A concept of a small controlled, filtered venting system and an add-on decay heat removal system to mitigate the consequences of core-melt accidents
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5664312
Core-melt accidents as modeled in risk studies result in severe consequences to the environment of a nuclear power plant, only if the containment function of the plant is assumed to fail during the accident. To protect the containment function of a pressurized water reactor with double containment during a core-melt accident against the dominant late failure modes, a relief condenser vent system, if useful or necessary, in combination with an outside spray cooling between the primary steel containment and the secondary concrete containment, is proposed. The outside spray cooling system supports the removal of the decay heat by condensing evaporated sump water at the primary containment shell. Pressure buildup caused by the generated noncondensable gases is effectively limited by the relief condenser vent system located within the primary containment. Thereby, a relatively small flow of the steam-gas mixture in the containment is first guided through a condenser where most of the steam is condensed. The remaining noncondensable gases are then released via a conventional outside filter train in a controlled manner. Safety problems due to hydrogen combustion, which may arise due to the operation of the proposed system, can be prevented by design and operation of the system. By venting, the containment atmosphere is finally inerted.
- Research Organization:
- Swiss Federal Nuclear Safety Inspectorate, 5303 Wurenlingen
- OSTI ID:
- 5664312
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 73:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
Steam vents and drains subsystem design description: 4 x 350 MW(t) Modular HTGR [High-Temperature Gas-Cooled Reactor] Plant
Troubleshooting surface condenser venting systems
Design criteria and concepts for vented containment systems
Technical Report
·
Sun Jun 01 00:00:00 EDT 1986
·
OSTI ID:714069
Troubleshooting surface condenser venting systems
Technical Report
·
Thu Aug 01 00:00:00 EDT 1996
·
OSTI ID:414840
Design criteria and concepts for vented containment systems
Conference
·
Mon Dec 31 23:00:00 EST 1979
·
OSTI ID:6884468
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
BUILDING MATERIALS
CONCRETES
CONDENSERS
CONTAINMENT
CONTAINMENT SHELLS
COOLING
COOLING SYSTEMS
ENERGY SYSTEMS
ENVIRONMENTAL IMPACTS
FAILURES
MATERIALS
MATHEMATICAL MODELS
MELTDOWN
MITIGATION
PRESSURE EFFECTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
RHR SYSTEMS
RISK ASSESSMENT
SPRAY COOLING
VENTILATION SYSTEMS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
BUILDING MATERIALS
CONCRETES
CONDENSERS
CONTAINMENT
CONTAINMENT SHELLS
COOLING
COOLING SYSTEMS
ENERGY SYSTEMS
ENVIRONMENTAL IMPACTS
FAILURES
MATERIALS
MATHEMATICAL MODELS
MELTDOWN
MITIGATION
PRESSURE EFFECTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
RHR SYSTEMS
RISK ASSESSMENT
SPRAY COOLING
VENTILATION SYSTEMS
WATER COOLED REACTORS
WATER MODERATED REACTORS