TRAC-PF1/MOD1 predictions of a noncondensible gas on pressurizer insurge transients

Conference · Wed Jan 01 04:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6883218

Hassan, Y A

The pressurizer response to pressurized water reactor transients plays an important role in determining the pressure history of the primary coolant system. In accidents, nitrogen gas can be discharged into the reactor system from the accumulator and flooding tanks after the water inventory is depleted. The presence of the noncondensible gases has a significant effect on pressurizer response. The purpose of this study is to simulate the Massachusetts Institute of Technology (MIT) pressurizer insurge transients in which the vapor region contains steam mixed with nitrogen using the TRAC-PF1/MOD1 thermal-hydraulic computer code. The predicted peak pressurizer pressure results are in good agreement with the data for various noncondensible mass fractions. The calculations show higher pressures with adiabatic vessel wall (no heat loss) during insurges; however, reasonable agreement with the measurements is obtained when the heat loss from the vessel wall is taken into account.

• Research Organization: Babcock and Wilcox, Lynchburg, VA
• OSTI ID: 6883218
• Report Number(s): CONF-860610-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
PRESSURIZERS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
STEAM
T CODES
TRANSIENTS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS