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28 results on '"Leniau, B."'

1. Experimental level densities of atomic nuclei

Author

Guttormsen, M., Aiche, M., Garrote, F. L. Bello, Bernstein, L. A., Bleuel, D. L., Byun, Y., Ducasse, Q., Eriksen, T. K., Giacoppo, F., Görgen, A., Gunsing, F., Hagen, T. W., Jurado, B., Klintefjord, M., Larsen, A. C., Lebois, L., Leniau, B., Nyhus, H. T., Renstrøm, T., Rose, S. J., Sahin, E., Siem, S., Tornyi, T. G., Tveten, G. M., Voinov, A., Wiedeking, M., and Wilson, J.

Subjects
Nuclear Experiment
Abstract

It is almost 80 years since Hans Bethe described the level density as a non-interacting gas of protons and neutrons. In all these years, experimental data were interpreted within this picture of a fermionic gas. However, the renewed interest of measuring level density using various techniques calls for a revision of this description. In particular, the wealth of nuclear level densities measured with the Oslo method favors the constant-temperature level density over the Fermi-gas picture. From the basis of experimental data, we demonstrate that nuclei exhibit a constant-temperature level density behavior for all mass regions and at least up to the neutron threshold., Comment: 8 pages, 8 figures

Published
2015
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2. Scissors resonance in the quasi-continuum of Th, Pa and U isotopes

Author

Guttormsen, M., Bernstein, L. A., Görgen, A., Jurado, B., Siem, S., Aiche, M., Ducasse, Q., Giacoppo, F., Gunsing, F., Hagen, T. W., Larsen, A. C., Lebois, M., Leniau, B., Renstrøm, T., Rose, S. J., Tornyi, T. G., Tveten, G. M., Wiedeking, M., and Wilson, J. N.

Subjects
Nuclear Experiment
Abstract

The gamma-ray strength function in the quasi-continuum has been measured for 231-233Th, 232,233Pa and 237-239U using the Oslo method. All eight nuclei show a pronounced increase in gamma strength at omega_SR approx 2.4 MeV, which is interpreted as the low-energy M1 scissors resonance (SR). The total strength is found to be B_SR = 9-11 mu_N^2 when integrated over the 1 - 4 MeV gamma-energy region. The SR displays a double-hump structure that is theoretically not understood. Our results are compared with data from (gamma, gamma') experiments and theoretical sum-rule estimates for a nuclear rigid-body moment of inertia., Comment: 11 pages, 9 figures

Published
2013
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3. Constant-temperature level densities in the quasi-continuum of Th and U isotopes

Author

Guttormsen, M., Jurado, B., Wilson, J. N., Aiche, M., Bernstein, L. A., Ducasse, Q., Giacoppo, F., Goergen, A., Gunsing, F., Hagen, T. W., Larsen, A. C., Lebois, M., Leniau, B., Renstroem, T., Rose, S. J., Siem, S., Tornyi, T., Tveten, G. M., and Wiedeking, M.

Subjects
Nuclear Experiment
Abstract

Particle-gamma coincidences have been measured to obtain gamma-ray spectra as a function of excitation energy for 231-233Th and 237-239U. The level densities, which were extracted using the Oslo method, show a constant temperature behavior. The isotopes display very similar temperatures in the quasi-continuum, however, the even-odd isotopes reveal a constant entropy increase Delta S compared to their even-even neighbors. The entropy excess depends on available orbitals for the last unpaired valence neutron of the heated nuclear system. Also, experimental microcanonical temperature and heat capacity have been extracted. Several poles in the heat capacity curve support the idea that an almost continuous melting of Cooper pairs is responsible for the constant-temperature behavior., Comment: 9 figures

Published
2013
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9. LICORNE: A new and unique facility for producing intense, kinematically focused neutron beams at the IPN Orsay

Author

Wilson J.N., Lebois M., Halipre P., Leniau B., Matea I., Verney D., Oberstedt S., Billnert R., Oberstedt A., Georgiev G., and Ljungvall J.

Subjects
Physics, QC1-999
Abstract

LICORNE is a new neutron source recently installed at the tandem accelerator of the Institut de Physique Nucléaire d'Orsay, where a Li7-beam is used to bombard a hydrogen-containing target to produce an intense forward-directed neutron beam. The directionality of the beam, which is the unique characteristic of LICORNE, will permit the installation of γ-ray detectors dedicated to the investigation of fission fragment de-excitation which are unimpeded by neutrons from the source. A first experimental program will focus on the measurement of prompt γ-ray emission in the neutron-induced fission of fertile and fissile isotopes at incident neutron energies relevant for the core design of Generation-IV nuclear reactors. Other potential uses of the LICORNE facility for both fundamental and applied physics research are also presented.

Published
2013
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10. MURE 2 : SMURE, Serpent-MCNP Utility for Reactor Evolution User Guide -Version 1 Main Contributors

Author

Méplan, O., Hajnrych, Jan, Bidaud, A., David, S., Capellan, N., Leniau, B., Nuttin, A., Havluj, Frantisek, Vocka, Radim, Wilson, J., Chambon, R., 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), Mines Nantes (Mines Nantes), 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 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 Laboratoire de Physique Subatomique et de Cosmologie

Subjects
[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], [INFO.INFO-CL]Computer Science [cs]/Computation and Language [cs.CL]
Published
2017

11. 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

12. 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

13. Understanding Total Monte Carlo uncertainty propagation in burn up calculations with Generalized Perturbation Theory

Author

Bidaud, A., Olbratowski, P., Doligez, W., Autino, E., Aufiero, M., Leniau, B., 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), 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 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], [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex], Nuclear Experiment
Abstract

