Vermont Yankee simulator qualification: large-break LOCA
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6866849
Yankee Atomic Electric Company (YAEC) has developed simulator benchmark capabilities for the Seabrook, Maine Yankee, and Vermont Yankee Nuclear Power Station (VYNPS) simulators. The goal is to establish that each simulator has a satisfactory real-time response for different scenarios that will enhance operator training. Vermont Yankee purchased a full-scope plane simulator for the VYNPS, a four-unit boiling water reactor with a Mark-I containment. The following seven benchmark cases were selected by YAEC and VYNPC to supplement the Simulator Acceptance Test Program: (1) control rod swap; (2) partial reactor scram; (3) recirculation pump trip; (4) main steam isolation valve (MSIV) closure without scram, (5) main steamline break, (6) small-break loss-of-coolant accident (LOCA), and (7) large-break LOCA. Five simulator benchmark sessions have been completed. Each session identified simulator capabilities and limitations that needed correction. This paper discusses results from the latest large-break LOCA case.
- OSTI ID:
- 6866849
- Report Number(s):
- CONF-8711195-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ANALOG SYSTEMS
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COMPUTER CODES
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ENRICHED URANIUM REACTORS
FLUID MECHANICS
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HEAT TRANSFER
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PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTOR SIMULATORS
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SAFETY
SIMULATORS
THERMAL REACTORS
VERMONT YANKEE REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ANALOG SYSTEMS
BWR TYPE REACTORS
COMPUTER CODES
CONTAINERS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
FUNCTIONAL MODELS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
POWER REACTORS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTOR SIMULATORS
REACTORS
SAFETY
SIMULATORS
THERMAL REACTORS
VERMONT YANKEE REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS