Belgonucleaire

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Title DOI
https://doi.org/10.1051/ndata:07607 Deformation dependent TUL multi-step direct model
https://doi.org/10.1051/ndata:07640 EMPIRE ultimate expansion: resonances and covariances
https://doi.org/10.1115/icem2001-1191 Source Term Assessment: The ARIANE Programme
https://doi.org/10.1115/icem2001-1194 Microstructure of Spent MOX Fuel Stored Under Dry Air for 25 Years
Critical experiments: Recent and future international programmes in VENUS
https://doi.org/10.1016/b978-0-444-89571-4.50007-4 MOX fuel development: yesterday, today and tomorrow
https://doi.org/10.13182/nt70-a28758 Breeding Ratio for Fast Reactors
https://doi.org/10.13182/nt79-a16178 Mechanical Behavior of Honeycomb Spot-Welded Spacer Grids Irradiated in Two Fuel Rod Bundles
Qualification of the Tihange-2 PWR power plant dried waste solidification system
https://doi.org/10.1161/01.cir.54.3.388 CONTRIBUTION TO THE THEORY OF EXPONENTIAL EXPERIMENTS WITH FAST NEUTRONS
https://doi.org/10.13182/nt79-a32372 Safety Aspects of Light Water Reactor Radwaste Solidification Processes
https://doi.org/10.13182/nt71-a31009 Safeguards Inspection—An Analysis of Detection Methods and Diversion Strategies
https://doi.org/10.1063/1.1292186 Capability of the MIMAS process to convert the stockpiles of separated plutonium into MOX fuel for use in LWRs
https://doi.org/10.1063/1.1292319 Qualification of the bubble detector as neutron dosemeter at the MOX plant of BELGONUCLEAIRE
https://doi.org/10.1063/1.1292320 Microscopic determination of the size distribution of PuO[sub 2]-rich zones and pores in MOX pellets with an image analysis system
https://doi.org/10.1016/j.healun.2006.12.007 IFPE/PRIMO-BD8, Belgonucleaire and SCK-CEN PRIMO Ramped MOX Fuel Rod BD8
https://doi.org/10.13182/nse88-a29043 Physics Methods for Calculating Light Water Reactor Increased Performances
https://doi.org/10.1007/978-3-642-75935-2_21 A Personal Computer Version of the MCDA Approach Strange
https://doi.org/10.1016/s0221-0363(06)87084-8 Methodes de preparation et de distension colique pour une coloscopie virtuelle
https://doi.org/10.1115/icem2013-96020 Decommissioning the Belgonucleaire Dessel MOX Plant: Presentation of the Project and Situation End August 2013
https://doi.org/10.1007/978-94-017-2288-9_18 Commercial MOX Fuel Fabrication and Irradiation Experience in Belgium
https://doi.org/10.1115/icem2007-7022 WDC: Advanced System for Characterization of Alpha-Bearing Waste Contained in 200L and 400L Drums: Performances and Lessons Learned From the First Industrial Measurement Campaigns
https://doi.org/10.1016/0022-3107(71)90067-0 “Safeguards”—Étude d'un modèle stochastique gaussien pour la détection d'un détournement de matière fissile
https://doi.org/10.1115/icone17-75782 Release of Materials During the Decommissioning of the Belgonucleaire Dessel MOX Fuel Fabrication Plant
https://doi.org/10.1016/s0221-0363(06)87087-3 Difficultes et pieges en coloscopie virtuelle
https://doi.org/10.1016/0022-3115(88)90204-8 Feed-back of quality control data evaluation to production experience of mixed uranium-plutonium dioxide fuels
https://doi.org/10.1051/kmae:1930013 Aménagement des étangs
https://doi.org/10.1109/tns.1979.4329827 An Electron Cyclotron Resonance Source for Cyclone
https://doi.org/10.1115/icem2007-7219 Alpha-Contaminated Solid Waste Sorting and Conditionining at Belgoprocess (Belgium): Lessons Learned From the First Three Years Operation
https://doi.org/10.1115/icem2013-96317 DASAO: Software Tool for the Management of Safeguards, Waste and Decommissioning
https://doi.org/10.1016/0022-3115(77)90048-4 The creep strain limit experiment
https://doi.org/10.1016/0004-6981(84)90286-5 4409137 Solidification of radioactive waste effluents
https://doi.org/10.1016/0951-8320(88)90112-3 Bayesian analysis of the extreme value of a time history
https://doi.org/10.1007/978-94-011-4501-5_10 Safety of the Belgonucleaire Mox Fabrication Plant
https://doi.org/10.3917/cges.035.0035 Le clair-obscur
https://doi.org/10.13182/nt71-a30918 Breeding Ratio For Fast Reactors
COMETHE II: A COMPUTER CODE FOR PREDICTING THE MECHANICAL AND THERMAL BEHAVIOR OF A FUEL PIN.
