HTR-10 full core first criticality analysis with MCNP

Nuclear Engineering and Design

Volumn 222, Issue 2-3 SPEC, 2003, Pages 263-270

  Şeker, Volkan ^a   Çolak, Üner ^a  

^a HACETTEPE UNIVERSITY   (Turkey)

Author keywords

[No Author keywords available]

Indexed keywords

CODES (STANDARDS); DATA REDUCTION; GAS COOLED REACTORS; MONTE CARLO METHODS; REACTOR CORES; TRANSPORT PROPERTIES;

CRITICALITY ANALYSIS;

HIGH TEMPERATURE REACTORS;

EID: 0038752975     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(03)00031-1     Document Type: Conference Paper

References (7)

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4. International Atomic Energy Agency, 2001. Evaluation of High Temperature Gas Cooled Reactor Performance. Interim draft of First CRP-5 TECDOC.
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