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3. Reactivity monitoring using the area method for the subcritic al VENUS-F core within the framework of the FREYA Project

Author

Marie, N., Lehaut, G., Lecouey, J. L., Billebaud, A., Chabod, S., Doligez, X., Lecolley, F. R., Kochetkov, A., Uyttenhove, W., Vittiglio, G., Wagemans, J., Mellier, F., Ban, G., Thyébault, H. E., and Villamarin, D.

Subjects
Physics - Instrumentation and Detectors, Nuclear Experiment
Abstract

Accelerator-Driven Systems (ADS) could be employed to incinerate minor actinides and so partly contribute to answer the problem of nuclear waste management. An ADS consists of the coupling of a subcritical fast reactor to a particle accelerator via a heavy material spallation target. The on-line reactivity monitoring of such an ADS is a serious issue regarding its safety. In order to study the methodology of this monitoring, zero-power experimentswere undertaken at the GUINEVERE facility within the framework of the FP6-IP-EUROTRANS programme. Such experiments have been under completion within the FREYA FP7 project. The GUINEVERE facility is hosted at the SCK-CEN site in Mol (Belgium). It couples the VENUS-F subcritical fast core with the GENEPI-3C accelerator. The latter delivers a beam of deuterons, which are converted into 14-MeV neutrons via fusion reactions on a tritiated target. This paper presents one of the investigated methods for ADS on-line reactivity monitoring which has to be validated in the program of the FREYA project. It describes the results obtained when Pulsed Neutron Source experiments are analysed using the so called Area Method, in order to estimate the reactivity of a few sub-critical configurations of the VENUS-F reactor, around keff= 0.96. First the GUINEVERE facility is described. Then, following general considerations on the Area method, the results of its application to the neutron population time decrease spectra measured after a pulse by several fission chambers spread out over the whole reactor are discussed. Finally the reactivity values extracted are compared to the static reactivity values obtained using the Modified Source Multiplication (MSM) method., Comment: International Workshop on Technology and Components of Accelerator Driven Systems (TCADS) OECD Nuclear Energy Agency, Nantes : France (2013)

Published
2013

6. Axial Power Distribution Using Improved Axial Reflector Constants Calculation.

Author

Rispo, A., Doligez, X., Ravaux, S., and Trakas, C.

Abstract

AbstractMost of the neutronic core calculation schemes used by industrialists for nuclear reactor studies are based on a two-step deterministic scheme: A two-dimensional transport calculation at the assembly level produces homogenized and condensed nuclear data used by a full three-dimensional core solver under the diffusion approximation. The validity domain of such schemes is driven by the hypotheses of the diffusion approximation, implying wide meshes (10 to 20 cm), and is hence limited to studies that do not require a thinner description of neutron behavior. Consequently, local phenomena and heterogeneous interfaces are not yet fully validated with industrial two-level calculation schemes. For instance, the axial core-reflector interface, which is characterized by extra thermalization of neutrons leading to a local (≈2-cm height) increase of the neutron flux at the axial edges of fuel pins, is specifically challenging for deterministic methods. To cope with this issue, specific safety studies are performed with reference Monte Carlo simulations. This paper shows that enhancing the equivalence method enables flux discrepancies to be reduced from 12% to 6% for mixed oxide fuels and from 9.3% to <1% for uranium oxide fuel (impacting the power discrepancy from 5% to 3% and from 0.3% to almost 0.0%, respectively) between Monte Carlo and deterministic simulations (SCIENCE V2). The improved equivalence method uses dedicated discontinuity factors and constants, according to an optimized mesh composed by a mesh for each medium and a refined mesh in the fuel region. [ABSTRACT FROM AUTHOR]

Published
2024
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8. EXTENDED MSM METHOD TO ESTIMATE THE REACTIVITY OF A SUB-CRITICAL CORE DRIVEN BY AN ACCELERATOR BASED NEUTRON SOURCE

Author

Billebaud A., Lecouey J.-L., Chevret T., Chabod S., Doligez X., Kochetkov A., Krása A., Lecolley F.-R., Lehaut G., Marie N., Messaoudi N., Uyttenhove W., Vittiglio G., Wagemans J., Bécares V., Villamarin D., and Mellier F.

Subjects
ads, accelerator based neutron source, msm method, reactivity monitoring, Physics, QC1-999
Abstract

The Modified Source Multiplication method is used to determine an unknown reactivity level of a reactor from a known one if one has access to the detector counting for both levels when the reactor is fed by a constant neutron source like an Am-Be source. When available, an accelerator driven source, in continuous mode, can be useful as its intensity can be tunable and then adapted to the experimental conditions. However, in that case, the MSM technique must be extended to account for an external source whose intensity, energy and angular distributions can vary from one measurement to another. In this paper, this Modified Multi-Source Multiplication (MMSM) method is applied to measurements done during the FREYA project in the GUINEVERE facility, operated with the GENEPI-3C accelerator providing a mixture of (D,T) and (D,D) neutrons. The monitoring of these sources through the detection of the associated charged particles allows the calculation of the MMSM factors and the estimate of the reactivity values. The results are compared in different configurations with the reactivity obtained with an Am-Be source or in dynamic measurements performed with GENEPI-3C. Their excellent agreement shows the possibility of using such accelerator-based neutron sources for MSM measurements when they are correctly monitored. This is of great interest for deep sub-critical level characterization for which detector count rates per source neutrons might be low.

Published
2021
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14. Study of Argentinian and Brasilian Nuclear Symbiotic Scenarios using CLASS

Author

Alderete Tommasi, F.M., Bidaud, A., Mouginot, B., Leniau, B., Thiollière, Nicolas, Doligez, X., Courtin, F., Sormani, A., Clavel, J.B., Issoufou, Z., David, S., Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS)-Université Grenoble Alpes [2016-2019] (UGA [2016-2019]), Laboratoire SUBATECH Nantes (SUBATECH), Mines Nantes (Mines Nantes)-Université de Nantes (UN)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), Institut de Physique Nucléaire d'Orsay (IPNO), and Université Paris-Sud - Paris 11 (UP11)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS)

Subjects
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

International audience; The aim of this paper is to analyze and comparenuclear scenarios including the Argentinian and theBrazilian nuclear fleets working either in a collaborativescenario or separately.Brazilian nuclear fleet is composed of PWRs (PressurizedWater Reactors). Fordecades,ArgentinahasbeenoperatingPressurizedHeavyWaterReactors(PHWR),inparticularaCanadianDeuteriumUranium(CANDU)typereactor.Thankstotheirveryefficientneutroneconomy,thosereactorsareknowntobeabletoacceptlargespectrumoffueltypes.TheycanbecriticalwhenfueledbyDUPIC(DirectUseofPWRfuelinCANDU),orwithreprocessedfuelfromirradiatedenricheduranium.Theycouldbeevenalmostbreedersifusedwiththorium-­‐basedfuels.Inthispaper,wepresenthowthespecificreactorphysicsofCANDUhavebeenimplementedinthescenariocodeCLASS(CoreLibraryforAdvancedScenarioSimulation).ThenwediscusstheadvantagesofacollaborativescenariobetweenArgentinaandBrazil.

Published
2016

15. The Impact of Reactor Model Simplification for Fuel Evolution: A Bias Quantification for Fuel Cycle Dynamic Simulations

Author

Somaini, A., David, S., Doligez, X., Zakari-Issoufou, A.A., Bidaud, A., Cappelan, N., Meplan, O., Nuttin, A., Prevot, P., Courtin, F., Leniau, B., Mouginot, B., Thiollière, Nicolas, Institut de Physique Nucléaire d'Orsay (IPNO), Université Paris-Sud - Paris 11 (UP11)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS)-Université Grenoble Alpes [2016-2019] (UGA [2016-2019]), Laboratoire SUBATECH Nantes (SUBATECH), and Mines Nantes (Mines Nantes)-Université de Nantes (UN)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS)

Subjects
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

International audience; In nuclear scenario studies, the use of simplified assembly models to simulate fuel irradiation in nuclear reactor core can lead to important biases. To calculate the spent fuel composition, the CLASS package (Core Library for Advanced Scenario Simulations) uses a physic model (usually, we define physics model as: 1- Fuel Loading Model, 2- Cross Section Predictor, 3- Bateman Solver), based on a large number of different fuel evolution simulations. For that, a simple and reproducible model has been chosen: the “assembly model” that is described in this paper. In this model, the whole core is represented by a single assembly, or a part of it, with reflecting boundary conditions.As a first step to quantify the errors related to this approximation, three real size assembly configurations have been simulated: a reflected one, an axial open one and a realistic one (with moderator and reflector at its top and bottom). An exhaustive comparison is presented in this paper. Hence this work focuses on the neutron axial leakage impact on burn-up and isotope inventories calculations.Evolutions up to 50 GWd/t have been simulated with the depletion code MURE for all the geometries and main isotope inventories, fission and capture cross sections and Keff have been reported for each time step. Axial leakage effects on neutron spectrum and inventory distributions have been observed. In this paper, a bias quantification of axial leakage and a comparison with homogeneous leakage models, available in the Serpent code, are analyzed.

Published
2016

16. Validation of the Nodal Drift Method on a CANDU LOCA and First Application to the TWIGL Seed-Blanket REA

Author

Nuttin, A., Prévot, P., Capellan, N., David, S., Doligez, X., Méplan, O., Vernay, Emmanuelle, Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Université Grenoble Alpes [2016-2019] (UGA [2016-2019])-Centre National de la Recherche Scientifique (CNRS), Institut de Physique Nucléaire d'Orsay (IPNO), and Université Paris-Sud - Paris 11 (UP11)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS)

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

International audience; The Nodal Drift Method (NDM) has been developed for a broad and coarse safety review ofpromising thorium-fueled High Conversion Water Reactor (HCWR) options. Conceived as a missing linkbetween too approximate point kinetics and too sophisticated industrial codes, NDM is based on 2-groupdiffusion theory and a lumped parameter model with maximized mesh size. It has been validated on aCANDU LOCA (Loss Of Coolant Accident) benchmark, without any need for thermal calculations. Withsame principle of pre-tabulated cross sections and as a first application to PWR-like REA (Rod EjectionAccident), the well-known TWIGL benchmark of a ramp transient within a heterogeneous core has beencalculated. From its good results have been deduced a few perspectives towards future HCWR studies.

Published
2016

17. MgO effect on an ADS neutronic parameters

Author

Thiollière, Nicolas, Courtin, F., Leniau, B., Mouginot, B., Doligez, X., Bidaud, A., Laboratoire SUBATECH Nantes (SUBATECH), Mines Nantes (Mines Nantes)-Université de Nantes (UN)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), Institut de Physique Nucléaire d'Orsay (IPNO), Université Paris-Sud - Paris 11 (UP11)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS), and Vernay, Emmanuelle

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

ISBN 978-1-49-51-6286-2; International audience; Accelerator Driven Systems (ADS) are specifically studied for their capacity intransmuting Minor Actinides (MA). Electronuclear scenarios involving MA transmutation in ADSare widely researched. The dynamic fuel cycle simulation code CLASS (Core Library forAdvanced Scenarios Simulations) is used for predicting the inventory evolution induced by acomplex nuclear fleet. For managing reactors, the code CLASS is based on physic models. A FuelLoading Model (FLM) provides the fuel composition at Beginning Of Cycle (BOC) according tothe storages composition and the reactor requirements. A Cross Section Predictor (CSP) estimatesmean cross sections needed for solving evolution equations. Physic models are built from reactorscalculation set ahead of the scenario calculation. An ADS standard composition at BOC is amixture of plutonium and MA oxide. The high number of fissile isotopes present in the sub-criticalcore leads to an issue for building an ADS FLM. A high number of isotopic vectors at BOC isneeded to get an exhaustive simulation set. Also, ADS initial reactivity is adjusted with an inertmatrix that induces an additional degree of freedom. The building of an ADS FLM for CLASSrequires two steps. For any heavy nuclide composition at beginning of cycle, the core reactivitymust be imposed at a sub-critical level. Also, the reactivity coefficient evolution should bemaintained during the irradiation. For building a FLM, a simulation set has been built. Reactorsimulations are done with the transport code MCNP6 (Monte Carlo N particle transport code).The ADS geometry is based on the EFIT (European Facility for Industrial-Scale Transmutation)concept. The simulation set is composed of more than 8000 randomized. A complete neutronicstudy is presented that highlight the effect on MgO on neutronic parameters.

Published
2015

18. Mean cross section prediction in PWR-MOX using neural network

Author

Leniau, B., Mouginot, B., Thiollière, Nicolas, Doligez, X., Bidaud, A., Courtin, F., Ernoult, M., Laboratoire SUBATECH Nantes (SUBATECH), Mines Nantes (Mines Nantes)-Université de Nantes (UN)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), Institut de Physique Nucléaire d'Orsay (IPNO), Université Paris-Sud - Paris 11 (UP11)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), Laboratoire de Physique Subatomique et de Cosmologie (LPSC), and Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS)

Subjects
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

ISBN 978-1-49-51-6286-2; International audience; Fuel depletion calculation codes require one-group mean cross sections of manynuclides to solve Bateman's equations. In such codes, the mean cross sections are assed by themean of iterative calls of Boltzmann equation solver thanks to neutron transport codes. This is atime consuming task, especially with Monte Carlo codes such as MCNP. This paper presents amethodology based on neural network for building a cross section predictor for a PWR reactorloaded with any MOX fuel. This approach allows performing fuel depletion calculation in lessthan one minute with an excellent accuracy. A maximum deviation of 3% on actinides is obtainedat the end of cycle between inventories calculated from neural networks and from the referencecoupled neutron transport / fuel depletion calculation.

Published
2015

20. Core library for advanced scenario simulation, C.L.A.S.S.: principle & application

Author

Mouginot, B., Leniau, B., Thiollière, Nicolas, Ernoult, M., David, S., Doligez, X., Bidaud, A., Meplan, O., Montesanto, R., Bellot, G., Clavel, J.B., Duhamel, I., Letang, E., Miss, J., Laboratoire SUBATECH Nantes (SUBATECH), Mines Nantes (Mines Nantes)-Université de Nantes (UN)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), Institut de Physique Nucléaire d'Orsay (IPNO), Université Paris-Sud - Paris 11 (UP11)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS), and Institut de Radioprotection et de Sûreté Nucléaire (IRSN)

Subjects
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

International audience; The global warming, the increase of world population and the depletion of fossil resourceshave lead us in a major energy crisis. Using electronuclear energy could be one of the meansto solve a part of these issues. The way out of this crisis may be enlightened by the study oftransitional scenarios, guiding the political decisions. The reliability of those studies passesthrough the wide variety of the simulation tools and the comparison between them.From this perspective and in order to perform complex electronuclear scenario simulation,the open source Core Library for Advance Scenario Simulation (CLASS) is being developed.CLASS main asset is its ability to include any kind of reactor, whether the system is innovativeor standard. A reactor is fully described by its evolution database that must contain a set ofdifferent fuel compositions in order to simulate transitional scenarios. CLASS aims at being auseful tool to study scenarios involving Generation IV reactors as well as innovative fuel cycles,like the Thorium cycle.The following contribution will present in detail the CLASS software. Starting with the workingprinciple of this tool, one will explain the working process of the different modules suchas the evolution module. It will be followed by an exhaustive presentation of the UOX-MOXbases generation procedure. Finally a brief analysis of the error made by the CLASS evolutionmodule will be presented.