https://doi.org/10.1051/rgn/19752076 Première conférence nucléaire européenne
An injector cyclotron for CYCLONE
Sensitivity of LMFBR Containment Response to the Parameters of a HCDA Situation
https://doi.org/10.1115/icem2001-1201 MOX Application Routes
https://doi.org/10.1115/icem2001-1273 Disposing of Excess Weapons Materials: Past and Future of Belgian Plutonium Technology
https://doi.org/10.1115/icem2001-1210 Latest Developments About Spent Fuel Management in Belgium
https://doi.org/10.1115/icem2001-1057 Management of Alpha-Contaminated Solid Waste in Belgium
Economic Effect on the Plutonium Cycle of Employing 235 U in Fast Reactor Start-Up
Experience in the use of the nickel plating process as a preventive or a corrective measure
The decommissioning of large and complex glove box structures in a mixed oxide fuel fabrication plant
Intermediate- and high-level waste management at a spent-fuel reprocessing plant
The elastic model for arbitrary radially cracked fuel implemented in COMETHE-4D
Pu and MA management in thermal HTGRs - impact at fuel, reactor and fuel cycle levels - HTR2008-58176
Building a Wims validation database for the calculation of spent nuclear fuel inventory
Synthesis of the technical feasibility evaluation of spent fuel conditioning in Belgium
Calculation of the cost of Generating Power in a Fast Reactor by the Discounting Method
Mixed oxide thermal behaviour at BOL: COMETHE III-J models and impact on power-to-melt
Plutonium Assembly in the Core of the BR3/Vulcain Core
Determination of reactivity components of a power reactor by the means of interpretation of transients and stationary experiments
Validation of MOX fuel through recent BELGONUCLEAIRE international programmes
The VIPEX programme for neutron code validation for MOX fuel
The management of spent fuel and nuclear waste in Europe: Solutions exist, they must be implemented - 'Les Entretiens Europeens' 2018 - 'Les Cahiers des Entretiens Europeens', January 2019 + 'La Lettre des Entretiens Europeens', 'Nuclear Waste Management in Europe' Special, October 2018
EXPERIMENTAL INVESTIGATIONS OF THE INTERACTIONS BETWEEN (U,Pu)O/sub 2-x/ AND FUEL CAN OF AUSTENITIC STEEL.
https://doi.org/10.1007/978-94-011-5070-5_18 MOX Fabrication and Transportation Safety Issues in Belgium
https://doi.org/10.1016/b978-0-7204-0572-9.50029-0 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/10.1115/icem2011-59027 Decommissioning the BELGONUCLEAIRE Dessel MOX Plant: Presentation of the Project and Situation on 30/06/2011
https://doi.org/10.1016/b978-0-7204-0572-9.50018-6 THE CREEP STRAIN LIMIT EXPERIMENT
https://doi.org/10.1016/b978-0-7204-0572-9.50017-4 JOINT PROGRAMME OF UNI-AXIAL CREEP MEASUREMENTS OF HTR COMPACTS AND MATRIX MATERIAL UNDER TENSILE LOAD AT 900°C
Improvement of the intestinal microbiota of weaned piglets with innovative nutritional olutions
https://doi.org/10.1016/j.revmed.2024.10.441 Essai de phase III randomisé COMMODORE 2 : résultats d’une étude multicentrique évaluant crovalimab vs éculizumab chez des patients atteints d’hémoglobinurie paroxystique nocturne (HPN) naïfs de traitement par un inhibiteur du complément
https://doi.org/10.1093/femsle/fnaf012 About two French cases of disseminated Cryptococcus neoformans infection associated with COVID-19
https://doi.org/10.1680/frfc.01572.0014 13 Multivariant strategy study for the use of plutonium in a nuclear programme: the case of the large and small country
https://doi.org/10.13182/nse68-a18837 One-Velocity Calculations for the Analysis of Reactor Physics Experiments
https://doi.org/10.1111/ene.70565 Multiple Mononeuropathy Secondary to Parvovirus B19 Infection: A Case Series
Influence curves for calculation of the structural distortion effect on reactivity
Physics design of PWR reloads with a nodal code system
METHODS OF CALCULATION USED IN DESIGNING LARGE FAST-NEUTRON POWER REACTORS.