Development and evaluation of dose calculation algorithm with a combination of Monte Carlo and point-kernel methods for boron neutron capture therapy
We developed a 'hybrid algorithm' that combines the Monte Carlo (MC) and point-kernel methods for fast dose calculation in boron neutron capture therapy. The objectives of this study were to experimentally verify the hybrid algorithm and to verify the calculation accuracy and time of a ...
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Veröffentlicht in: | Biomedical physics & engineering express 2023-05, Vol.9 (3), p.35025 |
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creator | Nojiri, Mai Takata, Takushi Hu, Naonori Sakurai, Yoshinori Suzuki, Minoru Tanaka, Hiroki |
description | We developed a 'hybrid algorithm' that combines the Monte Carlo (MC) and point-kernel methods for fast dose calculation in boron neutron capture therapy. The objectives of this study were to experimentally verify the hybrid algorithm and to verify the calculation accuracy and time of a 'complementary approach' adopting both the hybrid algorithm and the full-energy MC method. In the latter verification, the results were compared with those obtained using the full-energy MC method alone. In the hybrid algorithm, the moderation process of neutrons is simulated using only the MC method, and the thermalization process is modeled as a kernel. The thermal neutron fluxes calculated using only this algorithm were compared with those measured in a cubic phantom. In addition, a complementary approach was used for dose calculation in a geometry simulating the head region, and its computation time and accuracy were verified. The experimental verification indicated that the thermal neutron fluxes calculated using only the hybrid algorithm reproduced the measured values at depths exceeding a few centimeters, whereas they overestimated those at shallower depths. Compared with the calculation using only the full-energy MC method, the complementary approach reduced the computation time by approximately half, maintaining nearly same accuracy. When focusing on the calculation only using the hybrid algorithm only for the boron dose attributed to the reaction of thermal neutrons, the computation time was expected to reduce by 95% compared with the calculation using only the full-energy MC method. In conclusion, modeling the thermalization process as a kernel was effective for reducing the computation time. |
doi_str_mv | 10.1088/2057-1976/acc33c |
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The objectives of this study were to experimentally verify the hybrid algorithm and to verify the calculation accuracy and time of a 'complementary approach' adopting both the hybrid algorithm and the full-energy MC method. In the latter verification, the results were compared with those obtained using the full-energy MC method alone. In the hybrid algorithm, the moderation process of neutrons is simulated using only the MC method, and the thermalization process is modeled as a kernel. The thermal neutron fluxes calculated using only this algorithm were compared with those measured in a cubic phantom. In addition, a complementary approach was used for dose calculation in a geometry simulating the head region, and its computation time and accuracy were verified. The experimental verification indicated that the thermal neutron fluxes calculated using only the hybrid algorithm reproduced the measured values at depths exceeding a few centimeters, whereas they overestimated those at shallower depths. Compared with the calculation using only the full-energy MC method, the complementary approach reduced the computation time by approximately half, maintaining nearly same accuracy. When focusing on the calculation only using the hybrid algorithm only for the boron dose attributed to the reaction of thermal neutrons, the computation time was expected to reduce by 95% compared with the calculation using only the full-energy MC method. In conclusion, modeling the thermalization process as a kernel was effective for reducing the computation time.</description><identifier>ISSN: 2057-1976</identifier><identifier>EISSN: 2057-1976</identifier><identifier>DOI: 10.1088/2057-1976/acc33c</identifier><identifier>PMID: 37021631</identifier><identifier>CODEN: NJOPFM</identifier><language>eng</language><publisher>England: IOP Publishing</publisher><subject>Algorithms ; boron neutron capture therapy ; Boron Neutron Capture Therapy - methods ; dose calculation algorithm ; Monte Carlo method ; Neutrons ; point-kernel ; Radiotherapy Dosage ; Radiotherapy Planning, Computer-Assisted - methods ; treatment planning</subject><ispartof>Biomedical physics & engineering express, 2023-05, Vol.9 (3), p.35025</ispartof><rights>2023 The Author(s). Published by IOP Publishing Ltd</rights><rights>Creative Commons Attribution license.