PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

Forgione N.1, Martelli D.1, Del Nevo A.2, Di Piazza I.2
1University of Pisa, Pisa, Italy
Italian National Agency for New Technologies, Energy and Sustainable Economic Development , Brasimone, Italy

Abstract

Method of coupling RELAP5/Mod3.3 with CFD code was developed for simulation of thermal hydraulics in lead-bismuth test facility NACIE designed to qualify components and procedures relevant to HLM nuclear technologies. NACIE facility includes lead-bismuth loop with the heat source (fuel pin simulator) and gas lift device to promote liquid metal flow in the loop. Tests are performed varying gas flow rate and electric power supplied to the heater. The numerical model is capable of simulating both natural and assisted circulation tests.

Keywords
lead-bismuth coolant, thermal hydraulics, computer codes, NACIE test facility, lead-bismuth loop, comparison of experimental and calculation results

Article Text (PDF)

References

UDC 621.039.5 : 004.94

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, issue 3:8, 2015