Measuring the delayed neutrons multiplicity and kinetic parameters for the thermal induced fission of 235U, 239Pu and 233U

In the normal operation of nuclear reactors, the kinetic behavior of the neutron population in the core is driven by the so-called delayed neutrons (DN). The DN yield per fission, their average lifetime and their groups’ abundances are the main physical parameters used to predict the kinetic behavio...

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Autores principales: Geslot Benoit, Sardet Alix, Casoli Pierre, Leconte Pierre, De Izarra Grégoire, Chebboubi Abdelhazize, Kessedjian Grégoire, Méplan Olivier, Doré Diane, Soldner Torsten, Mutti Paolo
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spelling oai:doaj.org-article:0141c74deed545f1a88ab369060626a42021-12-02T17:12:45ZMeasuring the delayed neutrons multiplicity and kinetic parameters for the thermal induced fission of 235U, 239Pu and 233U2100-014X10.1051/epjconf/202125301004https://doaj.org/article/0141c74deed545f1a88ab369060626a42021-01-01T00:00:00Zhttps://www.epj-conferences.org/articles/epjconf/pdf/2021/07/epjconf_animma2021_01004.pdfhttps://doaj.org/toc/2100-014XIn the normal operation of nuclear reactors, the kinetic behavior of the neutron population in the core is driven by the so-called delayed neutrons (DN). The DN yield per fission, their average lifetime and their groups’ abundances are the main physical parameters used to predict the kinetic behavior of the reactor and its reactivity. The overall uncertainty associated to reactivity predictions, which is linked directly to the nuclear reactor safety margins, is thus closely dependent on a few parameters associated with DN. Depending on the nuclear data library, DN kinetic parameters present significant discrepancies, even for major fissile isotopes such as 235U or 239Pu. In this context, CEA has long been working for improving DN nuclear data. In 2018, CEA launched the ALDEN project (Average Lifetime of DElayed Neutrons) in the framework of a collaboration between CEA/DES, CEA/DRF, CNRS/IN2P3 (LPSC, CENBG, LPC), ENSICAEN and Caen University. This program aims at measuring the kinetics of the delayed neutrons to derive the DN yield, their average lifetime and abundances. Two experimental campaigns focusing on the thermal fission of 235U were conducted in 2018 and 2019. They demonstrated the concept feasibility and gave high quality estimations of the DN multiplicity (1.631 ± 0.014 %) and average lifetime (8.82 ± 0.6 s) for 235U. More recently in March 2021, a more ambitious irradiation campaign was conducted on 239Pu and 233U. This paper details the new experimental setup, which was upgraded to meet ILL safety requirements for handling plutonium. The data analysis process is presented, with a focus on the problem of dead time correction. Finally, some preliminary delayed neutron decay curves are showed and discussed.Geslot BenoitSardet AlixCasoli PierreLeconte PierreDe Izarra GrégoireChebboubi AbdelhazizeKessedjian GrégoireMéplan OlivierDoré DianeSoldner TorstenMutti PaoloEDP Sciencesarticledelayed neutronsfission chambers3he proportional countersfissile isotopesuranium 235uranium 233plutonium 239PhysicsQC1-999ENEPJ Web of Conferences, Vol 253, p 01004 (2021)
institution DOAJ
collection DOAJ
language EN
topic delayed neutrons
fission chambers
3he proportional counters
fissile isotopes
uranium 235
uranium 233
plutonium 239
Physics
QC1-999
spellingShingle delayed neutrons
fission chambers
3he proportional counters
fissile isotopes
uranium 235
uranium 233
plutonium 239
Physics
QC1-999
Geslot Benoit
Sardet Alix
Casoli Pierre
Leconte Pierre
De Izarra Grégoire
Chebboubi Abdelhazize
Kessedjian Grégoire
Méplan Olivier
Doré Diane
Soldner Torsten
Mutti Paolo
Measuring the delayed neutrons multiplicity and kinetic parameters for the thermal induced fission of 235U, 239Pu and 233U
description In the normal operation of nuclear reactors, the kinetic behavior of the neutron population in the core is driven by the so-called delayed neutrons (DN). The DN yield per fission, their average lifetime and their groups’ abundances are the main physical parameters used to predict the kinetic behavior of the reactor and its reactivity. The overall uncertainty associated to reactivity predictions, which is linked directly to the nuclear reactor safety margins, is thus closely dependent on a few parameters associated with DN. Depending on the nuclear data library, DN kinetic parameters present significant discrepancies, even for major fissile isotopes such as 235U or 239Pu. In this context, CEA has long been working for improving DN nuclear data. In 2018, CEA launched the ALDEN project (Average Lifetime of DElayed Neutrons) in the framework of a collaboration between CEA/DES, CEA/DRF, CNRS/IN2P3 (LPSC, CENBG, LPC), ENSICAEN and Caen University. This program aims at measuring the kinetics of the delayed neutrons to derive the DN yield, their average lifetime and abundances. Two experimental campaigns focusing on the thermal fission of 235U were conducted in 2018 and 2019. They demonstrated the concept feasibility and gave high quality estimations of the DN multiplicity (1.631 ± 0.014 %) and average lifetime (8.82 ± 0.6 s) for 235U. More recently in March 2021, a more ambitious irradiation campaign was conducted on 239Pu and 233U. This paper details the new experimental setup, which was upgraded to meet ILL safety requirements for handling plutonium. The data analysis process is presented, with a focus on the problem of dead time correction. Finally, some preliminary delayed neutron decay curves are showed and discussed.
format article
author Geslot Benoit
Sardet Alix
Casoli Pierre
Leconte Pierre
De Izarra Grégoire
Chebboubi Abdelhazize
Kessedjian Grégoire
Méplan Olivier
Doré Diane
Soldner Torsten
Mutti Paolo
author_facet Geslot Benoit
Sardet Alix
Casoli Pierre
Leconte Pierre
De Izarra Grégoire
Chebboubi Abdelhazize
Kessedjian Grégoire
Méplan Olivier
Doré Diane
Soldner Torsten
Mutti Paolo
author_sort Geslot Benoit
title Measuring the delayed neutrons multiplicity and kinetic parameters for the thermal induced fission of 235U, 239Pu and 233U
title_short Measuring the delayed neutrons multiplicity and kinetic parameters for the thermal induced fission of 235U, 239Pu and 233U
title_full Measuring the delayed neutrons multiplicity and kinetic parameters for the thermal induced fission of 235U, 239Pu and 233U
title_fullStr Measuring the delayed neutrons multiplicity and kinetic parameters for the thermal induced fission of 235U, 239Pu and 233U
title_full_unstemmed Measuring the delayed neutrons multiplicity and kinetic parameters for the thermal induced fission of 235U, 239Pu and 233U
title_sort measuring the delayed neutrons multiplicity and kinetic parameters for the thermal induced fission of 235u, 239pu and 233u
publisher EDP Sciences
publishDate 2021
url https://doaj.org/article/0141c74deed545f1a88ab369060626a4
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