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                             147 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Adequate Treatment of Correlated Experimental Data in Nuclear Data Evaluations Avoiding Peelle's Pertinent Puzzle Neudecker, D.
 2014
 118 C p. 364-366
3 p.
 artikel
2 Advanced Uncertainty Quantification For Fission Observables Neudecker, D.
 2014
 118 C p. 353-356
4 p.
 artikel
3 A Feasibility and Optimization Study to Design a Nondestructive ATR Fuel Permanent Scanning System to Determine Fuel Burnup Navarro, J.
 2014
 118 C p. 571-574
4 p.
 artikel
4 A Fully Lane-consistent Dispersive Optical Model Potential for Even Fe Isotopes Based on a Soft-rotator Model Sun, W.
 2014
 118 C p. 191-194
4 p.
 artikel
5 A Method Using Pseudo-measurements and Shrinkage for the Estimation of Cross Section Covariances Varet, S.
 2014
 118 C p. 357-359
3 p.
 artikel
6 Analysis of 238Pu and 56Fe Evaluated Data for Use in MYRRHA Díez, C.J.
 2014
 118 C p. 516-518
3 p.
 artikel
7 Analysis of Pu Isotopes in Melted Fuel by Neutron Resonance Transmission: Examination by Linear Absorption Model Kitatani, F.
 2014
 118 C p. 505-509
5 p.
 artikel
8 Analysis of the Neutronic Properties of the Prototype FBR Monju Based on Several Evaluated Nuclear Data Libraries van Rooijen, W.F.G.
 2014
 118 C p. 426-429
4 p.
 artikel
9 An Evaluation of the Scattering Law for Light and Heavy Water in ENDF-6 Format, Based on Experimental Data and Molecular Dynamics Márquez Damián, J.I.
 2014
 118 C p. 169-171
3 p.
 artikel
10 Angular Momentum Distribution of Fission Fragments Stetcu, I.
 2014
 118 C p. 230-232
3 p.
 artikel
11 A Nuclear Data Project on Neutron Capture Cross Sections of Long-Lived Fission Products and Minor Actinides Igashira, M.
 2014
 118 C p. 72-77
6 p.
 artikel
12 Application of the Continuum Discretized Coupled Channels Method to Nucleon-induced Reactions on 6,7Li for Energies up to 150 MeV Guo, H.
 2014
 118 C p. 254-257
4 p.
 artikel
13 Application of the PSI-NUSS Tool for the Estimation of Nuclear Data Related k eff Uncertainties for the OECD/NEA WPNCS UACSA Phase I Benchmark Zhu, T.
 2014
 118 C p. 453-455
3 p.
 artikel
14 Applications of Nuclear Data Covariances to Criticality Safety and Spent Fuel Characterization Williams, M.L.
 2014
 118 C p. 341-345
5 p.
 artikel
15 Average Description of Dipole Gamma Transitions in Hot Atomic Nuclei Plujko, V.A.
 2014
 118 C p. 237-239
3 p.
 artikel
16 Bayesian Statistical Analysis Applied to NAA Data for Neutron Flux Spectrum Determination Chiesa, D.
 2014
 118 C p. 564-567
4 p.
 artikel
17 Benchmark Calculations for Reflector Effect in Fast Cores by Using the Latest Evaluated Nuclear Data Libraries Fukushima, M.
 2014
 118 C p. 405-409
5 p.
 artikel
18 Benchmarking of ENDF/B-VII.1 and JENDL-4.0 in the Fast Neutron Range Cornock, M.
 2014
 118 C p. 430-432
3 p.
 artikel
19 Benchmarking TENDL-2012 van der Marck, S.C.
 2014
 118 C p. 446-449
4 p.
 artikel
20 Calculating Level Densities of Heavy Nuclei by the Shell Model Monte Carlo Method Alhassid, Y.
 2014
 118 C p. 233-236
4 p.
 artikel
21 Calculation of Delayed Neutron Yields for Various Libraries Huynh, T.D.
 2014
 118 C p. 476-479
4 p.
 artikel
22 Calculations of Compound Nucleus Spin-parity Distributions Populated via the (p,t) Reaction in Support of Surrogate Reaction Measurements Benstead, J.
