Publications in OpenAlex of which a co-author is affiliated to this organization
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| Title | DOI |
|---|---|
| https://doi.org/10.1016/j.nds.2007.11.003 | EMPIRE: Nuclear Reaction Model Code System for Data Evaluation |
| https://doi.org/10.1016/0022-3115(93)90193-3 | History of fast reactor fuel development |
| https://doi.org/10.1002/eqe.4290120405 | The generation of spectrum compatible accelerograms for the design of nuclear power plants |
| https://doi.org/10.1016/0029-5493(80)90205-8 | A method for the generation of artificial earthquake accelerograms |
| https://doi.org/10.1016/0022-3115(92)90448-t | MOX fuel development: yesterday, today and tomorrow |
| https://doi.org/10.1016/0377-2217(86)90160-8 | Strange: An interactive method for multi-objective linear programming under uncertainty |
| https://doi.org/10.1016/0377-2217(90)90308-x | Nuclear waste management: An application of the multicriteria PROMETHEE methods |
| https://doi.org/10.1016/0895-7177(89)90370-1 | An interactive decision support system (IDSS) for multicriteria decision aid |
| https://doi.org/10.13182/nt94-a34950 | Mixed-Oxide Fuel Fabrication Technology and Experience at the Belgonucléaire and CFCa Plants and Further Developments for the MELOX Plant |
| https://doi.org/10.1093/rpd/ncm190 | Summary of personal neutron dosemeter results obtained within the EVIDOS project |
| https://doi.org/10.13182/nt82-a32982 | On the Vibrational Behavior of Pressurized Water Reactor Fuel Rods |
| https://doi.org/10.1016/0022-460x(85)90339-6 | On the peak factor of stationary Gaussian processes |
| https://doi.org/10.1016/0029-5493(85)90045-7 | The generation of non-separable artificial earthquake accelerograms for the design of nuclear power plants |
| https://doi.org/10.1016/0377-2217(87)90028-2 | Nuclear fuel cycle optimization using multi-objective stochastic linear programming |
| https://doi.org/10.1002/eqe.4290100506 | Frequency domain analysis of time integration operators |
| https://doi.org/10.1016/0167-188x(85)90013-8 | Application of multi-objective stochastic linear programming to power systems planning |
| https://doi.org/10.13182/nse90-a23754 | Superphénix Reactivity and Feedback Coefficients |
| https://doi.org/10.13182/nse90-a23759 | An Analysis of the Dynamic Behavior of the Core |
| European fast reactor (EFR) fuel element design | |
| https://doi.org/10.13182/nt70-a28809 | Comethe II-A Computer Code for Predicting the Mechanical and Thermal Behavior of a Fuel Pin |
| https://doi.org/10.5194/angeo-23-2983-2005 | Pitch angle distribution of trapped energetic protons and helium isotope nuclei measured along the Resurs-01 No. 4 LEO satellite |
| https://doi.org/10.13182/nt77-a31831 | Results of the Postirradiation Examinations of the Rapsodie-I Experiment Fuel Pins |
| https://doi.org/10.13182/nt93-a34801 | In-Pile Performance of Mixed-Oxide Fuel with Particular Emphasis on MIMAS Fuel |
| https://doi.org/10.1007/978-94-009-2111-5_7 | Application of “Strange” to Energy Studies |
| https://doi.org/10.1103/physrevc.78.064611 | Deformation-dependent Tamura-Udagawa-Lenske multistep direct model |
| https://doi.org/10.13182/nse90-a23752 | Superphénix Core-Loading Strategy Using the Checkerboard Pattern |
| https://doi.org/10.1115/icone10-22022 | The REBUS Experimental Programme for Burn-Up Credit |
| https://doi.org/10.1016/0029-5493(90)90304-g | French LMFBR core thermo-hydraulic studies for nominal and accident conditions |
| https://doi.org/10.1016/0029-5493(81)90118-7 | A two-time step algorithm for seismic analysis of a PWR core |
| https://doi.org/10.1016/0011-2275(76)90055-2 | Theoretical investigations of hydrogen, nitrogen, and oxygen homogenous and annular wick heat pipes |
| https://doi.org/10.1007/978-3-662-02473-7_9 | Interactive Methods for Multi-Objective Integer Linear Programming |
| https://doi.org/10.13182/nt77-a31886 | Coated Nuclear Fuel Particles: The Coating Process and Its Model |
