Free Access to the whole issue
EPJ Web of Conferences
Volume 42 (2013)
WONDER-2012 – 3rd International Workshop On Nuclear Data Evaluation for Reactor applications
Aix-en-Provence, France, September 25-28, 2012O. Serot, C. De Saint Jean, O. Litaize and G. Noguere (Eds.)
ISBN: 978-2-7598-0961-5
Microscopic and Integral Nuclear data Measurements
Open Access
Fission Fragment characterization with FALSTAFF at NFS 01001
Published online: 18 March 2013
Open Access
Neutron capture and fission reactions on 235U: cross sections, α-ratios and prompt γ-ray emission from fission 01002
Published online: 18 March 2013
Open Access
Neutron-induced cross sections of actinides via the surrogate-reaction method 01003
Published online: 18 March 2013
Open Access
(n,xn γ) reaction cross section measurements for (n,xn) reaction studies 01005
Published online: 18 March 2013
Open Access
Measurement of mass yields from the 241Am(2nth,f) reaction at the Lohengrin Spectrometer 01006
Published online: 18 March 2013
Open Access
Development of a Gas Filled Magnet spectrometer coupled with the Lohengrin spectrometer for fission study 01007
Published online: 18 March 2013
Evaluation of Nuclear data (Theories, Models, Codes)
Open Access
Evaluation of neutron induced reaction cross sections in the resolved and unresolved resonance region at EC – JRC – IRMM 02001
Published online: 18 March 2013
Open Access
Evaluation of stable tungsten isotopes in the resolved resonance region 02002
Published online: 18 March 2013
Open Access
Validation of capture yield calculations in the Resolved Resonance Energy Range with CONRAD code 02003
Published online: 18 March 2013
Open Access
Recent Developments in the CONRAD Code regarding Experimental Corrections 02004
Published online: 18 March 2013
Open Access
A dispersive optical model potential for nucleon induced reactions on 238U and 232Th nuclei with full coupling 02005
Published online: 18 March 2013
Uncertainties and Covariance Matrices
Open Access
Needs of reliable nuclear data and covariance matrices for Burnup Credit in JEFF-3 library 03001
Published online: 18 March 2013
Open Access
Status of XSUSA for Sampling Based Nuclear Data Uncertainty and Sensitivity Analysis 03003
Published online: 18 March 2013
Gamma Production
Open Access
Nuclear data production, calculation and measurement: a global overview of the gamma heating issue 04001
Published online: 18 March 2013
Open Access
A Monte Carlo Simulation of Prompt Gamma Emission from Fission Fragments 04003
Published online: 18 March 2013
Processing and Benchmarking
Open Access
First feedback with the AMMON integral experiment for the JHR calculations 05001
Published online: 18 March 2013
Open Access
Reanalysis of the Gas-cooled fast reactor experiments at the zero power facility Proteus – Spectral indices 05002
Published online: 18 March 2013
Open Access
Criticality experiments and benchmarks for cross section evaluation: the neptunium case 05003
Published online: 18 March 2013
Open Access
Reactivity effect breakdown calculations with deterministic and stochastic perturbations analysis – JEFF-3.1.1 to JEFF3.2T1 (BRC-2009) actinides application 05004
Published online: 18 March 2013
Open Access
Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations 05005
Published online: 18 March 2013
Fission Modeling
Open Access
Sub-barrier resonance fission and its effects on fission fragment properties, exemplified on 234,238U(n,f) 06001
Published online: 18 March 2013
Open Access
Intermediate Structures in Fission and Consequences on Average Partial Cross Sections 06002
Published online: 18 March 2013
Open Access
Evaluation of excitation energy and spin in fission fragments using the statistical model, and the FIPPS project 06004
Published online: 18 March 2013
Open Access
Modelling the widths of fission observables in GEF 06005
Published online: 18 March 2013
Poster Session
Open Access
Review of the n_TOF experimental program for Reactor Applications 07001
Published online: 18 March 2013
Open Access
Application of GRS method to evaluation of uncertainties of calculation parameters of perspective sodium-cooled fast reactor 07002
Published online: 18 March 2013
Open Access
Kriging approach for the experimental cross-section covariances estimation 07003
Published online: 18 March 2013
Open Access
Processing and validation of JEFF-3.1.1 and ENDF/B-VII.0 group-wise cross section libraries for shielding calculations 07004
Published online: 18 March 2013
Open Access
Testing of Neutron Data for Fe, Cr, Ni based on Integral Experiments 07005
Published online: 18 March 2013
Open Access
Verification of Neutron Data for Main Reactor Materials from RUSFOND Library based on Integral Experiments 07006
Published online: 18 March 2013
Open Access
Point-by-Point model description of average prompt neutron data as a function of total kinetic energy of fission fragments 07007
Published online: 18 March 2013