPP Upgrading and Safety Enhancement Programme includes results of activities performed in the course of last years to define all important activities leading to enhancement of nuclear safety and performance reliability and effectiveness within the plant life-time period and to establish conditions for extending the life-time of these units for 40 years. The V-2 NPP Upgrading and Safety Enhancement Programme aims to assure safe operation with a probability of the core damages less than 10 -4 /reactor · year

  10. Chapter 7. Radioactive wastes

    2000-01-01

    The inspection and assessment activities of Nuclear Regulatory Authority of the Slovak Republic (UJD) focused on minimization of activity and the quantity of produced radioactive waste (RAW), and on increasing safety of waste management. The general scheme of rad-waste management in the Slovak Republic is presented. The radioactive wastes produced during the operation of NPP V-1, NPP V-2 and NPP Mochovce in 1999 are listed.Liquid RAW was treated and conditioned into a solid form at the nuclear facility Technology for treatment and conditioning of RAW. In 1999 combustible solid waste was treated at the nuclear facility Incinerator of VUJE Trnava. Produced liquid and solid RAW are stored at designed equipment at individual nuclear installations (in case of NPP V-1, NPP V-2 Bohunice and NPP Mochovce in compliance with the Regulation No. 67/1987 Coll. law).The status of free capacity of these storages as of 31.121999 is presented. Storage solidified product built the SE-VYZ was fully filled at the end of 1999. In 1999 there was a significant improvement in the process of radioactive waste management by: (A) issuing approval for commissioning the National Repository for RAW, (B) issuing approval for commissioning the Treatment and Conditioning Center for RAW, (C) having the application for approval to transport conditioned RAW to the National repository Mochovce in the final stage of evaluation. At the beginning of 2000 it is realistic to expect that RAW conditioned in the Conditioning center of RAW will start to be disposed at the National repository of RAW in Mochovce

  11. Radiological characterisation of contaminated concretes from the object 44/20 of NPP A1

    Slavik, O.; Listjak, M.; Pely, I.; Soos, F.

    2005-01-01

    Results of radiological characterisation of contaminated concretes from object 44/20 of the NPP A-1 Jaslovske Bohunice are summarized in this work. These works were carried out in VUJE in the laboratory of environmental dosimetry in 2004 and partially in 2005. The main results of radiological characterisation can be summarised as follow: (1) Contamination of concretes is in all cases surficial, it reaches up to 5-10 mm, the dominant contaminant is 137 Cs; (2) The spawn concrete is mostly contaminated only from one side (one being adjacent to the ceiling concrete), crucial part of them is even on this side contaminated in very low level complying with free release level; (3) The ceiling concrete blocks are contaminated mostly on one side, only (the inner side of shafts), their decontamination will require removing of about 5 mm thick surface layer. (4) The floor concrete is covered by heavily contaminated dust 137 CS, 100-500 Bq/g), originating from sorting of the wet RAW .Its decontamination will require removing of 10 mm thick surface concrete layer; (5) The core samples taken from the whole depth profile of the ceiling concrete show also only surface contamination, samples prepared from the deeper layers have not demonstrated any contamination in these layers. Control measurements of deeper concrete layers, however, went on with negative results also in year 2005; (6) The relative content for 90 Sr in these concretes is in average about 8%, for 241 Am determined by gamma-spectrometry is 0.4% and for 239 , 240 Pu determined radiochemically is 0.33% in comparison with the content of 137 Cs. (authors)

  12. Radioactive waste management at WWER type reactors

    1993-05-01

    This report was prepared within the framework of the Technical Assistance Regional Project on Advice on Waste Management at WWER Type Reactors, which was initiated by the IAEA in 1991. The Regional Project is an integral part of the IAEA's activities directed towards improvement of the safety and reliability of nuclear power plants with WWER type reactors (Soviet designed PWRs). Forty-five WWER type units are currently in operation and twenty-five are under construction in Bulgaria, Czechoslovakia, Finland, Hungary and the former USSR. The idea of regional collaboration between eastern European countries under the auspices of the IAEA was discussed for the first time during the last meeting of the Council for Mutual Economic Assistance (CMEA) on spent fuel and radioactive waste management, held in Rez, Czechoslovakia, in October 1990. Since then, the CMEA and some of its former Member States have ceased to exist. However, there are many reasons for eastern European countries to continue their regional collaboration at a higher level. The USSR, the designer and supplier of WWER type reactors in eastern European countries, participated in the first phase of the project. The majority of WWER type reactors are situated in States of the former USSR (Russia and Ukraine). The main results of the first phase of the Regional Project are: (i) Re-establishment of communication channels among eastern European countries operating WWER type reactors by incorporating the IAEA's technical assistance; (ii) Identification of common waste management problems (administrative and technical) requiring resolution; (iii) Familiarization with radioactive waste management systems at nuclear power plants with WWER type reactors - Paks (Hungary), Loviisa (Finland), Jaslovske Bohunice (Czechoslovakia) and Novovoronezh (Russian Federation). Tabs

  13. Chapter No.9. Emergency planning

    2002-01-01

    Emergency preparedness is a set of measures the aim of which is to mitigate possible impacts of events during the operation of nuclear facilities, transport of nuclear materials and radioactive waste as well as to reduce consequences to environment and population. An emergency planning of UJD is understood as an establishment of technical and organisational means determined for prognosis of development of events having radiation consequences together with capability to suggest the countermeasures needed to minimise the impact to population. Emergency Response Centre (ERC) of UJD is a technical support tool of UJD and at the same time it fulfils the role of advisory body for the National Emergency Commission for Radiation Accidents (NECRA) In 2001 UJD continued in further increase of equipment quality in the ERC by completion of facilities necessary to transmit necessary data from nuclear facilities, for communication and other HW and SW means. That it is why the application of geographic information systems (GIS), higher quality of data transmission from nuclear facilities and installation of new database platform could be enabled. Also the documentation of ERC has been completed by the emergency procedures of NPP Mochovce and guides of the RODOS system were finished. In the area of emergency preparedness UJD activities in 2001 were focused on preparation and realisation of emergency exercises and execution of inspections. In accordance with the inspection plan inspectors executed several inspections which were targeted to control the course of exercises at nuclear facilities, documentation and the way of training of members of the UJD headquarters. The function of systems of notification and warning, communication, monitoring and technical support means of both NPP Bohunice and NPP Mochovce has been verified and checked as well. The ultimate attention, however, was paid to the preparation of UJD emergency headquarters. The preparation was realised in a form of

