Neutron measurement at the thermal column of the Malaysian Triga Mark II reactor using gold foil activation method and TLD
In order to design facilities for boron neutron capture therapy (BNCT), the neutron measurement must be considered to obtain the optimal design of BNCT facility such as collimator and shielding. The previous feasibility study showed that the thermal column could generate higher thermal neutrons yiel...
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| Veröffentlicht in: | IOP conference series. Materials Science and Engineering 2018-01, Vol.298 (1), p.12031 |
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| creator | Shalbi, Safwan Wan Salleh, Wan Norhayati Idris, Faridah Mohamad Ashraff Rosdi, Muhammad Aliff Sarkawi, Muhammad Syahir Jamsari, Nur Liyana Mohd Nasir, Nur Aishah |
| description | In order to design facilities for boron neutron capture therapy (BNCT), the neutron measurement must be considered to obtain the optimal design of BNCT facility such as collimator and shielding. The previous feasibility study showed that the thermal column could generate higher thermal neutrons yield for BNCT application at the TRIGA MARK II reactor. Currently, the facility for BNCT are planned to be developed at thermal column. Thus, the main objective was focused on the thermal neutron and epithermal neutron flux measurement at the thermal column. In this measurement, pure gold and cadmium were used as a filter to obtain the thermal and epithermal neutron fluxes from inside and outside of the thermal column door of the 200kW reactor power using a gold foil activation method. The results were compared with neutron fluxes using TLD 600 and TLD 700. The outcome of this work will become the benchmark for the design of BNCT collimator and the shielding |
| doi_str_mv | 10.1088/1757-899X/298/1/012031 |
| format | Article |
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The previous feasibility study showed that the thermal column could generate higher thermal neutrons yield for BNCT application at the TRIGA MARK II reactor. Currently, the facility for BNCT are planned to be developed at thermal column. Thus, the main objective was focused on the thermal neutron and epithermal neutron flux measurement at the thermal column. In this measurement, pure gold and cadmium were used as a filter to obtain the thermal and epithermal neutron fluxes from inside and outside of the thermal column door of the 200kW reactor power using a gold foil activation method. The results were compared with neutron fluxes using TLD 600 and TLD 700. The outcome of this work will become the benchmark for the design of BNCT collimator and the shielding</description><identifier>ISSN: 1757-8981</identifier><identifier>EISSN: 1757-899X</identifier><identifier>DOI: 10.1088/1757-899X/298/1/012031</identifier><language>eng</language><publisher>Bristol: IOP Publishing</publisher><subject>Collimators ; Fast neutrons ; Feasibility studies ; Gold ; Metal foils ; Neutron flux ; Neutrons ; Nuclear capture ; Shielding ; Thermal neutrons</subject><ispartof>IOP conference series. Materials Science and Engineering, 2018-01, Vol.298 (1), p.12031</ispartof><rights>Published under licence by IOP Publishing Ltd</rights><rights>2018. This work is published under http://creativecommons.org/licenses/by/3.0/ (the “License”). 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Materials Science and Engineering</title><addtitle>IOP Conf. Ser.: Mater. Sci. Eng</addtitle><description>In order to design facilities for boron neutron capture therapy (BNCT), the neutron measurement must be considered to obtain the optimal design of BNCT facility such as collimator and shielding. The previous feasibility study showed that the thermal column could generate higher thermal neutrons yield for BNCT application at the TRIGA MARK II reactor. Currently, the facility for BNCT are planned to be developed at thermal column. Thus, the main objective was focused on the thermal neutron and epithermal neutron flux measurement at the thermal column. In this measurement, pure gold and cadmium were used as a filter to obtain the thermal and epithermal neutron fluxes from inside and outside of the thermal column door of the 200kW reactor power using a gold foil activation method. The results were compared with neutron fluxes using TLD 600 and TLD 700. 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| subjects | Collimators Fast neutrons Feasibility studies Gold Metal foils Neutron flux Neutrons Nuclear capture Shielding Thermal neutrons |
| title | Neutron measurement at the thermal column of the Malaysian Triga Mark II reactor using gold foil activation method and TLD |
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