Managing Water Addition to a Degraded Core

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

OSTI ID:10134771

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: 10134771
• Report Number(s): EGG-M-91375; CONF-911079-30; ON: DE92010807
• Resource Relation: Conference: 19. Nuclear Regulatory Commission (NRC) Water Reactor Safety Information Meeting , Bethesda, MD (United States), 28-30 Oct 1991; Other Information: PBD: [1991]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
NUCLEAR POWER PLANTS
REACTOR CORES
DAMAGE
CORIUM
HEAT TRANSFER
REACTOR SAFETY
WATER
FLUID FLOW
STEAM
PRESSURIZATION
FUEL CANS
RUPTURES
OXIDATION
Nuclear Criticality Safety Program (NCSP)
Loss-of-Coolant Accident (LOCA)
Ballooning
Bursting
Rapid Oxidation
Debris Bed Formation
Core Damage States
Fuel Rod Cladding
220900
220200
COMPONENTS AND ACCESSORIES