| https://doi.org/10.13182/nt78-a32076 | Liquid-Metal Fast Breeder Reactor Fuel Rod Performance and Modeling at High Burnup |
| https://doi.org/10.1007/978-3-642-46536-9_32 | Multi-Objective Decision Making under Uncertainty: An Example for Power System |
| https://doi.org/10.1524/ract.1978.25.34.149 | Chemical Aspects of Mixed Oxide Fuel Production |
| https://doi.org/10.13182/nt74-a15917 | Plutonium Coated Particles Development |
| https://doi.org/10.13182/nt04-a3564 | Plutonium Management in the Medium Term |
| https://doi.org/10.1016/0029-5493(82)90173-x | Seismic analysis of PWR-RCC fuel assemblies |
| https://doi.org/10.1016/0022-3115(93)90029-x | Radial plutonium and fission product isotope profiles in mixed oxide fuel pins evaluated by secondary ion mass spectrometry |
| https://doi.org/10.13182/nse70-a19992 | Minimum Critical Mass in Fast Reactors with Bounded Power Density |
| https://doi.org/10.1016/0022-3115(79)90561-0 | Potential causes of failures associated with power changes in LWR's |
| https://doi.org/10.1016/0032-5910(72)80021-4 | Deactivation, key step in UO2 and (U, Pu)O2 low-density pellet fabrication |
| https://doi.org/10.1016/0022-3115(91)90385-k | Foundations for the definition of MOX fuel quality requirements |
| https://doi.org/10.1016/0022-460x(89)90639-1 | Non-stationary random vibrations of linear multi-degree-of-freedom systems |
| https://doi.org/10.1016/0029-5493(80)90176-4 | Improvements to COMETHE III-J fuel rod modeling code |
| https://doi.org/10.1016/0029-5493(79)90085-2 | Modeling of the transient heat transfer in a nuclear reactor fuel rod using a variational procedure |
| https://doi.org/10.1016/0029-5493(87)90273-1 | The seismic analysis of a free standing FBR core a case study — SNR-2 preliminary design |
| https://doi.org/10.1016/0022-3115(70)90043-7 | Vibrocompaction electrodynamique de nodules frittes d'oxyde d'uranium |
| https://doi.org/10.1016/0022-3115(79)90063-1 | Safety aspects of micro-heterogeneities in LWR mixed oxide fuels |
| https://doi.org/10.1006/bbrc.2000.3259 | Cloning, Genomic Organization, and Tissue Distribution of Human Ssf-1 |
| https://doi.org/10.1016/b978-0-08-037938-8.50013-6 | AN INTERACTIVE DECISION SUPPORT SYSTEM (IDSS) FOR MULTICRITERIA DECISION AID |
| https://doi.org/10.13182/nt79-a32358 | Safety Aspects of Using Gadolinium as Burnable Poison in Pressurized Water Reactors |
| https://doi.org/10.1016/0149-1970(85)90009-5 | The present accuracy of physics characteristics of unirradiated fast reactor cores |
| https://doi.org/10.1016/0198-7593(84)90048-1 | Combined heat and power (CHP) vs separate heat and power (SHP) generation for primary energy conservation |
| https://doi.org/10.5194/angeo-25-2029-2007 | The measurements of light high-energy ions in NINA-2 experiment |
| BR3/VULCAIN NUCLEAR POWER STATION: CONSTRUCTION AND OPERATIONAL EXPERIENCE. | |
| https://doi.org/10.1016/0022-3115(77)90059-9 | Results of in-pile creep measurements on pressurized capsules made of stabilized stainless steels WNr. 1.4981, CW and WNr. 1.4970, CW, A |
| https://doi.org/10.1016/0029-5493(86)90098-1 | Fluid-coupling coefficients in an array of hexagonal prisms |
| https://doi.org/10.1016/0029-5493(77)90066-8 | Nuclear accident simulation in a 1/6 scale model of the SNR-300 fast breeder reactor |
| https://doi.org/10.1016/0377-2217(87)90027-0 | A heuristic algorithm for allocation of components in manufacturing processes |
| https://doi.org/10.1016/0029-5493(72)90036-2 | Cladding-strength analysis under the combined effect of creep and plasticity in fast-reactor environments |
| https://doi.org/10.1097/00004032-199908000-00011 | DETERMINATION OF NEUTRON SPECTRA IN A MOX PLANT FOR THE QUALIFICATION OF THE BD-PND BUBBLE DETECTOR |
| https://doi.org/10.1016/0029-5493(80)90200-9 | Fuel behavior aspects of the interpretation of the SCARABEE fast reactor safety experiments |
| https://doi.org/10.1007/978-3-642-83555-1_6 | An Interactive Dss for Multiobjective Investment Planning |
