The continuous-energy neutron data library ENDF60 for use with MCNP{trademark} was released in the fall of 1994, and was based on ENDF/B-Vl evaluations through Release 2. As part of the data validation process for this library, a number of criticality benchmark calculations were performed. The original suite of nine criticality benchmarks used to test ENDF60 has now been expanded to 86 benchmarks. This report documents the specifications for the suite of 86 criticality benchmarks that have been developed for validating nuclear data
The criticality analysis of VVER-1000 mock-up benchmark experiments from the LR-0 research reactor o...
The current edition of the International Handbook of Evaluated Criticality Safety Benchmark Experime...
The COG suite of criticality benchmarks has been formally expanded from 591 to 3,395 to coverthe ent...
The continuous-energy neutron data library ENDF60, for use with the Monte Carlo N-Particle radiation...
Since the nuclear data forms a vital component in reactor physics computations, the nuclear communit...
Submit~wl for publication in the proceedings of the F~tlJ hw?rnationd Conference on Nuclear Critical...
The latest ENDF/B nuclear data library released in 2018 is the result of a new international approac...
The MCNP Monte Carlo code, in conjunction with its continuous-energy ENDF/B-V and ENDF/B-VI cross-se...
Abstract. This paper addresses the assessment of MCNPX-2.5.0 criticality calculations using continuo...
Recently, a suite of 86 criticality benchmarks for the Monte Carlo N-Particle (MCNP) transport code ...
In this chapter we present our MCNP modeling, concerning fast critical experimental benchmarks, abou...
In nuclear criticality safety applications, a number of important uncertainties have to be addressed...
To validate the new Evaluated Nuclear Data File (ENDF)/B-VIII.0β4 library, 31 different critical cor...
The criticality safety benchmark calculations with the RTS&T general purpose Monte Carlo code were e...
The purpose of the ''Criticality Model Report'' is to validate the MCNP (CRWMS M&O 1998h) code's...
The criticality analysis of VVER-1000 mock-up benchmark experiments from the LR-0 research reactor o...
The current edition of the International Handbook of Evaluated Criticality Safety Benchmark Experime...
The COG suite of criticality benchmarks has been formally expanded from 591 to 3,395 to coverthe ent...
The continuous-energy neutron data library ENDF60, for use with the Monte Carlo N-Particle radiation...
Since the nuclear data forms a vital component in reactor physics computations, the nuclear communit...
Submit~wl for publication in the proceedings of the F~tlJ hw?rnationd Conference on Nuclear Critical...
The latest ENDF/B nuclear data library released in 2018 is the result of a new international approac...
The MCNP Monte Carlo code, in conjunction with its continuous-energy ENDF/B-V and ENDF/B-VI cross-se...
Abstract. This paper addresses the assessment of MCNPX-2.5.0 criticality calculations using continuo...
Recently, a suite of 86 criticality benchmarks for the Monte Carlo N-Particle (MCNP) transport code ...
In this chapter we present our MCNP modeling, concerning fast critical experimental benchmarks, abou...
In nuclear criticality safety applications, a number of important uncertainties have to be addressed...
To validate the new Evaluated Nuclear Data File (ENDF)/B-VIII.0β4 library, 31 different critical cor...
The criticality safety benchmark calculations with the RTS&T general purpose Monte Carlo code were e...
The purpose of the ''Criticality Model Report'' is to validate the MCNP (CRWMS M&O 1998h) code's...
The criticality analysis of VVER-1000 mock-up benchmark experiments from the LR-0 research reactor o...
The current edition of the International Handbook of Evaluated Criticality Safety Benchmark Experime...
The COG suite of criticality benchmarks has been formally expanded from 591 to 3,395 to coverthe ent...