NDA OF HTGR FUEL USING THE RANDOM DRIVER*

Year
1974
Author(s)
J.E. Foley - Los Alamos National Laboratory
T.L. Atwell - Los Alamos National Laboratory
Abstract
This paper discusses the use of an active neutron source interrogation system known as Random Driver for the nondestructive assay of uranium in HTGR (in-process) fuel particles. The system employs a random source of fast neutrons consisting of four AmLi (oc, n) sources to induce fissions in the 235|j present. Fission events are detected by coincidence counting of prompt-fission neutrons using a pair of fast plastic scintillation detectors. A PDP-11/05 minicomputer is used for data acquisition and reduction. Details of the assay system and preliminary results on the assay of HTGR fuel particles are presented.