Assessment of cross-section library impact on neutron beam quality in AB-BNCT monte carlo studies
Abstract This study investigated the impact of nuclear reaction cross-sections data from various nuclear data libraries on neutron parameters in Monte Carlo simulations using the PHITS code for accelerator-based BNCT (AB-BNCT). Specifically, it evaluated the effect of different proton data libraries...
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Nature Portfolio
2025-08-01
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| Online Access: | https://doi.org/10.1038/s41598-025-15446-2 |
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| author | Hong-Bing Song Jing-Gang Xu Xiong Yang Zhi-Feng Li Sheng Wang Chang-Li Ruan Xiang-Pan Li |
| author_facet | Hong-Bing Song Jing-Gang Xu Xiong Yang Zhi-Feng Li Sheng Wang Chang-Li Ruan Xiang-Pan Li |
| author_sort | Hong-Bing Song |
| collection | DOAJ |
| description | Abstract This study investigated the impact of nuclear reaction cross-sections data from various nuclear data libraries on neutron parameters in Monte Carlo simulations using the PHITS code for accelerator-based BNCT (AB-BNCT). Specifically, it evaluated the effect of different proton data libraries-ENDF/B VII.1, ENDF/B VIII.1, CP2020, and JENDL-5.0-on the neutron yields from the 7Li(p, n)7Be reaction in a natural lithium target. The results showed that the calculated target neutron yields differed by up to 16.86%, with notable variations in the target neutron energy spectra. Furthermore, the study assessed the impact of neutron libraries-ENDF/B VII.1, ENDF/B VIII.0, ENDF/B VIII.1, JEFF-3.3, CENDL-3.2, and JENDL-5.0-on neutron beam parameters at the BSA exit, based on the neutron spectrum at the lithium target. It was found that the epithermal neutron intensity and fast neutron component calculated with the ENDF/B VIII.1 neutron library were 5.51%-8.61% and 19.04%-63.94% higher, respectively, than that obtained with the other neutron libraries, due to a more prominent neutron flux peak. The fast neutron component, calculated using the JENDL-5.0 neutron library, was 23.42%-63.94% lower compared to other libraries, while the gamma-ray component derived from the JEFF-3.3, CENDL-3.2, and JENDL-5.0 neutron libraries was 6.79%-10.08% higher than that from the ENDF/B series. Further analysis revealed that the discrepancies were primarily caused by differences in the neutron cross-section data of F, Pb, Mg, Cu, and H in specific neutron libraries. In particular, the differences in the neutron cross-sections of F and Pb accounted for the variations in the obtained BSA outlet spectra and neutron parameters when using the ENDF/B VIII.1 and JENDL-5.0 neutron libraries. The elevated gamma-ray component observed in the JEFF-3.3 and CENDL-3.2 neutron libraries, compared to the ENDF/B series, was largely due to the different cross-sections of Mg, Cu, and H. These findings underscored the considerable discrepancies arising from variations in nuclear data libraries and emphasized the critical importance of appropriate selection of nuclear data libraries for BNCT applications. |
| format | Article |
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| institution | Kabale University |
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| spelling | doaj-art-039f809e42344d44b061e44b6901affb2025-08-20T04:01:51ZengNature PortfolioScientific Reports2045-23222025-08-0115111910.1038/s41598-025-15446-2Assessment of cross-section library impact on neutron beam quality in AB-BNCT monte carlo studiesHong-Bing Song0Jing-Gang Xu1Xiong Yang2Zhi-Feng Li3Sheng Wang4Chang-Li Ruan5Xiang-Pan Li6Department of Radiotherapy, Renmin Hospital of Wuhan UniversityDepartment of Nuclear Science and Technology, School of Energy and Power Engineering, Xi’an Jiao-Tong UniversityDepartment of Radiotherapy, Renmin Hospital of Wuhan UniversityDepartment of Nuclear Science and Technology, School of Energy and Power