Radiolytic gas generation after loss-of-coolant accident in a boiling-water reactor

Journal Article · · Nucl. Saf.; (United States)

OSTI ID:6205497

Christensen, H; Soederman, E

This report elucidates the probable true supply of radiolytic gas to a nitrogen-filled pressure suppression containment under accident conditions in boiling-water reactors. Calculations have been performed using a computer-based program developed at Riso National Laboratory in Denmark. Measurements of the radiolytic gas contents in water and vapor after shutdown have been performed at Oskarshamn I. These measurements have been compared with results from computer calculations. It is concluded that, after an accident, a recombiner system would probably not be required to limit the concentration of radiolytic gas to safe values but, in any event, would only be necessary considerably later in the accident than was previously assumed.

• Research Organization: Studsvik Energiteknik AB, Nykoeping, Sweden
• OSTI ID: 6205497
• Journal Information: Nucl. Saf.; (United States), Vol. 25:3
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONTAINMENT SYSTEMS
GASES
OKG-1 REACTOR
REACTOR ACCIDENTS
LOSS OF COOLANT
CORE SPRAY SYSTEMS
EXPLOSIONS
HYDROGEN
IMPURITIES
NITROGEN
OXYGEN
PRESSURE SUPPRESSION
RADIOLYSIS
REACTOR SAFETY
REACTOR SHUTDOWN
SENSITIVITY ANALYSIS
ACCIDENTS
BWR TYPE REACTORS
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CONTAINMENT
DECOMPOSITION
ECCS
ELEMENTS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLUIDS
NONMETALS
POWER REACTORS
RADIATION CHEMISTRY
RADIATION EFFECTS
REACTOR PROTECTION SYSTEMS
REACTORS
SAFETY
SHUTDOWNS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled