Author/Authors :
Rosselet، Marc نويسنده , , Marc; Chawla، نويسنده , , Rakesh; Williams، نويسنده , , Tony ، نويسنده ,
Abstract :
Accidental water ingress in pebble-bed type, high temperature reactor (HTR) cores can result
in large positive reactivity changes and in consequent reductions in shutdown margins. since such systems
generally tend to be undermoderated. The prediction of such effects, which are particularly important in
the case of low-enriched uranium (LEU) fuel, is a challenging task due to the complex interaction of, on
the one hand, an increase in moderation and, on the other, a reduction in neutron streaming. Experiments
have been carried out at the PROTEUS facility of the Paul Scberrer Institute in Switzerland to quantify
water ingress effects in LEU-HTR systems and to assess the performance of certain deterministic codes in
predicting them. In order to simulate water ingress, polyethylene rods were inserted between the pebbles of
various detenninistic configurations and a pulsed-neutron-source technique was used to measure the
variation of keff with the stepwise removal of these polyethylene rods. Generation time, as well as
reactivity measurements, were compared with calculations, made with various types of streaming
corrections, for three different subcritical states