Analysis of Barite Concrete as a Potential Neutron Radiation Shielding Material for BNCT Facilities
This research aimed to determine the potential of barite concrete as a neutron radiation shielding material in the development of boron neutron capture therapy, by obtaining its neutron attenuation coefficient. Barite concrete samples were supplied by the Center of Accelerator Science and Technology...
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| Format: | Article |
| Language: | English |
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Universiti Brunei Darussalam
2019-04-01
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| Series: | ASEAN Journal on Science and Technology for Development |
| Subjects: | |
| Online Access: | https://ajstd.org/index.php/ajstd/article/view/528 |
| _version_ | 1827365871457140736 |
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| author | Rini Murtafi'atin Widarto Widarto Susilo Susilo Ngurah Made Dharma Putra |
| author_facet | Rini Murtafi'atin Widarto Widarto Susilo Susilo Ngurah Made Dharma Putra |
| author_sort | Rini Murtafi'atin |
| collection | DOAJ |
| description | This research aimed to determine the potential of barite concrete as a neutron radiation shielding material in the development of boron neutron capture therapy, by obtaining its neutron attenuation coefficient. Barite concrete samples were supplied by the Center of Accelerator Science and Technology in Yogyakarta, Indonesia. The experiment consisted of two parts, namely density analysis and determination of the neutron attenuation coefficient. For the latter, plutonium-beryllium was used as the neutron source, while a high purity germanium detector was used to measure the neutron radiation level. The results showed that barite concrete with a 2130 kg.m–3 density had a neutron attenuation coefficient of 0.0871 cm–3. |
| first_indexed | 2024-03-08T08:37:56Z |
| format | Article |
| id | doaj.art-0899d93e414440ed8d85729ac22da600 |
| institution | Directory Open Access Journal |
| issn | 0217-5460 2224-9028 |
| language | English |
| last_indexed | 2024-03-08T08:37:56Z |
| publishDate | 2019-04-01 |
| publisher | Universiti Brunei Darussalam |
| record_format | Article |
| series | ASEAN Journal on Science and Technology for Development |
| spelling | doaj.art-0899d93e414440ed8d85729ac22da6002024-02-02T00:18:28ZengUniversiti Brunei DarussalamASEAN Journal on Science and Technology for Development0217-54602224-90282019-04-01361192110.29037/ajstd.528504Analysis of Barite Concrete as a Potential Neutron Radiation Shielding Material for BNCT FacilitiesRini Murtafi'atin0Widarto Widarto1Susilo Susilo2Ngurah Made Dharma Putra3Department of Physics, Mathematics and Science Faculty, Semarang State University, Semarang 50229, IndonesiaCenter of Accelerator Science and Technology, National Nuclear Energy Agency, Yogyakarta 55281, IndonesiaDepartment of Physics, Mathematics and Science Faculty, Semarang State University, Semarang 50229, IndonesiaDepartment of Physics, Mathematics and Science Faculty, Semarang State University, Semarang 50229, IndonesiaThis research aimed to determine the potential of barite concrete as a neutron radiation shielding material in the development of boron neutron capture therapy, by obtaining its neutron attenuation coefficient. Barite concrete samples were supplied by the Center of Accelerator Science and Technology in Yogyakarta, Indonesia. The experiment consisted of two parts, namely density analysis and determination of the neutron attenuation coefficient. For the latter, plutonium-beryllium was used as the neutron source, while a high purity germanium detector was used to measure the neutron radiation level. The results showed that barite concrete with a 2130 kg.m–3 density had a neutron attenuation coefficient of 0.0871 cm–3.https://ajstd.org/index.php/ajstd/article/view/528barite concretedensityneutron attenuation coefficient |
| spellingShingle | Rini Murtafi'atin Widarto Widarto Susilo Susilo Ngurah Made Dharma Putra Analysis of Barite Concrete as a Potential Neutron Radiation Shielding Material for BNCT Facilities ASEAN Journal on Science and Technology for Development barite concrete density neutron attenuation coefficient |
| title | Analysis of Barite Concrete as a Potential Neutron Radiation Shielding Material for BNCT Facilities |
| title_full | Analysis of Barite Concrete as a Potential Neutron Radiation Shielding Material for BNCT Facilities |
| title_fullStr | Analysis of Barite Concrete as a Potential Neutron Radiation Shielding Material for BNCT Facilities |
| title_full_unstemmed | Analysis of Barite Concrete as a Potential Neutron Radiation Shielding Material for BNCT Facilities |
| title_short | Analysis of Barite Concrete as a Potential Neutron Radiation Shielding Material for BNCT Facilities |
| title_sort | analysis of barite concrete as a potential neutron radiation shielding material for bnct facilities |
| topic | barite concrete density neutron attenuation coefficient |
| url | https://ajstd.org/index.php/ajstd/article/view/528 |
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