A study of criticality and thermal loading in a conceptual micronuclear heat pipe reactor for space applications
Neutronic analysis of a conceptual heat pipe-cooled micronuclear reactor with 70 % enriched uranium nitride fuel is carried out by modeling the core and peripheral control drum movement to estimate the power distribution. The core configuration results in non-uniformities and hotspots. For...
Main Authors: | Aziz Umair, Koreshi Zafar U., Sheikh Shakil R., Khan Hamda |
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Format: | Article |
Language: | English |
Published: |
VINCA Institute of Nuclear Sciences
2020-01-01
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Series: | Nuclear Technology and Radiation Protection |
Subjects: | |
Online Access: | http://www.doiserbia.nb.rs/img/doi/1451-3994/2020/1451-39942003208A.pdf |
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