Author/Authors :
Binh، نويسنده , , Do Quang; Huy، نويسنده , , Ngo Quang; Lan، نويسنده , , Nguyen Phuoc; Thong، نويسنده , , Ha Van ، نويسنده ,
Abstract :
This article presents a new method for determining the radial distribution
of fuel burn-up by measuring neutron counts from the reactor core at
subcritical states by detectors of the reactor control system. Initial results of an
experiment carried out for some fuel elements of the Dalat reactor are also
introduced.