Managing Water Addition to a Degraded Core

Conference · Mon Oct 28 04:00:00 EST 1991

OSTI ID:5642843

Kuan, P. ^[1]; Hanson, D. J. ^[1]; Odar, F. ^[2]

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1. Idaho National Engineering Laboratory (INEL), Idaho Falls, ID (United States). EG&G Idaho, Inc.
2. US Nuclear Regulatory Commission (USNRC), Washington, DC (United States)

In this paper we present information that can be used in severe accident management by providing an improved understanding of the effects of water addition to a degraded core. This improved understanding is developed using a diagram showing a sequence of core damage states. Whenever possible, a temperature and a time after accident initiation are estimated for each damage state in the sequence diagram. This diagram can be used to anticipate the evolution of events during an accident. Possible responses of plant instruments are described to identify these damage states and the effects of water addition. The rate and amount of water addition needed (1) to remove energy from the core, (2) to stabilize the core or (3) to not adversely affect the damage progression, are estimated. Analysis of the capability to remove energy from large cohesive and particulate debris beds indicates that these beds may not be stabilized in the core region, and they may partially relocate to the lower plenum of the reactor vessel.

• Research Organization: Idaho National Engineering Laboratory (INEL), Idaho Falls, ID (United States). EG&G Idaho, Inc.; US Nuclear Regulatory Commission (USNRC), Washington, DC (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Nuclear Regulatory Commission (USNRC), Office of Nuclear Regulatory Research
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5642843
• Report Number(s): EGG-M-91375; CONF-911079--30; ON: DE92010807
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
Ballooning
Bursting
CHEMICAL REACTIONS
CORIUM
Core Damage States
DAMAGE
Debris Bed Formation
ENERGY TRANSFER
FAILURES
FLUID FLOW
FUEL CANS
Fuel Rod Cladding
HEAT TRANSFER
HYDROGEN COMPOUNDS
Loss-of-Coolant Accident (LOCA)
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
Nuclear Criticality Safety Program (NCSP)
OXIDATION
OXYGEN COMPOUNDS
POWER PLANTS
PRESSURIZATION
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
RUPTURES
Rapid Oxidation
SAFETY
STEAM
THERMAL POWER PLANTS
WATER