| https://doi.org/10.13182/nt81-a32623 | Fabrication of Plutonium-Enriched Fuel at Belgonucleaire |
| Study of nuclear accidents by chemical simulation experiments | |
| https://doi.org/10.13182/nt87-a15994 | Refueling System Fabrication and Testing |
| https://doi.org/10.1016/0029-5493(80)90178-8 | Benchmarking results of the COMETHE code |
| https://doi.org/10.1016/0029-5493(80)90170-3 | General description and organization of COMETHE III-J |
| https://doi.org/10.1093/rpd/ncm219 | The response of the BTI bubble detectors in mixed gamma-neutron workplace fields |
| https://doi.org/10.13182/nt70-a28728 | Crash-A Computer Program for the Evaluation of the Creep and Plastic Behavior of Fuel-Pin Sheaths |
| https://doi.org/10.13182/nt70-a28762 | Plutonium Recycle Studies for the Sena Pwr Reactor |
| https://doi.org/10.13182/nt87-a15993 | Fabrication of Fuel Elements Interplay between Typical SNR Mark la Specifications and the Fuel Element Fabrication |
| https://doi.org/10.13182/nt78-a32128 | Use of Zero Power Plutonium Reactor Measurements as a Support of Criticality Prediction for the SNR-300 |
| Comparative analysis of a hypothetical 0.1 $/SEC transient overpower accident in an irradiated LMFBR core using different computer models | |
| https://doi.org/10.13182/nse68-a19547 | On the Expansion of Experimental Functions in Series of Descending Exponentials of Real Argument |
| https://doi.org/10.13182/nse84-a17782 | Worths and Interactions of Simulated Fast Breeder Reactor Control Rods in ZEBRA and SNEAK Assemblies |
| https://doi.org/10.13182/nt77-a31776 | Plutonium Assemblies in Reload 1 of the Dodewaard Reactor |
| https://doi.org/10.1016/j.nucengdes.2004.08.061 | VALMOX: validation of nuclear data for high burn-up MOX fuels |
| https://doi.org/10.1016/0029-5493(80)90171-5 | Fuel behaviour models incorporated in COMETHE III-J |
| https://doi.org/10.1016/0022-3115(79)90074-6 | Sensitivity of fuel rod behaviour on as-fabricated characteristics |
| https://doi.org/10.1016/0022-3115(82)90330-0 | Performance-related characteristics of water reactor fuel |
| https://doi.org/10.13182/nt79-a32353 | Comparative Study of Heterogeneous and Homogeneous Liquid-Metal Fast Breeder Reactor Cores in Some Accident Conditions |
| Eddy current inspection methodology | |
| Implications of plutonium and americium recycling on MOX fuel fabrication | |
| Safety problems related to microheterogeneities in physically mixed oxide fuels | |
| https://doi.org/10.1115/icone12-49164 | The REBUS Experimental Programme for Burn-Up Credit |
| https://doi.org/10.13182/nt83-a33164 | Plutonium-Enriched Thermal Fuel Production Experience in Belgium |
| https://doi.org/10.13182/nse88-a23578 | Analysis of a Delayed Return to Full Power Using a Three-Dimensional Simulator |
| https://doi.org/10.1520/stp15156s | Two-Dimensional Neutron and Gamma Calculations for Devices Irradiated in BR2 Reflector Positions |
| https://doi.org/10.13182/nt89-a34310 | The Fast Breeder Reactor Fuel Cycle in Europe—Present Status and Prospects |
| https://doi.org/10.1115/1.3264412 | An Automatic Procedure for the Generation of Accelerograms Enveloping Several Design Response Spectra |
| https://doi.org/10.1016/0022-3115(82)90354-3 | Auswirkungen von brennstofftoleranzen auf die betriebsdaten eines schnellen reaktors |
| https://doi.org/10.1016/0029-5493(80)90190-9 | A COMETHE version with transient capability |
| https://doi.org/10.1016/0022-3115(82)90355-5 | Fuel characteristics required for LWR fuel rod calculations |
| https://doi.org/10.1016/0022-3115(79)90068-0 | Densifications of UO2 — PuO2 fuel |
| https://doi.org/10.1016/0022-3115(82)90342-7 | Gas chromatography in nuclear fuel rod fabrication |
| https://doi.org/10.2533/000942905777675471 | Fuel Production for LWRs – MOX Fuel Aspects |
| https://doi.org/10.1016/0022-3115(77)90047-2 | Joint programme of uni-axial creep measurements of htr compacts and matrix material under tensile load at 900°C |
| https://doi.org/10.1088/0305-4624/8/3/i04 | Gas-cooled fast breeder reactors |