A mathematical model for the thermal-hydraulic analysis of nuclear power plants

International Communications in Heat and Mass Transfer

Volumn 27, Issue 6, 2000, Pages 795-805

  Han, Gee Y ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; HYDRAULICS; PRESSURIZED WATER REACTORS; STEAM GENERATORS; THERMODYNAMICS; TRANSIENTS;

FEEDBACK REACTIVITY; NUCLEAR SAFETY; REACTOR KINETICS;

NUCLEAR POWER PLANTS;

COMPUTER AIDED PROCESS PLANNING; CONTROL SYSTEM; MATHEMATICAL MODELING; NUCLEAR POWER PLANT;

EID: 0034252764     PISSN: 07351933     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0735-1933(00)00160-3     Document Type: Article

References (8)

1. A simple dynamic model and transient simulation of the nuclear power reactor on microcomputers
2. Development of transient simulation code for pressurized water reactors
3. Simulation of a pressurized water nuclear power plant in the DESIRE simulation language