Xenon poisoning is neutron removal by xenon-135, which reduces reactor reactivity. Its important precursor is iodine-135. At a long-established constant neutron flux, production through precursor decay is balanced by xenon radioactive decay and neutron capture. A steady model must account for that additional absorber in its neutron balance.
After a rapid removal of the imposed neutron flux, capture removal becomes small immediately, while the existing iodine population continues supplying xenon. The xenon population can therefore rise before eventually falling as the precursor reservoir is exhausted. The resulting extra negative reactor reactivity is a delayed effect, rather than an instantaneous disappearance of the absorber when nuclear fission stops.
An intermediate post-shutdown maximum is possible. This explains why the reactivity associated with a previously operating system can differ substantially from its long-time shutdown value. The population model below quantifies that mechanism; a population maximum is not by itself an operating or restart prescription.
Let be the constant precursor production rate per volume. Here is the precursor yield per nuclear fission, and and are number densities. At a steady state,
For fixed homogeneous coefficients and spatial shape, the reactivity contribution of an added absorption coefficient is . Thus the model gives
When capture removal dominates xenon radioactive decay, , and hence
The limit is independent of the xenon neutron absorption cross section: at high neutron flux, nearly every xenon atom supplied by the precursor ultimately consumes a neutron. The assumptions include constant pre-shutdown neutron flux, sufficient time for precursor and xenon equilibrium, the supplied single-precursor model with no direct xenon fission source, and fixed parameters for translating absorption into reactor reactivity.
The general solution contains both decay of the initial xenon and continued feeding from the initial iodine. Use for removal of the flux, and retain as the pre-shutdown value in the initial conditions. Neglect post-shutdown nuclear fission and neutron capture. Then
Multiply this first-order linear differential equation by the integrating factor and integrate:
With the preceding steady initial conditions, and , this is
If , the coefficient of the first exponential term is small compared with the coefficients of the feeding term, yielding
This approximation neglects the finite initial xenon population and is consequently not a small relative error at , where its value is zero while the exact is positive. The exact expression supplies the initial value and satisfies . For equal nuclear decay constants, the continuous limit of the exact solution is .
The approximate population peaks about after flux removal. Differentiate the preceding difference of exponentials. The stationary condition is
so for distinct nuclear decay constants,
Using hours consistently,
and therefore
The approximate population is positive for , starts at zero, tends back to zero and has only this one stationary point, so it is a maximum.
Figure 1.
Normalized precursor-fed absorber response after source removal
. Details.
The delayed maximum corresponds to a delayed maximum in the magnitude of the absorber's negative contribution to reactor reactivity, within the fixed model. It does not determine a permissible restart time, which would require information absent here. The estimate also inherits the high-flux initial-population approximation of part (ii); the exact solution can peak at a different time when that approximation is unsuitable.

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