• Control of reactivity
• Removal of the decay heat,
• Enclosure of radioactive substances and
• Limiting radiation exposure.

The last two protection objectives in particular are of great importance for the decommissioning and dismantling of nuclear facilities with or without reactor. In line with the ALARA principle, we will answer all your questions on nuclear safety using hazard analyses, incident and accident analyses, the drafting of licensing documents according to the Radiological Protection Ordinance such as safety reports, compiling documents on fire protection and planning radiation protection facilities.

• Drafting of licensing documents in accordance with national and international regulations: Preliminary Safety Analysis Report (PSAR)
• Interim Safety Analysis Report (ISAR)
• Final Safety Analysis Report (FSAR)
• Environmental Impact Analysis Report (EIA)



Implementing all analyses that are necessary for the safety analysis report

• Hazard analysis
• Accident analyses
• Failure Mode and Effect Analyses (FMEA)
• Contributions to the (Periodic) Security Review (PSR)
• Contributions to the Probabilistic Safety Analyses (PSA)

• Shielding calculations
• Radiation protection concepts including radiation protection instrumentation
• Description of the radiation protection measures
• Definition of radiation protection areas
• Layout design (controlled area entrance/exit, locks, entire buildings)
• Specifying personal radiation protection equipment
• Planning, specification, procurement, installation of the radiation protection instrumentation
• Implementing country-specific limit levels
• Reduction of radiation exposure to personnel
• Calculating the release of radioactive substances and the consequences

• Personal and local dosimetry
• Contamination measurement equipment
• Gamma spectrometry
• Ventilation monitoring

Determining radioactive inventory and dose rates

• Identifying radiation sources, nuclide vectors
• Compiling information about nuclide-specific radioactivity of radiation sources
• Activity-dependent analysis of the nuclide
• Defining relevant nuclide vectors
• Determining the radioactivity of individual components
• Logical grouping of sources
• Dose and dose rate calculation by means of qualified computing programmes
• Calculating the local dose rate for:
• oIndividual components
• oWorkstations and rooms
• Designing the shielding
• Calculating the individual and collective dose for operating personnel and population during normal and emergency operation mode including maintenance and service

ㆍMonitoring radiological emissions
• Specifying the measuring instruments, procurement, installation, commissioning, training:
• Sampling system, pipeline and control for isokinetic sampling
• Collector and/or monitor for aerosol, tritium, carbon, iodine, inert gas

ㆍMonitoring chemical emissions
• Specifying the measuring instruments, procurement, installation, commissioning, training:
• Sampling system, pipeline and control
• Analytical instruments for: CO2, NO2, NOX, Corg, HCl, CO, NO, SO2, O2



I.Care.fire: Web-based mobile support in creating a fire protection concept


ㆍProblem
• Creation / modification of the fire protection concept is necessary:
• in case of structural changes
• in case of displacement of fire loads
• as part of new construction, operation, decommissioning and dismantling
• in set time intervals



I.CARE.fire provides you with:

• Time and cost saving during plant inspections and data collection of the inventory (fire load)
• User-friendly handling
• High level of safety due to a simplified procedure for the inspection
• Digitalised and documented actual state via photographs
• Simplified target/actual comparison
• Increased safety standard due to wide-ranging documentation options
• Sustainability by means of traceability - changes are documented
• Immediate availability in the nuclear power station (intranet)