<?xml version="1.0" encoding="UTF-8"?><?xml-stylesheet type="text/xsl" href="static/style.xsl"?><OAI-PMH xmlns="http://www.openarchives.org/OAI/2.0/" xmlns:xsi="http://www.w3.org/2001/XMLSchema-instance" xsi:schemaLocation="http://www.openarchives.org/OAI/2.0/ http://www.openarchives.org/OAI/2.0/OAI-PMH.xsd"><responseDate>2026-09-19T10:58:34Z</responseDate><request verb="GetRecord" identifier="oai:dspace.mit.edu:1721.1/45495" metadataPrefix="dim">https://dspace.mit.edu/server/oai/request</request><GetRecord><record><header><identifier>oai:dspace.mit.edu:1721.1/45495</identifier><datestamp>2021-07-05T14:03:20Z</datestamp><setSpec>com_1721.1_7582</setSpec><setSpec>com_1721.1_7581</setSpec><setSpec>col_1721.1_131023</setSpec></header><metadata><dim:dim xmlns:dim="http://www.dspace.org/xmlns/dspace/dim" xmlns:xsi="http://www.w3.org/2001/XMLSchema-instance" xmlns:doc="http://www.lyncode.com/xoai" xsi:schemaLocation="http://www.dspace.org/xmlns/dspace/dim http://www.dspace.org/schema/dim.xsd">
   <dim:field mdschema="dc" element="contributor" qualifier="advisor" lang="en_US">Mujid S. Kazimi and Michael J. Driscoll.</dim:field>
   <dim:field mdschema="dc" element="contributor" qualifier="author" lang="en_US">Bollmann, Chad A. (Chad Arnold), 1974-</dim:field>
   <dim:field mdschema="dc" element="contributor" qualifier="department" lang="en_US">Massachusetts Institute of Technology. Department of Nuclear Science and Engineering</dim:field>
   <dim:field mdschema="dc" element="contributor" qualifier="department" lang="en_US">Sloan School of Management</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="accessioned">2009-04-29T17:50:24Z</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="available">2009-04-29T17:50:24Z</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="copyright" lang="en_US">1998</dim:field>
   <dim:field mdschema="dc" element="date" qualifier="issued" lang="en_US">1998</dim:field>
   <dim:field mdschema="dc" element="identifier" qualifier="uri">http://hdl.handle.net/1721.1/45495</dim:field>
   <dim:field mdschema="dc" element="identifier" qualifier="oclc" lang="en_US">42255431</dim:field>
   <dim:field mdschema="dc" element="description" lang="en_US">Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering; and, (S.M.)--Massachusetts Institute of Technology, Sloan School of Management, 1998.</dim:field>
   <dim:field mdschema="dc" element="description" lang="en_US">Includes bibliographical references (leaves 109-111).</dim:field>
   <dim:field mdschema="dc" element="description" qualifier="abstract" lang="en_US">A study of the DUPIC (Direct Use of Spent PWR Fuel In CANDU) cycle was made to analyze cycle performance relative to that of PWR and CANDU fuel cycles in terms of uranium utilization and spent fuel production efficiency. The DUPIC cycle was found to be most efficient in terms of minimizing spent fuel production as well as most efficient (within limits) in terms of maximizing natural uranium utilization. It was found minimally productive to change PWR fuel management practices in order to extend burnup in the CANDU portion of the cycle. A policy analysis regarding potential implementation of the DUPIC cycle in North America, between the U.S. and Canada, was also made. CASMO computer models of PWR, CANDU, and CANFLEX fuel assemblies were created and benchmarked. The PWR models were then used to develop analytical correlations that predict PWR spent fuel isotopic compositions. Correlations that predict reactivity gain and burnup increase in CANDU reactors due to AIROX processing of PWR spent fuel were created. An estimate of fission product removal fractions during AIROX processing was developed. An integrated model that predicts CANDU discharge burnup extension due to the use of spent PWR fuel and AIROX processing was completed and used to analyze and compare the DUPIC cycle to other fuel cycles. The potential issues involved in implementation of a DUPIC cycle between the U.S. and Canada were examined. Stakeholders and influential groups were identified and their values were projected. A significant unresolved issue centers around which nation assumes custody of the DUPIC spent fuel and the disposal costs of that fuel. A plan for DUPIC cycle implementation was developed.</dim:field>
