Multiobjective Optimization Shielding Design for Compact Accelerator-Driven Neutron Sources by Application of NSGA-II and MCNP
To find the optimal shielding design for compact accelerator-driven neutron sources (CANS) using multiobjective optimization, we developed a new method called nondominated sorting genetic algorithm-Monte Carlo method (NSGA-MC). NSGA-MC employs NSGA-II to optimize the shielding parameters based on ca...
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| Veröffentlicht in: | IEEE transactions on nuclear science 2021-02, Vol.68 (2), p.110-117 |
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| creator | Ma, Baolong Song, Lei Yan, Mingfei Ikeda, Yujiro Otake, Yoshie Wang, Sheng |
| description | To find the optimal shielding design for compact accelerator-driven neutron sources (CANS) using multiobjective optimization, we developed a new method called nondominated sorting genetic algorithm-Monte Carlo method (NSGA-MC). NSGA-MC employs NSGA-II to optimize the shielding parameters based on calculations made by the Monte Carlo N-Particle Transport Code (MCNP). A layered shielding configuration with two materials of borated polyethylene (BPE) and lead (Pb) in the order of BPE/Pb/BPE/Pb for RIKEN Accelerator-driven Compact Neutron Source (RANS) was examined using this method, and two objectives were optimized simultaneously: equivalent dose rate and shielding structure weight. As a result, a tradeoff relationship between the objectives was finally obtained in the form of a Pareto front. The optimization results revealed significant improvements compared with the current RANS shielding configurations in terms of both dose and weight. The results indicate that a reduction in shielding weight of about 60% can be obtained by adopting the optimized shielding structure design, without sacrificing shielding performance. The performance of the method was discussed by showing advantages of NSGA-MC over the so-called weight sum method. |
| doi_str_mv | 10.1109/TNS.2020.3040500 |
| format | Article |
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NSGA-MC employs NSGA-II to optimize the shielding parameters based on calculations made by the Monte Carlo N-Particle Transport Code (MCNP). A layered shielding configuration with two materials of borated polyethylene (BPE) and lead (Pb) in the order of BPE/Pb/BPE/Pb for RIKEN Accelerator-driven Compact Neutron Source (RANS) was examined using this method, and two objectives were optimized simultaneously: equivalent dose rate and shielding structure weight. As a result, a tradeoff relationship between the objectives was finally obtained in the form of a Pareto front. The optimization results revealed significant improvements compared with the current RANS shielding configurations in terms of both dose and weight. The results indicate that a reduction in shielding weight of about 60% can be obtained by adopting the optimized shielding structure design, without sacrificing shielding performance. The performance of the method was discussed by showing advantages of NSGA-MC over the so-called weight sum method.</description><identifier>ISSN: 0018-9499</identifier><identifier>EISSN: 1558-1578</identifier><identifier>DOI: 10.1109/TNS.2020.3040500</identifier><identifier>CODEN: IETNAE</identifier><language>eng</language><publisher>New York: IEEE</publisher><subject>Acceleration ; Compact accelerator-driven neutron sources (CANS) ; Configurations ; Design ; Design optimization ; Dosage ; equivalent dose rate ; Genetic algorithms ; Lead ; Linear programming ; Monte Carlo N-particle transport code (MCNP) ; Monte Carlo simulation ; multiobjective shielding design ; Multiple objective analysis ; Neutron sources ; Neutrons ; nondominated sorting genetic algorithm (NSGA) ; Optimization ; Pareto optimization ; Polyethylene ; Polyethylenes ; Shielding ; shielding weight ; Sociology ; Sorting ; Sorting algorithms ; Statistics ; Weight</subject><ispartof>IEEE transactions on nuclear science, 2021-02, Vol.68 (2), p.110-117</ispartof><rights>Copyright The Institute of Electrical and Electronics Engineers, Inc. (IEEE) 2021</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c291t-9c2faf5b026d0cfd02022634ac661eae2758b78fbb87227205be4e1a7aa7ba603</citedby><cites>FETCH-LOGICAL-c291t-9c2faf5b026d0cfd02022634ac661eae2758b78fbb87227205be4e1a7aa7ba603</cites><orcidid>0000-0003-3494-8935 ; 0000-0003-1131-0066</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://ieeexplore.ieee.org/document/9270021$$EHTML$$P50$$Gieee$$H</linktohtml><link.rule.ids>314,776,780,792,27901,27902,54733</link.rule.ids><linktorsrc>$$Uhttps://ieeexplore.ieee.org/document/9270021$$EView_record_in_IEEE$$FView_record_in_$$GIEEE</linktorsrc></links><search><creatorcontrib>Ma, Baolong</creatorcontrib><creatorcontrib>Song, Lei</creatorcontrib><creatorcontrib>Yan, Mingfei</creatorcontrib><creatorcontrib>Ikeda, Yujiro</creatorcontrib><creatorcontrib>Otake, Yoshie</creatorcontrib><creatorcontrib>Wang, Sheng</creatorcontrib><title>Multiobjective Optimization Shielding Design for Compact Accelerator-Driven Neutron Sources by Application of NSGA-II and MCNP</title><title>IEEE transactions on nuclear science</title><addtitle>TNS</addtitle><description>To find the optimal shielding design for compact accelerator-driven neutron sources (CANS) using multiobjective optimization, we developed a new method called nondominated sorting genetic algorithm-Monte Carlo method (NSGA-MC). NSGA-MC employs NSGA-II to optimize the shielding parameters based on calculations made by the Monte Carlo N-Particle Transport Code (MCNP). A layered shielding configuration with two materials of borated polyethylene (BPE) and lead (Pb) in the order of BPE/Pb/BPE/Pb for RIKEN Accelerator-driven Compact Neutron Source (RANS) was examined using this method, and two objectives were optimized simultaneously: equivalent dose rate and shielding structure weight. As a result, a tradeoff relationship between the objectives was finally obtained in the form of a Pareto front. The optimization results revealed significant improvements compared with the current RANS shielding configurations in terms of both dose and weight. The results indicate that a reduction in shielding weight of about 60% can be obtained by adopting the optimized shielding structure design, without sacrificing shielding performance. The performance of the method was discussed by showing advantages of NSGA-MC over the so-called weight sum method.</description><subject>Acceleration</subject><subject>Compact accelerator-driven neutron sources (CANS)</subject><subject>Configurations</subject><subject>Design</subject><subject>Design optimization</subject><subject>Dosage</subject><subject>equivalent dose rate</subject><subject>Genetic algorithms</subject><subject>Lead</subject><subject>Linear programming</subject><subject>Monte Carlo N-particle transport code (MCNP)</subject><subject>Monte Carlo simulation</subject><subject>multiobjective shielding design</subject><subject>Multiple objective analysis</subject><subject>Neutron sources</subject><subject>Neutrons</subject><subject>nondominated sorting genetic algorithm (NSGA)</subject><subject>Optimization</subject><subject>Pareto optimization</subject><subject>Polyethylene</subject><subject>Polyethylenes</subject><subject>Shielding</subject><subject>shielding weight</subject><subject>Sociology</subject><subject>Sorting</subject><subject>Sorting