 2014
 118 C p. 295-297
3 p.
 artikel
23 Characterization of the Caliban and Prospero Critical Assemblies Neutron Spectra for Integral Measurements Experiments Casoli, P.
 2014
 118 C p. 554-557
4 p.
 artikel
24 Cluster Emission for the Pre-equilibrium Exciton Model with Spin Variables Běták, E.
 2014
 118 C p. 284-286
3 p.
 artikel
25 Combined Use of Integral Experiments and Covariance Data Palmiotti, G.
 2014
 118 C p. 596-636
41 p.
 artikel
26 Combining Total Monte Carlo and Benchmarks for Nuclear Data Uncertainty Propagation on a Lead Fast Reactor's Safety Parameters Alhassan, E.
 2014
 118 C p. 542-544
3 p.
 artikel
27 Comparison of ENDF/B-VII.1 and ENDF/B-VII.0 Results for the Expanded Criticality Validation Suite for MCNP and for Selected Additional Criticality Benchmarks Mosteller, R.
 2014
 118 C p. 442-445
4 p.
 artikel
28 Comparison of Two Approaches for Nuclear Data Uncertainty Propagation in MCNPX for Selected Fast Spectrum Critical Benchmarks Zhu, T.
 2014
 118 C p. 388-391
4 p.
 artikel
29 Connecting the Dots, or Nuclear Data in the Age of Supercomputing Bauge, E.
 2014
 118 C p. 32-37
6 p.
 artikel
30 CONRAD Evaluation Code: Development Status and Perspectives Archier, P.
 2014
 118 C p. 488-490
3 p.
 artikel
31 Consistent Analysis of the Nuclear Reaction Mechanisms Involved in Deuteron-induced Activation at Low and Medium Energies Avrigeanu, M.
 2014
 118 C p. 301-304
4 p.
 artikel
32 Consistent Treatment of (α, x) Reaction Cross Sections and α-particle Emission Particularly in Fast–neutron Induced Reactions Avrigeanu, V.
 2014
 118 C p. 262-265
4 p.
 artikel
33 Continuous Integration and Deployment Software to Automate Nuclear Data Verification and Validation Arcilla, R.
 2014
 118 C p. 422-425
4 p.
 artikel
34 Coupled-Channel Models of Direct-Semidirect Capture via Giant-Dipole Resonances Thompson, I.J.
 2014
 118 C p. 292-294
3 p.
 artikel
35 Coupled-channel Treatment of Isobaric Analog Resonances in (p,p′) Capture Processes Thompson, I.J.
 2014
 118 C p. 298-300
3 p.
 artikel
36 Cross Section Calculations of Deuteron-induced Reactions Using the Extended CCONE Code Nakayama, S.
 2014
 118 C p. 305-307
3 p.
 artikel
37 Current Density and Angular Distribution of Neutrons Emitted During Scission Carjan, N.
 2014
 118 C p. 199-203
5 p.
 artikel
38 Development of JENDL Decay and Fission Yield Data Libraries Katakura, J.
 2014
 118 C p. 104-107
4 p.
 artikel
39 Development Progress of the GAIA Nuclear Data Processing Software Ferran, G.
 2014
 118 C p. 491-493
3 p.
 artikel
40 EASY-II Renaissance: n, p, d, α, γ-induced Inventory Code System Sublet, J.-Ch.
 2014
 118 C p. 115-117
3 p.
 artikel
41 Electron-antineutrino Disappearance Observed by the Daya Bay Reactor Neutrino Experiment Heng, Y.
 2014
 118 C p. 91-97
7 p.
 artikel
42 Energy Dependence of Plutonium and Uranium Average Fragment Total Kinetic Energies Lestone, J.P.
 2014
 118 C p. 208-210
3 p.
 artikel
43 Estimation of Nuclear Reaction Model Parameter Covariances and the Related Neutron Induced Cross Sections with Physical Constraints De Saint Jean, C.
