Xenon-135 (135Xe) is an unstable isotope of xenon with a half-life of 9.14 hours, decaying to long-lived caesium-135. 135Xe is a fission product and it is the most powerful known neutron-absorbing nuclear poison (2 million barns; up to 3 million barns under reactor conditions), with a significant effect on nuclear reactor operation. The yield of xenon-135 from fission is about 6.6% (uranium) or 7.4% (plutonium), the great majority from iodine-135. It is normal for fission products to be formed in such a chain of decays.
135Xe effects on reactor restart
In a typical nuclear reactor fueled with uranium-235, the presence of 135Xe as a fission product presents designers and operators with problems due to its large neutron cross section for absorption. Because absorbing neutrons can impair a nuclear reactor's ability to increase power, reactors are designed to mitigate this effect and operators are trained to anticipate and react to these transients. This practice dates to the first fission piles, constructed by the Manhattan Project during the Second World War. Enrico Fermi suspected that 135Xe would act as a powerful neutron poison and followed the advice of Emilio Segrè by contacting his student Chien-Shiung Wu. Wu's unpublished paper on 135Xe verified Fermi's guess that it absorbed neutrons and was the cause of the disruptions to the B Reactor then in use at Hanford, Washington to breed plutonium for the American implosion bomb. During periods of steady state operation at a constant neutron flux level, the 135Xe concentration builds up to its equilibrium value for that reactor power in about 40 to 50 hours. When the reactor power is increased, 135Xe concentration initially decreases because the burn up is increased at the new higher power level. Because 95% of the 135Xe production is from decay of 135I, which has a 6.58 hour half-life, the production of 135Xe remains constant; at this point, the 135Xe concentration reaches a minimum. The concentration then increases to the new equilibrium level (more accurately steady state level) for the new power level in roughly 40 to 50 hours. During the initial 4 to 6 hours following the power change, the magnitude and the rate of change of concentration is dependent upon the initial power level and on the amount of change in power level; the 135Xe concentration change is greater for a larger change in power level. When reactor power is decreased, the process is reversed. Iodine-135 is a fission product of uranium with a yield of about 6% (counting also the 135I produced almost immediately from decay of fission-produced tellurium-135). This 135I decays with a 6.58 hour half-life to 135Xe. Thus, in an operating nuclear reactor, 135Xe is being continuously produced. 135Xe has a very large neutron absorption cross-section, so in the high-neutron-flux environment of a nuclear reactor core, the 135Xe soon absorbs a neutron and becomes effectively stable 136Xe. (The half-life of 136Xe is >1021 years, and it is not treated as a radioisotope.) Thus, in about 50 hours, the 135Xe concentration reaches equilibrium where its creation by 135I decay is balanced with its destruction by neutron absorption. When reactor power is decreased or shut down by inserting neutron-absorbing control rods, the reactor neutron flux is reduced and the equilibrium shifts initially towards higher 135Xe concentration. The 135Xe concentration peaks about 11 hours after reactor power is decreased. Since 135Xe has a 9.14 hour half-life, the 135Xe concentration gradually decays back to low levels over 72 hours. The temporarily high level of 135Xe with its high neutron absorption cross-section makes it difficult to restart the reactor for several hours. The neutron-absorbing 135Xe acts like a control rod, reducing reactivity. The inability of a reactor to be started due to the effects of 135Xe is sometimes referred to as xenon-precluded start-up, and the reactor is said to be "poisoned out". The period of time that the reactor is unable to overcome the effects of 135Xe is called the "xenon dead time". If sufficient reactivity control authority is available, the reactor can be restarted, but the xenon burn-out transient must be carefully managed. As the control rods are extracted and criticality is reached, neutron flux increases many orders of magnitude and the 135Xe begins to absorb neutrons and be transmuted to 136Xe. The reactor burns off the nuclear poison. As this happens, the reactivity and neutron flux increases, and the control rods must be gradually reinserted to counter the loss of neutron absorption by the 135Xe. Otherwise, the reactor neutron flux will continue to increase, burning off even more xenon poison, on a path to runaway criticality. The time constant for this burn-off transient depends on the reactor design, power level history of the reactor for the past several days, and the new power setting. For a typical step up from 50% power to 100% power, 135Xe concentration falls for about 3 hours. Xenon poisoning was a contributing factor to the Chernobyl disaster; during a run-down to a lower power, a combination of operator error and xenon poisoning caused the reactor thermal power to fall to near-shutdown levels. The crew's resulting efforts to restore power placed the reactor in a highly unsafe configuration. A flaw in the SCRAM system inserted positive reactivity, causing a thermal transient and a steam explosion that tore the reactor apart. Reactors using continuous reprocessing like many molten salt reactor designs might be able to extract 135Xe from the fuel and avoid these effects. Fluid fuel reactors cannot develop xenon inhomogeneity because the fuel is free to mix. Also, the Molten Salt Reactor Experiment demonstrated that spraying the liquid fuel as droplets through a gas space during recirculation can allow xenon and krypton to leave the fuel salts. Removing 135Xe from neutron exposure improves neutron economy, but causes the reactor to produce more of the long-lived fission product 135Cs. The long lived (but 76000 times less radioactive) caesium-135 condenses in a separate tank after the decay of 135Xe, and is physically separate from the 30.05-year-half-life caesium-137 (137Cs) produced in the fuel, and it is practical to handle them separately (fission yield is approximately 6% for both).
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