Published May 1984
| Version v1
Journal article
Radiolytic gas generation after loss-of-coolant accident in a boiling-water reactor
Description
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
Additional details
Publishing Information
- Journal Title
- Nucl. Saf.
- Journal Volume
- 25
- Journal Issue
- 3
- Series
- Nucl. Saf.
- Journal Page Range
- 329-340
- ISSN
- 0029-5604
- CODEN
- NUSAA
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17044942
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONTAINMENT SYSTEMS; CORE SPRAY SYSTEMS; EXPLOSIONS; GASES; HYDROGEN; IMPURITIES; LOSS OF COOLANT; NITROGEN; OKG-1 REACTOR; OXYGEN; PRESSURE SUPPRESSION; RADIOLYSIS; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR SHUTDOWN; SENSITIVITY ANALYSIS
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; CONTAINMENT; DECOMPOSITION; ECCS; ELEMENTS; ENRICHED URANIUM REACTORS; FLUIDS; NONMETALS; POWER REACTORS; RADIATION EFFECTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SHUTDOWN; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS