Evaluation of thermal properties of mixed oxide fuel by molecular dynamics

2000 ◽  
Vol 307 (1-2) ◽  
pp. 1-9 ◽  
Author(s):  
Kazuhiro Yamada ◽  
Ken Kurosaki ◽  
Msayoshi Uno ◽  
Shinsuke Yamanaka
Keyword(s):  
Molecular Dynamics ◽  
Thermal Properties ◽  
Mixed Oxide ◽  
Oxide Fuel ◽  
Mixed Oxide Fuel

Molecular dynamics study of mixed oxide fuel

2001 ◽  
Vol 294 (1-2) ◽  
pp. 160-167 ◽  
Author(s):  
Ken Kurosaki ◽  
Kazuhiro Yamada ◽  
Masayoshi Uno ◽  
Shinsuke Yamanaka ◽  
Kazuya Yamamoto ◽  
...  
Keyword(s):  
Molecular Dynamics ◽  
Mixed Oxide ◽  
Oxide Fuel ◽  
Mixed Oxide Fuel

Weapons-Derived Mixed Oxide Fuel Test Irradiation Summary

2005 ◽  
Author(s):  
S. A. Hodge ◽  
R. N. Morris ◽  
L. J. Ott
Keyword(s):  
Mixed Oxide ◽  
Oxide Fuel ◽  
Mixed Oxide Fuel

scholarly journals A Concept Study on Advanced Radioisotope Solid Solutions and Mixed-Oxide Fuel Forms for Future Space Nuclear Power Systems

2021 ◽  
pp. 1-9
Author(s):  
Richard M. Ambrosi ◽  
Daniel P. Kramer ◽  
Emily Jane Watkinson ◽  
Ramy Mesalam ◽  
Alessandra Barco
Keyword(s):  
Power Systems ◽  
Solid Solutions ◽  
Mixed Oxide ◽  
Nuclear Power ◽  
Oxide Fuel ◽  
Concept Study ◽  
Mixed Oxide Fuel ◽  
Future Space ◽  
Space Nuclear Power

Failure behavior of plutonium-uranium mixed oxide fuel under reactivity-initiated accident condition

1992 ◽  
Vol 188 ◽  
pp. 154-161 ◽  
Author(s):  
T. Abe ◽  
N. Nakae ◽  
K. Kodato ◽  
M. Matsumoto ◽  
T. Inabe
Keyword(s):  
Mixed Oxide ◽  
Failure Behavior ◽  
Oxide Fuel ◽  
Mixed Oxide Fuel ◽  
Accident Condition

Atomistic Level Molecular Dynamics Analysis and its Integrity in the Interim of Irradiation

2021 ◽  
Vol 318 ◽  
pp. 39-47
Author(s):  
Ahli K.D. Willie ◽  
Hong Tao Zhao ◽  
M. Annor-Nyarko
Keyword(s):  
Thermal Conductivity ◽  
Molecular Dynamics ◽  
Mixed Oxide ◽  
Md Simulation ◽  
Lattice Thermal Conductivity ◽  
Gas Diffusion ◽  
Mixed Oxide Fuel ◽  
Fission Gas ◽  
Increasing Temperature ◽  
End Members

In this work, molecular dynamics (MD) simulation was utilized in relation to access the thermal conductivity of UO2, PuO2 and (U, Pu)O2 in temperature range of 500–3000 K. Diffusion study on mixed oxide (MOX) was also performed to assess the effect of radiation damage by heavy ions at burnup temperatures. Analysis of the lattice thermal conductivity of irradiated MOX to its microstructure was carried out to enhance the irradiation defects with how high burnup hinders fuel properties and its pellet-cladding interaction. Fission gas diffusion as determined was mainly modelled by main diffusion coefficient. Degradation of diffusivity is predicted in MOX as composition deviate from the pure end members. The concentration of residual anion defects is considerably higher than that of cations in all oxides. Depending on the diffusion behavior of the fuel lattice, there was decrease in the ratio of anion to cation defects with increasing temperature. Besides, the modern mixed oxide fuel releases fission gas compared to that of UO2 fuel at moderate burnups.

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