Method and apparatus for measuring burn-up of nuclear fuel in a

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G21C 1706

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active

040240177

ABSTRACT:
The burn-up of nuclear fuel in a reactor is measured by producing two measuring signals, each of which is a function of the flux of a different neutron energy or group, and comparing the two signals to compute the burn-up.

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Glasstone & Sesonske, "Nuclear Reactor Engineering," Van Nostrand Co., Princeton, N.J., pp. 695-699.

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