International audience; The last few years has seen Total Monte Carlo becoming the most used method for uncertainty propagation in burn up calculations.This straightfoward approach allows for the direct observation of output uncertainties (keff, isotopic concentrations etc…)of the coupled Bateman equation (fuel depletion) and Boltzmann equation (neutron transport). The application of GPT in thiscoupled case implies not only the calculation of nuclide adjoint functions but also the calculation of a number of importancefunctions. The coupling is thus almost never done.In this paper, we compare the propagation of Pu239 fission, capture and (n,2n) cross sections’ uncertainties with both TMC andGPT methods in a simple Na-cooled fast reactor assembly. In such a case, the change of spectrum due to the change in in onenuclide’s cross sections is expected to be smaller than in a thermal spectrum where the importance of individual resonances ishigh. We will see that it can’t be negligeted. Thanks to the combined use of TMC and GPT we can separate the effects of uncertaintieson a selection of other heavy nuclide densitities.The power normalisation gives minor, but important contributions. The sensitivities to depletion terms are the dominant termsfor Pu239 and its direct daughters’ evolution. The minor actinide density uncertainties are dominated by the impact of Pu239on neutron spectrum and then on minor actinides’ average cross sections. The results of uncertainty analyses could thereforebe very different if basic uncertainties with complete energy and cross nuclide correlations were available.

Published
2016

14. 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

15. 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

16. 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

17. 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

18. Characterization of spent fuel radiation sources: Application to the shielding of the thorium cycle

Author

Leniau, B., N. Wilson, J., 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 Heurteau, Sophie

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

International audience

Published
2012

19. Experimental level densities of atomic nuclei

Author

Guttormsen, M., primary, Aiche, M., additional, Bello Garrote, F. L., additional, Bernstein, L. A., additional, Bleuel, D. L., additional, Byun, Y., additional, Ducasse, Q., additional, Eriksen, T. K., additional, Giacoppo, F., additional, Görgen, A., additional, Gunsing, F., additional, Hagen, T. W., additional, Jurado, B., additional, Klintefjord, M., additional, Larsen, A. C., additional, Lebois, L., additional, Leniau, B., additional, Nyhus, H. T., additional, Renstrøm, T., additional, Rose, S. J., additional, Sahin, E., additional, Siem, S., additional, Tornyi, T. G., additional, Tveten, G. M., additional, Voinov, A., additional, Wiedeking, M., additional, and Wilson, J., additional

Published
2015
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20. Scissors resonance in the quasicontinuum of Th, Pa, and U isotopes

Author

Guttormsen, M., primary, Bernstein, L. A., additional, Görgen, A., additional, Jurado, B., additional, Siem, S., additional, Aiche, M., additional, Ducasse, Q., additional, Giacoppo, F., additional, Gunsing, F., additional, Hagen, T. W., additional, Larsen, A. C., additional, Lebois, M., additional, Leniau, B., additional, Renstrøm, T., additional, Rose, S. J., additional, Tornyi, T. G., additional, Tveten, G. M., additional, Wiedeking, M., additional, and Wilson, J. N., additional

Published
2014
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22. Constant-temperature level densities in the quasicontinuum of Th and U isotopes

Author

Guttormsen, M., primary, Jurado, B., additional, Wilson, J. N., additional, Aiche, M., additional, Bernstein, L. A., additional, Ducasse, Q., additional, Giacoppo, F., additional, Görgen, A., additional, Gunsing, F., additional, Hagen, T. W., additional, Larsen, A. C., additional, Lebois, M., additional, Leniau, B., additional, Renstrøm, T., additional, Rose, S. J., additional, Siem, S., additional, Tornyi, T., additional, Tveten, G. M., additional, and Wiedeking, M., additional

Published
2013
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25. 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

28. Development of a kinematically focused neutron source with the p(7Li,n)7Be inverse reaction.

Author

Lebois, M., Wilson, J.N., Halipré, P., Leniau, B., Matea, I., Oberstedt, A., Oberstedt, S., and Verney, D.

Subjects
*NEUTRON sources, *BERYLLIUM isotopes, *NUCLEAR reactions, *KINEMATICS, *NEUTRON beams, *POLYPROPYLENE, *ANGULAR distribution (Nuclear physics)
Abstract

Abstract: Directional beams of neutrons can be produced, if a nuclear reaction, which emits neutrons, is initiated in inverse kinematics with a heavy ion projectile bombarding a light target. In this paper we investigate the use of the p(7Li,n)7Be inverse reaction to produce kinematically focused, quasi-mono-energetic neutron beams with a view to develop such an unusual neutron source for fundamental and applied nuclear physics studies. An experiment was carried out to validate the concept and to test the viability of two types of hydrogen-rich solid targets: polypropylene and TiH2. Neutron time-of-flight/energy spectra at 3m distance from the source have been measured at 7Li bombarding energies of 13.5, 15, 15.5, 16, and 17MeV, and neutron backgrounds from parasitic reactions have been characterized. The neutron angular distribution in the laboratory has been measured at 15MeV. A Monte-Carlo code based on two-body relativistic kinematics has been developed and validated by comparison with the experimental data. Code-based extrapolations have then been used to deduce neutron energy spectra and maximum neutron fluxes available for future irradiation of samples placed in the neutron beam at small distances. For neutrons produced with thin and thick polypropylene targets the maximum available fluxes are calculated to be 107n/s/sr and 7×107 n/s/sr respectively. The development of a dedicated facility to produce kinematically focused neutrons is discussed. [Copyright &y& Elsevier]

Published
2014
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