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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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Main Author: Abdul Aziz bin Mohamed Prof. Madya Dr
Format: Article
Language:English
Published: 2017
Subjects:
Thermal-hydraulic
Neutron kinetics
Neutronic
Online Access:http://dspace.uniten.edu.my:8080/jspui/handle/123456789/71
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spelling my.uniten.dspace-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
institution Universiti Tenaga Nasional
building UNITEN Library
collection Institutional Repository
continent Asia
country Malaysia
content_provider Universiti Tenaga Nasional
content_source UNITEN Institutional Repository
url_provider http://dspace.uniten.edu.my/
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 http://dspace.uniten.edu.my:8080/jspui/handle/123456789/71
_version_ 1644492150269804544
score 13.222552

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