Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis

• Published in: Nuclear engineering and design Vol. 236; no. 13; pp. 1422 - 1444
• Main Authors: Ma, Weimin, Bubelis, Evaldas, Karbojian, Aram, Sehgal, Bal Raj, Coddington, Paul
• Format: Journal Article
• Language: English
• Published: Amsterdam Elsevier B.V 01.07.2006; Elsevier
• Subjects: Applied sciences; Controled nuclear fusion plants; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Fuels; Installations for energy generation and conversion: thermal and electrical energy; Nuclear fuels; Computation code; Natural circulation; Steady state; Pump; Transients; Nuclear reactor; Hybrid reactor; Test facility; Transmutation; Bismuth; Thermohydraulics; Safety; Heat sink
• ISSN: 0029-5493; 1872-759X; 1872-759X
• DOI: 10.1016/j.nucengdes.2006.01.006

TALL is a medium-size experimental facility constructed at KTH, to study the steady-state and transient thermal-hydraulics performance of LBE-cooled reactors, with the primary purpose of supporting the European transmutation demonstration (ETD) using LBE-cooled accelerator-driven systems (ADS). This paper presents the results of transient experiments performed on the TALL test facility, whose aim is to provide a data base for validation of computer codes which may be used for the analysis of the safety of those systems. This paper also presents the results of the post-test calculations, carried out at PSI, using the TRAC/AAA code. The transient experiments performed include the loss of heat sink, the loss of pump, the loss of both primary and secondary flows, overpower, overcooling, heater trip, and the operational transients of start-up and shut-down. The experimental results show the excellent natural circulation performance of a LBE-cooled system which should contribute to a good safety performance. The TRAC/AAA calculations provide results which agree well with the experimental data.