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            <front>

                <journal-meta>
                                    <journal-id></journal-id>
            <journal-title-group>
                                                                                    <journal-title>Journal of Nuclear Sciences</journal-title>
            </journal-title-group>
                            <issn pub-type="ppub">2147-7736</issn>
                                        <issn pub-type="epub">2148-3981</issn>
                                                                                            <publisher>
                    <publisher-name>Ankara University</publisher-name>
                </publisher>
                    </journal-meta>
                <article-meta>
                                        <article-id pub-id-type="doi">10.1501/nuclear_0000000006</article-id>
                                                                <article-categories>
                                            <subj-group  xml:lang="en">
                                                            <subject>Engineering</subject>
                                                    </subj-group>
                                            <subj-group  xml:lang="tr">
                                                            <subject>Mühendislik</subject>
                                                    </subj-group>
                                    </article-categories>
                                                                                                                                                        <title-group>
                                                                                                                        <article-title>Calculation of neutron flux for the intense neutron source (µCF-INS) in optimum conditions</article-title>
                                                                                                                                                                                                <trans-title-group xml:lang="tr">
                                    <trans-title>Calculation of neutron flux for the intense neutron source (µCF-INS) in optimum conditions</trans-title>
                                </trans-title-group>
                                                                                                    </title-group>
            
                                                    <contrib-group content-type="authors">
                                                                        <contrib contrib-type="author">
                                                                <name>
                                    <surname>Chashti</surname>
                                    <given-names>M.</given-names>
                                </name>
                                                            </contrib>
                                                    <contrib contrib-type="author">
                                                                <name>
                                    <surname>M.</surname>
                                    <given-names>Chashti</given-names>
                                </name>
                                                            </contrib>
                                                    <contrib contrib-type="author">
                                                                <name>
                                    <surname>Z.</surname>
                                    <given-names>Kalantari S.</given-names>
                                </name>
                                                            </contrib>
                                                    <contrib contrib-type="author">
                                                                <name>
                                    <surname>Kalantari</surname>
                                    <given-names>S. Z.</given-names>
                                </name>
                                                            </contrib>
                                                                                </contrib-group>
                        
                                        <pub-date pub-type="pub" iso-8601-date="20140601">
                    <day>06</day>
                    <month>01</month>
                    <year>2014</year>
                </pub-date>
                                        <volume>1</volume>
                                        <issue>2</issue>
                                        <fpage>39</fpage>
                                        <lpage>43</lpage>
                        
                        <history>
                                    <date date-type="received" iso-8601-date="20140630">
                        <day>06</day>
                        <month>30</month>
                        <year>2014</year>
                    </date>
                                            </history>
                                        <permissions>
                    <copyright-statement>Copyright © 2014, Journal of Nuclear Sciences</copyright-statement>
                    <copyright-year>2014</copyright-year>
                    <copyright-holder>Journal of Nuclear Sciences</copyright-holder>
                </permissions>
            
                                                                                                <abstract><p>In this study, the neutron spectrum of a high intense neutron source (µCF-INS) based on muon catalyzed fusion was investigated in new conditions. In order to determine optimum conditions for the production of high neutron flux with 14.1 MeV energy our study was grouped intothree steps: the first includes the moderation µ- before entering into fuel mixture, the second is the calculation of neutron intensity produced by µCF cycle in D/T target and the third is simulation of output neutron flux from the device. The muon catalyzed fusion cycles were analyzed according to kinetic equations solved by Rung-Kutta method of the fourth order. Finally, transport of neutrons in DT mixture and its container was simulated by the MCNP4C code to calculate the output neutron intensity. The results show that the intensity of neutron produced by µCF-INS generator is in order of 1017ns.  When this result is compared with those from other neutron generators, µCF-INS generator operating at optimum conditions has a high neutron production yield</p></abstract>
                                                                                    
            
                                                            <kwd-group>
                                                    <kwd>neutron generator</kwd>
                                                    <kwd>   muon catalyzed fusion</kwd>
                                                    <kwd>   moderation</kwd>
                                                    <kwd>   neutron flux</kwd>
                                                    <kwd>   µCF-INS</kwd>
                                            </kwd-group>
                                                        
                                                                                                                                                    </article-meta>
    </front>
    <back>
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    </article>
