Automated system of radiation control for NPP
Automated system of radiation control for NPP ASRC-01
- Open two-level multiprocessor canal structure
- Consolidation and supply of the system depends on the project’s specifications
- Complete set of detection assembly by ionizing radiation and required measurement range
- Possibility to add additional functions
- Informative software
The system meet the requirements of Russian current regulatory system and basic international norms that define general specifications and quality control during the development, manufacture and operation of ASRC-01R.
System designation
The system is designed to get and process information about characteristics of radiation condition of NPP and environment in all working conditions including accidents within and beyond the design as well as NPP’s condition after decommissionong
Areas of application of the system
The system may be implemented at NPP with water-moderated power reactor. Systems’ equipment may be installed at any sites with enhanced radiological hazard such as nuclear-fuel processing combines, research reactors, nuclear waste sites, etc.
Engineering model
The system has open apportioned two-level hierarchy structure where:
Lower level– provides measurement amd management of canals
Higher levelprovides information integration of measurement and management characteristics that allows overall control and evaluation of radiation safety at NPP
Functional structure of the system
Lower levelof the system is composed of the following interdependent functional automated subsystems:
- Subsystem for radiation technical monitoring RTM
- Subsystem for radiation monitoring of premises RMP
- Subsystem for individual dosimetric control RDC
- Subsystem for contamination radiation monitoring CRM
- Higher level of the system is implemented on the base of software and hardware complex of SHC BU-01R which provides information from software and hardware facilities (SHF) of lower level and external subscribers, data processing, arching and presentation in display facilities, external data exchange and provides integral analysis of radiation safety of energy unit (EU).COMPLEX OF FUNCTIONAL TASKS COMPLETED WITHIN SUBSYSTEMS
Subsystem RTM:
- Fuel rod failure monitoring;
- Detection and evaluation of flow volume in the primary coolant circuit;
- Containment vessel leak tightness monitoring;
- Monitoring of flow from the equipment cooled with process water;
- Monitoring of the efficiency of water cleanup system (WCS), gas cleaning system (GCS) and ventilation system;
- Monitoring of volume and radionuclide composition of aerosol emissions and dumping from the NPP
- Grouping of solid radioactive waste of NPP
- Forecasting of change of radionuclide activity beyond safety barriers
Subsystem RMP: - Monitoring of radiation environment in the premises of energy unit;
- Analysis and forecast of changes of radiation environment;
- Emergency monitoring of radiation environment in premises to choose mean of egress;
Subsystem RDC - Monitoring and registration of individual external doses of the personnel;
- Monitoring and registration of expected internal doses of the personnel;
- Monitoring and registration of personnel attendance of the access controlled area;
- Arrangement of access of the personnel to work in the access controlled area;
- Monitoring of the personnel presence in the access controlled area;
Subsystem CRM: - Monitoring of contamination level of the premises surfaces, equipment inside the premises, skin integument, personal protective equipment of the personnel;
- Quality control of work clothes and personal protective equipment laundering in special laundry;
- Monitoring of the movement of radioactive waste and contaminated equipment;
- Task solution of periodic monitoring of radioactive contamination of the site;
Complex of periodic monitoring pm
It is implemented within functional subsystems RTM and RMP and provides:
- Monitoring of radioactive environment of the premises and process medium;
- Monitoring of volumetric activity of tritium, carbon-14 and other nuclides in water and air;
- Monitoring of radionuclide composition and radionuclide activity in samples of air, water and solid samples;
Parameters controlled by the system and their measurement ranges
Subsystem RTM
| Radionuclides volumetric activity in the primary coolant, Bq/m3 | 3,7·103 — 3,7·1013 |
| Radionuclides volumetric activity in liquid, Bq/m3 | 3,7·103 — 3,7·1013 |
| Radionuclides volumetric activity in open stream (basic steam pipes PG), Bq/m3 | 3,7·104 — 3,7·108 |
| N-16 Radionuclides volumetric activity in open stream (basic steam pipes PG), Bq/m3 | 3,7·104 — 3,7·108 |
| Inert radioactive gases volumetric activity in gas-vapor mixture (basic electron blow down), Bq/m3 | 3,7·104 — 3,7·109 |
| Volumetric activity in emissions and blow downs, Bq/m3 | 1,0·103 — 3,7·1012 |
| Beta-active aerosols volumetric activity in vent systems, emissions and blow downs, Bq/m3 | 3,7·10-2 — 3,7·106 |
| Iodine vapor volumetric activity in emissions and blow downs, Bq/m3 | 1,8·10-1 — 1,8·104 |
| Radionuclides volumetric activity in water environment of low activity, Bq/m3 | 1,0·103 — 3,7·107 |
| Equivalent dose power of neutron emission, Sv/h | 2,0·10-6 — 1·10-1 |
| Absorbed dose power of gamma-emission in containment of the reactor unit in emergency, Gy/h | 10-6 — 104 |
Subsystem RMP
| Ambient equivalent dose power (power of gamma-emission absorbed dose in premises Sv/h (Gy/h) | 10-7— 101 |
| Inert radioactive gases volumetric activity in the air of the premises, Bq/m3 | 3,7·103 — 3,7·109 |
| Beta-active aerosols volumetric activity in the air of the premises, Bq/m3 | 3,7·103 — 3,7·109 |
| Iodine vapor volumetric activity in the air of the premises, Bq/m3 | 3,7·10-1 — 3,7·106 |
Subsystem RDC
| External radiation effective dose, Sv | 10-5 — 1,0 |
| Body content of incorporate isotopes | |
| Cesium-137 in body, Bq | 5,0·102 — 1,0·106 |
| Cobalt-60 in body, Bq | 5,0·102 — 1,0·106 |
| Iodine-131 in thyroid, Bq | 4,0·100 — 1,0·106 |
| Iodine-133 in thyroid, Bq | 4,0·101 — 1,0·106 |
Subsystem CRM
| Flux density of beta-particles if the personnel hands are contaminated (b-part/s m)2) | 1,67·103— 334·103 |
| Flux density of beta-particles if the personnel body and work wear are contaminated (b-part/s m)2) | 1,67·103— 334·103 |
| Power of gamma-emission individual dose rate if personnel’ clothes is contaminated, Sv/h | 10-7— 10-2 |
Compliance with specifications
The system belongs to the systems of normal operation that are essential for NPP safety – class 3N according to OPB-88/99. Subsystem RDC, AWSs of higher level, stationary instrumentation stock of the system and its’ service equipment belong to 4N class according to OPB-88/89.
System’s equipment of 3N class meets all requirements to temperature conditions, seismic resistance, fire safety and electromagnetic compatibility.