WPEC Subgroup 44 computational Inter-comparison exercise on correlations in nuclear data libraries

[1]  K. Shibata,et al.  JENDL-4.0: A New Library for Nuclear Science and Engineering , 2011 .

[2]  Roberto Capote,et al.  Nuclear data evaluation methodology including estimates of covariances , 2010 .

[3]  Andrew M. Holcomb,et al.  Augmented ENDF/B-VIII.0 covariance library for SCALE 6.3 , 2021 .

[4]  Georg Schnabel,et al.  Fitting and Analysis Technique for Inconsistent Nuclear Data , 2018, 1803.00960.

[5]  M. Ishikawa,et al.  CIELO Collaboration Summary Results: International Evaluations of Neutron Reactions on Uranium, Plutonium, Iron, Oxygen and Hydrogen , 2018 .

[6]  R. Capote,et al.  Evaluation of the Neutron Data Standards , 2018 .

[7]  Petter Helgesson,et al.  Combining Total Monte Carlo and Unified Monte Carlo : Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances , 2017 .

[8]  Arjan J. Koning,et al.  Monte Carlo nuclear data adjustment via integral information , 2018, The European Physical Journal Plus.

[9]  F. Gunsing,et al.  Unrecognized Sources of Uncertainties (USU) in Experimental Nuclear Data , 2019 .

[10]  Dimitri Rochman,et al.  Correlation ν̅p − σ − χ in the fast neutron range via integral information , 2017 .

[11]  Eric Bauge,et al.  Fission yields and cross sections: correlated or not? , 2021, EPJ Nuclear Sciences & Technologies.

[12]  R. Q. Wright,et al.  ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data , 2018 .

[13]  Arjan J. Koning,et al.  TENDL: Complete Nuclear Data Library for Innovative Nuclear Science and Technology , 2019, Nuclear Data Sheets.

[14]  E. Bauge,et al.  Evaluation of the Covariance Matrix of 239Pu Neutronic Cross Sections in the Continuum Using the Backward-Forward Monte-Carlo Method , 2011 .

[15]  Roberto Capote,et al.  A New Formulation of the Unified Monte Carlo Approach (UMC-B) and Cross-Section Evaluation for the Dosimetry Reaction 55 Mn(n,γ) 56 Mn , 2012 .

[16]  Arjan J. Koning.  Bayesian Monte Carlo method for nuclear data evaluation , 2015 .

[17]  C. J. Díez,et al.  The joint evaluated fission and fusion nuclear data library, JEFF-3.3 , 2020, The European Physical Journal A.

[18]  M. W. Herman,et al.  IAEA CIELO Evaluation of Neutron-induced Reactions on 235U and 238U Targets , 2018 .

[19]  Roberto Capote,et al.  An Investigation of the Performance of the Unified Monte Carlo Method of Neutron Cross Section Data Evaluation , 2008 .