NEUTRONIC ANALYSIS IN ENHANCED CANDU 6 (EC6) REACTOR FUELED NATURAL URANIUM AND PLUTONIUM UTILIZATION
Neutronic analysis study on the Enhanced CANDU 6 Reactor (EC6) fueled by natural uranium and plutonium utilization has been done. Evaluation studies carried out using 36 fuel elements in the fuel bundle and analyzed by SRAC 2002 coding system and JENDL version 3.2 as a nuclear data library. This stu...
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| Format: | Theses |
| Language: | Indonesia |
| Online Access: | https://digilib.itb.ac.id/gdl/view/21640 |
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| Institution: | Institut Teknologi Bandung |
| Language: | Indonesia |
| Summary: | Neutronic analysis study on the Enhanced CANDU 6 Reactor (EC6) fueled by natural uranium and plutonium utilization has been done. Evaluation studies carried out using 36 fuel elements in the fuel bundle and analyzed by SRAC 2002 coding system and JENDL version 3.2 as a nuclear data library. This study aimed to compare the neutronic characteristics of assembly design that uses natural uranium fuel and plutonium utilization. The fraction of plutonium that used in this study was 0.01%, 0.03%, 0.05%, and 0.1%. The study results showed that use of natural uranium and plutonium utilization produce critical condition from the beginning of the operation to end over 20 years. EC6 reactor can use fuels other than natural uranium, small fraction plutonium utilization. |
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