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Specific outcomes of the research on the spent fuel long-term evolution in interim dry storage and deep geological disposal

Journal of nuclear materials, 2006-06, Vol.352 (1-3), p.246-253

2006

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Overview of the French research on the evolution of spent fuel rod after discharge from the reactor

MRS proceedings, 2009, Vol.1193 (1), Article 605

2009

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Helium behavior in UO2 polycrystalline disks

Journal of nuclear materials, 2003-09, Vol.321 (2-3), p.121-128

2003

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He migration in implanted UO2 sintered disks

Journal of nuclear materials, 2004-05, Vol.327 (2-3), p.88-96

2004

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A NRA study of temperature and heavy ion irradiation effects on helium migration in sintered uranium dioxide

Journal of nuclear materials, 2006-10, Vol.357 (1), p.198-205

2006

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Vacancy defects induced in sintered polished UO2 disks by helium implantation

Applied surface science, 2006-02, Vol.252 (9), p.3256-3261

2006

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Modeling the relationship between psychophysical perception and electrically evoked compound action potential threshold in young cochlear implant recipients: clinical implications for implant fitting

Clinical neurophysiology, 2004-12, Vol.115 (12), p.2811-2824

2004

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Vacancy defects induced in sintered polished UO 2 disks by helium implantation

Applied surface science, 2006-02, Vol.252 (9), p.3256-3261

2006

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Thermal evolution of vacancy defects induced in sintered UO 2 disks by helium implantation

Applied surface science, 2006-02, Vol.252 (9), p.3262-3268

2006

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Thermal evolution of vacancy defects induced in sintered UO2 disks by helium implantation

Applied surface science, 2006-02, Vol.252 (9), p.3262-3268

2006

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Thermal evolution of the vacancy defects distribution in 1MeV helium implanted sintered UO2

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2007-08, Vol.261 (1-2), p.883-887

2007

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Microstructure effects on He diffusion in sintered UO2 by μNRA

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2005-10, Vol.240 (1-2), p.271-276

2005

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Evolution of the spent nuclear fuel during the confinement phase in repository conditions: Major outcomes of the French research

MRS proceedings, 2006, Vol.932, Article 68.1

2006

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Behaviour of fission gases in an irradiated nuclear fuel under α external irradiation

Journal of nuclear materials, 2003-09, Vol.321 (2), p.324-330

2003

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Positron annihilation characteristics in UO 2 : for lattice and vacancy defects induced by electron irradiation

Physica status solidi. C, 2007-09, Vol.4 (10), p.3627-3632

2007

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Deuterium trapping in sintered polished UO2 disks

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2005-10, Vol.240 (1-2), p.434-439

2005

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Microstructure effects on He diffusion in sintered UO$_2$ by $\mu$NRA

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2005, Vol.240, p.271-276

2005

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Profile measurements of helium implanted in UO2 sintered pellets by using the 3He(d, α)1H nuclear reaction analysis technique

Journal of nuclear materials, 2004-05, Vol.327 (2-3), p.159-164

2004

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He migration in implanted UO 2 sintered disks

Journal of nuclear materials, 2004, Vol.327 (2), p.88-96

2004

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Profile measurements of helium implanted in UO 2 sintered pellets by using the 3He(d, α) 1H nuclear reaction analysis technique

Journal of nuclear materials, 2004, Vol.327 (2), p.159-164

2004

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Helium behavior in UO 2 polycrystalline disks

Journal of nuclear materials, 2003, Vol.321 (2), p.121-128

2003

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Influence of communication mode on speech intelligibility and syntactic structure of sentences in profoundly hearing impaired French children implanted between 5 and 9 years of age

International journal of pediatric otorhinolaryngology, 1998-06, Vol.44 (1), p.15-22

1998

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GERMINAL — A computer code for predicting fuel pin behaviour

Journal of nuclear materials, 1992-06, Vol.188, p.303-307

1992

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Cochlear implantation safety and reliability in paediatric cases

Audiological medicine, 2007, Vol.5 (4), p.210-217

2007

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GERMINAL – A computer code for predicting fuel pin behaviour

Nuclear Materials for Fission Reactors, 1992, p.303-307

1992

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Specific outcomes of the research on the spent fuel long-term evolution in interim dry storage and deep geological disposal

Overview of the French research on the evolution of spent fuel rod after discharge from the reactor

Helium behavior in UO2 polycrystalline disks

He migration in implanted UO2 sintered disks

A NRA study of temperature and heavy ion irradiation effects on helium migration in sintered uranium dioxide

Vacancy defects induced in sintered polished UO2 disks by helium implantation

Modeling the relationship between psychophysical perception and electrically evoked compound action potential threshold in young cochlear implant recipients: clinical implications for implant fitting

Vacancy defects induced in sintered polished UO 2 disks by helium implantation

Thermal evolution of vacancy defects induced in sintered UO 2 disks by helium implantation

Thermal evolution of vacancy defects induced in sintered UO2 disks by helium implantation

Thermal evolution of the vacancy defects distribution in 1MeV helium implanted sintered UO2

Microstructure effects on He diffusion in sintered UO2 by μNRA

Evolution of the spent nuclear fuel during the confinement phase in repository conditions: Major outcomes of the French research

Behaviour of fission gases in an irradiated nuclear fuel under α external irradiation

Positron annihilation characteristics in UO 2 : for lattice and vacancy defects induced by electron irradiation

Deuterium trapping in sintered polished UO2 disks

Microstructure effects on He diffusion in sintered UO$_2$ by $\mu$NRA

Profile measurements of helium implanted in UO2 sintered pellets by using the 3He(d, α)1H nuclear reaction analysis technique

He migration in implanted UO 2 sintered disks

Profile measurements of helium implanted in UO 2 sintered pellets by using the 3He(d, α) 1H nuclear reaction analysis technique

Helium behavior in UO 2 polycrystalline disks

Influence of communication mode on speech intelligibility and syntactic structure of sentences in profoundly hearing impaired French children implanted between 5 and 9 years of age

GERMINAL — A computer code for predicting fuel pin behaviour

Cochlear implantation safety and reliability in paediatric cases

GERMINAL – A computer code for predicting fuel pin behaviour

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