Reactor Theory (II) Flashcards
topic 4
Neutron multiplication
neutrons in current generation divided by neutrons in previous generation; critical k=1, supercritical k>1, subcritical k<1
infinite multiplication factor formule
fast fission * resonance escape probability* thermal utilization * reproduciton
fast fission
number of neutrons below fast fission threshold energy divided by number of initial fission neutrons
resonance escape probability
number of neutrons below resonance threshold energy divided by number of neutrons below fast fission threshold energy
thermal utilization
number of thermal neutrons absorbed in fuel divided by number of neutrons below resonance threshold energy
reproduction factor
average number of fission neutrons produced divided by number of thermal neutrons absorbed in fuel
effective multiplication factor formula
infinite fomula * thermal and fast neutron non-leakage
fast non-leakage
number of fast neutrons that don’t leak divided by number of fast neutrons produced by all fissions
thermal non-leakage
number of thermal neutrons that don’t leak from reactor divided by number of neutrons that reach thermal energies
Reactivity
departure from criticality; (Keff - 1) divided by Keff
Neutron poisons
absorbs neutrons that don’t contribute to any return; Xe-139 for 72 hours post shutdown and Sm-149 no decay after shutdown
Differential rod worth
reactivity change per movement of control rod
Integral rod worth
total reactivity worth of rod at withdraw positions