Published April 2020
| Version v1
Journal article
Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide
Creators
- 1. Egyptian Nuclear and Radiological Regulatory Authority (ENRRA), Cairo (Egypt)
- 2. University of Alexandria, Alexandria (Egypt)
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.
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Technology
- Journal Volume
- 52
- Journal Issue
- 4
- Series
- 13 refs, 17 figs, 4 tabs
- Journal Page Range
- p. 674-680
- ISSN
- 1738-5733
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 51108555
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP; COMPARATIVE EVALUATIONS; CRITICALITY; FUEL CYCLE; FUELS; HTR-10 REACTOR; M CODES; PLUTONIUM ISOTOPES; REACTOR CORES; SAFEGUARDS; SECURITY; THORIUM OXIDES; URANIUM; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CHALCOGENIDES; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM REACTORS; EVALUATION; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; ISOTOPES; METALS; OXIDES; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TEST FACILITIES; TEST REACTORS; THORIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES