DEVELOPMENT AND VERIFICATION OF NEUTRONIC ANALYSIS AND BURNUP/DEPLETION PROGRAM CODE: LINKAGE CODE OPENMC AND ORIGEN
The research of this thesis discusses the development of program code that coupling the ORIGEN2.2 burnup program with the Monte Carlo OpenMC neutron analysis program called OpenMC-ORIGEN (Op-OR). This study also discusses the results of the comparison of Op- OR program with other programs to vali...
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| Format: | Theses |
| Language: | Indonesia |
| Subjects: | |
| Online Access: | https://digilib.itb.ac.id/gdl/view/32641 |
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| Institution: | Institut Teknologi Bandung |
| Language: | Indonesia |
| Summary: | The research of this thesis discusses the development of program code that coupling the
ORIGEN2.2 burnup program with the Monte Carlo OpenMC neutron analysis program called
OpenMC-ORIGEN (Op-OR). This study also discusses the results of the comparison of Op-
OR program with other programs to validate the program. This program is written using the
Python3 program language in updating the ORIGEN2.2 cross-section library from the
OpenMC program, reading the output from ORIGEN2.2, and writing new input for both.
Using explicit Euler coupling schemes between two program. The accuracy of the results of
this program will be verified by comparing the results with the results of previous studies with
the same parameters. The results of comparisons of Op-OR program with previous studies
differences is quite small. |
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