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

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

Losa E.1, Kostal M.2, Rataj J.2, White T.1, Katovsky K.1
1Czech Technical University in Prague, Praha, Czech Republic
2Research Centre Rez, Praha, Czech Republic

Abstract

In the analysis of experimental capabilities for metal cooled reactors, the calculation of neutron flux in irradiation module filled with lead and lead-bismuth was performed and the sensitivity analysis with the influence of nuclear data libraries was carried out. Research reactors, VR-1 and LR-0 were used as the neutron sources. Each reactor is offering the specific features for the possible future experiments and the calculation models were validated on different experiments in the past.

Keywords
small size reactors, fast reactors, heavy liquid metal coolants, analytical studies, experimental capabilities, neutron sources

Article Text (PDF)

References

UDC 621.039.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2016, issue 1, 1:9