An improved neutron monitoring and startup source for a thermal nuclear reactor including a fast neutron emitting material encapsulated within a cladding substantially black to thermal neutrons. In another embodiment the inventive source, or any source, is advantageously affixed to movable control elements so as to reside out of the reactor core for periods of high neutron flux.
A secondary source positioning mechanism for a fuel assembly in a nuclear reactor locates an individual one of the secondary sources in a respective guide thimble of the fuel assembly aligned with an opening defined through the upper core plate which overlies the fuel assembly. The positioning mechanism has a tapered locating boss which registers with a chamfer on the lower side of the core plate about one of its openings and a resilient holddown device which resiliently couples the upper end of a rod containing the secondary source to the locating boss in a manner which restrains the upper end of the rod in the lateral direction and positions the secondary source rod in the axial direction.
An accurate determination of whether the reactivity of individual spent fuel assemblies exceeds a threshold value is made while each assembly is being transferred from the reactor core to the fuel storage rack. The reactivity of each spent assembly is compared with that of a standard assembly by comparing the subcritical multiplication resulting from insertion of a neutron source into the assemblies. The measuring apparatus preferably exteriorly resembles a control element assembly wherein one control element finger containing the neutron source is yoked to another finger containing a neutron detector. The fingers are simultaneously inserted into a standard assembly having a known reactivity and subcritical multiplication, and the resulting flux signal is recorded. Thereafter spent assemblies are sequentially measured to assure that no assembly having a subcritical multiplication greater than that of the standard is ever placed into the storage rack.
A gas cooled nuclear reactor may have a stationary pile of spherical operating elements. The reactor may be controlled and shut down by absorber rods displaceable in channels of the side reflector. The neutron sources required for the safe start-up of such pellet pile reactors, which in the case of higher capacity pile reactors are installed in bores of the side reflector, are arranged in the stationary pile, where they are more effective and do not occupy positions in the side reflector. They may be located in one or more graphite elements having the same diameter as the operating elements. These elements may be introduced and removed into and from the core together with the operating elements and remain stationary in operation.
In-core nuclear instrumentation for a fast breeder reactor includes a neutron flux measuring unit disposed in a control rod assembly, whereby it is possible to measure a change in in-core neutron flux reliably and highly accurately without requiring a major modification in core design.