Analysis of a PWR natural circulation transient at beginning of life

Conference · Fri Jan 01 04:00:00 EST 1988 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5914309

Mosteller, R D; Jensen, P J; Anderson, M J; Eisenhart, L D; Abdollahian, R; Chao, J; Eich, W J

A pressurized water reactor (PWR) with a positive moderator temperature coefficient (MTC) of reactivity is potentially susceptible to a severe overheating transient, particularly if some of its scram setpoints have been disabled. This study identifies an actual scenario in which such a transient could occur and analyzes it to determine whether domestic PWRs are susceptible to a catastrophic power excursion, which might occur as the result of a scram failure. The MTC is of paramount importance in transients of this type. In fact, the behavior of the MTC is the primary factor in determining the severity of the transient. To determine the inherent safety of PWR cores with respect to such postulated transients, a PWR that constitutes the most susceptible reactor of this type has been analyzed. It contains low-enrichment fuel of an advanced design, partial length burnable poisons, and a high critical soluble boron concentration at beginning of life (BOL). The analysis of the transient employed portions of the Electric Power Research Institute's ARMP-02 physics package in conjunction with its advanced nodal code ARROTTA and a slightly modified version of its RETRAN-02 systems transient code. This study has demonstrated that US PWRs are not susceptible to catastrophic power excursions that might occur as the result of a scram failure during natural circulation tests.

• OSTI ID: 5914309
• Report Number(s): CONF-881011-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 57
• Country of Publication: United States
• Language: English

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A CODES
ACTINIDES
BORON
BURNABLE POISONS
CALIBRATION
COMPUTER CODES
COMPUTERIZED SIMULATION
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COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
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KINETICS
MASS TRANSFER
MATERIALS
MECHANICS
METALS
MODERATING RATIO
MODERATORS
NATURAL CONVECTION
NEUTRON ABSORBERS
NUCLEAR POISONS
POWER DENSITY
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
R CODES
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REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR INSTRUMENTATION
REACTOR KINETICS
REACTOR MATERIALS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
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SCRAM
SEMIMETALS
SENSITIVITY
SHUTDOWNS
SIMULATION
SLIGHTLY ENRICHED URANIUM
SOLUBLE POISONS
TEMPERATURE DEPENDENCE
TRANSIENTS
URANIUM
WATER COOLED REACTORS
WATER MODERATED REACTORS