Incineration of 241Am induced by thermal neutrons

Fioni, Gabriele; Cribier, M.; Marie, F.; Aubert, M.; Ayrault, Sophie; Bolognese, T.; Cavedon, J.M.; Chartier, Fredéric; Deruelle, Olivier; Doneddu, F.; Faust, H.; Gaudry, A.; Gunsing, F.; Leconte, Ph.; Lelievre, F.; Martino, J.; Oliver, R.; Pluquet, A.; Röttger, Stefan; Spiro, M.; Veyssiére, C.

doi:10.1016/s0375-9474(01)00920-4

Cited by 36 publications

(23 citation statements)

References 5 publications

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“…These cross sections were obtained in a pure Maxwellian neutron flux. They complement previous measurements done on 241 Am [14] and 243 Am [6] capture cross sections. The obtained effective and 25.3 meV cross sections are shown in table 4.…”

Section: Americium Transmutation Chainsupporting

confidence: 82%

Measurements of thermal fission and capture cross sections of minor actinides within the Mini-INCA project

Bringer¹,

AlMahamid

Chabod³

et al. 2007

Nd2007

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Abstract. In the framework of nuclear waste transmutation studies, the Mini-INCA project has been initiated at CEA/DSM to determine optimal conditions for transmutation and incineration of Minor Actinides (MA) in high intensity neutron fluxes in the thermal region. Our experimental tool is based on alpha-and gamma-spectroscopy of irradiated samples and microscopic fission-chambers. It can provide both microscopic information on nuclear reactions (total and partial cross sections for neutron capture and/or fission reactions) and macroscopic information on transmutation and incineration potentials. The 232 Th, 237 Np, 241 Am, and 244 Cm transmutation chains have been explored in details, showing some discrepancies in comparison with evaluated data libraries but in overall good agreement with recent experimental data.

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Section: Americium Transmutation Chainsupporting

confidence: 82%

Measurements of thermal fission and capture cross sections of minor actinides within the Mini-INCA project

Bringer¹,

AlMahamid

Chabod³

et al. 2007

Nd2007

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“…The results on cross sections of neutron radiation capture with the formation of 242g Am and 242m Am nuclei obtained in the given paper are somewhat higher than the data given in paper of Fioni et al [1], 241 Am(n,γ) 242 Am = (696 ± 48) barn and also the value given in ENDF/B-VII (620.8 barn). Most probably, this difference is conditioned by the fact that the neutrons in the IRT MEPhI reactor channels are thermalized insufficiently.…”

Section: Resultscontrasting

confidence: 64%

“…The data on neutron cross sections of 242g Am nucleus given in paper [1] and obtained in our measurements give grounds to assume that the recommended cross sections for this nuclide based on theoretical evaluations are essentially overstated. In any case, further experimental researches of characteristics of neutrons242g Am nucleus interaction are required.…”

Section: Resultsmentioning

confidence: 75%

“…However, the data on cross section of 242g Am formation and cross sections of 242g Am interactions with neutrons are extremely few. Sufficiently reliable experimental data on radiation capture cross section are given in publications of G. Fioni et al only [1,2]. The value 2100 barn of 242g Am fission cross section by thermal neutrons given in all libraries of evaluated data is based on theoretical estimations [3].…”

Section: Introductionmentioning

confidence: 99%

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Measurement of the ^242gAm (T_1/2=16.02 hour) fission cross section

Fomushkin

Gavrilov

Andreev

et al. 2007

Nd2007

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Abstract. There was performed a cycle of 242g Am fission characteristics measurements with the use of IRT-MEPhI reactor. The 242g Am isotope was produced in the course of irradiating 241 Am targets in the experimental channel with the density of neutron flux ≈2 · 10 13 1/(cm 2 ·s). Then, with no isolation of americium-242 from the irradiated targets the time dependencies of induced fission fragments yield from the targets were measured. Moreover the irradiated americium targets undertook irradiation in another channel of IRT reactor with the density of thermal neutron flux ≈5.6 · 10 10 1/(cm 2 · s). The fission fragments were registered with the aid of dielectric track detectors. In each time dependence of fission fragments an exponent with T 1/2 = 16.02 hour is available; the cross section of 242g Am fission by thermal and resonance neutrons was determined by the intensity of induced fissions with the given half-life. The quantity of 242g Am nuclei in each of irradiated targets was determined basing on accumulation of 242 Cm, daughter product of 242g Am decay. Based on the experimental results for the 242g Am nuclide, the evaluations of both the fission cross section by thermal neutrons and the fission resonance integral were obtained.

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“…In addition, 242 Am has a spin-isomer which lives 141 years while the ground state lives only 16 hours. The measured fission cross sections are 6856 ±656 barn for the isomer and 2644±281 barn for the ground state [4][5]. This reveals that the entrance channel of the reaction is affected by the spin; one of the remaining questions is consequently the influence of the spin on the final state (i.e.…”

Section: Motivationsmentioning

confidence: 99%

Measurement of mass yields from the²⁴¹Am(2n_th,f) reaction at the Lohengrin Spectrometer

Amouroux

Blanc

Bidaud

et al. 2013

EPJ Web of Conferences

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Abstract. The study of fission yields has a major impact on the characterization and understanding of the fission process and is mandatory for reactor applications. While the yields are known for the major actinides ( 235 U, 239 Pu) in the thermal neutron-induced fission, only few measurements have been performed on 242 Am. The interest of 242 Am concerns the reduction of radiotoxicity of 241 Am in nuclear wastes using transmutation reactions. This paper presents the measurement of the fission mass yields from the reaction 241 Am(2n th ,f) performed at the Lohengrin mass spectrometer (ILL, France) for both the light and the heavy peaks: a total of 41 mass yields have been measured. The experiment was also meant to determine whether there is a difference in mass yields between the isomeric state and the ground state as it exists in fission and capture cross sections. The method used to address this question is based on a repeated measurement of a set of fission mass yields as a function of the ratio between the 242g Am and the 242m Am fission rates. The presented experiment is also a first step towards the measurement of the isotopic fission yields of 242 Am .

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Incineration of 241Am induced by thermal neutrons

Cited by 36 publications

References 5 publications

Measurements of thermal fission and capture cross sections of minor actinides within the Mini-INCA project

Measurements of thermal fission and capture cross sections of minor actinides within the Mini-INCA project

Measurement of the ^242gAm (T_1/2=16.02 hour) fission cross section

Measurement of mass yields from the²⁴¹Am(2n_th,f) reaction at the Lohengrin Spectrometer

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Incineration of 241Am induced by thermal neutrons

Cited by 36 publications

References 5 publications

Measurements of thermal fission and capture cross sections of minor actinides within the Mini-INCA project

Measurements of thermal fission and capture cross sections of minor actinides within the Mini-INCA project

Measurement of the 242gAm (T1/2=16.02 hour) fission cross section

Measurement of mass yields from the241Am(2nth,f) reaction at the Lohengrin Spectrometer

Contact Info

Product

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About

Measurement of the ^242gAm (T_1/2=16.02 hour) fission cross section

Measurement of mass yields from the²⁴¹Am(2n_th,f) reaction at the Lohengrin Spectrometer