Workshop on Nuclear Data Evaluation for Reactor Applications |
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Château de Cadarache
Saint-Paul-lez-Durance
France
Last updated on 19 Sept 2006
| Name | Preliminary title |
|---|---|
| BAUGE Eric | Evaluation of the covariance matrix of neutronic cross sections using the Backward-Forward Monte-Carlo Method |
| BELGYA Tamas | Determination of thermal neutron capture cross sections using cold neutron beams at the Budapest PGAA-NIPS facilities |
| BERNARD David | Modelling of 241Am(n,γ)242mAm isomeric ratio in the resonances |
| BERTHOUMIEUX Eric | A R-Matrix package to study charged particles resonant reactions |
| BLOCK Robert C. | Neutrons Scattered by Quantum Entangled Hydrogen in Water? |
| BORELLA Alessandro | AGS, a code to propagate uncertainties of cross section measurement data |
| BOULAND Olivier | Experimental and Evaluated Subthreshold Fission (with H. Weigmann) |
| CHEN Zhenpeng | R-matrix analysis with the code RAC |
| COSTE-DELCLAUX Mireille | New improvements in mixture self-shielding treatment with the APOLLO2 code |
| COURCELLE Arnaud | Quantum crystal lattice model of resonance scattering |
| DAGAN Ron | On the effect of energy dependent scattering kernel for burn up evaluation |
| DANON Yaron | Cross Section measurements at the RPI Gaerttner LINAC Laboratory |
| DE SAINT JEAN Cyrille | Status of CONRAD a nuclear process analysis |
| DEAN Christopher | |
| DORE Diane | |
| DUPONT Emmeric | |
| FORT Eric | Revisiting nubar evaluation in the resolved resonance range |
| FRÖHNER Fritz | Limitations of the fitacs code, Moldauer effect ((n,γn') reaction) in the unresolved range ENDF-compatible average parameters |
| FURMAN Walter | Measurement of delayed neutron yield from neutron induced fission of 237Np |
| GUBER Klaus | |
| GUNSING Frank | Current status of the n-TOF facility at CERN |
| HALE Gerry M. | Using R-matrix theory to analyze rsonant reactions |
| HARADA Hideo | Measurement of the thermal neutron capture cross section of 237Np for the study of nuclear transmutation |
| HENRIKSSON Hans | Evaluated data projects at the NEA |
| HORI Jun-ichi | Neutron capture cross section measurements of fission product nuclei with Linac Time-of-Flight Method |
| HWANG Richard | Exploration of an alternative method for treating unresolved resonances |
| JACQMIN Robert | |
| JANEVA Natalia | Thick Filter Transmission Measurements |
| JOUANNE Cedric | |
| KÄPPELER Franz | Neutron capture data in the keV region: problems and perspectives |
| KAHLER Albert C. | Current Status of the NJOY Nuclear Data Processing Code System and initial ENDF/B-VII data testing results |
| KAWANO Toshihiko | Evaluation of neutron capture cross sections for actinides |
| KONING Arjan | TALYS meets the URR: low energy nuclear model calculations |
| KOPECKY Stefan | The impact of the resolution function on resonance parameters |
| KOYUMDJIEVA Nina | Statistical modelling of resonant cross section structure in URR, model of the characteristic function |
| LARSON Nancy | Future developments for SAMMY & Use of Covariance Matrices in SAMMY |
| LETOURNEAU Alain | Actinide cross section measurements in the thermal energy region |
| LITAIZE Olivier | Simulation of NE213 Gamma Response Function Using an Improved Multiparameter Minimisation Method |
| LUBITZ Cecil R. | |
| LUKYANOV Alexander | Multilevel Parameterization of Neutron Resonance Cross Sections |
| LYNN John E. | Fission Reaction Theory in evaluation of the unresolved region of actinide cross sections |
| MATTES Margarete | Thermal neutron scattering cross section |
| MOXON Michael | Neutron Data Analysis with the REFIT Code |
| NOGUERE Gilles | |
| RIBON Pierre | Is it worth taking into account self shielding for nu-fission? |
| RICH Emilie | |
| RIDIKAS Danas | |
| ROCHMAN Dimitri | Status of the CSISRS database for present and future evaluations work & Cross section covariance calculations in the resonance and fast neutron regions |
| RUGAMA Yolanda | Evaluated data projects at the NEA |
| RUGGIERI Jean Michel | |
| SAGE Cristophe | |
| SCHILLEBEECKX Peter | The use of C6D6 detectors for determination of capture cross section data |
| SEROT Olivier | |
| SIRAKOV Ivan | The evaluation of cross section data in the Unresolved Resonance Region |
| SUBLET Jean Christophe | Current status of the CALENDF code |
| TUDORA Anabella | Experimental prompt fission neutron "sawtooth" data described by the "point by point" model |
| UKRAINTSEV V.F. | Transfer of nuclear data uncertainties to the uncertainties of fuel characteristic by interval calculation |
| ULLMANN John | Neutron capture measurements using the DANCE detector at Los Alamos |
| VOLEV Konstentin | 232Th cross sections and resonance parameters up to 50 keV |
| WAGEMANS Cyriel | Problems related to the evaluation of (n,f) and (n,charged particle) cross sections for thermal neutrons |
| WARE Timothy | |
| WEIGMANN Herman | Experimental and Evaluated Subthreshold Fission (with O. Bouland) |
Participants
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