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Jean NOIROT

affiliation not provided to SSRN

SCHOLARLY PAPERS

3

DOWNLOADS

136

TOTAL CITATIONS

0

Scholarly Papers (3)

1.

Post-Irradiation Examinations on a Fast Reactor Mox Fuel Pin with High Pu Content Irradiated in Phenix at High Burnup

Number of pages: 44 Posted: 21 Jan 2025
affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN and affiliation not provided to SSRN
Downloads 72 (883,195)

Abstract:

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FBR MOX, high Pu content, Post-irradiation examinations, radial microstructure evolution

2.

Post-Irradiation Examinations on a Fast Reactor Mox Fuel Pin with High Pu Content Irradiated at High Burnup in Phenix

Number of pages: 46 Posted: 02 Apr 2025
affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN and affiliation not provided to SSRN
Downloads 38 (1,222,651)

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FBR MOX, high Pu content, Post-irradiation examinations, radial microstructure evolution

3.

Coupling dissolution studies with post-irradiation examinations on irradiated FNR-PHENIX fuel to understand the effect of local burnup on its behavior in nitric acid

Number of pages: 40 Posted: 24 Mar 2026
affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN, affiliation not provided to SSRN and affiliation not provided to SSRN
Downloads 26 (1,500,778)

Abstract:

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Spent nuclear fuel, Dissolution, Burnup, Post-irradiation examinations, Fast neutron reactor, MOX fuel