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Nuclear and industrial area Verification//Calibration Technical Quality Control Wastes treatment
Quality Management Design Medical Approach, Radiation protection, Environment protection Technologies

 

 

1. Nuclear and industrial area
  1. Materials irradiation;
  2. Materials testing in the neutron flow;
  3. Gamma irradiation testing for materials and nuclear equipment;
  4. Neutron Activation Analysis (NAA);
  5. Prompt gamma spectrometry;
  6. Neutronography analysis on nuclear fuel;
  7. Gamma scanning on fuel elements;
  8. Radiation source for industrial applications (sealed 192 Ir and  60Co sources):
    • SR-Ir-A, max activity 4.44 TBq (120 Ci) and focal spot 3x3 mm;
    • SR-Ir-B, max activity 2.31 TBq (70 Ci) and focal spot 2.5x2.5 mm;
    • SR-Ir-C, max activity 1.155 TBq (35 Ci) and focal spot 2x2 mm;
    • SR-Ir-D, max activity 0.555 TBq (15 Ci) and focal spot 1.5x1.5 mm;
    • SR-Ir-E, max activity 0.185 TBq (5 Ci) and focal spot 1x1 mm;
    • SR-Ir-F, max activity 0.037 TBq (1 Ci) and focal spot 0.5x0.5 mm.
  9. Sealed 60Co radioactive source capsule for industrial generators;
  10. Assays and tests for closed radioactive sources;
  11. Measurement of radioactive samples by beta spectrometry with liquid scintillates;
  12. Measurements of radiation field ( gamma, neutrons, contamination);
  13. Identification and quantitative determination of  gamma emitting radionuclides;
  14. Spectrometry of secondary electrons;
  15. Mass spectrometry with inductive joined plasm;
  16. Mechanical and thermo-hydraulic analyses;
  17. Structural analyses on polycrystalline materials;
  18. Microphysics characterization for surface and thin films;
  19. Defects control by eddy-currents;
  20. Metallographic examinations on radioactive and inert materials;
  21. Corrosion experiments in static autoclaves;
  22. Experiments regarding microbial corrosion;
  23. Tensile tests and creep tests on irradiated and non-irradiated materials;
  24. Thermo-mechanical tests for metallic and ceramic materials in various stages of stress and environments conditions;
  25. Salt fog tests for components and parts used in nuclear or industrial fields;
  26. Analyze and evaluation of risk and safety for the transport and storage of radioactive materials;
  27. The qualification testing facility for type A, B and C packages to be used for transport and storage of radioactive materials;
  28. Computer codes for applications in the nuclear field (reactor physics, fuel, etc.);
  29. Computing methodologies for process simulation in the nuclear power plant;
  30. Reliability studies and analyses for predictable or experimental determination of reliability parameters of nuclear equipments and installations by SCN or CNE – Cernavoda;
  31. Reliability studies and analyses of predictive maintenance for nuclear or classic equipments and installations;
  32. Failed Fuel Location System (FFLS) BSI–63105 – for Nuclear CANDU Power Plants;
  33. FFLS Assembly (carriage, moderator tank, coils assembly, collectors and coupling T assembly);
  34. Radioactivity Monitoring of Heat Transport System – BSI–63103 – for nuclear CANDU Power Plants;
  35. Fixed area gamma monitors – BSI 79–67873–TS;
  36. Assembly of detection with ionization dual spherical chamber of high sensitivity for measurement exposure flows of gamma radiation in the range 10nSV/h, 100mSv/h, AD – R – 00;
  37. Detection assembly with ionization cylindrical chamber for measurement of sources activities of gamma radiations, AD–A–01;
  38. Ionization chamber with boron irretrievable with incorporated  cable, CIBN – 422, for nuclear reactors control;
  39. Ionization chamber gamma under pressure CIG - P - 321, for low level measurement of gamma radiation;
  40. Intensifier for ionization chamber with  starting comparators for end system of reactor CANDU 600 ( TD 63740 and 68232 );
  41. Intensifier for ionization chamber without starting comparators ( TD 63740 007 ) for power regulation system;
  42. Monitory station of radiation in ambient medium SLM - 16G;
  43. Local station of radiation monitory EMR – 15G – SLM;
  44. Assays and test of dosimetry equipment;
  45. Equipment type "Digital programming comparator" for reactor end system ( PDC – BSI – 68230 – 1);
  46. SIMAG – WATCH – supervision system of closed precincts;
  47. Redundant security system for irradiation capsules;
  48. System for control by acquisition and image processing of the welding and brazing samples in fuel elements;
  49. System for dimensional determinations in the quality control of mechanical products, by acquisition and image processing;
  50. Computerized data acquisition system for industrial facilities;
  51. Control–command systems for alarms in industrial installations;
  52. System with distribution control for industrial applications;
  53. Industrial systems for activation of step by step motors;
  54. IT system for  processing, data correlation and diagnosis for the nuclear area and civil protection;
  55. Support system decision in real time for evaluation of emergency situations;
  56. System for staff training;
  57. Integrated systems for information and interactive communication;
  58. Air breathing stations;
  59. Hypodermic stations;
  60. Neutron detection block;
  61. Adsorber C801;
  62. Container D2O – 200 – 04;
  63. Electrical heater EH 801;
  64. Spacers piece load;
  65. Installation of osmosis reverting;
  66. Cooler with nitrogen H803;
  67. Aluminum doors with lead protection screen;
1.1 Verification//Calibration 1.2 Technical Quality Control
  1. Qualification (type) tests and production (batch) tests: climatic, mechanical, functional and reliability tests for equipment, components and partly utilized in the nuclear area;
  2. Control and testing (non-destructive examination, functional tests, etc.) of the following equipment:
    • Stainless steel cask 220 l for solid wastes/liquids;
    • Finned pipe;
    • Air breathing stations;
    • Cask and container for standard heavy water.
  3. Leak tests for the following equipment:
