Design study of an irradiation experiment with inert matrix and mixed-oxide fuel at the Halden boiling water reactor

Journal of Nuclear Materials

Volumn 274, Issue 1, 1999, Pages 160-166

  Kasemeyer, U ^a   Joo, H K ^b   Ledergerber, G ^c  

^a OECD HALDEN REACTOR PROJECT   (Norway)

^b Korea Atomic Energy Research Institute   (South Korea)

^c PAUL SCHERRER INSTITUTE   (Switzerland)

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER REACTORS; NEUTRON DETECTORS; NEUTRON IRRADIATION; PLUTONIUM; PLUTONIUM COMPOUNDS; REACTOR OPERATION; URANIUM DIOXIDE;

INERT MATRIX FUELS (IMF);

MIXED OXIDE FUELS;

EID: 0032671891     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0022-3115(99)00095-1     Document Type: Article

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