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Criticality safety analysis of spent fuel pool for TRIGA Puspati reactor using MCNP5

Spent fuel pool uses water to temporarily cool spent nuclear fuels before final disposal. The Malaysian Nuclear Agency is recently working on its spent fuel pool facility to store irradiated TRIGA fuel rods. These irradiated fuels still contain significant amount of fissile material which are capabl...

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Main Authors: Bahri, N. S., Zainal, J., Hamzah, K., Mohammad Saleh, M. A., Rabir, M. H.
Format: Conference or Workshop Item
Language:English
Published: 2019
Subjects:
TP Chemical technology
Online Access:http://eprints.utm.my/id/eprint/91014/1/Nurlaila%20SyamsulBahri2019_CriticalitySafetyAnalysis.pdf
http://eprints.utm.my/id/eprint/91014/
http://dx.doi.org/10.1088/1757-899X/555/1/012001
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spelling my.utm.910142021-05-31T13:21:21Z http://eprints.utm.my/id/eprint/91014/ Criticality safety analysis of spent fuel pool for TRIGA Puspati reactor using MCNP5 Bahri, N. S. Zainal, J. Hamzah, K. Mohammad Saleh, M. A. Rabir, M. H. TP Chemical technology Spent fuel pool uses water to temporarily cool spent nuclear fuels before final disposal. The Malaysian Nuclear Agency is recently working on its spent fuel pool facility to store irradiated TRIGA fuel rods. These irradiated fuels still contain significant amount of fissile material which are capable to induce criticality in the fuel storage facility. This study is therefore performed to investigate the safety criticality analysis for the proposed fuel storage rack design of 5x5 arrays. MCNP5 code was used to model the 5x5 array of fuel storage rack in order to determine the optimal fuel pitch distance. The analysis was based on the standard UZrH1.6 TRIGA fuel cladded with stainless steel used in PUSPATI TRIGA Reactor, which is 19.9% enriched 235U and 20% weight of Uranium. By varying the pitch distance between 4 cm to 14 cm with no neutron absorber included, the optimum fuel rack design was determined where sub-criticality condition can be maintained. 2019 Conference or Workshop Item PeerReviewed application/pdf en http://eprints.utm.my/id/eprint/91014/1/Nurlaila%20SyamsulBahri2019_CriticalitySafetyAnalysis.pdf Bahri, N. S. and Zainal, J. and Hamzah, K. and Mohammad Saleh, M. A. and Rabir, M. H. (2019) Criticality safety analysis of spent fuel pool for TRIGA Puspati reactor using MCNP5. In: International Nuclear Science, Technology and Engineering Conference 2018, iNuSTEC 2018, 23-25 Nov 2018, Universiti Teknologi Malaysia (UTM) Skudai, Johor, Malaysia. http://dx.doi.org/10.1088/1757-899X/555/1/012001
institution Universiti Teknologi Malaysia
building UTM Library
collection Institutional Repository
continent Asia
country Malaysia
content_provider Universiti Teknologi Malaysia
content_source UTM Institutional Repository
url_provider http://eprints.utm.my/
language English
topic TP Chemical technology
spellingShingle TP Chemical technology
Bahri, N. S.
Zainal, J.
Hamzah, K.
Mohammad Saleh, M. A.
Rabir, M. H.
Criticality safety analysis of spent fuel pool for TRIGA Puspati reactor using MCNP5
description Spent fuel pool uses water to temporarily cool spent nuclear fuels before final disposal. The Malaysian Nuclear Agency is recently working on its spent fuel pool facility to store irradiated TRIGA fuel rods. These irradiated fuels still contain significant amount of fissile material which are capable to induce criticality in the fuel storage facility. This study is therefore performed to investigate the safety criticality analysis for the proposed fuel storage rack design of 5x5 arrays. MCNP5 code was used to model the 5x5 array of fuel storage rack in order to determine the optimal fuel pitch distance. The analysis was based on the standard UZrH1.6 TRIGA fuel cladded with stainless steel used in PUSPATI TRIGA Reactor, which is 19.9% enriched 235U and 20% weight of Uranium. By varying the pitch distance between 4 cm to 14 cm with no neutron absorber included, the optimum fuel rack design was determined where sub-criticality condition can be maintained.
format Conference or Workshop Item
author Bahri, N. S.
Zainal, J.
Hamzah, K.
Mohammad Saleh, M. A.
Rabir, M. H.
author_facet Bahri, N. S.
Zainal, J.
Hamzah, K.
Mohammad Saleh, M. A.
Rabir, M. H.
author_sort Bahri, N. S.
title Criticality safety analysis of spent fuel pool for TRIGA Puspati reactor using MCNP5
title_short Criticality safety analysis of spent fuel pool for TRIGA Puspati reactor using MCNP5
title_full Criticality safety analysis of spent fuel pool for TRIGA Puspati reactor using MCNP5
title_fullStr Criticality safety analysis of spent fuel pool for TRIGA Puspati reactor using MCNP5
title_full_unstemmed Criticality safety analysis of spent fuel pool for TRIGA Puspati reactor using MCNP5
title_sort criticality safety analysis of spent fuel pool for triga puspati reactor using mcnp5
publishDate 2019
url http://eprints.utm.my/id/eprint/91014/1/Nurlaila%20SyamsulBahri2019_CriticalitySafetyAnalysis.pdf
http://eprints.utm.my/id/eprint/91014/
http://dx.doi.org/10.1088/1757-899X/555/1/012001
_version_ 1702169633353629696
score 13.211869

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