Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide
We used MCNP6 computer code to model HTR-10 core reactor. We used two types of fuel; UO2 and (Th+Pu)O2 mixture. We determined the critical height at which the reactor approached criticality in both two cases. The neutronic and burnup parameters were investigated. The results indicated that the core...
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doaj-04a19207aff243598e465dce919862442020-11-25T02:30:47ZengElsevierNuclear Engineering and Technology1738-57332020-04-01524674680Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxideMohamed A. Alzamly0Moustafa Aziz1Alya A. Badawi2Hanaa Abou Gabal3Abdel Rraouf A. Gadallah4Egyptian Nuclear and Radiological Regulatory Authority (ENRRA), Egypt; Corresponding author.Egyptian Nuclear and Radiological Regulatory Authority (ENRRA), Egypt; Corresponding author.Department of Nuclear and Radiation Engineering, Faculty of Engineering, University of Alexandria, EgyptDepartment of Nuclear and Radiation Engineering, Faculty of Engineering, University of Alexandria, EgyptEgyptian Nuclear and Radiological Regulatory Authority (ENRRA), EgyptWe used MCNP6 computer code to model HTR-10 core reactor. We used two types of fuel; UO2 and (Th+Pu)O2 mixture. We determined the critical height at which the reactor approached criticality in both two cases. The neutronic and burnup parameters were investigated. The results indicated that the core fueled with mixed (Th+Pu)O2, achieved about 24% higher fuel cycle length than the UO2 case. It also enhanced safeguard security by burning Pu isotopes. The results were compared with previously published papers and good agreements were found. Keywords: Pebble-bed, HTR-10, Burnup, Thorium based fuelhttp://www.sciencedirect.com/science/article/pii/S1738573319303043 |
collection |
DOAJ |
language |
English |
format |
Article |
sources |
DOAJ |
author |
Mohamed A. Alzamly Moustafa Aziz Alya A. Badawi Hanaa Abou Gabal Abdel Rraouf A. Gadallah |
spellingShingle |
Mohamed A. Alzamly Moustafa Aziz Alya A. Badawi Hanaa Abou Gabal Abdel Rraouf A. Gadallah Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide Nuclear Engineering and Technology |
author_facet |
Mohamed A. Alzamly Moustafa Aziz Alya A. Badawi Hanaa Abou Gabal Abdel Rraouf A. Gadallah |
author_sort |
Mohamed A. Alzamly |
title |
Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide |
title_short |
Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide |
title_full |
Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide |
title_fullStr |
Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide |
title_full_unstemmed |
Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide |
title_sort |
burnup analysis for htr-10 reactor core loaded with uranium and thorium oxide |
publisher |
Elsevier |
series |
Nuclear Engineering and Technology |
issn |
1738-5733 |
publishDate |
2020-04-01 |
description |
We used MCNP6 computer code to model HTR-10 core reactor. We used two types of fuel; UO2 and (Th+Pu)O2 mixture. We determined the critical height at which the reactor approached criticality in both two cases. The neutronic and burnup parameters were investigated. The results indicated that the core fueled with mixed (Th+Pu)O2, achieved about 24% higher fuel cycle length than the UO2 case. It also enhanced safeguard security by burning Pu isotopes. The results were compared with previously published papers and good agreements were found. Keywords: Pebble-bed, HTR-10, Burnup, Thorium based fuel |
url |
http://www.sciencedirect.com/science/article/pii/S1738573319303043 |
work_keys_str_mv |
AT mohamedaalzamly burnupanalysisforhtr10reactorcoreloadedwithuraniumandthoriumoxide AT moustafaaziz burnupanalysisforhtr10reactorcoreloadedwithuraniumandthoriumoxide AT alyaabadawi burnupanalysisforhtr10reactorcoreloadedwithuraniumandthoriumoxide AT hanaaabougabal burnupanalysisforhtr10reactorcoreloadedwithuraniumandthoriumoxide AT abdelrraoufagadallah burnupanalysisforhtr10reactorcoreloadedwithuraniumandthoriumoxide |
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1724827995842019328 |