  14. Needs for European decommissioning academy (EDA)

    Slugen, Vladimir

    2014-01-01

    According to analyses presented at EC meeting focused on decommissioning organized at 11.9.2012 in Brussels, it was stated that at least 500 new international experts for decommissioning will be needed in Europe up to 2025, which means about 35 per year. Having in mind the actual EHRO-N report from 2013 focused on operation of nuclear facilities and an assumption that the ratio between nuclear experts, nuclearized and nuclear aware people is comparable also for decommissioning, as well as the fact that the special study branch for decommissioning in the European countries almost does not exist, this European Decommissioning Academy (EDA) could be helpful in the over-bridging this gap. The main goal is - from about 74% of nuclearized experts (graduated at different technical Universities and increased their nuclear knowledge and skills mostly via on-job training and often in the area of NPP operation) to create nuclear experts for decommissioning via our post-gradual coursed organized in two semester study at our Academy, which will include the lessons, practical exercises in our laboratories, on-site training at NPP V-1 in Jaslovske Bohunice, Slovakia as well as 3 days technical tour to JAVYS (Slovakia), UJV Rez (Czech Rep.) and PURAM (Hungary), respectively. Beside the exams in selected topics (courses), the final thesis written under supervision of recognized experts will be the precondition for graduation and certification of the participants. For the first run of the EDA scheduled on 2014 we would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future in Europe. The growing decommissioning market creates a potential for new activities, with highly skilled jobs in an innovative field, involving high-level technologies. A clear global positioning of the EU will stimulate the export of know-how to

  15. Deposition of 60Co and 137Cs adsorbed on zeolite in matrices on the blast furnace slag

    Foeldesova, M.; Lukac, P.; Dillinger, P.

    1995-01-01

    The experimental data (leaching tests and compressive strength measurements) are presented for case the radionuclides from model water solution and radioactive waste water were uptake on natural and chemically modified granular zeolitic tuffite which show improved sorption ability and were subsequently incorporated into cement casts on blast furnace slags (BSF) basis. The all experiment were carried out with zeolite tuffite from Nizny Hrabovec, Slovak Republic. The natural zeolite was treated by the NaOH solution. The blends of individual components were casted into rectangular prism moulds (1 x 1 x 3 cm). The cast consisted invariably of 90% of BSF, 10% of fine zeolite and solution of water glass and to this basic mixture were added either 10 or 20% granular active, or non active zeolite during the mix formation, in excess to content of previous solid components. The water/cement ratio varied in interval 0.32-0.40. Model solutions labelled by cesium-137 or cobalt-60 have been used for sorption experiment and real waste water concentrate from NPP Jaslovske Bohunice as well. The real water consisted of cesium-134, cesium-137, cobalt-60, in borate and nitrate form. The radioactivity of dry cement casts was measured in 4π geometry. The leaching experiments were performed in three solutions: water (W), 0.03 M HCl (A) and 0.04 M NaOH (B). The mechanical properties of sample with non active granular zeolites and their corrosion characteristics as reflected by the bulk density changes. The experiments showed that leaching of radionuclides, which were sorbed from solution and radioactive waste water, in water and bases solution were negligible. Changes of radioactivity of casts, prepared from model solution, in acid solution, which were less than 5%. The mechanical strength of prepared composites is favourable and shows good compatibility of zeolitic additives with a basic matrix. Leaching experiments and mechanical strength are hopeful and show good retention of observed

  16. Severe accident management development program for VVER-1000 and VVER-440/213 based on the westinghouse owners group approach

    Felix, E.; Dessars, N.

    2003-01-01

    The development of the Westinghouse Owners Group Severe Accident Management Guidelines (WOG SAMG) between 1991 and 1994 was initiated in response to the U.S. Nuclear Regulatory Commission (NRC) requirement for addressing the regulatory severe accident concerns. Hence, the WOG SAMG is designed to interface with other existing procedures at the plant and is used in accident sequences that have progressed to the point where these other procedures are not applicable any longer, i.e. following core damage. The primary purpose of the WOG SAMG is to reach a controlled stable state, which can be declared when fission product releases are controlled, challenges to the confinement fission product boundary have been mitigated, and adequate heat removal is provided to the core and the containment. Although the WOG SAMG is a generic severe accident management guidance developed for use by the entirety of the operating Westinghouse PWR plants, provisions have been made in their development to address specific features of individual plants such as confinement type and the feasibility of reactor cavity flooding. Similarly, the generic SAMG does not address unique plant features and equipment, but rather allows for consideration of plant specific features and strategies. This adaptable approach has led to several SAMG development programs for VVER-1000 and VVER-440 type of power plants, under Westinghouse' s lead. The first of these programs carried out to completion was for Temelin NPP - VVER-1000 - in the first quarter of 2003. Other ongoing programs aim at providing a similar work for VVER-440 design, namely Dukovany, Mochovce and Bohunice NPPs. The challenge of adapting the existing generic WOG material to plants other than PWRs mainly arises for VVER-440 because of important differences in confinement design, making it more vulnerable to ex-vessel phenomena such as hydrogen burn. Also, for both eastern designs, cavity flooding strategy requires special consideration and

  17. IAEA meeting report of the consultants' meeting on safety improvements of WWER-440 model 230 nuclear power plants

    1998-05-01

    In 1992 the identification and ranking of safety issues for WWER-440/230 NPPs were completed. Some 100 safety issues have been identified and ranked according to their safety impact on the plant's defence in depth. The IAEA work was based on a conceptual design review and a series of safety review missions to each one of the four sites (Bohunice, Kozloduy, Novovoronezh and Kola) where WWER-440/230 NPPs were in operation. Results were published by the IAEA in February and May 1992. Since the initial publications the IAEA has continued its activities and conducted a number of follow-up missions and technical visits to the NPP sites to review the status of implementation of safety upgradings. In September of 1994 a Consultants Meeting (CM) was held in Vienna to consolidate all the information available to the AEA. The results of that meeting were included in the report WWER-SC-107. During 1995-1997 further information became available from technical visits conducted by the IAEA at the four sites. Therefore, in February 1998 the IAEA convened a CM in Vienna to prepare an up-to-date report on the status of safety improvements at WWER-440/230 NPPs. This report contains the results of that meeting. It reviews the status of remedial actions implemented at each plant in response to the safety issues originally identified in the IAEA reports and the remaining safety concerns. For convenience the issues are presented under broad titles related to: integrity of barriers (Section 2); performance of basic functions (Section 3); performance of supporting functions (Section 4); internal hazards (Section 5); external hazards (Section 6); accident analysis (Section 7); operational functions (Section 8); Section 9 provides an overview of the results of PSA studies performed and under way. Section 10 provides specific information on the status of Armenia NPP. It is presented separately because the IAEA assistance to this plant was provided in the framework of the national technical co

  18. Status and prospects of the core surveillance system SCORPIO-VVER in Czech Republic and Slovakia

    Molnar, J.; Vocka, R.

