Oxidation Behavior of Am-containing MOX Fuel Pellets in Air

Modeling of MOX Fuel Pellet-Clad Interaction Using ABAQUS

10th International Conference on Nuclear Engineering, Volume 4 ◽

10.1115/icone10-22142 ◽

2002 ◽

Author(s):

Richard G. Ambrosek ◽

Robert C. Pedersen ◽

Amanda Maple

Keyword(s):

Axial Length ◽

Fuel Pellet ◽

Solution Technique ◽

Outer Diameter ◽

Symmetric Model ◽

Post Irradiation ◽

Fuel Pellets ◽

Mox Fuel ◽

Test Reactor

Post-irradiation examination (PIE) has indicated an increase in the outer diameter of fuel pins being irradiated in the Advanced Test Reactor (ATR) for the MOX irradiation program. The diameter increase is the largest in the region between fuel pellets. The fuel pellet was modeled using PATRAN and the model was evaluated using ABAQUS, version 6.2. The results from the analysis indicate the non-uniform clad diameter is caused by interaction between the fuel pellet and the clad. The results also demonstrate that the interaction is not uniform over the pellet axial length, with the largest interaction occurring in the region of the pellet-pellet interface. Results were obtained for an axi-symmetric model and for a 1/8 pie shaped segment, using the coupled temperature-displacement solution technique.

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Radial Density Distribution in Irradiated FBR MOX Fuel Pellets

Nuclear Technology ◽

10.13182/nt14-34 ◽

2015 ◽

Vol 189 (3) ◽

pp. 312-317 ◽

Cited By ~ 3

Author(s):

Akihiro Ishimi ◽

Kozo Katsuyama ◽

Hirofumi Nakamura ◽

Takeo Asaga ◽

Hirotaka Furuya

Keyword(s):

Density Distribution ◽

Radial Density ◽

Fuel Pellets ◽

Mox Fuel ◽

Radial Density Distribution

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Development of fission gas release model for MOX fuel pellets with treatment of heterogeneous microstructure

Journal of Nuclear Science and Technology ◽

10.1080/00223131.2021.1973924 ◽

2021 ◽

pp. 1-13

Author(s):

Yudai Tasaki ◽

Yutaka Udagawa ◽

Masaki Amaya

Keyword(s):

Gas Release ◽

Heterogeneous Microstructure ◽

Fuel Pellets ◽

Mox Fuel ◽

Fission Gas ◽

Release Model ◽

Fission Gas Release

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Development of recycling processes for clean rejected MOX fuel pellets

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2013.12.060 ◽

2014 ◽

Vol 270 ◽

pp. 227-237 ◽

Cited By ~ 6

Author(s):

P.M. Khot ◽

G. Singh ◽

B.K. Shelke ◽

B. Surendra ◽

M.K. Yadav ◽

...

Keyword(s):

Fuel Pellets ◽

Mox Fuel

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Radial Power Profile of MOX and LEU Fuel Pellet Versus Burnup

10th International Conference on Nuclear Engineering, Volume 4 ◽

10.1115/icone10-22483 ◽

2002 ◽

Cited By ~ 1

Author(s):

Gray S. Chang ◽

Robert C. Pedersen

Keyword(s):

Performance Evaluation ◽

Fuel Pellet ◽

Light Water Reactors ◽

Spent Fuel ◽

Light Water ◽

Fuel Pellets ◽

Mox Fuel ◽

Power Profile ◽

Fission Power ◽

Water Reactors

One of challenge to burn the WG-Pu in Mixed Oxide (MOX) fuel in light water reactors (LWR) is to demonstrate that the differences between WG-MOX, RG-MOX, and LWR LEU fuel are minimal, and therefore, the commercial MOX and LEU fuel experience base is applicable. The MCWO-calculated Radial Power Profile of LEU, Weapons Grade-MOX and Reactor Grade-MOX fuel pellets at various burnups are similar toward the end of life (50 GWd/t). Therefore, the LEU fuel performance evaluation code — FRAPCON-3 with modifications, such as, the detailed fission power profiles versus burnup, can be used in the MOX fuel pellet performance analysis. MCWO also calculated the 240Pu/Pu ratio in WG-MOX versus burnup, which reaches an average of 31.25% at discharged burnup of 50 GWd/t. It meets the spent fuel standard for WG-Pu disposition in LWR.

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