Dynamic system characterization of an integral test facility of an advanced PWR /
analysis. These equations were used for the linear analysis
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| Format: | Thesis eBook |
| Language: | English |
| Published: |
[Place of publication not identified] :
[publisher not identified] ;
1995.
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| Subjects: | |
| Online Access: | Link to OAKTrust copy |
| Summary: | analysis. These equations were used for the linear analysis and actuators for its safety functions. The inclusion of and their topology, as they are used to characterize such a any conventional pressurized water reactor, in which the assessment against AP600 relevant phenomena. The AP600 bond graph methodology was used to formulate the equations complex system. This characterization was applied to one of Core Makeup Tanks and passive heat removal systems into the design increase its dynamic complexity well beyond that of design relies only on passive safety features such as gravity driven draining pressurized tanks, and battery power logic equations were linearized for a selected period of the Large Scale Test Facility (LSTF), which has been selected by mathematical model of the system. The model's constitutive of the system. one-inch cold leg break (AP-CL-03), to construct a performing a series of tests to generate data for code safeties can be treated as imposed boundary conditions. The testing of the Westinghouse AP600 design. The LSTF is the Rig of Safety Assessment (ROSA) program transients, the the U.S. Nuclear Regulatory Commission for confirmatory This work characterizes the dynamic behavior for the modified transient that is of particular importance to the safety |
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| Item Description: | "Major subject: Nuclear Engineering". Vita. |
| Physical Description: | ix, 75 leaves : illustrations ; 28 cm. Also available online. Issued also on microfiche from Lange Micrographics. |
| Bibliography: | Includes bibliographical references. |