Method and apparatus for measuring subchannel voids in a light water reactor test fuel assembly
AssigneeGeneral Electric Company
InventorsLeroy M. Shiraishi, Donald A. Wilhelmson, Bruce Matzner
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AssigneeGeneral Electric Company
InventorsLeroy M. Shiraishi, Donald A. Wilhelmson, Bruce Matzner
Estimating the term…
A light water nuclear reactor test assembly for emulating the performance of a nuclear boiling water reactor fuel bundle and measuring the subchannel void fraction in the two-phase region of the emulated fuel bundle by gamma ray attenuation is disclosed. The emulated fuel bundle has individual emulated nuclear fuel rods typically heated by individual electrical currents instead of nuclear reaction and are cylindrically hollow. A gamma-emitting source is placed on a probe and mounted for vertical excursion inside a selected emulated hollow fuel rod. A detector, typically a Geiger-Muller counter, is placed for corresponding vertical excursion inside another and preferably adjacent fuel rod. Gamma radiation from the source to the detector through the walls of the emulated fuel rods is measured. Preferably, both detector and source are collimated so that the detector does not receive gamma ray scattering from the interior of the test assembly. Preferably the detector is both collimated as to the gamma rays emitted by the source and cooled by an overlying heavy metal shield, this shield conducting heat from the vicinity of the detector to a water-cooled line passing through the metal shield. By utilizing a relatively low energy neutron source, the gamma signal at the detector can be directly attributed to gamma absorption of the liquid moderator fraction present between the emulated fuel rod containing the detector and the emulated fuel rod containing the source.
In combination with a nuclear fuel bundle test assembly having:
In combination with a nuclear fuel test bundle assembly having:
Dependencies are inferred from the claim text.