Published
2014

21. An Alternative Source Jerk Method Implementation for the Subcriticality Estimation of the VENUS-F Subcritical Core in the FREYA Project

Author

Kochetkov, A., Baeten, P., Uyttenhove, W., Vittiglio, G., Wagemans, J., Billebaud, A., Chabod, S., Lecouey, J. L., Ban, G., Lecolley, F. R., Nathalie Marie, Lehaut, G., Doligez, X., Mellier, F., Centre d'Etude de l'Energie Nucléaire (SCK-CEN), Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Joseph Fourier - Grenoble 1 (UJF)-Centre National de la Recherche Scientifique (CNRS), Laboratoire de physique corpusculaire de Caen (LPCC), Université de Caen Normandie (UNICAEN), Normandie Université (NU)-Normandie Université (NU)-École Nationale Supérieure d'Ingénieurs de Caen (ENSICAEN), Normandie Université (NU)-Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3), Institut de Physique Nucléaire d'Orsay (IPNO), and Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Paris-Sud - Paris 11 (UP11)

Subjects
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

International audience; As a prolongation of the FP-6 GUINEVERE (Generation of Uninterrupted Intense NEutron pulses at the lead VEnus REactor)project at the VENUS-F facility at SCK• CEN, the FP-7 FREYA (Fast Reactor Experiments for hYbrid Applications) project was launched in2011. The FREYA project aims at validating the methodology for subcriticality monitoring of a subcritical core as proposed in the MUSEexperiments conclusions. This is needed for the reactivity monitoring of a powerful ADS (Accelerator Driven System) like MYRRHA.Experiments are also needed for sub-critical and critical ADS and LFR (Lead Fast Reactor) core characterisation for benchmarking andlicensing purposes. Several levels of sub-criticality of the first subcritical core were measured applying the integral Source Jerk methodand compared to the reference results obtained with the MSM (Modified Source Multiplication) method.

Published
2014

22. Effect of heterogeneity in plutonium recycling in steady state PWR

Author

Ernoult, M., David, S., Doligez, X., Nuttin, A., Capellan, N., Meplan, O., Leniau, B., Institut de Physique Nucléaire d'Orsay (IPNO), Université Paris-Sud - Paris 11 (UP11)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS), Laboratoire SUBATECH Nantes (SUBATECH), Mines Nantes (Mines Nantes)-Université de Nantes (UN)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), and Vernay, Emmanuelle

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

International audience; The possible delay of decades for the deployment of fourth generation reactors brings upnew issues. Countries like France which are storing Plutonium for years in prediction ofstarting FBR could have to adapt their plutonium management strategy.We have compared different strategies for plutonium recycling in PWR reactors. We havechosen to limit the scope of this study to PWRs considering the standard uranium cycle,and we investigated the influence of the heterogeneity in the assembly that would containthe recycled plutonium. The comparison of different strategies is made at steady-state.This paper present a specific method developed to allow complete and detailed studiesof equilibrium scenarios and how it has been implemented and integrated inside the opensourceMURE package.We will then discuss of the results obtained through this method apply to PWRs loadedwith homogeneous and heterogeneous assemblies using the following criteria: resourceconsumption, Pu inventories in the cycle and waste production

Published
2014

23. Current progress and future plans of the FREYA Project

Author

Kochetkov, A., Baeten, P., Billebaud, A., Chabod, S., Doligez, X., Lecolley, F. R., Lecouey, J. L., Lehaut, G., Nathalie Marie, Mellier, F., Thyébault, H. E., Uyttenhove, W., Vittiglio, G., Wagemans, J., Ban, G., Dessagne, P., Kerveno, M., Mercatali, L., Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Joseph Fourier - Grenoble 1 (UJF)-Centre National de la Recherche Scientifique (CNRS), Institut de Physique Nucléaire d'Orsay (IPNO), Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Paris-Sud - Paris 11 (UP11), Laboratoire de physique corpusculaire de Caen (LPCC), Université de Caen Normandie (UNICAEN), Normandie Université (NU)-Normandie Université (NU)-École Nationale Supérieure d'Ingénieurs de Caen (ENSICAEN), Normandie Université (NU)-Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3), Institut Pluridisciplinaire Hubert Curien (IPHC), Université de Strasbourg (UNISTRA)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), and Guesnon, Sandrine

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

International audience; Reactor physics experiments are required for the design of a Fast Spectrum TransmutationExperimental Facility MYRRHA/FASTEF working in subcritical mode and in critical mode.Reactor physics experiments aim to validate a methodology for on-line subcriticalitymonitoring. For this purpose, building on the former activities accomplished in the previousFP6 project GUINEVERE, investigations on the subcritical VENUS-F (lead/uranium) corescoupled with the GENEPI-3C accelerator will be extended. This activity has been planned inwithin the framework of the on-going FREYA (Fast Reactor Experiments for hYbridApplications) FP7 project. This paper presents the current progress of the project and thefuture plans.

