To validate the new Evaluated Nuclear Data File (ENDF)/B-VIII.0β4 library, 31 different critical cores were selected and used for a benchmark test of the important parameter keff. The four utilized libraries are processed using Nuclear Data Processing Code (NJOY2016). The results obtained with the ENDF/B-VIII.0β4 library were compared against those calculated with ENDF/B-VI.8, ENDF/B-VII.0, and ENDF/B-VII.1 libraries using the Monte Carlo N-Particle (MCNP(X)) code. All the MCNP(X) calculations of keff values with these four libraries were compared with the experimentally measured results, which are available in the International Critically Safety Benchmark Evaluation Project. The obtained results are discussed and analyzed in this paper
The current edition of the International Handbook of Evaluated Criticality Safety Benchmark Experime...
The criticality analysis of VVER-1000 mock-up benchmark experiments from the LR-0 research reactor o...
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Since the nuclear data forms a vital component in reactor physics computations, the nuclear communit...
In this chapter we present our MCNP modeling, concerning fast critical experimental benchmarks, abou...
The MCNP Monte Carlo code, in conjunction with its continuous-energy ENDF/B-V and ENDF/B-VI cross-se...
Recently, a suite of 86 criticality benchmarks for the Monte Carlo N-Particle (MCNP) transport code ...
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The continuous-energy neutron data library ENDF60 for use with MCNP{trademark} was released in the f...
International audienceThe development of bias estimation methodologies has been a great tool for dat...
The continuous-energy neutron data library ENDF60, for use with the Monte Carlo N-Particle radiation...
Submit~wl for publication in the proceedings of the F~tlJ hw?rnationd Conference on Nuclear Critical...
Criticality benchmark testing was performed with evaluated nuclear data libraries for thermal, low-e...
The latest ENDF/B nuclear data library released in 2018 is the result of a new international approac...
The NJOY Nuclear Data Processing System is used all over the world to process evaluated nuclear data...
The current edition of the International Handbook of Evaluated Criticality Safety Benchmark Experime...
The criticality analysis of VVER-1000 mock-up benchmark experiments from the LR-0 research reactor o...
In this report we investigate the adequacy of the available {sup 233}U cross-section data for calcul...
Since the nuclear data forms a vital component in reactor physics computations, the nuclear communit...
In this chapter we present our MCNP modeling, concerning fast critical experimental benchmarks, abou...
The MCNP Monte Carlo code, in conjunction with its continuous-energy ENDF/B-V and ENDF/B-VI cross-se...
Recently, a suite of 86 criticality benchmarks for the Monte Carlo N-Particle (MCNP) transport code ...
The criticality safety benchmark calculations with the RTS&T general purpose Monte Carlo code were e...
The continuous-energy neutron data library ENDF60 for use with MCNP{trademark} was released in the f...
International audienceThe development of bias estimation methodologies has been a great tool for dat...
The continuous-energy neutron data library ENDF60, for use with the Monte Carlo N-Particle radiation...
Submit~wl for publication in the proceedings of the F~tlJ hw?rnationd Conference on Nuclear Critical...
Criticality benchmark testing was performed with evaluated nuclear data libraries for thermal, low-e...
The latest ENDF/B nuclear data library released in 2018 is the result of a new international approac...
The NJOY Nuclear Data Processing System is used all over the world to process evaluated nuclear data...
The current edition of the International Handbook of Evaluated Criticality Safety Benchmark Experime...
The criticality analysis of VVER-1000 mock-up benchmark experiments from the LR-0 research reactor o...
In this report we investigate the adequacy of the available {sup 233}U cross-section data for calcul...