Criticality Safety Analysis for Cask Design with High Discharged Fuel Burnup Using MCNPX Code | ||||
| Arab Journal of Nuclear Sciences and Applications | ||||
| Volume 56, Issue 5, October 2023, Page 80-86 PDF (705.98 K) | ||||
| Document Type: Original Article | ||||
| DOI: 10.21608/ajnsa.2023.189116.1711 | ||||
 View on SCiNiTO | ||||
| Authors | ||||
Moustafa Abdelwahab Aziz   1; amal elsaway2
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| 1Nuclear Safety Center, Egyptian Atomic Energy Authority, Cairo, Egypt | ||||
| 2department of radiation safety research center for nuclear safety atomic energy authority | ||||
| Abstract | ||||
| MCNPX computer code is used to model the general PWR cask which contain 32 typical PWR spent fuel assemblies. For Safe storage and transportation of the cask , factors that affect the criticality were studied using the concept of burn up credit. Several parameters such as initial fuel enrichment , fuel burnup history , cooling time , and axial burnup profile were analysed. The analysis was performed in two different steps , first burn the fuel assembly at different burnup and storage (cooling ) conditions , secondly, incorporate the details of the assemblies into the cask (canister ) model and perform a criticality calculations for the cask. Several cases of unnormal storage conditions are considered in the case of UO2- PWR only]. In this research high discharged fuel assemblies burn up include Standard UO2 - PWR and next generation MOX fuel. The present results are compared with similar GBC-32 benchmark and satisfactory agreements were found.. | ||||
| Keywords | ||||
| Key Words: Burnup credit; Axial Burnup; Wet Cask Design; Criticality Analysis; MCNPX code | ||||
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