An alternate high pressure injection system for pressurized-water reactors

<p>"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.</p> <p>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°c (636°F). The maximum core average fuel cladding temperature reached during a large size cold-leg break with ICIS is 478°c (893°F). This temperature is approximately 75°c (134°F) lower than when the convential ECCS is used.</p> <p>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°c (1429°F) with the convential ECCS and temperature of 583°c (1082°F) with the ICIS.</p> <p>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.</p> <p>Based on the results obtained from this prelimanary analysis it is concluded that the ICIS performs effectively in core cooling and results in milder transients than with convential ECCS's"--Abstract, page ii.</p>

Name thesis:degree_name

Ph. D. in Nuclear Engineering

Grantor

University of Missouri--Rolla

Year dc:date.available

2016

Author dc:creator

• Mueller, Gary Edward

• Nuclear Engineering

Repository record dc:identifier

https://scholarsmine.mst.edu/doctoral_dissertations/141

OAI identifier oai:identifier

oai:scholarsmine.mst.edu:doctoral_dissertations-1143