    2011-01-01

    The SCORPIO-VVER core monitoring system has proved since the first installation at Dukovany NPP in 1999 to be a valuable tool for the reactor operators and reactor physicists. It is now installed on four units of Dukovany NPP (Czech Republic) and two units of Bohunice NPP (Slovak Republic) replacing the original Russian VK3 system. By both Czech and Slovak nuclear regulatory bodies it was licensed as a Technical Specification Surveillance tool. Since it's first installation, the development of SCORPIO-VVER system continues along with the changes in WWER reactors operation. The system is being adapted according the utility needs and several notable improvements in physical modules of the system were introduced. The latest most significant changes were done in connection with implementation of a new digital I and C system, loading of the optimized gadolinium bearing Gd2 fuel assemblies, improvements in the area of core design (neutron physics, core thermal hydraulics and fuel thermal mechanics), adaptation of the system to up-rated unit conditions, in design and methodology of the limit and technical specifications checking (implementation of the on-line shutdown margin calculation to the system) and improvements in the predictive part of the system (Strategy Generator). After the currently finished upgrades (Upgrade 2 at EBO Slovakia in 2009, Upgrade 5 at EDU Czech Republic in 2010) the SCORPIO-VVER is still in focus of Central European nuclear power plants with the road map of modification and implementation up to 2015. In April 2011 the Upgrade 3 at EBO Slovakia has been contracted to support the changed reactor technical specification and for support of the new type of fuel planned to load in 2012. During the summer of 2011 the discussions started with EDU NPP in Czech Republic regarding to the future development of the SCORPIO-VVER system up to 2015. Parallel with the support of current installations at NPPs the project of new installations is ongoing. During

  19. Low level radioactive waste disposal

    Balaz, J.; Chren, O.

    2015-01-01

    The Mochovce National Radwaste Repository is a near surface multi-barrier disposal facility for disposal of processed low and very low level radioactive wastes (radwastes) resulting from the operation and decommissioning of nuclear facilities situated in the territory of the Slovak Republic and from research institutes, laboratories, hospitals and other institutions (institutional RAW) which are in compliance with the acceptance criteria. The basic safety requirement of the Repository is to avoid a radioactive release to the environment during its operation and institutional inspection. This commitment is covered by the protection barrier system. The method of solution designed and implemented at the Repository construction complies with the latest knowledge and practice of the repository developments all over the world and meets requirements for the safe radwaste disposal with minimum environmental consequences. All wastes are solidified and have to meet the acceptance criteria before disposal into the Repository. They are processed and treated at the Bohunice RAW Treatment Centre and Liquid RAW Final Treatment Facility at Mochovce. The disposal facility for low level radwastes consists of two double-rows of reinforced concrete vaults with total capacity 7 200 fibre reinforced concrete containers (FCCs) with RAW. One double-row contains 40 The operation of the Repository was started in year 2001 and after ten years, in 2011 was conducted the periodic assessment of nuclear safety with positive results. Till the end of year 2014 was disposed to the Repository 11 514 m 3 RAW. The analysis of total RAW production from operation and decommissioning of all nuclear installation in SR, which has been carried out in frame of the BIDSF project C9.1, has showed that the total volume estimation of conditioned waste is 108 thousand m 3 of which 45.5 % are low level waste (LLW) and 54,5 % very low level waste (VLLW). On the base of this fact there is the need to build 7

  20. Polish media and public opinion on NPP Mochovce commissioning

    Latek, Stanislaw

    1999-01-01

    The so called 'Mochovce Problem' was one of the major topics in Polish media in the period from May to July 1998. The nuclear power plant commissioning caused an unexpectedly strong reaction, especially in the newspapers, slightly less so in electronic media. Faced with clearly hostile media reaction to Mochovce NPP, the National Atomic Energy Agency representatives, together with atomic and nuclear experts, undertook to change these attitudes. In numerous interviews, letters to the editors and talks with journalists, they attempted to correct the mistakes, explain the true safety situation in the nuclear power plant, by whom it was constructed, who supervised and tested the systems and so on. The completion of Mochovce NPP construction improved significantly the electricity balance in Slovakia, thus decreasing the pressure for continuing the operation of older Bohunice V1 units beyond their design lifetime. For this reason, as well as in view of striving for improvement in environmental factors beyond Polish southern border, especially after Kyoto/97 decisions on greenhouse gases emissions, the public opinion in Poland should support the Mochovce NPP construction. In 1996 Poland has signed with Slovakia a bilateral inter-governmental agreement on the prompt notification on nuclear accidents and on the cooperation in the nuclear safety and radiological protection matters. On the basis of this agreement the experts from Polish National Atomic Energy Agency are in perpetual contact with Slovakian Nuclear Regulatory Body and in each and every moment can obtain full and comprehensive information on the plant parameters iportant for nuclear safety. The experts explanations, together with the NAEA top management visit to the plant itself, brought some results. The media became less aggressive, and Polish public and authorities - contrary to the Austrians - do not protest loudly against the commissioning of this newest European NPP. Now, in December 1998, the tune of

  1. Decommissioning of NPP A1 - HWGCR type

    Burclova, J.

    1998-01-01

    Prototype nuclear power plant A-1 located at Jaslovske Bohunice, was a HWGCR with channel type reactor KS 150 (refuelling during operation) and capacity of 143 MWe. Single unit has been constructed with reactor hall building containing reactor vessel, heavy water system and equipment for spent fuel handling. Another compartment of main building contents coolant system piping, six steam generators and six turbo compressors, the turbine hall was equipped by three turbines. Unit also shares liquid radwaste treatment and storage buildings and ventilation systems including chimney. It started operation in 1972 and was shutdown in 1977 after primary coolant system integrity accident. In 1979 a final decision was made to decommission this plant. The absence of waste treatment technologies and repository and not sufficient storage capacity affected the planning and realization of decommissioning for NPP A-1. The decommissioning policy for the first stage is for lack of regulations based on 'case by case' strategy. For these reasons and for not existence of Decommissioning Found until 1995 the preferred decommissioning option is based on differed decommissioning with safe enclosure of confinement. Transfer of undamaged spent fuel cooled in organic coolant to Russia was finished in 1990. It was necessary to develop new technology for the damaged fuel preparation for transport. The barriers check-up and dismantling of secondary circuit and cooling towers was performed during 1989/90. The complex plan for the first phase of A-1 decommissioning - the status with treated operational radwaste, removed contamination and restored treated waste and spent fuel (in case of interruption of transfer to Russia) was developed in 1993-1994. Under this project bituminization of all liquid operational radwaste (concentrates) was performed during 1995/96, vitrification of inorganic spent fuel coolant started at 1996, decontamination of spent fuel pool coolant occurs (under AEA Technology

  2. VUJE

    Anon

    2006-01-01

    The year 2006 presents a continuing successful development of the company aimed at complex services for the energy. At the end of 2006 our company will have celebrated the thirtieth anniversary of a self-existent Nuclear Power Plant Research Institute (VUJE), which was established on January 1, 1974 by the Czechoslovak Federal Ministry of Fuel and Power. On this occasion we can assert that a way of preservation of the institute and later its existence as the incorporation with the activities to manage all the activities of nuclear power plant was a good choice. Our company has shown during its 30-year existence that it is able to preserve the commenced trend to be a significant engineering company in the field of energy and it has confirmed continuously its image of modern, flexible and viable company. Our prosperity has been based on the prosperity of our clients and on our ability to offer and realise top technical solutions that will provide economic, reliable and safe operation of the devices in energy. In the past including 2006 our company has been realising the most important projects in Slovak energy as Modernization of Bohunice V-2, Technology of medium and low-level radioactive treatment for Mochovce nuclear power plant, the Reconstruction oj Krizovany substation. Our success has been achieved thanks to our employees, their knowledge, qualitative products and modern technologies. Regarding the approaching the thirtieth anniversary of our institute we have to take into consideration that the success of our company depends on the collective work of all employees and their activities. Therefore it is obvious that in the 2006 we have been continuing in the improvement of social security scheme of our employees and in the process of increasing of their qualifications. A story of our company is the story of a successful firm, which managed to hold its own trend under difficult economic conditions of the last time. I believe in a well done joint realisation of

  3. The Inspector General's report on Nuclear Safety and Radiation Protection 2008

    2009-01-01

    abroad; 20.1 - Japan: Kashiwasaki-Kariwa and Hamaoka power plants, the JSW casting and forging facilities at Muroran; 20.2 - Slovakia: Slovenske Elektrarne, Bohunice and Mochovce nuclear power plants; 20.3 - The USA: Constellation Energy, Calvert Cliffs nuclear power plant and Unistar Nuclear Energy; 21 - Appendices

  4. Deposition of {sup 60}Co and {sup 137}Cs adsorbed on zeolite in matrices on the blast furnace slag

    Foeldesova, M; Lukac, P; Dillinger, P [Slovak Technical Univ., Bratislava (Slovakia)

    1996-12-31

    The experimental data (leaching tests and compressive strength measurements) are presented for case the radionuclides from model water solution and radioactive waste water were uptake on natural and chemically modified granular zeolitic tuffite which show improved sorption ability and were subsequently incorporated into cement casts on blast furnace slags (BSF) basis. The all experiment were carried out with zeolite tuffite from Nizny Hrabovec, Slovak Republic. The natural zeolite was treated by the NaOH solution. The blends of individual components were casted into rectangular prism moulds (1x1x3 cm). The cast consisted invariably of 90% of BSF, 10% of fine zeolite and solution of water glass and to this basic mixture were added either 10 or 20% granular active, or non active zeolite during the mix formation, in excess to content of previous solid components. The water/cement ratio varied in interval 0.32-0.40. Model solutions labelled by cesium-137 or cobalt-60 have been used for sorption experiment and real waste water concentrate from NPP Jaslovske Bohunice as well. The real water consisted of cesium-134, cesium-137, cobalt-60, in borate and nitrate form. The radioactivity of dry cement casts was measured in 4{pi} geometry. The leaching experiments were performed in three solutions: water (W), 0.03 M HCl (A) and 0.04 M NaOH (B). The mechanical properties of sample with non active granular zeolites and their corrosion characteristics as reflected by the bulk density changes. The experiments showed that leaching of radionuclides, which were sorbed from solution and radioactive waste water, in water and bases solution were negligible. Changes of radioactivity of casts, prepared from model solution, in acid solution, which were less than 5%. The mechanical strength of prepared composites is favourable and shows good compatibility of zeolitic additives with a basic matrix. Leaching experiments and mechanical strength are hopeful and show good retention of observed

  5. Analysis of the similarity factors of the villages in the areas of the nuclear power plants from the premature death-rate performed by fuzzy logic method

    Letkovicova, M.; Rehak, R.; Korec, J.; Mihaly, B.; Prikazsky, V.

    1998-01-01

    Our paper examines the surrounding areas of NPP from the proportion of premature death-rate which is one of the complex indicators of the health situation of the population. Specially, attention is focused on NPP in Bohunice (SE-EBO) which has been in operation for the last 30 years and NPP Mochovce (SE-EMO) which was still under construction when data was collected. WHO considers every death of the individual before 65 years of age a premature death case, except death cases of children younger that 1 year. Because of the diversity of the population, this factor is a standard for the population of Slovak Republic (SR) as well as for the european population. The objective of the work is to prove, that even a long term production of energy in NPP does not evoke health problems for the population living in the surrounding areas, which could be recorded through analysis of premature death cases. Using the fuzzy logic method when searching for similar objects and evaluating the influence of the NPP on its surrounding area seems more natural than classical accumulation method, which separates objects into groups. When using the classical accumulation method, the objects in particular accumulation group are more similar than 2 objects in different accumulation groups. When using the fuzzy logic method the similarity is defined more naturally. Within the observed regions of the NPP, the percentage of directly standardized premature death cases is almost identical with the average for the SR. The most closely observed region of SE-EMO up to 5 kilometers zone even shows the lowest percentage. Also we did not record any areas that would have unfavourable values from the wind streams perspective neither than from the local water streams recipients of SE-EBO Manivier and Dudvah. The region of SE-EMO is also within the SR average, unfavourable coherent areas of premature death case are non existent. Galanta city region comes out of the comparison with the relatively worse

  6. Operating results of 220 MW SKODA saturated steam turbines

    Drahy, J.

    1992-01-01

    One of the steam turbines produced by the SKODA Works, the 220 MW steam turbine for saturated admission steam of a speed of 3000 r.p.m. is described; it is used in nuclear power plants with 400 MW PWR type reactors. 16 units of 8 turbines each have been in operation in the Jaslovske Bohunice and Dukovany power plants with the total period of operation of all machines exceeding 750,000 hours. The 220 MW steam turbine consists of a two-flow high-pressure section and of two identical two-flow low-pressure sections. The pressure of saturated steam at the inlet of the high-pressure section is 4.32 MPa (the corresponding temperature of the saturation limit being 255 degC) and during the expansion in the high-pressure section it drops to 0.6 MPa; steam moisture reaches 12%. In a separator and two-stage reheater using blend steam, the steam is freed of the moisture and is reheated to a temperature of 217 degC. Some operational problems are discussed, as are the loss of the material of the stator parts of the high-pressure section due to corrosion-erosion wear and corrosion-erosion wear of the guide wheels of the high-pressure section, and measures are presented carried out for the reduction of the corrosion-erosion effects of wet steam. One of the serious problems were the fatigue fractures of the blades of the 4th high-pressure stage, which appeared after 20 000 to 24 000 hours of operation in the dented tee-root. The guide wheels of the 4th stage were substituted by new guide wheels with uniform pitch of the channels and with increased number of guide blades. Also discussed are the dynamic behavior of the low-pressure section of the bridge structure, the operating reliability and the heat off-take for water heating of long-distance heating systems. (Z.S.) 9 figs

  7. Chapter No.4. Safety analyses

    2002-01-01

    In 2001 the activity in the field of safety analyses was focused on verification of the safety analyses reports for NPP V-2 Bohunice and NPP Mochovce concerning the new profiled fuel and probabilistic safety assessment study for NPP Mochovce. The calculation safety analyses were performed and expert reviews for the internal UJD needs were elaborated. An important part of work was performed also in solving of scientific and technical tasks appointed within bilateral projects of co-operation between UJD and its international partnership organisations as well as within international projects ordered and financed by the European Commission. All these activities served as an independent support for UJD in its deterministic and probabilistic safety assessment of nuclear installations. A special attention was paid to a review of probabilistic safety assessment study of level 1 for NPP Mochovce. The probabilistic safety analysis of NPP related to the full power operation was elaborated in the study and a contribution of the technical and operational improvements to the risk decreasing was quantified. A core damage frequency of the reactor was calculated and the dominant initiating events and accident sequences with the major contribution to the risk were determined. The target of the review was to determine the acceptance of the sources of input information, assumptions, models, data, analyses and obtained results, so that the probabilistic model could give a real picture of the NPP. The review of the study was performed in co-operation of UJD with the IAEA (IPSART mission) as well as with other external organisations, which were not involved in the elaboration of the reviewed document and probabilistic model of NPP. The review was made in accordance with the IAEA guidelines and methodical documents of UJD and US NRC. In the field of calculation safety analyses the UJD activity was focused on the analysis of an operational event, analyses of the selected accident scenarios

  8. Chapter 12. Public information

    2001-01-01

    'Nuclear Power Engineering Safety' running substantial articles from major UJD activities. The double issues 7/8 and 11/12 (2000) included safety analyses - NPP V-1 Bohunice and NPP Mochovce units safety assessment. The monthly 'Verejna sprava' (Public Administration) ran in 2000 two substantial articles on UJD legislative and state law activities. Contributions on UJD regulatory activity and international co-operation appear on a regular basis in 'Spravodajstvo SE, a.s.' (SE, a.s., Newsletter) and in-house journals 'Mochovce' and 'Bohunice'. UJD domestic and foreign activities were published in 5 issues in 'Slovak Nuclear Society (SNUS) Bulletin'. A report on the safety of nuclear installations and the management of spent nuclear fuel and radioactive wastes in the Slovak Republic in the journal 'Nuclear Europe Worldscan' No. 7-8/2000 was also published the year 2000. A number of substantial articles were published in the magazine Energia. A contribution on UJD's mission and tasks in the Slovak Republic was published in 'Energia Almanach' 2000/2001. Six contributions focused on UJD's domestic and foreign activities were prepared for the world information agency NucNet. A Slovak-English information material on UJD (12/2000) was prepared and published for the public. Also the Slovak-English 1999 Annual Report on the results of UJD activity and nuclear installation safety in the Slovak Republic was prepared and published. In 2000, four press conferences were held at UJD, with follow-up appearances by UJD management in television and radio. UJD executives made five appearances in television and gave six interviews and seven relevant interviews for Slovak Radio and magazines and dailies, respectively. In 2000, two video-clips were produced for the public, namely on the 'UJD tasks and mission' and 'emergency planning'. A highly successful press conference on Slovakia's NPP safety was arranged by UJD on the occasion of the visit to Slovakia by the OECD/ Nuclear Energy Agency

  9. Separation of radionuclides using host-guest materials

    Drabova, V.

    2014-01-01

    This thesis is focused on the development of complex procedure with using commercially available sorbents to separate anthropogenic actinides 237 Np, 241 Am, 238 Pu and 239 , 240 Pu and their determination in the liquid radioactive wastes by using alpha spectrometry. Abilities of using commercially available sorbent AnaLig(R)Pu-02 gel from IBC Advanced Technologies, Inc. were tested, this product belongs to host-guest materials based on molecular recognition technology. This material is capable of selectively capturing actinides in oxidation state IV. To adjust the oxidation state of 238 Pu and 239 , 240 Pu was used NaNO 2 . Pu(IV) forms in the medium of nitric acid complexes, [Np(NO 3 ) 6 ] - , which are captured on the column. For the second monitored radionuclide, neptunium is typical valence V, Np(V) in the concentrated nitric acid produces strong complexes, [Np(NO 3 ) 6 ] - , which are capable of the sorption on the column of AnaLig(R)Pu-02 gel. The most common state of americium in aqueous solutions is III. Whereas in this oxidation state, americium do not form complexes in 8 mol·dm -3 nitric acid is the result of the flow-through. On the base of experimental obtained results, solution of 0.1 mol·dm -3 NH 4 I in 9 mol·dm -3 HCl was selected for elution of plutonium. Neptunium was eluted from the column using 9 mol·dm -3 of HCl with addition of 0.5 cm 3 TiCl 3 . Optimizing conditions for the separation procedure was performed by using model solution of radioactive waste which was prepared according to the chemical composition of radioactive concentrate from NPP Mochovce and NPP Bohunice. The effect of the concentration of Fe 3+ , the effect of the concentration of the HCl, the effect of the concentration of the solution of NH 4 I and the effect of the volume of this solution to the yields of 238 Pu were studied. And also was studied the effect of 9 mol·dm -3 of HCl and the effect of volume of 15 % TiCl 3 to the yields of 237 Np. Sorbent DGA(R) Resin from

  10. Temelin 3,4 Siting

    Kubanova, Iva; Fuzer, Jiri

    2011-01-01

    In the future the Czech Republic will need new energetic resources in spite of current decrease of electricity consumption due to economical crisis. Nuclear power generation is considered as important part of energetic mix of the Czech Republic and this opinion is newly reflected in new government official statement issued in August 2010. CEZ, a. s. prepares new nuclear power plants projects accordingly governmental expectations. Currently 3 projects are in preparation. Temelin 3, 4 project is in the most advanced status, tender is in progress. Potential construction of Dukovany unit 5 and new Jaslovske Bohunice units are analyzed in feasibility studies. Temelin 3, 4 project activities were started 4 years ago. Preparatory analyses, market investigation, feasibility study including many particular studies were elaborated in years 2006-2008. Later on decision to work on bid invitation specification was done and followed. EIA process was started in July 2008 by Intention Announcement and continues. Public tender for EPC contract was announced in August 2009 and it is in progress accordingly schedule. Siting process is in the initial stage. EIA process started in July 2008 through Intention Announcement in spite of anti - nuclear political climate in the Czech Republic. EIA process is interstate process, Austria and Germany participate. Investigation Process Protocol was issued by Ministry of Environment in February 2009 with 34 main conditions and 165 additional comments, requirements, statements. CEZ, a. s. adopted the positive approach with philosophy to deal with all conditions and requirements properly. Elaboration of EIA documentation took 18 months. In May 2010 CEZ, a. s. handed over the EIA documentation to the Ministry of Environment and consequently all legal steps followed including hand-over of EIA documentation to Austria and Germany. In next weeks and months all comments will be gathered by Ministry of Environment and relevant decisions and legal steps

  11. Final Treatment Center Project for Liquid and Wet Radioactive Waste in Slovakia

    Kravarik, K.; Stubna, M.; Pekar, A.; Krajc, T.; Zatkulak, M.; Holicka, Z.; Slezak, M.

    2006-01-01

    The Final Treatment Center (FTC) for Mochovce nuclear power plant (NPP) is designed for treatment and final conditioning of radioactive liquid and wet waste produced from plant operation. Mochovce NNP uses a Russian VVER-440 type reactor. Treated wastes comprise radioactive concentrates, spent resin and sludge. VUJE Inc. as an experienced company in field of treatment of radioactive waste in Slovakia has been chosen as main contractor for technological part of FTC. This paper describes the capacity, flow chart, overall waste flow and parameters of the main components in the FTC. The initial project was submitted for approval to the Slovak Electric plc. in 2003. The design and manufacture of main components were performed in 2004 and 2005. FTC construction work started early in 2004. Initial non-radioactive testing of the system is planned for summer 2006 and then radioactive tests are to be followed. A one-year trial operation of facility is planned for completion in 2007. SE - VYZ will be operates the FTC during trial operation and after its completion. SE - VYZ is subsidiary company of Slovak Electric plc. and it is responsible for treatment with radioactive waste and spent fuel in the Slovak republic. SE - VYZ has, besides of other significant experience with operation of Jaslovske Bohunice Treatment Centre. The overall capacity of the FTC is 870 m 3 /year of concentrates and 40 m 3 /year of spent resin and sludge. Bituminization and cementation were provided as main technologies for treatment of these wastes. Treatment of concentrate is performed by bituminization. Concentrate and bitumen are metered into a thin film evaporator with rotating wiping blades. Surplus water is evaporated and concentrate salts are embedded in bitumen. Bitumen product is discharged into 200 l steel drums. Spent resin and sludge are decanted, dried and mixed with bitumen. These mixtures are also discharged into 200 l steel drums. Drums are moved along bituminization line on a roller

  12. Role of Slovakia within the IAEA Decommissioning Related Activities

    Michal, V.; Stubna, M.

    2009-01-01

    Slovakia has a long-term experience with the IAEA decommissioning related activities as a recipient of Agency assistance and then as a country offering assistance to others. Background, short 'history' and current status of Slovakian national technical cooperation (TC) projects SLR/4/008 'Robotic Technologies for Decontamination and Decommissioning of the Bohunice A1 NPP' and SLR/3/002 'Management of Radioactive Waste from the A1 Nuclear Power Plant Decommissioning' will be described in paper. The first TC project SLR/4/008 was solved by the main Slovakian counterpart, company VUJE, Inc., from 2001 to 2006. Second TC project SLR/3/002 is ongoing with extension to 2011. Thanks to the implementation of a long-term large-scale 'Project of the A1 NPP Decommissioning - Stage I' (1996-2007), financed by Slovak National Nuclear Account (decommissioning fund), as well as implementation of the IAEA TC national projects a comprehensive know-how in the field of D and D and RAW management was obtained. Moreover, technologies and facilities necessary for implementation of decommissioning and RAW management projects were developed. Thanks to this development Slovakia offers donor assistance to other countries in subjected fields through IAEA TC program. The type and scope of assistance for Armenia, Bulgaria, Egypt, Latvia, Lithuania and The Ukraine is described in the paper. The above-mentioned national projects are not only activities of Slovakia within the IAEA TC program. Regional TC project RER/3/005 'Support in Planning the Decommissioning of Nuclear Power Plants and Research Reactors' has been ongoing from 2007 with accepted extension to 2011. About nine countries from Eastern and Central Europe participate in the project (for the NPPs part) and Slovakia plays the role of LCC (Leading Country Coordinator). On the basis of suggestion of Nuclear Regulatory Authority of the Slovak Republic, VUJE is the coordinator of the regional project. Moreover, Slovakia would be the

  13. Environmental report 2005

    Ruzzini, P.

    2006-01-01

    This is the tenth Environmental Report we have been regularly issuing annually since 1996 in order to give you information about our efforts and activities taken in the environmental protection area and, at the same time, to keep the mutual dialogue on a standard high level. The year 2005 was not easy for Slovenske elektrarne, a.s. Our company was subject to complicated internal changes to implement as effective company management model as possible. We strove, above all, to enhance the process management system that had already been developed previously. It is true that we also had to resolve personnel matters when looking for an effective power engineering company management model and we had to part from many of our colleagues during that stage. The second priority task we faced was to make preparations for the takeover of our company by the Italian company ENEL, S.p.A., and to complete the privatization process covering 66 % of Slovenske elektrarne, a.s., stock. It was especially the second half of 2005 that brought very intensive mutual discussions and working negotiations held on all management levels. The third, but not less significant, task consisted in detaching the assets which would not be covered by the privatization, namely to detach the Set of Gabcikovo Hydro Power Plants, to detach the VYZ - Decommissioning of Nuclear Installations, Radioactive Treatment and Spent Fuel Management Plant and the EBO V-1 Plant. Despite relatively complicated conditions and the opened and liberalized market in the Slovak Republic, our company produced 26,470,901 MWh of electricity whereby the target was met to 115.00 %. Our company kept the stability of the electric power supply system of the Slovak Republic, despite a complicated situation in the area of electric power supplies in Europe. We can really state that we produced in a safe, reliable, ecological and economical manner. The reliable operations of nuclear power plants in Jaslovske Bohunice and Mochovce where 17

  14. Bubbler condenser related research work. Present situation

    2001-02-01

    Intensive discussions within the OECD Support Group on 'VVER-440 Bubbler Condenser Containment Research Work' between 1991 and 1994 demonstrated the need for supplementary research work to achieve an adequate level of basic knowledge. In 1994, the European Commission (EC) asked for a specific 'VVER-440/213 Bubble Condenser Qualification Feasibility Study', which was finished early in 1996, confirming the need for additional research in this field. The Feasibility study formed the basis for the Bubble Condenser Experimental Qualification Project (BCEQ) with two separate experimental activities to be executed within the frame of the PHARE/TACIS 2.13/95 project of the European Commission. A first activity served to study the thermal-hydraulic phenomena and the associated structure dynamic interactions. This part of the project was performed at EREC, in Elektrogorsk, Russia. The design of the test facility was based on the prototypical bubbler condenser configuration for the Hungarian Paks nuclear power plant. A second activity addressed the structural integrity of certain components of the bubbler condenser steel structures under DBA-typical conditions. This part of the project was performed at VUEZ, in Levice, Slovak Republic. The design of the components of this facility was based on the structural properties of the Dukovany and/or Bohunice nuclear power plants. A third component of the BCEQ project was specified later asking for analytical studies, which should be supported by a number of small-scale separate effects tests to be performed at SVUSS, in Bechovice, Czech Republic. The main experimental and analytical results of the BCEQ test campaigns have been presented and discussed within the frame of the 4. meeting of the Technical Advisory Committee to the BCEQ (Bubble Condenser Experimental Qualification) Project in Brussels in December 1999 and on occasion of the 11. OECD Support Group Meeting in Berlin in April 2000. The discussions had evidenced several

  15. Results of trial operation of new generation assemblies with improved vibration stability for WWER-440 reactors of V-230 and V-213 plants

    Vasilchenko, I.; Lushin, V.; Shumeev, A.

    2006-01-01

    FAs, in the region of FA-and-absorber rod butt joint due to arrangement of hafnium plates in the upper part of FA casing was also solved. The correctness of solutions, laid down in the design of the new generation fuel assemblies, is successfully confirmed by the results of trial operation. It is planned to apply the new generation fuel for WWER-440 reactors of V-213 type at power units of Dukovany NPP in 2005, and in 2006 at Mochovce NPP and at Bohunice NPP V-2 units 3 and 4. In 2007 it is planned to extend an application of vibration-proof working assemblies of new generation for power units of V-230 type at Kola NPP Unit 1

  16. Nuclear Regulatory Authority of the Slovak Republic. Annual Report 2002

    Seliga, M.

    2003-04-01

    the approved documentation. UJD represents the Slovak Republic in several international organisations and is responsible for fulfilment of commitments of the Slovak Republics resulting from both bilateral and multilateral agreements and conventions. Besides UJD provides independent information for the public in the nuclear area, co-operates with state authorities, research institutions, universities and further domestic and foreign institutions. Besides standard evaluation of nuclear safety in all nuclear installations in 2002 UJD paid, first of all, attention to an increase of nuclear safety of NPP Bohunice V-2. The participation of UJD in the 2 nd evaluation meeting held in sense of the Convention on Nuclear Safety where a Slovak National Report on Nuclear Safety was presented has been considered to be a very important feat. By the end of 2002 an IAEA IRRT mission focused on review of legal documents, role, inspection activities, commissioning works concerning new nuclear installations and emergency preparedness and other UJD practices was held. Based on results of comprehensive evaluation of nuclear safety of Slovak nuclear installations, which were supported by the international assessment UJD can declare that the operation of nuclear installations in the Slovak Republic during 2002 was safe and reliable and all international commitments resulting from international agreements in the area of nuclear safety and nuclear materials were fulfilled. A short summary of all UJD activities in 2002, draws near the work of UJD staff, supervising activities and at same time is help to provide the public an objective and independent information on real status of the nuclear safety of nuclear installations in the Slovak Republic. Ten years of the Nuclear Regulation Authority of the Slovak Republic activities are reviewed

  17. Co-ordinated research programme on benchmark study for the seismic analysis and testing of WWER-type nuclear power plants. V. 4G. Paks NPP: Analysis and testing. Working material

    1999-01-01

    related to different structures or systems of Paks NPP and Kozloduy NPP Unit 5/6 and experience data (previous laboratory results or earthquake experience) for WWER type NPPs. The reports from the CRP participants have been compiled in volumes of IAEA Working Material grouped under five broad categories. This volume covers the following subjects: structural response of Paks NPP; Evaluation of seismic resistance of low voltage switchgear, Bohunice V1 NPP; final report of the seismic investigations at Paks NPP; report on vibration test of the scale worm tank model; plan of shaking table test of worm tank model; dynamic response of the Paks NPP chimney; vibration analysis of the Paks NPP stacks; functionality of WWER electrical, instrumentation and control components; dynamic analysis of Paks reactor building structures; and computational-experimental examination and ensuring of equipment and pipelines seismic resistance at starting and operation WWER type NPPs

