Abstract
The measurement of pulsed neutron fluxes may be realized by a new method presented in this paper. The energy of the fissions induced in a uranium ( 235U or 238U) thread is measured, quasi-adiabatically, by recording its temperature through the change of its resistivity. We first review the theoretical aspects; then we go through the realization of the gauges, and finally we give the experimental results obtained for the diagnostics of a pulsed reactor. Measurements performed on the same reactor, CALIBAN, but running on two different modes - pulsed mode, using fissile resistors, and steady state, using fission chambers - show that its spectrum does not change between these two modes.
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