Simulation of subcooled flow instability for high flux research reactors using the extended code ATHLET

Nuclear Engineering and Design

Volumn 207, Issue 2, 2001, Pages 163-180

  Hainoun, A ^a   Schaffrath, A ^b  

^a DEPARTMENT OF MOLECULAR BIOLOGY AND BIOTECHNOLOGY   (Syrian Arab Republic)

^b INSTITUTE OF ION BEAM PHYSICS AND MATERIALS RESEARCH   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; BOILING LIQUIDS; COMPUTATIONAL METHODS; COOLANTS; COOLING; MATHEMATICAL MODELS; NUCLEAR REACTOR ACCIDENTS; PRESSURE DROP; THERMODYNAMICS;

HIGH FLUX RESEARCH REACTORS;

RESEARCH REACTORS;

EID: 0035400875     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(00)00410-6     Document Type: Article

References (11)

1. Fundamental studies of safety related thermohydraulics of natural circulation boiling parallel channel flow systems under startup conditions (mechanism of geysering in parallel channels)
2. The rate of growth (condensation) of vapor bubbles in a turbulent flow
3. Conceptual design loss-of-coolant accident analysis for the advanced neutron source reactor
4. Modeling of void formation in the subcooled boiling regime in the ATHLET code to simulate flow instability for research reactors
5. ATHLET Mode 1.2 Cycle A, User's Manual
6. Calculation of void volume fraction in the subcooled and quality regions
7. 2