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AUTHOR(S): A. S. Mollah
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ABSTRACT Nuclear data plays one of the most important roles in calculation and modeling of nuclear reactor configuration using both stochastic and deterministic methods. Both Monte Carlo and deterministic reactor physics codes require nuclear data in a specific format in which they have been designed to work properly. This requirement creates the need of a data processing code to process, convert and validate raw nuclear data provided by ENDF, JEFF etc. for their specific use in reactor physics code like MCNP, OpenMC, Serpent, Monk, WIMSD5b etc. The purpose of this study is to process raw nuclear data files in order to validate the critical experimental benchmark using the Monte Carlo code OpenMC and NJOY21 in order to perform the criticality analysis of VVER-1200. Solid geometry of nuclear core for simulation was constructed using Python API of OpenMC. All the OpenMC calculations of keff values with processed ENDF/B-VIII nuclear data library will be contrasted with the values obtained through experimentation, which are available in the International Critically Safety Benchmark Evaluation Project. The objective of this study is to process the ENDF/B-VIII nuclear data library for producing an ACE-hdf5 format that works with OpenMC and successfully completes a few important benchmark scenarios. In order to reduce all mistakes resulting from approximations in geometry modeling or cross-section processing, neutronic calculations for the VVER-1200 reactor were then performed using the three-dimensional, continuous-energy OpenMC Monte Carlo code. |
KEYWORDS OpenMC, VVER-1200, Criticality, safety, neutronic, NJOY21Received |
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Cite this paper A. S. Mollah. (2025) Processing and Validation of ENDF/B-VIII Nuclear Data Library Using NJOY21 and OpenMC for Modeling and Simulation of VVER-1200 reactor. International Journal of Applied Physics, 10, 27-36 |
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