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 |