Analisis Perhitungan Benchmark Keselamatan Kritikalitas Larutan Uranil Nitrat di Teras Slab 280T STACY
Criticality benchmark experiment at STACY critical facility is important for validation of computation technique and nuclear data library used in design of nuclear fuel cycle criticality safety. This paper discusses criticality safety benchmark calculation at STACY facility, which uses uranyl nitrat...
| Main Authors: | , , |
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| Format: | Article |
| Language: | English |
| Published: |
Lambung Mangkurat University Press
2017-03-01
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| Series: | Jurnal Fisika Flux |
| Subjects: | |
| Online Access: | http://ppjp.unlam.ac.id/journal/index.php/f/article/view/3115 |
| Summary: | Criticality benchmark experiment at STACY critical facility is important for
validation of computation technique and nuclear data library used in design of nuclear
fuel cycle criticality safety. This paper discusses criticality safety benchmark
calculation at STACY facility, which uses uranyl nitrate solution with MCNP-4C Monte
Carlo transport code. The continuous energy nuclear data library was utilized in
benchmark calculation to complete criticality safety analysis. The MCNP-4C criticality
(keff) prediction indicated overestimated results for all configurations except for
configuration 131. The biases of calculation with criticality experiment (keff = 1) were
under 0.26%. Configuration 140 calculation showed the most precisely agreement with
C/E value of 1.0001. From these results, it can be concluded that the capability and
reliability of MCNP-4C is constantly high in prediction of criticality accuracy for uranyl
nitrate solution at STACY 280T slab core. |
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| ISSN: | 1829-796X 2541-1713 |