  18. Political pressure on nuclear - responsibility or business?

    Petrech, Rastislav; Holy, Robert

    2001-01-01

    After more than 10 years since the fall of the 'iron curtain' some Central and East European countries were invited to talks on possible joining the European Union. The nuclear power industry and future development programmes in the countries were one of the crucial topics discussed. Nuclear field is probably the most sensitive one in terms of perception and acceptance by the public as well as politicians. To be able to really solve the issue of the nuclear industry future, it is necessary to know and understand the problems, which we'll have to cope with in a situation when the nuclear industry gets face-to-face in a competition with other electricity producers. Safety became the dominant issue roughly since the mid 80's, especially after the Chernobyl accident. Safety had always been important, however it was the top priority is this period. Public relations were seriously dealt with in parallel. Market liberalisation, decentralisation and privatisation has been the determining factor of further development of the nuclear industry since mid 90's. Probably the most important problem are the Public Relations. Positive public attitude and acceptance of nuclear power as an ,'ordinary' industry is the basic precondition for the further development. It is almost common practice that posts of NPP directors are occupied by public relations experts and experienced orators, whose power of arguments can convince people. Results of public opinion polls in many countries demonstrate that political views on the future of nuclear are in contradiction with public opinions. In Slovakia, for example, the nuclear has the support of 60-70 % in long-term. However, what is missing is a political force which might help completing Mochovce NPP units 3 and 4, even though in terms of near-future liberalisation this option proves to be the most advantageous one for replacement of older two units of Bohunice NPP (since the Government promised the units will be shut down in 2006 and 2008

  19. International Expert Team Concludes IAEA Peer Review of Slovakia's Regulatory Framework for Nuclear Safety

    2012-01-01

    that consideration of these would enhance the overall performance of the regulatory system: Coordination and allocation of responsibilities among State Authorities in the area of safety and improvement of planning and coordination of their activities; The development of a national policy and strategy document for nuclear safety; and A unified national radiation monitoring system to ensure its results could be used by competent authorities in normal situations as well as during emergencies. In a preliminary report, the IAEA has conveyed the team's main conclusions to UJD SR. A final report will be submitted to the Government of Slovakia in about three months. UJD SR has informed the team that the final report will be publicly available. The IAEA encourages nations to invite a follow-up IRRS mission about two years after the mission has been completed. Background. The IRRS mission to Slovakia was conducted from 28 May to 7 June 2012, mainly in Bratislava. The IRRS team carried out a review of nuclear legal and regulatory framework for nuclear safety. Special attention was given to the review of the regulatory implications for Slovakia of the TEPCO Fukushima Daiichi accident. The review addressed all facilities regulated by UJD SR including nine nuclear power units, as well as spent fuel and waste management facilities. The IRRS mission did not include a comprehensive review of the national regulatory infrastructure for radiation safety of Slovakia, which is planned to be covered in the IRRS follow-up mission. Team experts came from twelve different countries: Belgium, Brazil, Czech Republic, Finland, France, Hungary, Romania, Slovenia, South Korea, Sweden, Ukraine and United Kingdom. The IRRS team consisted also of 6 IAEA staff members. Quick Facts. Slovakia has nine nuclear power reactors at two sites (Bohunice, Mochovce): 3 units are in decommissioning, four units are in operation and two units under construction. Slovakia has no other fuel cycle facilities or research

  20. Chapter No.11. Public information

    2002-01-01

    pursuant to Act No 211/2000 of Coll. was published on UJD web site (www.ujd.gov.sk). From January 2001, 56 requests were registered asking for the information (by phone, e-mail, letter or personally). One written request from Greenpeace was not satisfied since the information is a matter of business secret. The matter is in the proceeding of the Supreme Court of the Slovak Republic. The Slovak press agencies, daily newspapers and electronic media were provided with 63 contributions on domestic and foreign UJD activities. UJD, together with SUJB, issues the expert journal 'Bezpecnost jadrovej energetiky (Nuclear Sector Safety)'. Two important articles on UJD legislative activities and on informing the public were published in monthly 'Verejna sprava (Public Administration)'. Contributions on supervisory activity and on UJD international co-operation are published regularly in 'Spravodajstvo SE (SE Information Service)', company journals 'Mochovce' and 'Bohunice'. Domestic and foreign UJD activities were presented in 5 issues of 'Bulletin Slovenskej nuklearnej spolocnosti (Slovak Nuclear Society Bulletin)'. This year, the report on nuclear facilities safety and on handling with spent nuclear fuel and radioactive waste in the Slovak Republic was published in European Nuclear Society journal 'Nuclear Europe Worldscan No 7-8/2001'. Several important contributions were published in journal 'Energia (Energy)'. Contributions on UJD tasks and mission in the Slovak Republic were published in 'Energia almanach (Energy Almanac 2001/2002)' and in 'Euro Nuclear'. Three contributions on domestic and foreign UJD activities were prepared for the world information Agency NucNet. Slovak-English additional information document on UJD was elaborated and issued for the public in December 2001. The 2001 Yearbook on UJD activities and on nuclear facilities safety in the Slovak Republic was prepared and issued in Slovak and English version. Four press conferences took place in 2001 in UJD followed

  1. Proceedings of the joint CSNI/CNRA workshop on redefining the large break LOCA: technical basis and its implications

    2003-01-01

    viewpoints and experiences of the largest utility. The presentation summarized the experi ence data for known degradation mechanisms. The EDF presentation also covered leak before-break concept which is one of the integral elements (along with the in-service inspections and leak detection) in redefining the LB LOCA. The SKI presentation discussed the experience with the degradation specific in-service inspection programs. The presentation also covered a number of efforts that are currently underway to develop risk-informed ISI program. It should be recognized that any risk informed approach to in-service inspection programs must be based on an extensive experience, which at present will probably not cover every possible degradation mechanism. The Framatome presentation described the standardize criteria, methods, and procedures for assuring the design and operational adequacy of reactor coolant pressure boundary leak detection systems used in plants. The presentation also covered a new system based on the measurements of local humidity. 3. What are possible new definitions for the LB-LOCA? What are their implications for current and future reactors? Two papers were presented which highlighted different approaches to incorporating a change in the LB-LOCA definition into a plant. The first paper, 'Slovak approach during the gradual upgrading of Bohunice V 1', by Mr Kliment, described a programme of back fits to an operating plant, to increase the DBA LB-LOCA from 32 mm equivalent to 200 mm. The second paper, 'Westinghouse Owner's Group Large Break Loca Redefinition Program', presented by Mr Bastien, described the simplifications of design and operation that would be achieved if the DBA LB-LOCA were (significantly) reduced in size