Mark I
E799459
Mark I is a General Electric-designed boiling water reactor containment system characterized by a compact, pressure-suppression torus configuration used in several nuclear power plants worldwide.
Statements (47)
| Predicate | Object |
|---|---|
| instanceOf |
boiling water reactor containment system
ⓘ
nuclear reactor containment design ⓘ |
| belongsToSeries | GE BWR containment Mark series NERFINISHED ⓘ |
| contrastedWith |
Mark II containment
ⓘ
Mark III containment ⓘ large dry containment ⓘ |
| countryOfUse |
Japan
NERFINISHED
ⓘ
United States of America ⓘ
surface form:
United States
several other countries ⓘ |
| designer | General Electric NERFINISHED ⓘ |
| developedBy | General Electric Nuclear Energy NERFINISHED ⓘ |
| followedBy |
Mark II
NERFINISHED
ⓘ
Mark III NERFINISHED ⓘ |
| hasComponent |
drywell
ⓘ
suppression pool ⓘ torus-shaped suppression pool ⓘ vent pipes from drywell to suppression pool ⓘ wetwell ⓘ |
| hasConfiguration | pressure-suppression containment ⓘ |
| hasCriticism | limited margin for pressure buildup in severe accidents ⓘ |
| hasDesignElement |
reinforced concrete secondary containment structures
ⓘ
steel primary containment structure ⓘ |
| hasDesignGoal |
provide pressure suppression capability
ⓘ
reduce containment size and cost ⓘ |
| hasFeature |
compact containment volume
ⓘ
pressure-suppression torus ⓘ wetwell and drywell arrangement ⓘ |
| hasMitigationMeasure |
filtered vent systems
ⓘ
hardened containment vent systems ⓘ |
| hasRegulatoryAttention | true ⓘ |
| hasRiskConcern |
potential for hydrogen accumulation
ⓘ
vulnerability to severe core damage events ⓘ |
| hasShape | compact torus configuration ⓘ |
| introducedAs | early generation BWR containment design ⓘ |
| manufacturer | General Electric NERFINISHED ⓘ |
| notableEventAssociation | Fukushima Daiichi nuclear disaster NERFINISHED ⓘ |
| precededBy | early prototype BWR containments ⓘ |
| pressureSuppressionMethod | steam condensation in suppression pool ⓘ |
| primaryFunction |
containment of radioactive materials in accident conditions
ⓘ
pressure suppression during loss-of-coolant accidents ⓘ |
| reactorType | boiling water reactor ⓘ |
| safetyEnhancement | post-Fukushima backfit modifications in several plants ⓘ |
| safetyObjective | limit release of fission products during accidents ⓘ |
| typicalApplication | BWR units of small to medium electrical output ⓘ |
| usedIn |
boiling water reactor nuclear power plants
ⓘ
commercial nuclear power plants ⓘ |
| usedWorldwide | true ⓘ |
Referenced by (1)
Full triples — surface form annotated when it differs from this entity's canonical label.