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Measurements of fission cross-sections and of neutron production rates; Mesures de sections efficaces de fission et du nombre de neutrons prompts emis par fission

Abstract

a) Measurements of neutron induced fission cross-sections in the low energy region. The variation of the fission cross sections of several fissile isotopes has been measured and analysed, for neutron energies below 0,025 eV. The monochromator was a crystal spectrometer used in conjunction with a mechanical velocity selector removing higher order Bragg reflections. The fissile material was laid down on the plates of a fission chamber by painting technic. An ionization chamber, having its plates coated with thin {sup 10}B layers, was used as the neutron flux monitor. b) Measurement of the fission cross section of {sup 235}U. We intend to measure the variation of the neutron induced fission cross section of {sup 235}U over the neutron energy range from 1 keV by the time of flight method. The neutron source is the uranium target of a pulsed 28 MeV electron linear accelerator. The detector is a large fission chamber, with parallel plates, containing about 10 g of {sup 235}U (20 deposits of 25 cm diameter). The relative fission data were corrected for the neutron spectrum measured with a set of BF{sub 3} proportional counters. c) Mean number {nu} of neutrons emitted in neutron induced fission. We measured the value  More>>
Authors:
Billaud, P; Clair, C; Gaudin, M; Genin, R; Joly, R; Leroy, J L; Michaudon, A; Ouvry, J; Signarbieux, C; Vendryes, G [1] 
  1. Commissariat a l'Energie Atomique, Saclay (France). Centre d'Etudes Nucleaires
Publication Date:
Jul 01, 1958
Product Type:
Technical Report
Report Number:
CEA-R-963
Resource Relation:
Other Information: 10 refs
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; ALPHA DETECTION; BF3 COUNTERS; BORON COATED ION CHAMBERS; COINCIDENCE CIRCUITS; COLLIMATORS; COMPARATIVE EVALUATIONS; COUNTING TECHNIQUES; CROSS SECTIONS; DATA COVARIANCES; FISSION CHAMBERS; GONIOMETERS; MEV RANGE 10-100; MONOCHROMATORS; NEUTRON SPECTRA; PARTICLE DISCRIMINATION; PLASTIC SCINTILLATORS; PLUTONIUM 239; SACLAY LINAC; SPATIAL DISTRIBUTION; THORIUM 232 TARGET; TIME DELAY; TIME-OF-FLIGHT METHOD; URANIUM 238 TARGET
OSTI ID:
20901014
Research Organizations:
CEA Saclay, 91 - Gif-sur-Yvette (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR07R0963063237
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
42 pages
Announcement Date:
Aug 28, 2007

Citation Formats

Billaud, P, Clair, C, Gaudin, M, Genin, R, Joly, R, Leroy, J L, Michaudon, A, Ouvry, J, Signarbieux, C, and Vendryes, G. Measurements of fission cross-sections and of neutron production rates; Mesures de sections efficaces de fission et du nombre de neutrons prompts emis par fission. France: N. p., 1958. Web.
Billaud, P, Clair, C, Gaudin, M, Genin, R, Joly, R, Leroy, J L, Michaudon, A, Ouvry, J, Signarbieux, C, & Vendryes, G. Measurements of fission cross-sections and of neutron production rates; Mesures de sections efficaces de fission et du nombre de neutrons prompts emis par fission. France.
Billaud, P, Clair, C, Gaudin, M, Genin, R, Joly, R, Leroy, J L, Michaudon, A, Ouvry, J, Signarbieux, C, and Vendryes, G. 1958. "Measurements of fission cross-sections and of neutron production rates; Mesures de sections efficaces de fission et du nombre de neutrons prompts emis par fission." France.
@misc{etde_20901014,
title = {Measurements of fission cross-sections and of neutron production rates; Mesures de sections efficaces de fission et du nombre de neutrons prompts emis par fission}
author = {Billaud, P, Clair, C, Gaudin, M, Genin, R, Joly, R, Leroy, J L, Michaudon, A, Ouvry, J, Signarbieux, C, and Vendryes, G}
abstractNote = {a) Measurements of neutron induced fission cross-sections in the low energy region. The variation of the fission cross sections of several fissile isotopes has been measured and analysed, for neutron energies below 0,025 eV. The monochromator was a crystal spectrometer used in conjunction with a mechanical velocity selector removing higher order Bragg reflections. The fissile material was laid down on the plates of a fission chamber by painting technic. An ionization chamber, having its plates coated with thin {sup 10}B layers, was used as the neutron flux monitor. b) Measurement of the fission cross section of {sup 235}U. We intend to measure the variation of the neutron induced fission cross section of {sup 235}U over the neutron energy range from 1 keV by the time of flight method. The neutron source is the uranium target of a pulsed 28 MeV electron linear accelerator. The detector is a large fission chamber, with parallel plates, containing about 10 g of {sup 235}U (20 deposits of 25 cm diameter). The relative fission data were corrected for the neutron spectrum measured with a set of BF{sub 3} proportional counters. c) Mean number {nu} of neutrons emitted in neutron induced fission. We measured the value of {nu} for several fissile isotopes in the case of fission induced by 14 MeV neutrons. The 14 MeV neutrons were produced by D (t, n) {alpha} reaction by means of a 300 kV Cockcroft Walton generator. (author)Fren. [French] a) Mesures de sectionficaces de fission a basse energie. Nous avons mesure et analyse la variation de la section efficace de fission de divers isotopes fissiles pour des neutrons d'energie inferieure a 0,025 eV. Le monochromateur est constitue par un spectrometre a cristal auquel est associe un selecteur mecanique destine a eliminer les diffractions de Bragg d'ordre superieur au premier. Le materiau fissile est contenu dans une chambre a fission sous forme de depots realises par peinture; une chambre d'ionisation a depots minces de B{sub 10} sert de moniteur. b) Mesure de la section efficace de fission de l'uranium-235. Nous comptons effectuer sous peu une mesure de la variation de la section efficace de fission de l'uranium-235 pour des neutrons d'energie superieure a 5 eV et jusqu'a 1 keV, par la methode du temps de vol. La source de neutrons est la cible en uranium d'un accelerateur lineaire pulse d'electrons de 28 MeV. Le detecteur est une chambre a fission a plateaux paralleles de grande dimension contenant au total environ 10 g d'uranium-235 (20 depots de 25 cm de diametre). Les mesures de fission sont corrigees pour tenir compte de la forme du spectre des neutrons, mesure a l'aide d'un assemblage de compteurs a BF{sub 3}. c) Etude sur le nombre moyen de neutrons emis par fission. Nous avons mesure la valeur du nombre moyen {nu} de neutrons emis par fission, de divers isotopes fissiles, induite par des neutrons de 14 MeV. Les neutrons de 14 MeV sont produits par reaction D(t, n) {alpha} a l'aide d'un generateur Cockroft-Walton de 300 kV. (auteur)}
place = {France}
year = {1958}
month = {Jul}
}