 2014
 118 C p. 336-340
5 p.
 artikel
44 Evaluated Activation Cross Section Data for Proton Induced Nuclear Reactions on W up to 3 GeV Incident Energy Konobeyev, A.Yu.
 2014
 118 C p. 112-114
3 p.
 artikel
45 Evaluation of Delayed Critical ORNL Unreflected HEU Metal Sphere (ORSphere) Marshall, M.A.
 2014
 118 C p. 469-471
3 p.
 artikel
46 Evaluation of the Covariance Matrix of Estimated Resonance Parameters Becker, B.
 2014
 118 C p. 381-383
3 p.
 artikel
47 Evaluation of Tungsten Neutron Cross Sections in the Resolved Resonance Region Pigni, M.T.
 2014
 118 C p. 147-150
4 p.
 artikel
48 Evaluation of Uncertainties in β eff by Means of Deterministic and Monte Carlo Methods Kodeli, I.
 2014
 118 C p. 370-373
4 p.
 artikel
49 Event-by-event Modeling of Prompt Neutrons and Photons from Neutron-induced and Spontaneous Fission with FREYA Vogt, R.
 2014
 118 C p. 220-223
4 p.
 artikel
50 Exclusive Multiple Emission Cross Sections in the Hybrid Monte Carlo Pre-equilibrium Model and in EMPIRE-3.1 Carlson, B.V.
 2014
 118 C p. 276-279
4 p.
 artikel
51 Exploring New Neutron-rich Nuclei with the Facility for Rare Isotope Beams Thoennessen, M.
 2014
 118 C p. 85-90
6 p.
 artikel
52 Extension of TALYS to 1 GeV Koning, A.J.
 2014
 118 C p. 187-190
4 p.
 artikel
53 Fitting Prompt Fission Neutron Spectra Using Kalman Filter Integrated with Empire Code Nobre, G.P.A.
 2014
 118 C p. 224-226
3 p.
 artikel
54 Fluctuations Above the Resonance Range in Evaluated Data of 55Mn Trkov, A.
 2014
 118 C p. 161-164
4 p.
 artikel
55 Gamma Heating Rate Evaluation for Material Irradiation Test in the Joyo Experimental Fast Reactor Maeda, S.
 2014
 118 C p. 494-497
4 p.
 artikel
56 Generation of an S ( α , β ) Covariance Matrix by Monte Carlo Sampling of the Phonon Frequency Spectrum Holmes, J.C.
 2014
 118 C p. 392-395
4 p.
 artikel
57 GRS Method for Uncertainties Evaluation of Parameters in a Prospective Fast Reactor Peregudov, A.
 2014
 118 C p. 548-550
3 p.
 artikel
58 Identification of Possible Discrepancies in HEU Metal Benchmarks Bess, J.D.
 2014
 118 C p. 466-468
3 p.
 artikel
59 Impact of Nuclear Data Uncertainties on Advanced Fuel Cycles and their Irradiated Fuel – a Comparison between Libraries Díez, C.J.
 2014
 118 C p. 538-541
4 p.
 artikel
60 Impact of the Doppler Broadened Double Differential Cross Section on Observed Resonance Profiles Dagan, R.
 2014
 118 C p. 179-182
4 p.
 artikel
61 Improved Nuclear Inputs for Nuclear Model Codes Based on the Gogny Interaction Martini, M.
 2014
 118 C p. 273-275
3 p.
 artikel
62 Improved Simulation of the Pre-equilibrium Triton Emission in Nuclear Reactions Induced by Nucleons Konobeyev, A.Yu.
 2014
 118 C p. 280-283
4 p.
 artikel
63 Improvement of 238U Inelastic Scattering Cross Section for an Accurate Calculation of Large Commercial Reactors Santamarina, A.
 2014
 118 C p. 118-121
4 p.
 artikel
64 Improvements and Extensions of the Neutron Cross Section and Fluence Standards Carlson, A.D.
 2014
 118 C p. 126-131
6 p.
 artikel
65 Inelastic Thermal Neutron Scattering Cross Sections for Reactor-grade Graphite Hawari, A.I.
 2014
 118 C p. 176-178
3 p.
 artikel
66 Integral Benchmark Data for Nuclear Data Testing Through the ICSBEP & IRPhEP Briggs, J.B.
 2014
 118 C p. 396-400
5 p.
 artikel
67 Integral Data Testing of ENDF/B-VII.1 Files - Success Stories and Need to Improve Stories Kahler, A.C.
 2014
 118 C p. 410-413
4 p.
 artikel
68 Interaction of Fast Nucleons with Actinide Nuclei Studied with GEANT4 Malyshkin, Yu.
 2014
 118 C p. 329-332
4 p.
 artikel
69 Inverse Sensitivity/Uncertainty Methods Development for Nuclear Fuel Cycle Applications Arbanas, G.
 2014
 118 C p. 374-377
4 p.
 artikel
70 Investigation of Nuclear Data Libraries with TRIPOLI-4 Monte Carlo Code for Sodium-cooled Fast Reactors Lee, Y.-K.
 2014
 118 C p. 433-436
4 p.
 artikel
71 Investigation of n+238U Fission Observables Litaize, O.
 2014
 118 C p. 216-219
4 p.
 artikel
72 Iron Filtered Neutron Spectra: Measurement and Comparison with Calculations Using Different Libraries Jansky, B.
 2014
 118 C p. 551-553
3 p.
 artikel
73 Joint Neutron Noise Measurements on Metallic Reactor Caliban Chapelle, A.
 2014
 118 C p. 558-560
3 p.
 artikel
74 MCNP6 Fission Cross Section Calculations at Intermediate and High Energies Mashnik, S.G.
 2014
 118 C p. 320-322
3 p.
 artikel
75 MCNP6 Simulation of Quasi-Monoenergetic 7Li(p,n) Neutron Sources below 150 MeV Mashnik, S.G.
 2014
 118 C p. 323-325
3 p.
 artikel
76 MCNP6 Study of Fragmentation Products from 112Sn+112Sn and 124Sn+124Sn at 1 GeV/A Mashnik, S.G.
 2014
 118 C p. 326-328
3 p.
 artikel
77 Methods and Issues for the Combined Use of Integral Experiments and Covariance Data: Results of a NEA International Collaborative Study Salvatores, M.
 2014
 118 C p. 38-71
34 p.
 artikel
78 Minor Actinides, Major Challenges, the Needs for and Benefits of International Collaboration Plompen, A.J.M.
 2014
 118 C p. 78-84
7 p.
 artikel
79 Modern Techniques for Inelastic Thermal Neutron Scattering Analysis Hawari, A.I.
 2014
 118 C p. 172-175
4 p.
 artikel
80 Monte Carlo Predictions of Prompt Fission Neutrons and Photons: a Code Comparison Talou, P.
 2014
 118 C p. 227-229
3 p.
 artikel
81 n+12C Cross Sections from an R-matrix Analysis of Reactions in the 13C System Hale, G.M.
