A design on the collimator for boron neutron capture therapy (BNCT) research facility at the thermal column of TRIGA MARK II

A design on the collimator for boron neutron capture therapy (BNCT) research facility at the thermal column of TRIGA MARK II

The development of the Boron Neutron Capture Therapy (BNCT) facility in Malaysia can be performed at the thermal column of the Malaysia research reactor. TRIGA MARK II is one of the facilities that can provide neutron source for BNCT facility. The specification of neutron flux and the gamma dose rat...

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Bibliographic Details
Main Authors: S., Shalbi, Norazlianie, Sazali, W. N. W., Salleh
Format: Conference or Workshop Item
Language:English
English
Published: IOP Publishing 2020
Subjects:
Q Science (General)
QD Chemistry
TP Chemical technology
Online Access:http://umpir.ump.edu.my/id/eprint/28072/
http://umpir.ump.edu.my/id/eprint/28072/
http://umpir.ump.edu.my/id/eprint/28072/1/Shalbi_2020_IOP_Conf._Ser.__Mater._Sci._Eng._736_062023.pdf
http://umpir.ump.edu.my/id/eprint/28072/7/A%20design%20on%20the%20collimator%20for%20boron%20neutron.pdf
id ump-28072
recordtype eprints
spelling ump-280722020-03-10T03:49:40Z http://umpir.ump.edu.my/id/eprint/28072/ A design on the collimator for boron neutron capture therapy (BNCT) research facility at the thermal column of TRIGA MARK II S., Shalbi Norazlianie, Sazali W. N. W., Salleh Q Science (General) QD Chemistry TP Chemical technology The development of the Boron Neutron Capture Therapy (BNCT) facility in Malaysia can be performed at the thermal column of the Malaysia research reactor. TRIGA MARK II is one of the facilities that can provide neutron source for BNCT facility. The specification of neutron flux and the gamma dose rate must consider for the development of the BNCT facility as a safety precaution for this research. Based on previous research, the thermal column identified as a suitable place for BNCT facility. To design the neutron collimator for BNCT purpose, the characterization of material towards thermal neutron flux explored using TLD and Microspec-6 and the collimator design was simulate using Monte Carlo N-Particle (MCNP) software based on the characterize materials in order to produce high thermal neutron flux. The combination of lead, HDPE, 30% borated polyethylene and aluminium as collimator design D1 simulate the highest thermal neutron 1.5770 x 109 neutron.cm−2s−1 and suitable for BNCT research purpose at the thermal column. IOP Publishing 2020 Conference or Workshop Item PeerReviewed pdf en http://umpir.ump.edu.my/id/eprint/28072/1/Shalbi_2020_IOP_Conf._Ser.__Mater._Sci._Eng._736_062023.pdf pdf en cc_by http://umpir.ump.edu.my/id/eprint/28072/7/A%20design%20on%20the%20collimator%20for%20boron%20neutron.pdf S., Shalbi and Norazlianie, Sazali and W. N. W., Salleh (2020) A design on the collimator for boron neutron capture therapy (BNCT) research facility at the thermal column of TRIGA MARK II. In: IOP Conference Series: Materials Science and Engineering; Energy Security and Chemical Engineering Congress (ESChE) 2019, 17-19 July 2019 , Kuala Lumpur, Malaysia. pp. 1-15., 736 (062023). ISSN 1757-8981 (Print), 1757-899X (Online) https://doi.org/10.1088/1757-899X/736/6/062023
repository_type Digital Repository
institution_category Local University
institution Universiti Malaysia Pahang
building UMP Institutional Repository
collection Online Access
language English
English
topic Q Science (General)
QD Chemistry
TP Chemical technology
spellingShingle Q Science (General)
QD Chemistry
TP Chemical technology
S., Shalbi
Norazlianie, Sazali
W. N. W., Salleh
A design on the collimator for boron neutron capture therapy (BNCT) research facility at the thermal column of TRIGA MARK II
description The development of the Boron Neutron Capture Therapy (BNCT) facility in Malaysia can be performed at the thermal column of the Malaysia research reactor. TRIGA MARK II is one of the facilities that can provide neutron source for BNCT facility. The specification of neutron flux and the gamma dose rate must consider for the development of the BNCT facility as a safety precaution for this research. Based on previous research, the thermal column identified as a suitable place for BNCT facility. To design the neutron collimator for BNCT purpose, the characterization of material towards thermal neutron flux explored using TLD and Microspec-6 and the collimator design was simulate using Monte Carlo N-Particle (MCNP) software based on the characterize materials in order to produce high thermal neutron flux. The combination of lead, HDPE, 30% borated polyethylene and aluminium as collimator design D1 simulate the highest thermal neutron 1.5770 x 109 neutron.cm−2s−1 and suitable for BNCT research purpose at the thermal column.
format Conference or Workshop Item
author S., Shalbi
Norazlianie, Sazali
W. N. W., Salleh
author_facet S., Shalbi
Norazlianie, Sazali
W. N. W., Salleh
author_sort S., Shalbi
title A design on the collimator for boron neutron capture therapy (BNCT) research facility at the thermal column of TRIGA MARK II
title_short A design on the collimator for boron neutron capture therapy (BNCT) research facility at the thermal column of TRIGA MARK II
title_full A design on the collimator for boron neutron capture therapy (BNCT) research facility at the thermal column of TRIGA MARK II
title_fullStr A design on the collimator for boron neutron capture therapy (BNCT) research facility at the thermal column of TRIGA MARK II
title_full_unstemmed A design on the collimator for boron neutron capture therapy (BNCT) research facility at the thermal column of TRIGA MARK II
title_sort design on the collimator for boron neutron capture therapy (bnct) research facility at the thermal column of triga mark ii
publisher IOP Publishing
publishDate 2020
url http://umpir.ump.edu.my/id/eprint/28072/
http://umpir.ump.edu.my/id/eprint/28072/
http://umpir.ump.edu.my/id/eprint/28072/1/Shalbi_2020_IOP_Conf._Ser.__Mater._Sci._Eng._736_062023.pdf
http://umpir.ump.edu.my/id/eprint/28072/7/A%20design%20on%20the%20collimator%20for%20boron%20neutron.pdf
first_indexed 2023-09-18T22:44:02Z
last_indexed 2023-09-18T22:44:02Z
_version_ 1777417105144020992

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