Doctoral Dissertations

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.

Advisor(s)

Edwards, D. R.

Committee Member(s)

Tsoulfanidis, Nicholas
Culp, Archie W., Jr.
Senne, Joseph H.
Landers, Robert G.

Department(s)

Nuclear Engineering and Radiation Science

Degree Name

Ph. D. in Nuclear Engineering

Publisher

University of Missouri--Rolla

Publication Date

Fall 1980

Pagination

xi, 159 pages

Note about bibliography

Includes bibliographical references (pages 121-122).

Rights

© 1980 Gary Edward Mueller, All rights reserved.

Document Type

Dissertation - Open Access

File Type

text

Language

English

Thesis Number

T 4593

Print OCLC #

7507409

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