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

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

Tarantino M.1, Forgione N.3, Martelli D.3, Barone G.3, Di Piazza I.1, Agostini P.1, Gaggini P.2
1Italian National Agency for New Technologies, Energy and Sustainable Economic Development, Brasimone, Italy
2Italian National Agency for New Technologies, Energy and Sustainable Economic Development, Bologna, Italy
3University of Pisa, Pisa, Italy

Abstract

The CIRCE pool facility equipped with 1 MW fuel pin bundle simulator was used to study thermal hydraulics of the primary system of HLM cooled pool reactor. The lead-bismuth eutectic (LBE) flow is provided by a gas lift system. There are LBE-air heat exchanger and decay heat removal system. Both experimental and analytical studies of thermal hydraulics including PLOHS+LOF accident were carried out. Comparison of experimental and analytical data is presented.

Keywords
fast reactor, pool design, lead-bismuth eutectic, thermal hydraulics, CIRCE test facility, fuel pin bundle simulator, accidents, experimental and analytical studies

Article Text (PDF)

References

UDC 621.039.572

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2016, issue 1, 1:8