Published
2013

24. Reactivity monitoring using the area method for the subcritical VENUS-F core within the framework of the FREYA Project

Author

Nathalie Marie, Lehaut, G., Lecouey, J. L., Billebaud, A., Chabod, S., Doligez, X., Lecolley, F. R., Kochetkov, A., Uyttenhove, W., Vittiglio, G., Wagemans, J., Mellier, F., Ban, G., Thyébault, H. E., Villamarin, D., Laboratoire de physique corpusculaire de Caen (LPCC), Université de Caen Normandie (UNICAEN), Normandie Université (NU)-Normandie Université (NU)-École Nationale Supérieure d'Ingénieurs de Caen (ENSICAEN), Normandie Université (NU)-Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3), Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Joseph Fourier - Grenoble 1 (UJF)-Centre National de la Recherche Scientifique (CNRS), Institut de Physique Nucléaire d'Orsay (IPNO), and Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Paris-Sud - Paris 11 (UP11)

Subjects
Physics - Instrumentation and Detectors, FOS: Physical sciences, Instrumentation and Detectors (physics.ins-det), Nuclear Experiment (nucl-ex), [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], Nuclear Experiment
Abstract

Accelerator-Driven Systems (ADS) could be employed to incinerate minor actinides and so partly contribute to answer the problem of nuclear waste management. An ADS consists of the coupling of a subcritical fast reactor to a particle accelerator via a heavy material spallation target. The on-line reactivity monitoring of such an ADS is a serious issue regarding its safety. In order to study the methodology of this monitoring, zero-power experimentswere undertaken at the GUINEVERE facility within the framework of the FP6-IP-EUROTRANS programme. Such experiments have been under completion within the FREYA FP7 project. The GUINEVERE facility is hosted at the SCK-CEN site in Mol (Belgium). It couples the VENUS-F subcritical fast core with the GENEPI-3C accelerator. The latter delivers a beam of deuterons, which are converted into 14-MeV neutrons via fusion reactions on a tritiated target. This paper presents one of the investigated methods for ADS on-line reactivity monitoring which has to be validated in the program of the FREYA project. It describes the results obtained when Pulsed Neutron Source experiments are analysed using the so called Area Method, in order to estimate the reactivity of a few sub-critical configurations of the VENUS-F reactor, around keff= 0.96. First the GUINEVERE facility is described. Then, following general considerations on the Area method, the results of its application to the neutron population time decrease spectra measured after a pulse by several fission chambers spread out over the whole reactor are discussed. Finally the reactivity values extracted are compared to the static reactivity values obtained using the Modified Source Multiplication (MSM) method., Comment: International Workshop on Technology and Components of Accelerator Driven Systems (TCADS) OECD Nuclear Energy Agency, Nantes : France (2013)

Published
2013

25. Analysis of prompt decay experiments for ADS reactivity monitoring at VENUS-F GUINEVERE facility

Author

Chabod, S., Doligez, X., Lehaut, G., Billebaud, A., Lecouey, J. L., Lecolley, F. R., Nathalie Marie, Kochetkov, A., Uyttenhove, W., Vittiglio, G., Wagemans, J., Mellier, F., Ban, G., Thyébault, H. E., Villamarin, D., Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Joseph Fourier - Grenoble 1 (UJF)-Centre National de la Recherche Scientifique (CNRS), Institut de Physique Nucléaire d'Orsay (IPNO), Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Paris-Sud - Paris 11 (UP11), Laboratoire de physique corpusculaire de Caen (LPCC), Université de Caen Normandie (UNICAEN), Normandie Université (NU)-Normandie Université (NU)-École Nationale Supérieure d'Ingénieurs de Caen (ENSICAEN), and Normandie Université (NU)-Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)

Subjects
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], ComputingMilieux_MISCELLANEOUS
Abstract

International audience

Published
2013

26. An alternative source Jerk method implementation for the subcriticality estimation of the Venus-F subcritical core in the FREYA project

Author

Kochetkov, A., Ban, G., Baeten, P., Billebaud, A., Chabod, S., Doligez, X., Lecolley, F. R., Lecouey, J. L., Lehaut, G., Nathalie Marie, Mellier, F., Thyébault, H. E., Uyttenhove, W., Vittiglio, G., Wagemans, J., Laboratoire de physique corpusculaire de Caen (LPCC), Université de Caen Normandie (UNICAEN), Normandie Université (NU)-Normandie Université (NU)-École Nationale Supérieure d'Ingénieurs de Caen (ENSICAEN), Normandie Université (NU)-Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3), Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Joseph Fourier - Grenoble 1 (UJF)-Centre National de la Recherche Scientifique (CNRS), and Guesnon, Sandrine

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Published
2013

27. Measurements of the Mass and Isotopic Yields of the 233U(nth,f) Reaction at the Lohengrin Spectrometer

Author

Sage, C., Martin, F., Kessedjian, G., Bidaud, A., Billebaud, A., Capellan, N., Chabod, S., Méplan, O., O. Bacri, C., Doligez, X., Cywinski, R., Faust, H., Köster, U., Letourneau, A., Materna, T., Panebianco, S., Mathieu, L., Serot, Olivier, Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS), Institut de Physique Nucléaire d'Orsay (IPNO), Université Paris-Sud - Paris 11 (UP11)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), Aval du cycle et Energie Nucléaire (ACEN), Centre d'Etudes Nucléaires de Bordeaux Gradignan (CENBG), Université Sciences et Technologies - Bordeaux 1-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS)-Université Sciences et Technologies - Bordeaux 1-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), Institut Laue-Langevin (ILL), ILL, and Vernay, Emmanuelle

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], ComputingMilieux_MISCELLANEOUS
Abstract

