Passive containment cooling for next generation water cooled reactors

Book · Mon Jul 01 00:00:00 EDT 1996

OSTI ID:248171

Cheng, X ^[1]; Erbacher, F J; Neitzel, H J ^[2]

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1. Technische Univ. Karlsruhe (Germany). Inst. fuer Stroemungslehre und Stroemungsmaschinen
2. Forschungszentrum Karlsruhe (Germany). Inst. fuer Angewandte Thermo- und Fluiddynamik

For next generation water cooled reactors passive safety systems should be investigated in respect to their feasibility and functional performance. The Research Center Karlsruhe and the Technical University Karlsruhe have proposed a composite containment concept which copes with severe accidents. One essential of this concept is the decay heat removal from the containment by natural air convection and thermal radiation in a passive way. To determine the coolability of such a passive cooling system and to study the physical phenomena involved, experimental separate-effects investigations are under way in the PASCO test facility which is a one-sided heated rectangular channel. In addition numerical calculations are performed by using the I-D code PASCO and the 3-D code FLUTAN. Experimental results in respect to the distribution of the fluid velocity, the fluid temperature and the wall temperature are presented. A comparison is made between the experimental data and code predictions. The deficiencies and needs for further research are being discussed. From the results achieved so far it has been found that the passive containment cooling by natural air convection coupled with thermal radiation is a very promising concept.

• OSTI ID: 248171
• Report Number(s): CONF-960306-; ISBN 0-7918-1226-X; TRN: 96:014855
• Resource Relation: Conference: ICONE 4: ASME/JSME international conference on nuclear engineering, New Orleans, LA (United States), 10-13 Mar 1996; Other Information: PBD: 1996; Related Information: Is Part Of ICONE-4: Proceedings. Volume 2: Advanced reactors; Rao, A.S. [ed.] [General Electric Nuclear Engineering, San Jose, CA (United States)]; Duffey, R.B. [ed.] [Brookhaven National Lab., Upton, NY (United States)]; Elias, D. [ed.] [Commonwealth Edison, Downers Grove, IL (United States)]; PB: 637 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
WATER COOLED REACTORS
CONTAINMENT SYSTEMS
COOLING
COOLING SYSTEMS
AIR FLOW
NATURAL CONVECTION
REACTOR ACCIDENTS
AFTER-HEAT REMOVAL
TEST FACILITIES
REACTOR SAFETY EXPERIMENTS
COMPUTERIZED SIMULATION
COMPARATIVE EVALUATIONS
EXPERIMENTAL DATA
THEORETICAL DATA