 2014
 118 C p. 165-168
4 p.
 artikel
82 Neutron Cross Section Covariances for 237Np in the Resolved Resonance Region Cho, Y.-S.
 2014
 118 C p. 378-380
3 p.
 artikel
83 Neutron Cross Section Evaluation of Tungsten and Tantalum Kim, H.I.
 2014
 118 C p. 151-154
4 p.
 artikel
84 Neutron Resonance Densitometry for Particle-like Debris of Melted Fuel Harada, H.
 2014
 118 C p. 502-504
3 p.
 artikel
85 New Approach for Nuclear Reaction Model in the Combination of Intra-nuclear Cascade and DWBA Hashimoto, S.
 2014
 118 C p. 258-261
4 p.
 artikel
86 New Evaluation of n+63,65Cu Nuclear Cross Section Data up to 200 MeV Neutron Energy Pereslavtsev, P.
 2014
 118 C p. 158-160
3 p.
 artikel
87 New JEFF-3.2 Sodium Neutron Induced Cross-sections Evaluation for Neutron Fast Reactors Applications: from 0 to 20 MeV Archier, P.
 2014
 118 C p. 140-143
4 p.
 artikel
88 New Resolved Resonance Region Evaluation for 63,65Cu for Nuclear Criticality Safety Program Sobes, V.
 2014
 118 C p. 155-157
3 p.
 artikel
89 [No title] Herman, Michal
 2014
 118 C p. xiv-xviii
nvt p.
 artikel
90 Nuclear Data and the Oklo Natural Nuclear Reactors Gould, C.R.
 2014
 118 C p. 585-587
3 p.
 artikel
91 Nuclear Data Library Effects on Fast to Thermal Flux Shapes Around PWR Control Rod Tips Vasiliev, A.
 2014
 118 C p. 575-578
4 p.
 artikel
92 Nuclear Data Needs for the Neutronic Design of MYRRHA Fast Spectrum Research Reactor Stankovskiy, A.
 2014
 118 C p. 513-515
3 p.
 artikel
93 Nuclear Data Sheets Symbols and Abbreviations 2014
 118 C p. IBC-
1 p.
 artikel
94 Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor Herrero, J.J.
 2014
 118 C p. 535-537
3 p.
 artikel
95 Nuclear Level Density within Extended Superfluid Model with Collective State Enhancement Plujko, V.A.
 2014
 118 C p. 240-242
3 p.
 artikel
96 Numerical Simulations for Low Energy Nuclear Reactions to Validate Statistical Models Kawano, T.
 2014
 118 C p. 183-186
4 p.
 artikel
97 On the Use of Zero Variance Penalty Conditions for the Generation of Covariance Matrix between Model Parameters Noguere, G.
 2014
 118 C p. 349-352
4 p.
 artikel
98 Physics of Neutron Interactions with 238U: New Developments and Challenges Capote, R.
 2014
 118 C p. 26-31
6 p.
 artikel
99 Preequilibrium Emission of Light Fragments in Spallation Reactions Kerby, L.M.
 2014
 118 C p. 316-319
4 p.
 artikel
100 Present Status of Evaluated Nuclear Data Library for ADS in China Han, Y.
 2014
 118 C p. 108-111
4 p.
 artikel
101 Processing and Validation of JEFF-3.1.2 Cross-section Library into Various Formats: ACE, PENDF, GENDF, MATXSR and BOXER Cabellos, O.
 2014
 118 C p. 456-458
3 p.
 artikel
102 Production and Performance of JEFF3.1.2 Nuclear Data Library in ANSWERS Codes Perry, R.J.
 2014
 118 C p. 463-465
3 p.
 artikel
103 Progress in Developing Nuclear Reaction Calculation Code CCONE for High Energy Nuclear Data Evaluation Iwamoto, O.
 2014
 118 C p. 204-207
4 p.
 artikel
104 Progress of Integral Experiments in Benchmark Fission Assemblies for a Blanket of Hybrid Reactor Liu, R.
 2014
 118 C p. 588-591
4 p.
 artikel
105 Prompt Fission Neutrons and γ Rays Talou, P.
 2014
 118 C p. 195-198
4 p.
 artikel
106 Prompt Neutron Decay Constants of Reflected Systems Ye, T.
 2014
 118 C p. 582-584
3 p.
 artikel
107 Propagation of Neutron Cross Section, Fission Yield, and Decay Data Uncertainties in Depletion Calculations Martinez, J.S.