algorithms</subject><subject>Statistics</subject><subject>Weight</subject><issn>0018-9499</issn><issn>1558-1578</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2021</creationdate><recordtype>article</recordtype><sourceid>RIE</sourceid><recordid>eNo9kM1Lw0AQxRdRsFbvgpcFz6mz22yyewyp1kI_hNZz2GwndUuaxE0i1IN_u1sqnoYZ3u_NzCPknsGIMVBPm-V6xIHDaAwhCIALMmBCyICJWF6SAQCTgQqVuiY3bbv3bShADMjPoi87W-d7NJ39QrpqOnuw39rPKrr-sFhubbWjE2ztrqJF7WhaHxptOpoYgyU63dUumDjPVnSJfedOXN07gy3NjzRpmtKas11d0OV6mgSzGdXVli7S5dstuSp02eLdXx2S95fnTfoazFfTWZrMA8MV6wJleKELkQOPtmCKrf-T82gcahNFDDXyWMg8lkWey5jzmIPIMUSmY63jXEcwHpLHs2_j6s8e2y7b-xsrvzLjoQIJMpLcq-CsMq5uW4dF1jh70O6YMchOKWc-5eyUcvaXskcezohFxH-54jEAZ-Nf0GR5IQ</recordid><startdate>20210201</startdate><enddate>20210201</enddate><creator>Ma, Baolong</creator><creator>Song, Lei</creator><creator>Yan, Mingfei</creator><creator>Ikeda, Yujiro</creator><creator>Otake, Yoshie</creator><creator>Wang, Sheng</creator><general>IEEE</general><general>The Institute of Electrical and Electronics Engineers, Inc. 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optimization</topic><topic>Polyethylene</topic><topic>Polyethylenes</topic><topic>Shielding</topic><topic>shielding weight</topic><topic>Sociology</topic><topic>Sorting</topic><topic>Sorting algorithms</topic><topic>Statistics</topic><topic>Weight</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Ma, Baolong</creatorcontrib><creatorcontrib>Song, Lei</creatorcontrib><creatorcontrib>Yan, Mingfei</creatorcontrib><creatorcontrib>Ikeda, Yujiro</creatorcontrib><creatorcontrib>Otake, Yoshie</creatorcontrib><creatorcontrib>Wang, Sheng</creatorcontrib><collection>IEEE All-Society Periodicals Package (ASPP) 2005-present</collection><collection>IEEE All-Society Periodicals Package (ASPP) 1998-Present</collection><collection>IEEE Electronic Library (IEL)</collection><collection>CrossRef</collection><collection>Aluminium Industry Abstracts</collection><collection>Bacteriology Abstracts (Microbiology B)</collection><collection>Ceramic 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of NSGA-II and MCNP</atitle><jtitle>IEEE transactions on nuclear science</jtitle><stitle>TNS</stitle><date>2021-02-01</date><risdate>2021</risdate><volume>68</volume><issue>2</issue><spage>110</spage><epage>117</epage><pages>110-117</pages><issn>0018-9499</issn><eissn>1558-1578</eissn><coden>IETNAE</coden><abstract>To find the optimal shielding design for compact accelerator-driven neutron sources (CANS) using multiobjective optimization, we developed a new method called nondominated sorting genetic algorithm-Monte Carlo method (NSGA-MC). 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The performance of the method was discussed by showing advantages of NSGA-MC over the so-called weight sum method.</abstract><cop>New York</cop><pub>IEEE</pub><doi>10.1109/TNS.2020.3040500</doi><tpages>8</tpages><orcidid>https://orcid.org/0000-0003-3494-8935</orcidid><orcidid>https://orcid.org/0000-0003-1131-0066</orcidid></addata></record> |
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| ispartof | IEEE transactions on nuclear science, 2021-02, Vol.68 (2), p.110-117 |
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| source | IEEE Electronic Library (IEL) |
| subjects | Acceleration Compact accelerator-driven neutron sources (CANS) Configurations Design Design optimization Dosage equivalent dose rate Genetic algorithms Lead Linear programming Monte Carlo N-particle transport code (MCNP) Monte Carlo simulation multiobjective shielding design Multiple objective analysis Neutron sources Neutrons nondominated sorting genetic algorithm (NSGA) Optimization Pareto optimization Polyethylene Polyethylenes Shielding shielding weight Sociology Sorting Sorting algorithms Statistics Weight |
| title | Multiobjective Optimization Shielding Design for Compact Accelerator-Driven Neutron Sources by Application of NSGA-II and MCNP |
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