Calculation, measurement and sensitivity analysis of kinetic parameters of Tehran Research Reactor

Annals of Nuclear Energy

Volumn 37, Issue 4, 2010, Pages 463-470

  Hosseini, S A ^a   Vosoughi, N ^a   Ghofrani, M B ^a   Gharib, M ^b  

^a SHARIF UNIVERSITY OF TECHNOLOGY   (Iran)

^b Tehran Research Reactor   (Iran)

Author keywords

[No Author keywords available]

Indexed keywords

COLD STATE; COMPARATIVE ANALYSIS; COOLANT TEMPERATURE; EFFECTIVE DELAYED NEUTRON FRACTION; EXPERIMENTAL METHODS; FISSION CROSS SECTION; FUEL BURN-UPS; FUEL ENRICHMENT; GENERATION TIME; INHOUR EQUATION; NORMAL BEHAVIOR; REACTOR PHYSICS; REACTOR POWER; TEHRAN RESEARCH REACTORS; TWO-STATE;

COOLANTS; KINETIC PARAMETERS; NEUTRON BEAMS; NEUTRONS; NUCLEAR FUELS; REACTOR CORES; RESEARCH; RESEARCH REACTORS; SENSITIVITY ANALYSIS;

TRANSIENT ANALYSIS;

EID: 77649187754     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2010.01.018     Document Type: Article

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