Gamma spectrometer supply, installation, setup and commissioning.

Measurement methodologies development:

• gamma-radiation emitting radionuclides content measurement in the loose (shot, slag, etc) and high density waste (up to 4,6 MT/cu.m. ) in the packages of A class solid radioactive waste (SRAW) (SRAW);
• gamma-radiation emitting radionuclides content measurement in the bulk equipment and high density waste (up to 4,6 MT/cu.m.) (steam super-heaters, steam separators and heat exchanger  tube sheets, separator drums, main circulation pumps, group distribution collectors) without package (A class SRAW);
• measurement of the gamma-radiation emitting radionuclides content in loose A class SRAW (shot, slag, etc) using the representative sample measurement principle;

Development of the software for the radiological characterization data results accounting and transfer to the existing A class SRAW buffer storage database. Existing radiological characterization equipment and newly developed measurement methodologies are utilised. Software also provides all radiological characterization data reception and transmission of to the existing INPP DMSD database.

Selection of equipment and means of radiation control and monitoring, description of their operation during preparation and radioactive waste retrieval

• Methods to determine the unconditional and further uncontrolled level, selection of equipment and description of its operation.
• Management of decommissioning waste (removal and processing of further uncontrolled waste).
• Evaluation of costs, associated with radiological measurements.

Maišiagala radioactive waste storage demolition design

• Selection of equipment and means of radiation control and monitoring, description of their operation during demolition of the vault, liquid radioactive waste reservoir and contaminated soil removal of by radionuclides

Radiation Safety Program

• Development and approval of Radioactive Safety Program.

 

Development of initial Technical specifications and Design documentation for equipment manufacture.

Supply of equipment:

• Complete I&C software and hardware
• Monitors of ambient equivalent dose rate and absorbed gamma radiation dose rate.
• Monitors of neutron radiation equivalent dose rate
• Monitors of specific alpha, beta activity of aerosols and radioactive noble gases in the air of industrial premises and in technological systems
• Monitors of specific alpha, beta activity of aerosols and radioactive noble gases, iodine in air emissions of the facility
• Monitors of specific gamma activity in liquid media and liquid emissions of the facility
• System for liquid and gaseous media sampling, including air and liquid emissions
• Technological process video surveillance system, including radiation resistant cameras
• Pedestrian and transport portal monitors
• Full height monitors of personnel surface contamination  with beta particles
• Monitors of personnel arms and legs, personal protection gear contamination
• Personal dosimetry equipment, personal direct-reading electronic dosimeters (не поставляли), electronic dosimeter reader

 

Expanding the capabilities of the B19 Facility for RAW characterization:

• expanding the list of characterized package types (ensuring the possibility to characterize small RAW packages weighting 2 tons);
• expanding the list of measured material types;
• realization of re-characterization procedure for radioactive waste packages accumulated in Buffer storage of B19 Facility;
• realization of independent characterization procedure for RAW packages from third-party manufacturers (comparative measurements);
• change of radioactive waste packages characterization passes and protocols format in accordance with the requirements of the TS;verification of correctness of chemical formulas of materials existing in characterization facility DB, used in algorithms for calculating radioactive waste packages activity, coordinate codes for new types of materials, describe their chemical formulas, specify ranges of permitted density of new materials, methods of sorting and RAP filling with new materials.

Expansion of capabilities of B19 Facility for RAW management:

• ensuring accounting of radioactive waste packages, stored on other sites for temporary storage of radioactive waste packages (in addition to the Buffer storage of B19 Facility);
• ensuring accounting of radioactive waste packages, manufactured and characterized on other facilities of Ignalina NPP;
• verification and update of procedures and formats of information exchange with INPP Project B17 DMSD data base;
• use of radioactive waste packages, stored on other sites for temporary storage of radioactive waste packages, to plan final disposal operation;
• ensuring the possibility to apply the modified WAC criteria (add/change conditions for verification of WAC criteria);
• realization of the procedure for verification of accumulated radioactive waste packages for compliance with modified WAC criteria without performing repeated measurement procedure.

