Uncertainty evaluation of calculated and measured kinetics parameters of Tehran Research Reactor

Nuclear Engineering and Design

Volumn 240, Issue 10, 2010, Pages 2761-2767

  Hosseini, Seyed Abolfazl ^a   Vosoughi, Naser ^a  

^a SHARIF UNIVERSITY OF TECHNOLOGY   (Iran)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT ANALYSIS; COLD STATE; COMPUTER CODES; COOLANT TEMPERATURE; DELAYED NEUTRONS; DELAYED-NEUTRON CONSTANTS; EFFECTIVE DELAYED NEUTRON FRACTION; ENERGY DEPENDENCE; EXPERIMENTAL METHODS; FISSION CROSS-SECTION; GENERATION TIME; INHOUR EQUATION; KINETICS PARAMETER; REACTOR PHYSICS; TEHRAN RESEARCH REACTORS; TWO-STATE; UNCERTAINTY EVALUATION;

COOLANTS; REACTOR CORES; RESEARCH; RESEARCH REACTORS; TRANSIENT ANALYSIS;

NEUTRONS;

EID: 77957694156     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2010.05.007     Document Type: Conference Paper

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