 2014
 118 C p. 480-483
4 p.
 artikel
108 Propagation of Nuclear Data Uncertainties for ELECTRA Burn-up Calculations Sjöstrand, H.
 2014
 118 C p. 527-530
4 p.
 artikel
109 Propagation of Nuclear Data Uncertainties in Deterministic Calculations: Application of Generalized Perturbation Theory and the Total Monte Carlo Method to a PWR Burnup Pin-Cell Sabouri, P.
 2014
 118 C p. 523-526
4 p.
 artikel
110 239Pu Prompt Fission Neutron Spectra Impact on a Set of Criticality and Experimental Reactor Benchmarks Peneliau, Y.
 2014
 118 C p. 459-462
4 p.
 artikel
111 239Pu Resonance Evaluation for Thermal Benchmark System Calculations Leal, L.C.
 2014
 118 C p. 122-125
4 p.
 artikel
112 Quantification of Uncertainties due to 235,238U, 239,240,241Pu and Fission Products Nuclear Data Uncertainties for a PWR Fuel Assembly da Cruz, D.F.
 2014
 118 C p. 531-534
4 p.
 artikel
113 Reactivity Impact of 2H and 16O Elastic Scattering Nuclear Data on Critical Systems with Heavy Water Roubtsov, D.
 2014
 118 C p. 414-417
4 p.
 artikel
114 Recent Developments of the Liège Intranuclear Cascade Model in View of its Use into High-energy Transport Codes Leray, S.
 2014
 118 C p. 312-315
4 p.
 artikel
115 Recent Investigations and Findings about the 2d- and 3d- Neutron Strength Functions and the p-wave Scattering Radius Mughabghab, S.F.
 2014
 118 C p. 287-291
5 p.
 artikel
116 Recent Results on Studying Photon Strength Functions in Rare-earth Nuclei Valenta, S.
 2014
 118 C p. 243-245
3 p.
 artikel
117 Remarks on KERMA Factors in ACE files Konno, C.
 2014
 118 C p. 450-452
3 p.
 artikel
118 R-matrix Analysis for n +16O Cross-sections up to E n = 6.0 MeV with Covariances Kunieda, S.
 2014
 118 C p. 250-253
4 p.
 artikel
119 Rotational-vibrational Description of Nucleon Scattering on Actinide Nuclei Using a Dispersive Coupled-channel Optical Model Quesada, J.M.
 2014
 118 C p. 270-272
3 p.
 artikel
120 Sensitivity Analysis for Reactor Period Induced by Positive Reactivity Using One-point Adjoint Kinetic Equation Chiba, G.
 2014
 118 C p. 401-404
4 p.
 artikel
121 Sensitivity and System Response of Pin Power Peaking in VVER-1000 Fuel Assembly Using TSUNAMI-2D Frybort, J.
 2014
 118 C p. 579-581
3 p.
 artikel
122 Sensitivity and Uncertainty Analysis of the GFR MOX Fuel Subassembly Lüley, J.
 2014
 118 C p. 545-547
3 p.
 artikel
123 Sensitivity of the Shielding Benchmarks on Variance-covariance Data for Scattering Angular Distributions Jouanne, C.
 2014
 118 C p. 384-387
4 p.
 artikel
124 Sensitvity and Uncertainty Analysis for a Minor-actinide Transmuter with JENDL-4.0 Iwamoto, H.
 2014
 118 C p. 519-522
4 p.
 artikel
125 Spallation Source Modelling for an ADS Using the MCNPX and GEANT4 Packages for Sensitivity Analysis of Reactivity Antolin, M.Q.
 2014
 118 C p. 510-512
3 p.
 artikel
126 Status of the ENDF/B Nuclear Data Library Brown, D.A.
 2014
 118 C p. 98-103
6 p.
 artikel
127 Study of Nuclear Decay Data Contribution to Uncertainties in Heat Load Estimations for Spent Fuel Pools Ferroukhi, H.
 2014
 118 C p. 498-501
4 p.
 artikel
128 Study of Various Potentials in Heavy-ion Collisions at Intermediate Energies Kaur, V.
 2014
 118 C p. 333-335
3 p.
 artikel
129 Systematic Study of Deuteron-induced Reactions from Threshold Ye, T.
 2014
 118 C p. 308-311
4 p.
 artikel
130 Table of Contents 2014
 118 C p. iii-xiii
nvt p.
 artikel
131 TENDL-2012 Processing, Verification and Validation Steps Sublet, J.-Ch.
 2014
 118 C p. 418-421
4 p.
 artikel
132 Testing JEFF-3.1.1 and ENDF/B-VII.1 Decay and Fission Yield Nuclear Data Libraries with Fission Pulse Neutron Emission and Decay Heat Experiments Cabellos, O.
 2014
 118 C p. 472-475
4 p.
 artikel
133 The CIELO Collaboration: Neutron Reactions on 1H, 16O, 56Fe, 235,238U, and 239Pu Chadwick, M.B.
 2014
 118 C p. 1-25
25 p.
 artikel
134 The Impact of Intermediate Structure on the Average Fission Cross Sections Bouland, O.
 2014
 118 C p. 211-215
5 p.
 artikel
135 The Influence of Changes in Iron Cross Section in the Thermal Region between CENDL-3.1 and ENDF/B-VII.0 Kostal, M.
 2014
 118 C p. 561-563
3 p.
 artikel
136 Theoretical Analysis of Gamma-ray Strength Function for Pd Isotopes Iwamoto, N.
 2014
 118 C p. 246-249
4 p.
 artikel
137 Theoretical Calculation of Actinide Nuclear Reaction Data Han, Y.
 2014
 118 C p. 132-135
4 p.
 artikel
138 Three Heavy Reflector Experiments in the IPEN/MB-01 Reactor: Stainless Steel, Carbon Steel, and Nickel dos Santos, A.
 2014
 118 C p. 568-570
3 p.
 artikel
139 Towards a Coupled-channel Optical Potential for Rare-earth Nuclei Nobre, G.P.A.
 2014
 118 C p. 266-269
4 p.
 artikel
140 Uncertainty Assessment for Fast Reactors Based on Nuclear Data Adjustment Ivanova, T.
 2014
 118 C p. 592-595
4 p.
 artikel
141 Uncertainty Propagation of Fission Product Yield Data in Spent Fuel Inventory Calculations Mills, R.W.
 2014
 118 C p. 484-487
4 p.
 artikel
142 Uncertainty Propagation with Fast Monte Carlo Techniques Rochman, D.
 2014
 118 C p. 367-369
3 p.
 artikel
143 Uncertainty Quantification of Prompt Fission Neutron Spectra Using the Unified Monte Carlo Method Rising, M.E.
 2014
 118 C p. 360-363
4 p.
 artikel
144 Uncertainty Study of Nuclear Model Parameters for the n+56Fe Reactions in the Fast Neutron Region below 20 MeV Duan, J.
 2014
 118 C p. 346-348
3 p.
 artikel
145 Updated and Revised Neutron Reaction Data for 233U Yu, B.
 2014
 118 C p. 136-139
4 p.
 artikel
146 Validation of Cross Sections with Criticality Experiment and Reaction Rates: the Neptunium Case Leong, L.S.
 2014
 118 C p. 437-441
5 p.
 artikel
147 Zirconium Evaluations for ENDF/B-VII.2 for the Fast Region Brown, D.A.
 2014
 118 C p. 144-146
3 p.
 artikel
                             147 gevonden resultaten
 
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