Update of methodological support for RAW characterization system due to expansion of possibilities of B19 Facility:

• update of Measurement Methodology, taking into consideration modified list of measured types of radioactive waste package materials and modified list of characterized package types (ensuring the possibility to characterize radioactive waste package weighting 2 tons, FIBC container with bulk very low level waste);
• update of radioactive waste package description, taking into consideration modified list of measured types of radioactive waste package materials and modified list of characterized package types (ensuring the possibility to characterize radioactive waste package weighting 2 tons, FIBC container with bulk very low level waste);
• update of sections of MM metrological support (calibration and verification) and realization of these procedures in software.

Update of operation documentation of B19 Facility:

• update sections of documents, describing modified procedures;
• description of order of activities for newly developed procedures, algorithms and software modules;
• correction of description of system structure and software modules.

Development of Measurement Methodologies:
• Measurement of gamma-emitting radionuclides in a bale with compacted raw
• Measurement of content of gamma-emitting radionuclides in T-container for forming of final package 20ft-1/2H ISO container with non-compactable raw
• Measurement of gamma-emitting radionuclides in drums with raw for forming final package – concrete container KTZ-3,6
• Measurement of gamma-emitting radionuclides in RAW on conveyor for forming of package – metal container for long-term storage in B4 facility

Pre-commissioning activities, testing and commissioning of Radiation Monitoring System for Solid Waste Management and Storage Facility at Ignalina NPP (Project B2).

Design, manufacture, qualification and supply of auxiliary equipment for monitors made by Mirion Technologies for Radiation Monitoring System of New Safe Confinement at Chernobyl NPP. Provision of technical assistance for qualification of Mirion Technologies monitors for the project and on-site services.

Supply, setup and commissioning of Thermoluminescent Dosimetry System for Radiation Protection Centre of Lithuania.

Supply, installation, setup and commissioning of Thermoluminescent Dosimetry System for Environmental Board of Estonia.

Manufacture, supply, installation supervision, pre-commissioning activities, testing and commissioning of the Radiation Monitoring System for Interim Spent Fuel Storage-2 (ISF-2) at Chernobyl NPP.

Design, manufacture, pre-commissioning activities, testing and commissioning of Personnel Dosimetry System for National Science Centre «Kharkov Institute of Physics and Technology».

Qualification and supply of Radiation Monitoring System for National Science Centre «Kharkov Institute of Physics and Technology».

Design, manufacture, pre-commissioning activities, testing and commissioning of Personnel and Vehicles Contamination Monitoring System at the Checkpoint-2 at Chernobyl NPP.

Design, manufacture and supply of Radiation Monitoring System for the New Solid Radioactive Waste Retrieval Facility at Ignalina NPP (Project B2).

Design, manufacture, supply, mounting, pre-commissioning activities, testing and commissioning of Radiation Monitoring System for Liquid Radioactive Waste Treatment Plant at Chernobyl NPP.

As a consortium, preparation of safety analysis report and environmental impact assessment report of Landfill facility
As a consortium, preparation of Technological part of the Project.
Preparation of Technical and Detailed Design of Integrated Radiological Control System (IRCS) consisting of:
• Radiation Monitoring System;
• Facility for characterization of Very Low Level Waste in the following packages:
  - Bale with compacted RAW;
  - FIBS container with bulk RAW;
  - 20ft-1/2H ISO container with non-compactable RAW.
• RAW Accounting, Storage and Characterization Systems.
Development of equipment and software for Integrated Radiological Control System.
Installation supervision, pre-commissioning activities, testing and commissioning of listed above systems.
Development of Measurement Methodologies:
• Measurement of content of gamma-emitting radionuclides in a bale with compacted raw;
• Measurement of content of gamma-emitting radionuclides in 20ft-1/2H ISO container with non-compactable raw;
• Measurement of content of gamma-emitting radionuclides in FIBS container with bulk RAW.