Engineering, Xi’an Jiao-Tong UniversityDepartment of Nuclear Science and Technology, School of Energy and Power Engineering, Xi’an Jiao-Tong UniversityDepartment of Radiotherapy, Renmin Hospital of Wuhan UniversityDepartment of Radiotherapy, Renmin Hospital of Wuhan UniversityAbstract This study investigated the impact of nuclear reaction cross-sections data from various nuclear data libraries on neutron parameters in Monte Carlo simulations using the PHITS code for accelerator-based BNCT (AB-BNCT). Specifically, it evaluated the effect of different proton data libraries-ENDF/B VII.1, ENDF/B VIII.1, CP2020, and JENDL-5.0-on the neutron yields from the 7Li(p, n)7Be reaction in a natural lithium target. The results showed that the calculated target neutron yields differed by up to 16.86%, with notable variations in the target neutron energy spectra. Furthermore, the study assessed the impact of neutron libraries-ENDF/B VII.1, ENDF/B VIII.0, ENDF/B VIII.1, JEFF-3.3, CENDL-3.2, and JENDL-5.0-on neutron beam parameters at the BSA exit, based on the neutron spectrum at the lithium target. It was found that the epithermal neutron intensity and fast neutron component calculated with the ENDF/B VIII.1 neutron library were 5.51%-8.61% and 19.04%-63.94% higher, respectively, than that obtained with the other neutron libraries, due to a more prominent neutron flux peak. The fast neutron component, calculated using the JENDL-5.0 neutron library, was 23.42%-63.94% lower compared to other libraries, while the gamma-ray component derived from the JEFF-3.3, CENDL-3.2, and JENDL-5.0 neutron libraries was 6.79%-10.08% higher than that from the ENDF/B series. Further analysis revealed that the discrepancies were primarily caused by differences in the neutron cross-section data of F, Pb, Mg, Cu, and H in specific neutron libraries. In particular, the differences in the neutron cross-sections of F and Pb accounted for the variations in the obtained BSA outlet spectra and neutron parameters when using the ENDF/B VIII.1 and JENDL-5.0 neutron libraries. The elevated gamma-ray component observed in the JEFF-3.3 and CENDL-3.2 neutron libraries, compared to the ENDF/B series, was largely due to the different cross-sections of Mg, Cu, and H. These findings underscored the considerable discrepancies arising from variations in nuclear data libraries and emphasized the critical importance of appropriate selection of nuclear data libraries for BNCT applications.https://doi.org/10.1038/s41598-025-15446-2Boron neutron capture therapy (BNCT)Nuclear reaction cross sectionsBeam shaping assembly (BSA)Neutron spectrumMonte carlo simulation |
| spellingShingle | Hong-Bing Song Jing-Gang Xu Xiong Yang Zhi-Feng Li Sheng Wang Chang-Li Ruan Xiang-Pan Li Assessment of cross-section library impact on neutron beam quality in AB-BNCT monte carlo studies Scientific Reports Boron neutron capture therapy (BNCT) Nuclear reaction cross sections Beam shaping assembly (BSA) Neutron spectrum Monte carlo simulation |
| title | Assessment of cross-section library impact on neutron beam quality in AB-BNCT monte carlo studies |
| title_full | Assessment of cross-section library impact on neutron beam quality in AB-BNCT monte carlo studies |
| title_fullStr | Assessment of cross-section library impact on neutron beam quality in AB-BNCT monte carlo studies |
| title_full_unstemmed | Assessment of cross-section library impact on neutron beam quality in AB-BNCT monte carlo studies |
| title_short | Assessment of cross-section library impact on neutron beam quality in AB-BNCT monte carlo studies |
| title_sort | assessment of cross section library impact on neutron beam quality in ab bnct monte carlo studies |
| topic | Boron neutron capture therapy (BNCT) Nuclear reaction cross sections Beam shaping assembly (BSA) Neutron spectrum Monte carlo simulation |
| url | https://doi.org/10.1038/s41598-025-15446-2 |
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