</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><cites>FETCH-LOGICAL-c473t-52802420fc8a51b044afec0c3040c997627f5f996ec7e3e42be9fb8e2f819f2d3</cites><orcidid>0000-0001-6436-6130 ; 0000-0003-2702-3344 ; 0000-0002-6195-3177</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://iopscience.iop.org/article/10.1088/2057-1976/acc33c/pdf$$EPDF$$P50$$Giop$$Hfree_for_read</linktopdf><link.rule.ids>314,776,780,27901,27902,53821,53868</link.rule.ids><backlink>$$Uhttps://www.ncbi.nlm.nih.gov/pubmed/37021631$$D View this record in MEDLINE/PubMed$$Hfree_for_read</backlink></links><search><creatorcontrib>Nojiri, Mai</creatorcontrib><creatorcontrib>Takata, Takushi</creatorcontrib><creatorcontrib>Hu, Naonori</creatorcontrib><creatorcontrib>Sakurai, Yoshinori</creatorcontrib><creatorcontrib>Suzuki, Minoru</creatorcontrib><creatorcontrib>Tanaka, Hiroki</creatorcontrib><title>Development and evaluation of dose calculation algorithm with a combination of Monte Carlo and point-kernel methods for boron neutron capture therapy</title><title>Biomedical physics & engineering express</title><addtitle>BPEX</addtitle><addtitle>Biomed. Phys. Eng. Express</addtitle><description>We developed a 'hybrid algorithm' that combines the Monte Carlo (MC) and point-kernel methods for fast dose calculation in boron neutron capture therapy. The objectives of this study were to experimentally verify the hybrid algorithm and to verify the calculation accuracy and time of a 'complementary approach' adopting both the hybrid algorithm and the full-energy MC method. In the latter verification, the results were compared with those obtained using the full-energy MC method alone. In the hybrid algorithm, the moderation process of neutrons is simulated using only the MC method, and the thermalization process is modeled as a kernel. The thermal neutron fluxes calculated using only this algorithm were compared with those measured in a cubic phantom. In addition, a complementary approach was used for dose calculation in a geometry simulating the head region, and its computation time and accuracy were verified. The experimental verification indicated that the thermal neutron fluxes calculated using only the hybrid algorithm reproduced the measured values at depths exceeding a few centimeters, whereas they overestimated those at shallower depths. Compared with the calculation using only the full-energy MC method, the complementary approach reduced the computation time by approximately half, maintaining nearly same accuracy. When focusing on the calculation only using the hybrid algorithm only for the boron dose attributed to the reaction of thermal neutrons, the computation time was expected to reduce by 95% compared with the calculation using only the full-energy MC method. In conclusion, modeling the thermalization process as a kernel was effective for reducing the computation time.</description><subject>Algorithms</subject><subject>boron neutron capture therapy</subject><subject>Boron Neutron Capture Therapy - methods</subject><subject>dose calculation algorithm</subject><subject>Monte Carlo method</subject><subject>Neutrons</subject><subject>point-kernel</subject><subject>Radiotherapy Dosage</subject><subject>Radiotherapy Planning, Computer-Assisted - methods</subject><subject>treatment planning</subject><issn>2057-1976</issn><issn>2057-1976</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2023</creationdate><recordtype>article</recordtype><sourceid>O3W</sourceid><sourceid>EIF</sourceid><recordid>eNp1kUtv1TAQhS0EolXpnlXlHSwa6kecxEt0oQ-piA2sLccZ96Y4tms7hf4Q_m9zSbnqAjYea_SdM5ozCL2l5AMlXXfGiGgrKtvmTBvDuXmBDvetl8_-B-g451tCCG1Y00jxGh3wljDacHqIfn-Ce3AhTuAL1n7AcK_drMsYPA4WDyEDNtqZ2a097W5CGst2wj-XF2tswtSPfi_4EnwBvNHJhT92MYy-VD8geXB4grINQ8Y2JNyHtCg8zGVXjY5lToDLFpKOD2_QK6tdhuOneoS-n3_-trmsrr9eXG0-XlembnmpBOsIqxmxptOC9qSutQVDDCc1MXJZnbVWWCkbMC1wqFkP0vYdMNtRadnAj9D71TemcDdDLmoaswHntIcwZ8Va2dJaCFovKFlRk0LOCayKaZx0elCUqN091C5wtQtcrfdYJCdP7nM_wbAX_E1_Ad6twBiiug1z8suyqo_wS0nFFeGCMKHiYBfy9B_kfyc_ArIHpQE</recordid><startdate>20230501</startdate><enddate>20230501</enddate><creator>Nojiri, Mai</creator><creator>Takata, Takushi</creator><creator>Hu, Naonori</creator><creator>Sakurai, Yoshinori</creator><creator>Suzuki, Minoru</creator><creator>Tanaka, Hiroki</creator><general>IOP