Study on the correlation of neutronic and thermal hydraulic of triga mark ii puspati reactor core
Volume :13, Issue No :2, Article ID :2, Page Start :7, Page End :14, ISSN :ISSN 1823-0180
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2017
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| Online Access: | Journal of nuclear and related technologies http://dspace.uniten.edu.my:8080/jspui/handle/123456789/71 |
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uniten-123456789-712017-06-15T02:55:35Z Study on the correlation of neutronic and thermal hydraulic of triga mark ii puspati reactor core Abdul Aziz bin Mohamed Prof. Madya Dr Thermal-hydraulic Neutron kinetics Neutronic Volume :13, Issue No :2, Article ID :2, Page Start :7, Page End :14, ISSN :ISSN 1823-0180 In order to prepare Malaysia to be nuclear ready, the Malaysian 1 MW TRIGA MARK II research reactor (RTP) located at the Malaysian Nuclear Agency was premeditated with the aim to effectually actualize the multitude areas of basic nuclear research, labor training and education. To meet the modern safety standards, analyses of a strong interaction between the thermal-hydraulic system behavior and the space-dependent neutron kinetics are needed as mere thermal-hydraulics codes are said to be incapable to succeed the present safety standards. This could be achieved through the coupling of neutronic and thermal-hydraulic codes of the reactor. Previous studies had shown that the coupled codes are able to successfully be employed for the correlation between thermal-hydraulic analysis and neutron kinetics at transient and steady state. In this study, the coupling was achieved through MCNP and TRIGLAV codes for neutronic and thermal-hydraulic respectively. Core-15 of RTP was modeled for both of the codes; hence calculating the criticality, analysis of power and neutron flux distribution. The consistency and accuracy of the developed Core-15 MCNP model was established by comparing calculations to the experimental results and TRIGLAV code. The criticality predictions for both codes are in very good agreement with the experimental results. The core reached its criticality after 66 fuels. The highest hot rod power peaking factor was found to be 1.28. The results are conservative and can be applied to show the reliability of MCNP and TRIGLAV codes. 2017-06-15T02:55:34Z 2017-06-15T02:55:34Z 2016 Article http://dspace.uniten.edu.my:8080/jspui/handle/123456789/71 en Journal of nuclear and related technologies |
| repository_type |
Digital Repository |
| institution_category |
Local University |
| institution |
Universiti Tenaga Nasional |
| building |
UNITEN Institutional Repository |
| collection |
Online Access |
| language |
English |
| topic |
Thermal-hydraulic Neutron kinetics Neutronic |
| spellingShingle |
Thermal-hydraulic Neutron kinetics Neutronic Abdul Aziz bin Mohamed Prof. Madya Dr Study on the correlation of neutronic and thermal hydraulic of triga mark ii puspati reactor core |
| description |
Volume :13, Issue No :2, Article ID :2, Page Start :7, Page End :14, ISSN :ISSN 1823-0180 |
| format |
Article |
| author |
Abdul Aziz bin Mohamed Prof. Madya Dr |
| author_facet |
Abdul Aziz bin Mohamed Prof. Madya Dr |
| author_sort |
Abdul Aziz bin Mohamed Prof. Madya Dr |
| title |
Study on the correlation of neutronic and thermal hydraulic of triga mark ii puspati reactor core |
| title_short |
Study on the correlation of neutronic and thermal hydraulic of triga mark ii puspati reactor core |
| title_full |
Study on the correlation of neutronic and thermal hydraulic of triga mark ii puspati reactor core |
| title_fullStr |
Study on the correlation of neutronic and thermal hydraulic of triga mark ii puspati reactor core |
| title_full_unstemmed |
Study on the correlation of neutronic and thermal hydraulic of triga mark ii puspati reactor core |
| title_sort |
study on the correlation of neutronic and thermal hydraulic of triga mark ii puspati reactor core |
| publishDate |
2017 |
| url |
Journal of nuclear and related technologies http://dspace.uniten.edu.my:8080/jspui/handle/123456789/71 |
| first_indexed |
2018-09-05T06:38:19Z |
| last_indexed |
2018-09-05T06:38:19Z |
| _version_ |
1610748977117921280 |