\"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°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.
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.
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 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.
","abstract_html":"<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>","abstract_has_math":false,"creators":["Mueller, Gary Edward"],"institution":"University of Missouri--Rolla","degree_name":"Ph. D. in Nuclear Engineering","degree_level":null,"degree_discipline":null,"degree_department":null,"school":null,"contributors":[],"advisors":[],"committee_chairs":[],"committee_members":[],"year":2016,"date_issued":"2016-02-10T08:00:00Z","date_published":"2016-02-10T08:00:00Z","updated_at":"2026-07-24T03:19:38Z","subjects":["Nuclear Engineering"],"languages":[],"rights":[],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"https://scholarsmine.mst.edu/doctoral_dissertations/141","outbound_label":"Repository record","outbound_source":"dc:identifier"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:creator","label":"Author","values":["Mueller, Gary Edward"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date.available","label":"Dc Date Available","values":["2016-02-10T08:00:00Z"]},{"key":"dc:type","label":"Dc Type","values":["Dissertation - Open Access"]},{"key":"thesis:degree_name","label":"Degree Name","values":["Ph. D. in Nuclear Engineering"]},{"key":"thesis:institution_name","label":"Thesis Institution Name","values":["University of Missouri--Rolla"]}]},{"id":"subjects_keywords","label":"Subjects and Keywords","entries":[{"key":"dc:subject","label":"Dc Subject","values":["Nuclear Engineering"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier","label":"Identifier","values":["https://scholarsmine.mst.edu/doctoral_dissertations/141"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description.abstract","label":"Abstract","values":["\"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°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.
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.
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 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.
"]},{"key":"dc:title","label":"Title","values":["An alternate high pressure injection system for pressurized-water reactors"]}]}],"canonical_facts":{"dc:creator":["Mueller, Gary Edward"],"dc:date.available":["2016-02-10T08:00:00Z"],"dc:description.abstract":["\"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°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.
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.
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 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.
"],"dc:identifier":["https://scholarsmine.mst.edu/doctoral_dissertations/141"],"dc:subject":["Nuclear Engineering"],"dc:title":["An alternate high pressure injection system for pressurized-water reactors"],"dc:type":["Dissertation - Open Access"],"thesis:degree_name":["Ph. D. in Nuclear Engineering"],"thesis:institution_name":["University of Missouri--Rolla"]},"updated_at":"2026-07-24T03:19:38Z"}