[en] The stochastic neutron flux fluctuations in boiling water reactors represent a significant source of information about thermohydraulic parameters. In this paper, experimental results of in core measurements are described together with the development of a theoretical model. (author)
Source
Williams, M.M.R. (ed.) (Queen Mary Coll., London (UK). Dept. of Nuclear Engineering); Progress in Nuclear Energy. New Series; v. 1(2-4); p. 187-203; ISBN 0 08 0221572; 
; 1977; p. 187-203; Pergamon Press Ltd; Oxford; Reactor noise - SMORN II; Gatlinburg, USA; 19 - 23 Sep 1977
; 1977; p. 187-203; Pergamon Press Ltd; Oxford; Reactor noise - SMORN II; Gatlinburg, USA; 19 - 23 Sep 1977