Patent Number: 042004918
Section: claims

1. A device for detecting the residual gamma radiation indicative of the recent power distribution of a used nuclear reactor fuel element comprising the combination of: a radiation detector of the type for decoding information available as to activated isotope emission along a filament wire; and  a wand, said wand being of sufficiently small diameter to be removably juxtaposed along said nuclear reactor fuel element and to be analyzed by said radiation detector, said wand comprising:  (a) a filament wire longitudinally disposed within a tubular housing of said wand composed of an activant medium, said activant medium being operative to register incident neutron flux as a long half life activated isotope along the length of said filament wire; and  (b) a sheath of converter material encasing said filament wire, said sheath being operative to produce neutron flux proportional only to incident gamma radiation in excess of a predetermined energy threshold emitted by said fuel element defined by the gamma emission of La-140 for registering said neutron flux in said filament wire as a spatial distribution of a long half life activated isotope which spatial distribution is directly proportional to the spatial distribution of fission products of said nuclear reactor fuel element.  providing a sheathing of a converting medium about a filament wire of an activant medium to form a wand, said converting medium being operative to selectively produce neutron flux proportional only to incident gamma radiation above a preselected energy threshold, said activant medium being operative to register incident neutron flux as a long half life activated isotope;  after a cooling period following shutdown of a nuclear reactor, juxtaposing said wand along a nuclear reactor fuel element within said nuclear reactor fixed in relation to said fuel element for a sufficient period to allow gamma fission products of La-140 to cause neutron flux generation within said converter medium and further to allow said neutron flux so generated incident upon said filament wire to register in said filament as a spatial distribution of a long half life activated isotope, which spatial distribution is directly proportional to said fission products spatial distribution; thereafter  removing said wand from said nuclear reactor; and thereafter  detecting radiation of said long half life activated isotope to identify the location and intensity of said activated isotope for mapping the power distribution history of the nuclear reactor fuel element. 2. A detecting device according to claim 1 wherein said filament is about 2 mm in diameter and said casing is about 10 mm in diameter. 3. A power distribution detecting device according to claim 1 wherein said converter medium is beryllium oxide. 4. A power distribution detecting device according to claim 1 wherein said neutron flux activant medium is a material having a neutron activation cross section of greater than about ten barns and whose activated isotope emits gamma or beta radiation with an energy greater than about 50,000 electron volts with a half life of greater than about one hour. 5. A power distribution detecting device according to claim 4 wherein said neutron flux activant medium comprises a member of the group consisting of gold, silver, manganese and lutetium. 6. A method for analyzing the recent power distribution of a used nuclear reactor fuel element comprising the steps of: