Non-leakage factor

A is the fraction of neutrons which are not lost through leakage to the surroundings the non-leakage factor). In order to minimize the neutron leakage, the reactor core is surrounded with a neutron reflector which for thermal neutrons in LWRs is water (graphite or beryllium are sometimes used in other reactor designs) for fast neutron reflection iron is frequently used. 

For the following neutron life cycle, calculate the fast fission factor, fast non-leakage probability, resonance escape probability, thermal non-leakage probability, thermal utilization factor, reproduction factor, Keff and core reactivity. 

The amount of water affects Kgff through thermal utilization factor, resonance escape probability, fast fission factor, and the non-leakage probabilities as shown in Figure 6.3(a), Of these factors, thermal utilization factor and resonance escape probability are affected more strongly. 

Another popular rectifier circuit is the full-controlled three-phase full wave rectifier. This circuit is more expensive because six thyristors are used. However, the form factor is much better, about 1.01, and the ripple current is 360 Hz. The higher frequency makes it easier to filter the ripple current. The half-controlled three-phase bridge rectifier circuit may require armature current smoothing reactors to reduce the ripple current. Another problem associated with the non-uniform DC input to the motor is the commutation. The motor must commutate under a relatively high degree of leakage reactance. 

With regard to long-lived radionuclides that show a low decontamination factor on the purification system (e. g. Cs in PWR primary coolant containing LiOH), the purification constant e also has to include the coolant losses via water exchange or leakages. On the other hand, fission products which form insoluble compounds or can be adsorbed onto non-dissolved corrosion product particulate matter may be removed from the coolant by plate-out onto the primary circuit surfaces. These and other parameters which are liable to affect the activity concentrations of the radionuclides in the primary coolant are the reason why a trustworthy calculation of source strengths can only be made using specific radionuclides such as fission product noble gas isotopes and iodine isotopes. 

Non-ideal diode behaviors (reverse leakage, series and shunt resistances, nonideal behavior, reverse breakdown) and the ideality factor. 

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