TEM analysis of pellet-cladding bonding layer in high burnup BWR fuel-Reference-Cited by-同舟云学术

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TEM analysis of pellet-cladding bonding layer in high burnup BWR fuel

Published:1996-08 Issue:1-4 Volume:116 Page:521-526
ISSN:0168-583X
Container-title:Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms
language:en
Short-container-title:Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms

Author:

Nogita K.,Une K.,Korei Y.

Publisher

Elsevier BV

Subject

Instrumentation,Nuclear and High Energy Physics

Reference25 articles.

1. Proc. IAEA Technical Committee Meeting on Fuel Performance at High Burnup for Water Reactors;Oishi,1990

2. Phase equilibrium studies in the UO2ZrO2 system

3. The lattice parameter of cubic ZrO2 formed on zirconium

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1. Preparation and oxidation of (U1-yZry)O2+x;MRS Advances;2024-04-12

2. FLUKA study of the actinides induced irradiation damage in Zircaloy-4 cladding during interim dry storage;Journal of Nuclear Materials;2022-11

3. Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing;Journal of Nuclear Materials;2022-10

4. Thermophysical properties of urania-zirconia (U,Zr)O2 mixed oxides by molecular dynamics;Journal of Nuclear Materials;2020-01

5. On the origins and the evolution of the fuel-cladding bonding phenomenon in PWR fuel rods;Journal of Nuclear Materials;2019-07

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