Publishing</general><scope>O3W</scope><scope>TSCCA</scope><scope>CGR</scope><scope>CUY</scope><scope>CVF</scope><scope>ECM</scope><scope>EIF</scope><scope>NPM</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7X8</scope><orcidid>https://orcid.org/0000-0001-6436-6130</orcidid><orcidid>https://orcid.org/0000-0003-2702-3344</orcidid><orcidid>https://orcid.org/0000-0002-6195-3177</orcidid></search><sort><creationdate>20230501</creationdate><title>Development and evaluation of dose calculation algorithm with a combination of Monte Carlo and point-kernel methods for boron neutron capture therapy</title><author>Nojiri, Mai ; Takata, Takushi ; Hu, Naonori ; Sakurai, Yoshinori ; Suzuki, Minoru ; Tanaka, Hiroki</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c473t-52802420fc8a51b044afec0c3040c997627f5f996ec7e3e42be9fb8e2f819f2d3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2023</creationdate><topic>Algorithms</topic><topic>boron neutron capture therapy</topic><topic>Boron Neutron Capture Therapy - methods</topic><topic>dose calculation algorithm</topic><topic>Monte Carlo method</topic><topic>Neutrons</topic><topic>point-kernel</topic><topic>Radiotherapy Dosage</topic><topic>Radiotherapy Planning, Computer-Assisted - methods</topic><topic>treatment planning</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Nojiri, Mai</creatorcontrib><creatorcontrib>Takata, Takushi</creatorcontrib><creatorcontrib>Hu, Naonori</creatorcontrib><creatorcontrib>Sakurai, Yoshinori</creatorcontrib><creatorcontrib>Suzuki, Minoru</creatorcontrib><creatorcontrib>Tanaka, Hiroki</creatorcontrib><collection>IOP Publishing Free Content</collection><collection>IOPscience (Open Access)</collection><collection>Medline</collection><collection>MEDLINE</collection><collection>MEDLINE (Ovid)</collection><collection>MEDLINE</collection><collection>MEDLINE</collection><collection>PubMed</collection><collection>CrossRef</collection><collection>MEDLINE - Academic</collection><jtitle>Biomedical physics & engineering express</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Nojiri, Mai</au><au>Takata, Takushi</au><au>Hu, Naonori</au><au>Sakurai, Yoshinori</au><au>Suzuki, Minoru</au><au>Tanaka, Hiroki</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Development and evaluation of dose calculation algorithm with a combination of Monte Carlo and point-kernel methods for boron neutron capture therapy</atitle><jtitle>Biomedical physics & engineering express</jtitle><stitle>BPEX</stitle><addtitle>Biomed. Phys. Eng. Express</addtitle><date>2023-05-01</date><risdate>2023</risdate><volume>9</volume><issue>3</issue><spage>35025</spage><pages>35025-</pages><issn>2057-1976</issn><eissn>2057-1976</eissn><coden>NJOPFM</coden><abstract>We developed a 'hybrid algorithm' that combines the Monte Carlo (MC) and point-kernel methods for fast dose calculation in boron neutron capture therapy. The objectives of this study were to experimentally verify the hybrid algorithm and to verify the calculation accuracy and time of a 'complementary approach' adopting both the hybrid algorithm and the full-energy MC method. In the latter verification, the results were compared with those obtained using the full-energy MC method alone. In the hybrid algorithm, the moderation process of neutrons is simulated using only the MC method, and the thermalization process is modeled as a kernel. The thermal neutron fluxes calculated using only this algorithm were compared with those measured in a cubic phantom. In addition, a complementary approach was used for dose calculation in a geometry simulating the head region, and its computation time and accuracy were verified. The experimental verification indicated that the thermal neutron fluxes calculated using only the hybrid algorithm reproduced the measured values at depths exceeding a few centimeters, whereas they overestimated those at shallower depths. Compared with the calculation using only the full-energy MC method, the complementary approach reduced the computation time by approximately half, maintaining nearly same accuracy. When focusing on the calculation only using the hybrid algorithm only for the boron dose attributed to the reaction of thermal neutrons, the computation time was expected to reduce by 95% compared with the calculation using only the full-energy MC method. 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subjects | Algorithms boron neutron capture therapy Boron Neutron Capture Therapy - methods dose calculation algorithm Monte Carlo method Neutrons point-kernel Radiotherapy Dosage Radiotherapy Planning, Computer-Assisted - methods treatment planning |
title | Development and evaluation of dose calculation algorithm with a combination of Monte Carlo and point-kernel methods for boron neutron capture therapy |
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