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                             45 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Advancing Inverse Sensitivity/Uncertainty Methods for Nuclear Fuel Cycle Applications Arbanas, G.
 2015
 123 C p. 51-56
6 p.
 artikel
2 A New Module for Large Scale Bayesian Evaluation in the Fast Neutron Energy Region Schnabel, G.
 2015
 123 C p. 196-200
5 p.
 artikel
3 A-priori and A-posteriori Covariance Data in Nuclear Cross Section Adjustments: Issues and Challenges Palmiotti, G.
 2015
 123 C p. 41-50
10 p.
 artikel
4 Author Index 2015
 123 C p. 237-238
2 p.
 artikel
5 Bayesian Evaluation Including Covariance Matrices of Neutron-induced Reaction Cross Sections of 181Ta Leeb, H.
 2015
 123 C p. 153-158
6 p.
 artikel
6 Bayesian Monte Carlo Method for Nuclear Data Evaluation Koning, A.J.
 2015
 123 C p. 207-213
7 p.
 artikel
7 Calculations of Nuclear Astrophysics and Californium Fission Neutron Spectrum Averaged Cross Section Uncertainties Using ENDF/B-VII.1, JEFF-3.1.2, JENDL-4.0 and Low-fidelity Covariances Pritychenko, B.
 2015
 123 C p. 119-123
5 p.
 artikel
8 Comparison of Integral Parameter Estimated Uncertainties in Fast Neutron Systems with COMMARA-2.1 and COMMARA-2.0 Covariance Data Aliberti, G.
 2015
 123 C p. 74-78
5 p.
 artikel
9 Contents 2015
 123 C p. iii-vi
nvt p.
 artikel
10 Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization Williams, M.L.
 2015
 123 C p. 92-96
5 p.
 artikel
11 Covariance Matrix Evaluations for Independent Mass Fission Yields Terranova, N.
 2015
 123 C p. 225-230
6 p.
 artikel
12 Covariance of Neutron Cross Sections for 16O through R-matrix Analysis Kunieda, S.
 2015
 123 C p. 159-164
6 p.
 artikel
13 Covariance Propagation in Spectral Indices Griffin, P.J.
 2015
 123 C p. 104-108
5 p.
 artikel
14 Covariances in the Generalized Nuclear Data (GND) Structure Mattoon, C.M.
 2015
 123 C p. 36-40
5 p.
 artikel
15 Current Issues in Nuclear Data Evaluation Methodology: 235U Prompt Fission Neutron Spectra and Multiplicity for Thermal Neutrons Trkov, A.
 2015
 123 C p. 8-15
8 p.
 artikel
16 Data Covariances from R-Matrix Analyses of Light Nuclei Hale, G.M.
 2015
 123 C p. 165-170
6 p.
 artikel
17 Evaluation of Cross Section Uncertainties Using Physical Constraints: Focus on Integral Experiments De Saint Jean, C.
 2015
 123 C p. 178-184
7 p.
 artikel
18 Experiments and Theoretical Data for Studying the Impact of Fission Yield Uncertainties on the Nuclear Fuel Cycle with TALYS/GEF and the Total Monte Carlo Method Pomp, S.
 2015
 123 C p. 220-224
5 p.
 artikel
19 Exploring the Impact of Nuclear Data Uncertainties in Ultra-high Resolution Gamma Spectroscopy for Isotopic Analysis Using Approximate Bayesian Computation Burr, T.
 2015
 123 C p. 140-145
6 p.
 artikel
20 “Full Model” Nuclear Data and Covariance Evaluation Process Using TALYS, Total Monte Carlo and Backward-forward Monte Carlo Bauge, E.
 2015
 123 C p. 201-206
6 p.
 artikel
21 Incorporating Experimental Information in the Total Monte Carlo Methodology Using File Weights Helgesson, P.
 2015
 123 C p. 214-219
6 p.
 artikel
22 Inventory Uncertainty Quantification using TENDL Covariance Data in Fispact-II Eastwood, J.W.
 2015
 123 C p. 84-91
8 p.
 artikel
23 Investigation of Inconsistent ENDF/B-VII.1 Independent and Cumulative Fission Product Yields with Proposed Revisions Pigni, M.T.