   <dim:field mdschema="dc" element="description" qualifier="statementofresponsibility" lang="en_US">by Chad A. Bollmann.</dim:field>
   <dim:field mdschema="dc" element="description" qualifier="degree" lang="en_US">S.M.</dim:field>
   <dim:field mdschema="dc" element="format" qualifier="extent" lang="en_US">139 leaves</dim:field>
   <dim:field mdschema="dc" element="language" qualifier="iso" lang="en_US">eng</dim:field>
   <dim:field mdschema="dc" element="publisher" lang="en_US">Massachusetts Institute of Technology</dim:field>
   <dim:field mdschema="dc" element="rights" lang="en_US">M.I.T. theses are protected by &#xd;
copyright. They may be viewed from this source for any purpose, but &#xd;
reproduction or distribution in any format is prohibited without written &#xd;
permission. See provided URL for inquiries about permission.</dim:field>
   <dim:field mdschema="dc" element="rights" qualifier="uri" lang="en_US">http://dspace.mit.edu/handle/1721.1/7582</dim:field>
   <dim:field mdschema="dc" element="subject" lang="en_US">Nuclear Engineering</dim:field>
   <dim:field mdschema="dc" element="subject" lang="en_US">Sloan School of Management</dim:field>
   <dim:field mdschema="dc" element="title" lang="en_US">Optimization of DUPIC cycle environmental and economic performance</dim:field>
   <dim:field mdschema="dc" element="title" qualifier="alternative" lang="en_US">Optimization of direct use of spent pressureized water reactor fuel in the Canadian Deuterium Reactor cycle environmental and economic performance</dim:field>
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   	&lt;Title>Optimization of DUPIC cycle environmental and economic performance&lt;/Title>
   	&lt;Subtitle>Optimization of direct use of spent pressureized water reactor fuel in the Canadian Deuterium Reactor cycle environmental and economic performance&lt;/Subtitle>
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   	&lt;PublicationDate>1998&lt;/PublicationDate>
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        	&lt;DisplayName>Bollmann, Chad A. (Chad Arnold), 1974-&lt;/DisplayName>
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    &lt;Keyword>Nuclear Engineering&lt;/Keyword>
    &lt;Keyword>Sloan School of Management&lt;/Keyword>
   	&lt;Abstract>A study of the DUPIC (Direct Use of Spent PWR Fuel In CANDU) cycle was made to analyze cycle performance relative to that of PWR and CANDU fuel cycles in terms of uranium utilization and spent fuel production efficiency. The DUPIC cycle was found to be most efficient in terms of minimizing spent fuel production as well as most efficient (within limits) in terms of maximizing natural uranium utilization. It was found minimally productive to change PWR fuel management practices in order to extend burnup in the CANDU portion of the cycle. A policy analysis regarding potential implementation of the DUPIC cycle in North America, between the U.S. and Canada, was also made. CASMO computer models of PWR, CANDU, and CANFLEX fuel assemblies were created and benchmarked. The PWR models were then used to develop analytical correlations that predict PWR spent fuel isotopic compositions. Correlations that predict reactivity gain and burnup increase in CANDU reactors due to AIROX processing of PWR spent fuel were created. An estimate of fission product removal fractions during AIROX processing was developed. An integrated model that predicts CANDU discharge burnup extension due to the use of spent PWR fuel and AIROX processing was completed and used to analyze and compare the DUPIC cycle to other fuel cycles. The potential issues involved in implementation of a DUPIC cycle between the U.S. and Canada were examined. Stakeholders and influential groups were identified and their values were projected. A significant unresolved issue centers around which nation assumes custody of the DUPIC spent fuel and the disposal costs of that fuel. A plan for DUPIC cycle implementation was developed.&lt;/Abstract>
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