Interpretation of experimental results from moderate-power in-pile testing of a Pu-Er-Zr-oxide inert matrix fuel

Annals of Nuclear Energy

Volumn 30, Issue 3, 2003, Pages 287-299

  Hellwig, Christian ^a   Kasemeyer, Uwe ^a   Ledergerber, Guido ^b   Lee, Byung Ho ^c   Lee, Young Woo ^c   Chawla, Rakesh ^a,d  

^a PAUL SCHERRER INSTITUTE   (Switzerland)

^b Leibstadt Nuclear Power Plant   (Switzerland)

^c Korea Atomic Energy Research Institute   (South Korea)

^d EPFL   (Switzerland)

Author keywords

[No Author keywords available]

Indexed keywords

NUCLEAR REACTORS; PLUTONIUM COMPOUNDS; POWDERS; PRESSURE EFFECTS; SINTERING; TEMPERATURE MEASUREMENT;

INERT MATRIX FUEL (IMF);

MIXED OXIDE FUELS;

EID: 0037289892     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(02)00059-2     Document Type: Article

References (7)

1. Categorisation and priorities for future research on inert matrix fuels: An extended synthesis of the panel discussions
2. Comparison of PWR core characteristics for 100% Pu-containing loadings
3. The irradiation test of inert-matrix fuel in comparison to uranium plutonium mixed oxide fuel at the Halden reactor
4. Transuranus: A fuel rod analysis code ready for use
5. Inert matrix fuel for the utilisation of plutonium
6. Preparation of simulated inert matrix fuel with different powders by dry milling method
7. Conceptual studies for pressurized water reactor cores employing plutonium-erbium-zirconium oxide inert matrix fuel assemblies