Resonance Escape Probability
The fast fission factor determined the number of fast neutrons produced by fissions at all energies, but in thermal reactors the bulk of fissions occurs at thermal energies and it is obvious these fission neutrons have to be thermalized. But during this thermalisation neutrons may collide not only with moderator nuclei, but also with fuel nuclei. Unfortunately, especially 238U exhibits resonance behaviour between the fast region and the thermal region. While the neutrons are slowing down through the resonance region of 238U, which extends from about 6 eV to 200 eV, there is a chance that some neutrons will be captured. The probability that a neutron will not be captured in entire resonance region is called the resonance escape probability.
See also: Nuclear Resonance
p ~ 0.75
It is obvious the resonance escape probability is strongly influenced by the arrangement and the geometry of the reactor core. In a homogenous reactor core, where fuel nuclei are surrounded by many of moderator nuclei, there is a significantly higher probability, that the resonance neutron will collide with the fuel nucleus. Therefore in homogenous reactor cores, the resonance escape probability is lower than in heterogeneous cores.
On the other hand, in a heterogeneous reactor core, all the fuel nuclei are in fuel pellets that are encapsulated within a fuel rod. This arrangement increases the probability, that the fast neutron will escape the fuel matrix. The neutron slows down in the moderator where there are no atoms of 238U and 240Pu present. Therefore in heterogeneous reactor cores, the resonance escape probability is significantly higher than in homogenous cores.
The resonance escape probability for all resonances can be calculated according to following equation:
The integral in this expression is called the effective resonance integral Ιeff. In practical situations, this integral strongly depends on the geometry of the unit cell. The geometry of the core strongly influences the spatial and energy self-shielding, that take place primarily in heterogeneous reactor cores. This phenomenon causes a significant increase in the resonance escape probability (“p” from four factor formula) in comparison with homogeneous cores. Without the spatial self-shielding provided by the separation of fuel and moderator, values of keff = 1 are possible with natural uranium fuel only if heavy water is used as the moderator. In the literature empirical relations have been developed for the effective resonance integral of the following form:
where the resonance integrals are in barns, rho is the material density in g/cm3, and D is the fuel rod diameter in cm. This equation is valid for isolated rods with diameter higher than 0.2cm.
For tightly packed lattice in the fuel assembly self-shielding increases somewhat through what is called a Dancoff correction.
From the equation it is obvious, the resonance escape probability is dependent also on the moderator-to-fuel ratio – NM / NF (the term before Ieff). With the change of the moderator-to-fuel ratio changes also the neutron flux spectrum in the reactor core. Most of light water reactors are designed as so called undermoderated and the neutron flux spectrum is slightly harder (the moderation is slightly insufficient) than in an optimum case. But this design provides important safety feature. This feature will be discussed in following section.
Main operational changes, that affect this factor:
- Change in the moderator temperature. It is known, the resonance escape probability is dependent also on the moderator-to-fuel ratio. As the moderator temperature increases the ratio of the moderating atoms (molecules of water) decreases as a result of the thermal expansion of water. Its density simply decreases. This, in turn, causes a hardening of neutron spectrum in the reactor core resulting in higher resonance absorption (lower p). Decreasing density of the moderator causes that neutrons stay at a higher energy for a longer period, which increases the probability of non-fission capture of these neutrons. This process is one of two processes, which determine the moderator temperature coefficient (MTC). The second process is connected with the leakage probability of the neutrons. The moderator temperature coefficient must be for most PWRs negative, which improves the reactor stability, because a reactor core heating causes a negative reactivity insertion.
- Change in the fuel temperature. The second operational change, which affects the resonance escape probability, is connected with the phenomenon usually known as the Doppler broadening. The effect of the Doppler broadening is generally considered to be even more important than a negative moderator temperature coefficient. Especially in case of reactivity initiated accidents (RIA), the Doppler coefficient of reactivity would be the first and most important effect in the compensation of the inserted positive reactivity. The time for heat to be transferred to the moderator is usually measured in seconds, while the Doppler coefficient is effective almost instantaneously. The Doppler broadening with the process of self-shielding causes, that the Doppler coefficient (or the fuel temperature coefficient) is for all power reactors always negative. Therefore an increase in the fuel temperature promptly causes an increase in the resonance integral (Ieff), which, in turn, causes a negative reactivity insertion. It is of the highest importance in the reactor safety.