International audience

Published
2011

28. 233U fission yields measurements in the heavy mass region

Author

Sage, C., Martin, F., Kessedjian, G., Billebaud, A., Chabod, S., Doligez, X., Méplan, O., Faust, H., Köester, U., Serot, Olivier, Letourneau, A., Panebianco, S., Materna, T., Mathieu, L., Cywinski, R., Bacri, C.O., Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS), Institut de Physique Nucléaire d'Orsay (IPNO), Université Paris-Sud - Paris 11 (UP11)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), Institut Laue-Langevin (ILL), Département de Physique Nucléaire (ex SPhN) (DPHN), Institut de Recherches sur les lois Fondamentales de l'Univers (IRFU), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay, Centre d'Etudes Nucléaires de Bordeaux Gradignan (CENBG), Université Sciences et Technologies - Bordeaux 1 (UB)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), Vernay, Emmanuelle, Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Joseph Fourier - Grenoble 1 (UJF)-Centre National de la Recherche Scientifique (CNRS), Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Paris-Sud - Paris 11 (UP11), ILL, and Université Sciences et Technologies - Bordeaux 1-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS)

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Published
2011

29. Thorium Molten Salt Fast Reactor Nuclear Data Uncertainty Analysis

Author

Bidaud, A., Hoogmoed, M., Doligez, X., Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS), and Vernay, Emmanuelle

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], ComputingMilieux_MISCELLANEOUS
Abstract

International audience

Published
2010

30. Effective delayed neutron fraction measurement in the critical VENUS-F reactor using noise techniques

Author

Doligez, X., primary, Billebaud, A., additional, Chabod, S., additional, Chevret, T., additional, Fourmentel, D., additional, Krasa, A., additional, Kochetkov, A., additional, Lecolley, F. R., additional, Lecouey, J. L., additional, Lehaut, G., additional, Marie, N., additional, Mellier, F., additional, Vittiglio, G., additional, and Wagemans, J., additional

Published
2015
Full Text
View/download PDF

31. Numerical tools for molten salt reactors simulation

Author

Doligez, X., Heuer, D., Merle-Lucotte, E., Ghetta, V., Allibert, M., Vernay, Emmanuelle, Laboratoire de Physique Subatomique et de Cosmologie (LPSC), and Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS)

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

paper 9207; International audience; Essentially, because the salt is the moderator, the coolant and the fuel, the study of Molten Salt Reactor are specific. There are strong coupling between neutronics, and other part of physic field like the chemistry for instance. The system presented in this paper is called Molten Salt Fast Reactor which is a molten salt reactor with no moderator inside the core with a salt composition which leads to a fast neutron spectrum. Previous studies showed that this concept (previously called Thorium Molten Salt Reactor – Non moderated) has very promising characteristics. We tried to explain computational problems due to the study of this concept, especially the coupling with the reprocessing and with the chemistry. Indeed, the reprocessing is done little by little in situ, so we have to consider it in our studies. We also show that the redox properties changes during operation because fissions change the salt chemistry (it is a reductive process). Our program is a coupling between MCNP and a home made evolution code called REM. It was validated for thermal neutron and epithermal neutron spectrum but not for fast neutron spectrum, so a brief study with ERANOS of the MSFR is also presented here.

Published
2009

32. Optimizing the burning efficiency and the deployment capacities of the molten salt fast reactor

Author

Merle-Lucotte, E., Heuer, D., Allibert, M., Doligez, X., Ghetta, V., Vernay, Emmanuelle, Laboratoire de Physique Subatomique et de Cosmologie (LPSC), and Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS)

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

paper 9149; International audience; Molten salt reactors in the present configuration, called Molten Salt Fast Reactors (MSFR), have been selected for further studies by the Generation IV International Forum. These reactors, characterized by a fast neutron spectrum, may be operated in simplified and safe conditions in the Th/233U fuel cycle with fluoride salts. Since 233U does not exist on earth and is not being directly produced today, we investigated the possibility of using, in this MSFR concept, the transuranic elements (TRU) currently produced in the world as an initial fissile load. We present here the concept, before focusing on a possible optimization in terms of minimization of the initial fissile inventory and improvement of the burning efficiency. Our studies demonstrate that an initial fissile inventory around 4 to 5 metric tons per GWe may be easily reached with a burning rate after 50 years of operation ranging from 87% to 93%. These studies also bring to light the limitations of the concept due to the irradiation damages to the structural materials. We conclude that this issue will have to be studied in depth to allow a realistic evaluation of the global possibilities of such a reactor.

Published
2009

33. Influence de l'unité de retraitement sur le comportement d'un TMSR

Author

Doligez, X., Heuer, D., Merle-Lucotte, E., Vernay, Emmanuelle, Laboratoire de Physique Subatomique et de Cosmologie (LPSC), and Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS)

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Published
2009

34. Le réacteur à sels fondus MSFR

Author

Heuer, D., Merle-Lucotte, E., Doligez, X., Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS), V. Ghetta, J. Fouletier, P. Taxil, Vernay, Emmanuelle, and V. Ghetta, J. Fouletier, P. Taxil

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Published
2009

35. Thorium Molten Salt Reactor reprocessing unit: characterization and influence on the core behaviour

Author

Doligez, X., Heuer, D., Merle-Lucotte, E., Ghetta, V., Allibert, M., Delpech, S., Picard, G., Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Joseph Fourier - Grenoble 1 (UJF)-Centre National de la Recherche Scientifique (CNRS), Laboratoire d'Electrochimie et de Chimie Analytique (LECA), Université Pierre et Marie Curie - Paris 6 (UPMC)-Ecole Nationale Supérieure de Chimie de Paris - Chimie ParisTech-PSL (ENSCP), Université Paris sciences et lettres (PSL)-Université Paris sciences et lettres (PSL)-Centre National de la Recherche Scientifique (CNRS), Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS), and Vernay, Emmanuelle