    • Breakage disks Calandria;
    • LISS Calandria;
    • Calandria fuel channels;
    • Assembly breakage disks Calandria;
    • Cooling batteries LAC;
    • Vertical and horizontal flux detectors.
1.3 Wastes treatment
  1. Characterization, conditioning and treatment of radioactive wastes;
  2. Assessment and certification of metallic wastes radioactivity;
  3. Radioactive samples assessment by beta spectrometry with liquid scintillators;
  4. Qualification tests and evaluation of technical characteristics for (casks) intended for transportation and storage of radioactive materials;
  5. Packages for storage of radioactive wastes (drums, barrels, casks);
  6. Equipment determine alpha contamination of the CANDU-type fuel;
  7. Pump for aerosols sampling, with independent supply;
  8. Monitor to determine alpha and beta contamination of floors and equipment;
  9. Equipment to determine alpha and beta contamination of hands, feet and outfits;
  10. Portable device for tritium sampling by bubbling;
  11. Method  and device for continuous monitoring of tritium concentration in liquid effluents at a nuclear plant;
  12. Device for continuous sampling of aerosols, tritium and radioactive iodine - type CAS – 1;
  13. Device for continuous assay of SO2 and H2S, type CAS – GP samples.
1.4 Quality Management
  1. Internal and external audit of the management quality system;
  2. Elaboration of documentation for company standards and procedures specific for the nuclear field.
1.5 DESIGN
  1. Design  of mechanical components for nuclear equipments;
  2. Design of storage structures for nuclear fuel and radioactive wastes;
  3. Design of equipments and installations required in research contracts of ICN;
  4. Design of equipments for biological protection against radiations;
  5. Design of electric drive and automations;
  6. Elaboration of documentation for investments in accordance with applicable legal provisions: study of pre-feasibility and feasibility, technical design;
  7. Design, execution and assembly of equipments and electronic installations for process control;
  8. Expertise, technical assistance, assembly and operation of control installation and data acquisition;
  9. Design and implementation of precision systems and equipments for industrial measurements (flow meter systems, voltage measurements and very small currents);
  10. Design, software implementation for nuclear and industrial applications;
  11. Verification and certification of pressure installations and equipments design subject to prescriptions of ISCIR – NC1 – 81 and NC2-83.
2. Medical Approach, Radiation protection, Environment protection
  1. Raw material irradiation for the production of radioisotopes of medical use;
  2. Materials irradiations;
  3. Studies for radio-sterilization of medical products;
  4. Monitoring system based on GIS for applications in the medical area;
  5. Design of equipments for biological protection against radiations;
  6. Aluminum doors with lead screening protection;
  7. Radioprotection integrated system;
  8. Fix gamma area monitors – BSI 79 – 67873 – TS;
  9. Station radiations monitoring in the environment - SLM – 16G;
  10. Local station for radiations monitoring - EMR – 15G – SLM;
  11. Tests on dosimeter used for monitoring environment radioactivity;
  12. System of acquisition and measurement of weather parameters used for the nuclear field SAM – 18G;
  13. Installations for air samples assay for environment monitoring;
  14. Background radiometry alpha/beta for measurement of air contamination, surface and various environment samples;
  15. Measurements of radiations field (gamma, neutrons, contamination);
  16. Identification and quantitative determination of gamma-emitting radionuclides;
  17. Measurement of radioactive samples by beta spectrometry with liquids scintintillators;
  18. Determination of natural uranium  content in water, soil and vegetation;
  19. Determination of natural uranium content in working areas atmosphere;
  20. Determination of  90Sr content in milk, dairy products and paste;
  21. Determination of uranium content in urine;
  22. Studies on the conservation of food supply by irradiation.
3. TECHNOLOGIES
  1. Technologies of experimental fuel elements fabrication;
  2. Technologies of nuclear fuel test;
  3. Technologies of nuclear materials test;
  4. Technologies for obtaining UO2 sinterable powders, UO2 sintered pellets with controlled microstructure;
  5. Technologies for fabrication of targets to obtain radioactive sources;
  6. Technologies for end cap-clad welds;
  7. Systems and technologies for out of pile testing;
  8. Technologies for maintenance of equipments at CNE – Cernavoda;
  9. Technologies of decontamination  of components and equipments in nuclear plants;
  10. Technology for evaporation treatment of active liquid effluents beta – gamma resulted from TRIGA reactor of SCN Pitesti and conditioning of resulted concentrate, in view of final storage;
  11. Technology for treating  liquid waste contaminated with natural uranium, with the recovery of uranium to be used in the nuclear fuel fabrication cycle;
  12. Technology for conditioning low active solid  beta-gamma waste, for final storage;
  13. Technology for treating/conditioning of spent ions exchanger use resulting from TRIGA – SCN Pitesti reactor (pilot plant scale);
  14. Technology from treatment of liquid waste resulted from Cernavoda CNE decontamination centre;
  15. Technology for treatment of gaseous radioactive waste contaminated with 14C, resulting at CNE Cernavoda;
  16. Technology for conditioning of radioactive wastes resulting from the treatment of gaseous radioactive waste contaminated with 14C, resulting at CNE Cernavoda;
  17. Technology of treatment / conditioning of ions exchangers contaminated with 14C, resulting from CNE Cernavoda;
  18. Technology for treatment and conditioning of organic liquid waste (oil solvents, liquid scintillators) at CNE Cernavoda;
  19. Technology for conditioning of spent sealed active sources.
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