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An alternate high pressure injection system for pressurized-water reactors

Thesis/Dissertation ·
OSTI ID:5328489
To evaluate the In-Core Injection system (ICIS) performance during a loss-of-coolant accident (LOCA) due to a major rupture in the primary system of a pressurized water reactor (PWR), tests were conducted using the thermal-hydraulic computer code RELAP4/MOD5. The results for the overall plant system show that the maximum core average fuel cladding temperature reached during an intermediate size cold-leg break in a Combustion Engineering PWR with ICIS is equal to the initial operating temperature of 335/sup 0/C (636/sup 0/F). The maximum core average fuel cladding temperature reached during a large size cold-leg break with ICIS is 478/sup 0/C (893/sup 0/F). This temperature is approximately 75/sup 0/C (134/sup 0/F) lower than when the convential ECCS is used. Results obtained from the hot channel analysis for a large size cold-leg break show that the most severe conditions in the core generate maximum cladding temperatures of 776/sup 0/C (1429/sup 0/F) with the convential ECCS and temperature of 583/sup 0/C (1082/sup 0/F) with the ICIS. These results are expected because of the higher flow rate in the core and thus shorter quenching time caused by the injection of the ICIS coolant throughout the blowdown period. Based on the results obtained from this preliminary analysis it is concluded that the ICIS performs effectively in core cooling and results in milder transients than with convential ECCS's.
Research Organization:
Missouri Univ., Rolla (USA)
OSTI ID:
5328489
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
COMPUTER CALCULATIONS
COMPUTER CODES
ECCS
ENGINEERED SAFETY SYSTEMS
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LOSS OF COOLANT
PERFORMANCE
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS