Analysis of PIUS Reactor Passive Shutdown Using PC-Based Model

Conference · Sun Oct 25 00:00:00 EDT 1992

OSTI ID:7178617

Cheng, H. S. ^[1]; Van Tuyle, G. J. ^[1]

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1. Brookhaven National Laboratory (BNL), Upton, NY (United States)

A simplified model of the PIUS 600 Reactor System is described, and results from two event simulations are discussed, and compared with ABB's predicted results. The model is based on a BWR Plant Analyzer developed by BNL, with PIUS-specific models added for the density locks. Initial results support the effectiveness of the passive reactor shutdown, although some significant power oscillations occur before the shutdown is completed.

• Research Organization: Brookhaven National Lab. (BNL), Upton, NY (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Nuclear Regulatory Commission (USNRC)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 7178617
• Report Number(s): BNL-NUREG-47809; CONF-921003-2; ON: DE92019258
• Resource Relation: Conference: ANP'92: International Conference on Design and Safety of Advanced Nuclear Power Plants, Tokyo (Japan), 25-28 Oct 1992
• Country of Publication: United States
• Language: English

Related Subjects

97 MATHEMATICS AND COMPUTING
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR SHUTDOWN
AFTER-HEAT REMOVAL
COMPUTERIZED SIMULATION
EXCURSIONS
P CODES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
ENRICHED URANIUM REACTORS
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
REMOVAL
SAFETY
SHUTDOWN
SIMULATION
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
Nuclear Criticality Safety Program (NCSP)
PIUS lnteractive Plant Analyzer (PIPA)
Failure Modes, Effects, and Criticality Analysis (FMECA)
Hazards and Operability (HAZOP) Analysis
Two-Phase Flow Coolant Dynamics
Density Locks
Boron Transport
Thermal Conduction
Fuel Elements
Neutron Kinetics
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled