Thermal neutron flux measurement at pneumatic transfer system (pts) of reactor triga puspati (rtp) using neutron activation analysis (naa) / Nur Zarifah Zahali
PUSPATI TRIGA Reactor is the only research reactor in Malaysia started its operation in 1982. It has conducted many research and analysis in nuclear and medical science. One of them is neutron flux measurement analysis by using Neutron Activation Analysis (NAA). The sample used is Au-197. The sam...
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| Format: | Student Project |
| Language: | English |
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Faculty of Applied Sciences
2017
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| Online Access: | https://ir.uitm.edu.my/id/eprint/23815/ |
| _version_ | 1848805836606930944 |
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| author | Zahali, Nur Zarifah |
| author_facet | Zahali, Nur Zarifah |
| author_sort | Zahali, Nur Zarifah |
| building | UiTM Institutional Repository |
| collection | Online Access |
| description | PUSPATI TRIGA Reactor is the only research reactor in Malaysia started its
operation in 1982. It has conducted many research and analysis in nuclear and
medical science. One of them is neutron flux measurement analysis by using
Neutron Activation Analysis (NAA). The sample used is Au-197. The samples
are prepared in the form of bare Aurum (Au) and Aurum covered with Cadmium
(Cd). Irradiation of samples takes place at Pneumatic Transfer System (PTS) of
PUSPATI TRIGA Reactor. After irradiation process, the counting of sample
which is the decay is measured by using high-purity germanium (HPGe) gamma
detector. The efficiency of detector will determine the precision of the neutron
flux. When the distance of detector is increased the Aurum efficiency is
decreased exponentially. Neutron Activation Analysis is the method used in
nuclear field to determine the concentration of element in a wide amount of
materials. The neutrons will bombard the elements or samples caused activity of
radioactive samples can be determined. The formula of neutron flux is used to
determine the thermal flux conducted in PTS. The experimental result give out
the thermal neutron flux at PTS is 5.75 x 1011 ncm-2 s-1 . It is quite accurate to
calculated result which is at 6.0 x 1011 nem-25-1 . |
| first_indexed | 2025-11-14T22:17:22Z |
| format | Student Project |
| id | uitm-23815 |
| institution | Universiti Teknologi MARA |
| institution_category | Local University |
| language | English |
| last_indexed | 2025-11-14T22:17:22Z |
| publishDate | 2017 |
| publisher | Faculty of Applied Sciences |
| recordtype | eprints |
| repository_type | Digital Repository |
| spelling | uitm-238152020-04-19T01:24:51Z https://ir.uitm.edu.my/id/eprint/23815/ Thermal neutron flux measurement at pneumatic transfer system (pts) of reactor triga puspati (rtp) using neutron activation analysis (naa) / Nur Zarifah Zahali Zahali, Nur Zarifah Radiation physics (General) Nuclear and particle physics. Atomic energy. Radioactivity Beam dynamics. Particle beams PUSPATI TRIGA Reactor is the only research reactor in Malaysia started its operation in 1982. It has conducted many research and analysis in nuclear and medical science. One of them is neutron flux measurement analysis by using Neutron Activation Analysis (NAA). The sample used is Au-197. The samples are prepared in the form of bare Aurum (Au) and Aurum covered with Cadmium (Cd). Irradiation of samples takes place at Pneumatic Transfer System (PTS) of PUSPATI TRIGA Reactor. After irradiation process, the counting of sample which is the decay is measured by using high-purity germanium (HPGe) gamma detector. The efficiency of detector will determine the precision of the neutron flux. When the distance of detector is increased the Aurum efficiency is decreased exponentially. Neutron Activation Analysis is the method used in nuclear field to determine the concentration of element in a wide amount of materials. The neutrons will bombard the elements or samples caused activity of radioactive samples can be determined. The formula of neutron flux is used to determine the thermal flux conducted in PTS. The experimental result give out the thermal neutron flux at PTS is 5.75 x 1011 ncm-2 s-1 . It is quite accurate to calculated result which is at 6.0 x 1011 nem-25-1 . Faculty of Applied Sciences 2017 Student Project NonPeerReviewed text en https://ir.uitm.edu.my/id/eprint/23815/1/PPb_NUR%20ZARIFAH%20ZAHALI%20AS%20C%2017_5.PDF Zahali, Nur Zarifah (2017) Thermal neutron flux measurement at pneumatic transfer system (pts) of reactor triga puspati (rtp) using neutron activation analysis (naa) / Nur Zarifah Zahali. (2017) [Student Project] <http://terminalib.uitm.edu.my/23815.pdf> (Unpublished) |
| spellingShingle | Radiation physics (General) Nuclear and particle physics. Atomic energy. Radioactivity Beam dynamics. Particle beams Zahali, Nur Zarifah Thermal neutron flux measurement at pneumatic transfer system (pts) of reactor triga puspati (rtp) using neutron activation analysis (naa) / Nur Zarifah Zahali |
| title | Thermal neutron flux measurement at pneumatic
transfer system (pts) of reactor triga puspati (rtp)
using neutron activation analysis (naa) / Nur Zarifah Zahali |
| title_full | Thermal neutron flux measurement at pneumatic
transfer system (pts) of reactor triga puspati (rtp)
using neutron activation analysis (naa) / Nur Zarifah Zahali |
| title_fullStr | Thermal neutron flux measurement at pneumatic
transfer system (pts) of reactor triga puspati (rtp)
using neutron activation analysis (naa) / Nur Zarifah Zahali |
| title_full_unstemmed | Thermal neutron flux measurement at pneumatic
transfer system (pts) of reactor triga puspati (rtp)
using neutron activation analysis (naa) / Nur Zarifah Zahali |
| title_short | Thermal neutron flux measurement at pneumatic
transfer system (pts) of reactor triga puspati (rtp)
using neutron activation analysis (naa) / Nur Zarifah Zahali |
| title_sort | thermal neutron flux measurement at pneumatic
transfer system (pts) of reactor triga puspati (rtp)
using neutron activation analysis (naa) / nur zarifah zahali |
| topic | Radiation physics (General) Nuclear and particle physics. Atomic energy. Radioactivity Beam dynamics. Particle beams |
| url | https://ir.uitm.edu.my/id/eprint/23815/ |