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   <dim:field mdschema="dc" element="contributor" qualifier="advisor" lang="en_US">Neil E. Todreas and William D. Hinkle.</dim:field>
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   <dim:field mdschema="dc" element="contributor" qualifier="department">Massachusetts Institute of Technology. Department of Nuclear Science and Engineering</dim:field>
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   <dim:field mdschema="dc" element="description" lang="en_US">Thesis (Nucl.E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1981.</dim:field>
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   <dim:field mdschema="dc" element="description" qualifier="statementofresponsibility" lang="en_US">by James North Loomis.</dim:field>
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   <dim:field mdschema="dc" element="rights" lang="en_US">M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission.</dim:field>
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   <dim:field mdschema="dc" element="subject" lang="en_US">Nuclear Engineering.</dim:field>
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   <dim:field mdschema="dc" element="subject" qualifier="lcsh" lang="en_US">Boiling water reactors Fluid dynamics</dim:field>
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   <dim:field mdschema="dc" element="subject" qualifier="lcsh" lang="en_US">Light water reactors Thermal properties</dim:field>
   <dim:field mdschema="dc" element="title" lang="en_US">Reactor thermal-hydraulic analysis improvement and application of the code COBRA-IIIC/MIT</dim:field>
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