Incorporating Experimental Information in the Total Monte Carlo Methodology Using File Weights
暂无分享,去创建一个
Petter Helgesson | Henrik Sjöstrand | Arjan J. Koning | Dimitri Rochman | Erwin Alhassan | Stephan Pomp | A. Koning | D. Rochman | S. Pomp | H. Sjöstrand | E. Alhassan | P. Helgesson
[1] A.J.M. Plompen,et al. Experimental Uncertainty and Covariance Information in EXFOR Library , 2012 .
[2] P. F. Rose,et al. ENDF-201: ENDF/B-VI summary documentation , 1991 .
[3] Michael E. Rising,et al. Quantification and propagation of nuclear data uncertainties , 2013 .
[4] E. Alhassan,et al. Propagation of nuclear data uncertainties for ELECTRA burn-up calculations , 2013, 1304.1701.
[5] D. Neudecker,et al. Consistent Procedure for Nuclear Data Evaluation Based on Modeling , 2008 .
[6] B. Pritychenko,et al. Towards a More Complete and Accurate Experimental Nuclear Reaction Data Library (EXFOR): International Collaboration Between Nuclear Reaction Data Centres (NRDC) , 2014, 2002.07114.
[7] 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 .
[8] R. Simes,et al. An improved Bonferroni procedure for multiple tests of significance , 1986 .
[9] D. Smith. A unified Monte Carlo approach to fast neutron cross section data evaluation. , 2008 .
[10] Janne Wallenius,et al. ELECTRA: European Lead-Cooled Training Reactor , 2012 .
[11] S Pomp,et al. Total Monte Carlo evaluation for dose calculations. , 2014, Radiation protection dosimetry.
[12] Petter Helgesson,et al. UO2 versus MOX: Propagated Nuclear Data Uncertainty for keff, with Burnup , 2014 .
[13] Arjan J. Koning,et al. Towards sustainable nuclear energy: Putting nuclear physics to work , 2008 .
[14] Arjan J. Koning,et al. Modern Nuclear Data Evaluation with the TALYS Code System , 2012 .
[15] Petter Helgesson,et al. Efficient Use of Monte Carlo: Uncertainty Propagation , 2014 .
[16] Petter Helgesson,et al. Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European Lead Cooled Training Reactor , 2015 .
[17] V. Zerkin. Web Tool for Constructing a Covariance Matrix from EXFOR Uncertainties , 2012 .
[18] 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 .