Loss of both offsite and onsite power

Lack of sufficient backup generators

Inadequate training of the plant personnel

Failure of the reactor protection systems

Neutron flux and current are both scalars; fluence is a vector indicating the

net number of neutrons per unit area over time.

Neutron fluence is the flux divided by the time; neutron current is a vector given by the dot product of neutron density and velocity

Neutron flux is a

scalar proportional to neutron density and speed; neutron current is a

vector given by the product of neutron density and velocity

Each neutron contributes to the temperature of the moderator

Flux only determines how fast neutrons move, not the power

Neutron flux governs the fission rate, which determines the amount of energy released

1.496 × 10^-11 J

1.502 × 10^-17 J

8.415 × 10¹⁸ J