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], ComputingMilieux_MISCELLANEOUS
Abstract

International audience

Published
2008

36. Optimization and simplification of the concept of non-moderated Thorium Molten Salt Reactor

Author

Elsa Merle, Heuer, D., Allibert, M., Doligez, X., Ghetta, V., Le Brun, C., Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS), and Vernay, Emmanuelle

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

The PHYSOR'08 Proceedings, providing all the 447 full papers presented, are available as a CD-ROM; International audience

Published
2008

37. Le réacteur à sels fondus MFSR

Author

Heuer, D., Merle-Lucotte, E., Doligez, X., Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS), V. Ghetta, J. Fouletier, P. Taxil, Vernay, Emmanuelle, and V. Ghetta, J. Fouletier, P. Taxil

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], ComputingMilieux_MISCELLANEOUS
Abstract

International audience

Published
2008

38. Etude par simulation numérique du retraitement des déchets du T.M.S.R. (Thorium Molten Salt Reactor)

Author

Doligez, X., Allibert, M., Ghetta, V., Heuer, D., Merle-Lucotte, E., bibliotheque, LPSC, Laboratoire de Physique Subatomique et de Cosmologie (LPSC), and Université Joseph Fourier - Grenoble 1 (UJF)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Centre National de la Recherche Scientifique (CNRS)

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], Molten salt reactors, TMSR, radiotoxicity, [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], reprocessing, thorium
Abstract

Les réacteurs à sels fondus semblent aujourd'hui présenter une alternative intéressante aux réacteurs de quatrième génération refroidis au sodium. En effet, les réacteurs à sels fondus ont beaucoup évolué depuis le M.S.B.R. (prototype américain de réacteur à sels fondus modéré au graphite et fonctionnant en spectre thermique). Le concept évolue aujourd'hui vers des réacteurs sans modérateur en coeur dont le spectre neutronique s'est considérablement durci par rapport au spectre thermique du M.S.B.R. Ces réacteurs possèdent une unité de retraitement couplée qui permet de purifier le sel et d'optimiser la gestion des déchets rejetés. On espère ainsi définir un retraitement efficace qui minimiserait la radiotoxicité de ce type de réacteur. Ce rapport explique comment on simule l'évolution des réacteurs à sels fondus et on calcule la radiotoxicité des déchets produits. Les résultats donnés ici ne sont qu'indicatifs et servent surtout à monter que les outils et méthodes développés pendant ce stage sont satisfaisants et permettront une étude beaucoup plus poussée lors de la thèse qui suit.

Published
2007

40. Measurements of the mass and isotopic yields of the 233U(nth, f) reaction at the Lohengrin spectrometer

Author

Martin, F., primary, Sage, C., additional, Kessedjian, G., additional, Bacri, C. O., additional, Bidaud, A., additional, Billebaud, A., additional, Capellan, N., additional, Chabod, S., additional, Cywinski, R., additional, Doligez, X., additional, Faust, H., additional, Koster, U., additional, Letourneau, A., additional, Materna, T., additional, Mathieu, L., additional, Meplan, O., additional, Panebianco, S., additional, and Serot, O., additional

Published
2011
Full Text
View/download PDF

43. Reactivity Measurement of the Lead Fast Subcritical VENUS-F Reactor Using Beam Interruption Experiments

Author

Chevret, T. M., Lecouey, J. L., Nathalie Marie, Lecolley, F. R., Lehaut, G., Ban, G., Billebaud, A., Chabod, S., Doligez, X., Kochetkov, X., Baeten, P., Uyttenhove, W., Vittiglio, G., Wagemans, J., Mellier, F., Bécares, V., Villamarin, D., Laboratoire de physique corpusculaire de Caen (LPCC), Université de Caen Normandie (UNICAEN), Normandie Université (NU)-Normandie Université (NU)-École Nationale Supérieure d'Ingénieurs de Caen (ENSICAEN), Normandie Université (NU)-Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3), Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Joseph Fourier - Grenoble 1 (UJF)-Centre National de la Recherche Scientifique (CNRS), Institut de Physique Nucléaire d'Orsay (IPNO), Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Paris-Sud - Paris 11 (UP11), and Centre d'Etude de l'Energie Nucléaire (SCK-CEN)

Subjects
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

International audience; In order to incinerate minor actinides and thus to reduce the issues linked to nuclear waste management, Accelerator-Driven Systems(ADS) are being under study. An ADS consists in the coupling of a particle accelerator with a sub-critical fast reactor. The on-line reactivitymonitoring is a serious issue regarding safety, therefore several methods to estimate the reactivity of such sub-critical systems have tobe investigated. Here, we present one method based on the study of the neutron population evolution during beam interruption experimentscarried out in the framework of the FREYA FP7 program [1,2] at the GUINEVERE facility, which couples the fast lead sub-critical reactorVENUS-F with the deuteron accelerator GENEPI-3C at SCK-CEN in Mol, Belgium. After describing the facility, the analysis based on pointkinetics theory and preliminary results of the reactivity measurements will be presented. Then, spatial effects that are not taken into accountby point kinetics theory will be highlighted using MCNP simulations, and correction factors to raw results will be calculated. In the end, finalresults will be compared to reference reactivity values obtained with the Modified Source Multiplication (MSM) method.

