Zobrazeno 1 - 10
of 11
pro vyhledávání: '"Christine Coquelet-Pascal"'
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, 2020, 149, pp.107776-. ⟨10.1016/j.anucene.2020.107776⟩
Annals of Nuclear Energy, Elsevier Masson, 2020, 149, pp.107776-. ⟨10.1016/j.anucene.2020.107776⟩
Annals of Nuclear Energy, 2020, 149, pp.107776-. ⟨10.1016/j.anucene.2020.107776⟩
Annals of Nuclear Energy, Elsevier Masson, 2020, 149, pp.107776-. ⟨10.1016/j.anucene.2020.107776⟩
The JANUS Phase 7 shielding experiment performed in the NESTOR experimental reactor in 1991 studied deep fast neutron propagation in mild steel, boron carbide and sodium. Several steel plates, followed by boxes containing boron carbide and sodium wer
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::bddb8ea35b2c9734d588a97adf74873a
https://hal.science/hal-03492045/file/S0306454920304746.pdf
https://hal.science/hal-03492045/file/S0306454920304746.pdf
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2020, 140, pp.107147. ⟨10.1016/j.anucene.2019.107147⟩
Annals of Nuclear Energy, 2020, 140, pp.107147. ⟨10.1016/j.anucene.2019.107147⟩
Annals of Nuclear Energy, Elsevier Masson, 2020, 140, pp.107147. ⟨10.1016/j.anucene.2019.107147⟩
Annals of Nuclear Energy, 2020, 140, pp.107147. ⟨10.1016/j.anucene.2019.107147⟩
The ASPIS Iron 88 campaign performed in the NESTOR facility studied deep neutron propagation in mild steel. Several plates of 5 cm thickness were used as a neutron shielding next to a fission plate. Gold, indium, rhodium, sulphur and aluminium detect
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b3c476961b7d3db717ad3449a0fc506f
https://hal-cea.archives-ouvertes.fr/cea-02534748
https://hal-cea.archives-ouvertes.fr/cea-02534748
Publikováno v:
Annals of Nuclear Energy. 159:108333
The JANUS Phase 1, Phase 2 and Phase 4 shielding experiments performed in the 90’s in the NESTOR reactor aimed to study deep neutron propagation in mild steel, stainless steel, sodium and boron carbide. Together with the other JANUS phases (up to P
Publikováno v:
Annals of Nuclear Energy. 154:108098
Internal storage is used in fast reactors as it allows burnt fissile assemblies to cool down before being removed from the reactor. These assemblies are usually stored in the neutron shielding zone far from the core to avoid additional induced fissio
Autor:
Laurent Braun, Christine Coquelet-Pascal, Benoit Geslot, Pavel Frajtag, Andreas Pautz, Pierre Leconte, Yifeng Jiang, Vincent Lamirand, Daniel Godat
Publikováno v:
EPJ Web of Conferences, Vol 253, p 04007 (2021)
The present article summarizes the development and testing of a reactivity modulation device developed by the French Atomic and Alternative Energies Commission (CEA). It was installed in the CROCUS reactor of the Swiss Federal Institute of Technology
Some Considerations on the Energy Deposition During a RIA Transient Based On Monte Carlo Simulations
Publikováno v:
EPJ Web of Conferences, Vol 253, p 04005 (2021)
Specific research reactors are capable of reproducing reactivity injection accidents in order to study the behavior of the nuclear fuel pins in accidental situations. In the CABRI research reactor, the fuel pin to be examined (test pin) is placed in
Publikováno v:
EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2021, 7, pp.17. ⟨10.1051/epjn/2021016⟩
EPJ N-Nuclear Sciences & Technologies, 2021, 7, pp.17. ⟨10.1051/epjn/2021016⟩
EPJ Nuclear Sciences & Technologies, Vol 7, p 17 (2021)
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2021, 7, pp.17. ⟨10.1051/epjn/2021016⟩
EPJ N-Nuclear Sciences & Technologies, 2021, 7, pp.17. ⟨10.1051/epjn/2021016⟩
EPJ Nuclear Sciences & Technologies, Vol 7, p 17 (2021)
International audience; Neutron calculations in the neutron shielding of fast neutron reactors are a complex problem as deterministic schemes are usually not suited for such calculations while Monte-Carlo codes have poor computational performance due
Autor:
Romain Eschbach, Jean-François Lebrat, Christine Coquelet-Pascal, Vanessa Vallet, Christophe Venard
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, 2018, ⟨10.1016/j.anucene.2018.05⟩
Annals of Nuclear Energy, Elsevier Masson, 2018, ⟨10.1016/j.anucene.2018.05.⟩
Annals of Nuclear Energy, 2018, ⟨10.1016/j.anucene.2018.05⟩
Annals of Nuclear Energy, Elsevier Masson, 2018, ⟨10.1016/j.anucene.2018.05.⟩
A good knowledge of the decay heat of the various elements of the core (fissile and fertile zones, structures, sodium…) as well as the associated uncertainties is critical for the safe operation of a nuclear facility, but also at the design stage a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4655eb26e3d6267cdbd85d4efe13a2ff
https://cea.hal.science/cea-02339833
https://cea.hal.science/cea-02339833
Autor:
Guillaume Krivtchik, Romain Eschbach, Christine Coquelet-Pascal, David Freynet, Elsa Merle-Lucotte
Publikováno v:
GLOBAL 2015 Proceedings
Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015)
Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015), Sep 2015, Paris, France. pp.814-823
HAL
EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, 2016, 2, pp.9. ⟨10.1051/epjn/e2015-50066-7⟩
EPJ Nuclear Sciences & Technologies, Vol 2, p 9 (2016)
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2016, 2, pp.9. ⟨10.1051/epjn/e2015-50066-7⟩
Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015)
Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015), Sep 2015, Paris, France. pp.814-823
HAL
EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, 2016, 2, pp.9. ⟨10.1051/epjn/e2015-50066-7⟩
EPJ Nuclear Sciences & Technologies, Vol 2, p 9 (2016)
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2016, 2, pp.9. ⟨10.1051/epjn/e2015-50066-7⟩
International audience; The consequences of various fleet evolution options on material inventories and flux in fuel cycle andwaste can be analysed by means of transition scenario studies. The COSI code is currently simulatingchronologically scenario
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b2d228ebd5892d374ec9d57862a78054
http://hal.in2p3.fr/in2p3-01247903
http://hal.in2p3.fr/in2p3-01247903
Publikováno v:
EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, 2017, 3, pp.22. ⟨10.1051/epjn/2017012⟩
EPJ Nuclear Sciences & Technologies, Vol 3, p 22 (2017)
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2017, 3, pp.22. ⟨10.1051/epjn/2017012⟩
EPJ N-Nuclear Sciences & Technologies, 2017, 3, pp.22. ⟨10.1051/epjn/2017012⟩
EPJ Nuclear Sciences & Technologies, Vol 3, p 22 (2017)
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2017, 3, pp.22. ⟨10.1051/epjn/2017012⟩
International audience; Scenario studies simulate the whole fuel cycle over a period of time, from extraction of natural resources to geological storage. Through the comparison of different reactor fleet evolutions and fuel management options, they c