Method and apparatus for measuring reactivity of fissile materia

Details Method and apparatus for measuring reactivity of fissile materia Method and apparatus for measuring reactivity of fissile materia

1982-09-07

1985-01-15

Walsh, Donald P.

Induced nuclear reactions: processes, systems, and elements

Testing, sensing, measuring, or detecting a fission reactor...

Flux monitoring

376257, 376245, G21C 1700

Patent

active

044938101

ABSTRACT:
Given are a method and apparatus for measuring nondestructively and non-invasively (i.e., using no internal probing) the burnup, reactivity, or fissile content of any material which emits neutrons and which has fissionable components. No external neutron-emitting interrogation source or fissile material is used and no scanning is required, although if a profile is desired scanning can be used. As in active assays, here both reactivity and content of fissionable material can be measured. The assay is accomplished by altering the return flux of neutrons into the fuel assembly. The return flux is altered by changing the reflecting material. The existing passive neutron emissions in the material being assayed are used as the source of interrogating neutrons. Two measurements of either emitted neutron or emitted gamma-ray count rates are made and are then correlated to either reactivity, burnup, or fissionable content of the material being assayed, thus providing a measurement of either reactivity, burnup, or fissionable content of the material being assayed. Spent fuel which has been freshly discharged from a reactor can be assayed using this method and apparatus. Precisions of 1000 MWd/tU appear to be feasible.

REFERENCES:
patent: 3636353 (1972-01-01), Untermyer
patent: 3755675 (1973-08-01), Stepan
patent: 4335466 (1982-06-01), Lee
Lee, David M., Passive & Active Neutron Methods for Assay/Verification of Spent Fuel, Mar. 15-30, 1982.
Keepin, Robert G., Nuclear Safeguards R&D LA-8373-PR, Sep. 1980.

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