 2015
 123 C p. 231-236
6 p.
 artikel
24 Multiple-scattering Corrections to Measurements of the Prompt Fission Neutron Spectrum Taddeucci, T.N.
 2015
 123 C p. 135-139
5 p.
 artikel
25 Nuclear Data Covariances in the Indian Context – Progress, Challenges, Excitement and Perspectives Ganesan, S.
 2015
 123 C p. 21-26
6 p.
 artikel
26 Nuclear Data Sheets Symbols and Abbreviations 2015
 123 C p. IBC-
1 p.
 artikel
27 Nuclear Data Uncertainty Propagation in Depletion Calculations Using Cross Section Uncertainties in One-group or Multi-group Díez, C.J.
 2015
 123 C p. 79-83
5 p.
 artikel
28 Nuclear Data Uncertainty Quantification: Past, Present and Future Smith, D.L.
 2015
 123 C p. 1-7
7 p.
 artikel
29 On the Methodology to Calculate the Covariance of Estimated Resonance Parameters Becker, B.
 2015
 123 C p. 171-177
7 p.
 artikel
30 Preface by the CW2014 Organizers Including Program, Advisory Board, Participants and Photo Neudecker, Denise
 2015
 123 C p. viii-xii
nvt p.
 artikel
31 Preface by the Editor: Ten Years of Special Issues on Nuclear Reaction Data Obložinský, Pavel
 2015
 123 C p. vii-
1 p.
 artikel
32 Preliminary Evaluation and Uncertainty Quantification of the Prompt Fission Neutron Spectrum of 239Pu Neudecker, D.
 2015
 123 C p. 146-152
7 p.
 artikel
33 Progress of Covariance Evaluation at the China Nuclear Data Center Xu, R.
 2015
 123 C p. 16-20
5 p.
 artikel
34 Quality Quantification of Evaluated Cross Section Covariances Varet, S.
 2015
 123 C p. 191-195
5 p.
 artikel
35 Quantification of Uncertainties in Nuclear Density Functional Theory Schunck, N.
 2015
 123 C p. 115-118
4 p.
 artikel
36 Random Sampling of Correlated Parameters – a Consistent Solution for Unfavourable Conditions Žerovnik, G.
 2015
 123 C p. 185-190
6 p.
 artikel
37 Recent Work Leading Towards a New Evaluation of the Neutron Standards Carlson, A.D.
 2015
 123 C p. 27-35
9 p.
 artikel
38 Subspace-based Inverse Uncertainty Quantification for Nuclear Data Assessment Khuwaileh, B.A.
 2015
 123 C p. 57-61
5 p.
 artikel
39 The LANL/LLNL Prompt Fission Neutron Spectrum Program at LANSCE and Approach to Uncertainties Haight, R.C.
 2015
 123 C p. 130-134
5 p.
 artikel
40 The Role of Uncertainty Quantification for Reactor Physics Salvatores, M.
 2015
 123 C p. 68-73
6 p.
 artikel
41 Thoughts on Sensitivity Analysis and Uncertainty Propagation Methods with Respect to the Prompt Fission Neutron Spectrum Impact on Critical Assemblies Rising, M.E.
 2015
 123 C p. 109-114
6 p.
 artikel
42 Truth and the Cosmos: After-dinner Talk at the International Workshop on Nuclear Data Covariances Chadwick, M.B.
 2015
 123 C p. xiii-xvi
nvt p.
 artikel
43 Uncertainty Quantification in Fission Cross Section Measurements at LANSCE Tovesson, F.
 2015
 123 C p. 124-129
6 p.
 artikel
44 Use and Impact of Covariance Data in the Japanese Latest Adjusted Library ADJ2010 Based on JENDL-4.0 Yokoyama, K.
 2015
 123 C p. 97-103
7 p.
 artikel
45 Variance Reduction Factor of Nuclear Data for Integral Neutronics Parameters Chiba, G.
 2015
 123 C p. 62-67
6 p.
 artikel
                             45 gevonden resultaten
 
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