Environmental Engineering Reference
In-Depth Information
Figure 20. Schematic presentation of Nuclear Power Plant.
3.6.2. Resilience Indicators
3.6.2.1. Single Indicator Change
Resilience indicators for nuclear power plant are defined as the integral of
the sudden change of the respective indicator. In our case we will define
following indicators:
3.6.2.1.1. Change of the Average Neutron Flux
The average thermal neutron flux is parameter which corresponds to the
energy produced in the nuclear reactor core. The thermal neutron flux is
subject to the time change and is controlled by the nuclear reactor control
system.. The sudden change of neutron flux is the result of the change of
reactor core reactivity. This change may be produced by the control rod
system which lead to the increase of the neutron flux in the reactor core..
There are potentially different control rods absorption. In this exercise we deal
only with one change of neutron flux due to the sudden absorbent insertion.
Resilience Index due to sudden change of neutron flux will be
tt
1
R
[100
q
]
dt
(4)
NF
NF
tt
0
where
