Investigation of the Applicability of Solid State Detectors for the Determination of Reactor Fuel Burn-Up, Development and Making of a Jumping Spark Counter. Final Report for the Period 14 December 1974 - 31 January 1979

摘要

A method was investigated for the determination of reactor fuel burnup by measuring the spontaneous fission cross sections ratio exp 235 U/ exp 238 U. The method was adopted for the determination of uranium in powdered solid samples. The angular distribution of fission fragments of exp 239 Pu has been measured by means of a polycarbonate solid state nuclear track detector, using a exp 252 Cf neutron source. (Atomindex citation 11:541694)