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Glossary:

AGR Advanced Gas-Cooled Reactor (UK)
BWR Boiling Water Reactor
CANDU Canadian Deuterium Uranium Reactor
Ci/km2 Old Unit for the ground contamination; 1 Ci/km2 = 37 kBq/m2
Cs-137 Caesium-137; Cs-137 has a half-life time of 30.2 years and is therefore an indicator for the long time radiological effects.
FBR Fast Breeder Reactor
GCR Gas Cooled Reactor (UK)
IAEA International Atomic Energy Agency
IAEA-Scenario The International Nuclear Safety Advisory Group, which is a working group established in the IAEA, has formulated in the INSAG-3 report in 1988 a minimal safety target for the existing NPPs: The frequency of large off-site releases of radioactivity should not exceed 10E-5 per reactor year (1 accident within 100 000 years). Even today, more than ten years later, not all operating NPPs meet this safety target. In the IAEA scenario the release frequency for all NPPs is defined as 10E-5 per reactor year. INSAG International Nuclear Safety Advisory Group; Reports INSAG 1-10.
kBq/m2 New unit (SI) for the ground contamination.
NPP Nuclear Power Plant
RBMK Reaktor Bolshoi Moshchhnoski Kanalkni (High-Power Channel Type Reactor); Chernobyl-type reactor
RT-Scenario In the Reactor Type scenario a generic release frequency (for large off-site releases of radionucludes) for a specific type of reactor is defined. Facility-specific differences (such as ageing, different safety systems and containment types, external hazards,…) are not taken into account. For a reactor specific scenario the accidental release frequencies from a level 2 PSA have to be known for every of the more than 200 operating reactors in Europe.
PWR Pressurized Water Reactor
WWER Vodo-Vodyannoy Energeticheskiy Reactor (water-cooled, water-moderated, reactor; Russian PWR)

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