44. Reactivity Measurements at GUINEVERE Facility Using the Integral kp Method

Author

Chabod, S., Billebaud, A., Lecolley, F. R., Lecouey, J. L., Lehaut, G., Nathalie Marie, Ban, G., Doligez, X., Kochetkov, A., Baeten, P., Krása, A., Uyttenhove, W., Vittiglio, G., Wageman, J., Mellier, F., Villamarin, D., Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Joseph Fourier - Grenoble 1 (UJF)-Centre National de la Recherche Scientifique (CNRS), Laboratoire de physique corpusculaire de Caen (LPCC), Université de Caen Normandie (UNICAEN), Normandie Université (NU)-Normandie Université (NU)-École Nationale Supérieure d'Ingénieurs de Caen (ENSICAEN), Normandie Université (NU)-Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3), Institut de Physique Nucléaire d'Orsay (IPNO), Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Paris-Sud - Paris 11 (UP11), and Centre d'Etude de l'Energie Nucléaire (SCK-CEN)

Subjects
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

International audience; In the framework of the GUINEVERE (EUROTRANS-IP FP6) and FREYA (FP7) projects, a two-level procedure is developed to measurethe time variations of an ADS reactivity ρ(t). First, the time variations of the reactor power and neutron source intensity are monitored online,allowing to extract the fast fluctuations of ρ(t) around a reference value. Then, absolute measurements of ρ are periodically performed toreadjust the relative measurements. These calibration measurements require the analysis of the decay of the neutron population triggeredby programmed beam interruptions. In this paper, we describe an innovative method developed to measure the prompt multiplicationfactor, kp, of a subcritical reactor (and therefore its absolute ρ). Unlike conventional methods used for reactivity measurements, ourapproach only relies on the prompt decay of the neutron population, therefore enabling the use of shorter beam interruptions (< 50 μs) thanusual (~ 1 ms). After a review of the method’s mechanics, we apply it to measurements performed at the GUINEVERE facility, with theVENUS-F reactor, a zero power lead subcritical fast reactor. During these measurements, the neutron source was operated in pulsemode. Our results, promising, are compared with reference reactivity values provided by a MSM analysis.

47. Americium early transmutation in thermal reactors: An option to a better nuclear spent fuel management

Author

Zakari-Issoufou, A. -A, Doligez, X., Somaini, A., Ernoult, M., David, S., Bouneau, S., Courtin, F., Leniau, B., Thiolliére, N., Mouginot, B., Adrien Bidaud, Institut de Physique Nucléaire d'Orsay (IPNO), Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Paris-Sud - Paris 11 (UP11), Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS)-Université Grenoble Alpes [2016-2019] (UGA [2016-2019]), Laboratoire de physique subatomique et des technologies associées (SUBATECH), Université de Nantes - UFR des Sciences et des Techniques (UN UFR ST), Université de Nantes (UN)-Université de Nantes (UN)-Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-IMT Atlantique Bretagne-Pays de la Loire (IMT Atlantique), and Institut Mines-Télécom [Paris] (IMT)-Institut Mines-Télécom [Paris] (IMT)

Subjects
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

ISBN 978-4-89047-167-6; International audience

50. Study of Space-energy Effects in Subcritical Reactor within a Time-dependent Multi-group 1-Dimensional Diffusion Approach

Author

Lehaut, G., Lecouey, J. L., Nathalie Marie, Baeten, P., Ban, G., Bécares, V., Billebaud, A., Chabod, S., Chevret, T., Doligez, X., Kochetkov, A., Krasa, A., Lecolley, F. R., Mellier, F., Uyttenhove, W., Villamarin, D., Vittiglio, G., Wagemans, J., Guesnon, Sandrine, Laboratoire de physique corpusculaire de Caen (LPCC), Université de Caen Normandie (UNICAEN), Normandie Université (NU)-Normandie Université (NU)-École Nationale Supérieure d'Ingénieurs de Caen (ENSICAEN), Normandie Université (NU)-Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3), Centre d'Etude de l'Energie Nucléaire (SCK-CEN), Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP )-Institut Polytechnique de Grenoble - Grenoble Institute of Technology-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Joseph Fourier - Grenoble 1 (UJF)-Centre National de la Recherche Scientifique (CNRS), Institut de Physique Nucléaire d'Orsay (IPNO), and Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Paris-Sud - Paris 11 (UP11)

Subjects
[PHYS.NEXP] Physics [physics]/Nuclear Experiment [nucl-ex], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]
Abstract

International audience; The GUINEVERE facility hosted at the SCK·CEN site in Mol (Belgium) couples the fast subcriticallead reactor VENUS-F with an external neutron source provided by interactions of deuteronsdelivered by the GENEPI-3C accelerator and a tritiated target located at the reactor core center.Part of the experimental program is devoted to the study of subcriticality monitoring techniques.It includes the analysis of Pulsed Neutron Source experiments using the so-called Area Methodtechnique which is based on Reactor Point Kinetics. Experimental results show that the extractedreactivity depends on the detector position inside the reactor. A time-dependent multigroup diffusionapproach using a simplified description of the VENUS-F reactor is developed to computecorrection factors which should allow one to overcome the shortcomings of the Area Method technique.Preliminary results are very promising since the application of the correction factors leadsto an overall reduction in the spread of the area ratio reactivity measurements.KEYWORDS: ADS, area method, multigroup diffusion equation, modal expansion.

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