학술논문

Estimation of Reactivity and Average Fuel Temperature of a Pressurized Water Reactor Using Sliding Mode Differentiator Observer
Document Type
Periodical
Source
IEEE Transactions on Nuclear Science IEEE Trans. Nucl. Sci. Nuclear Science, IEEE Transactions on. 60(4):3025-3032 Aug, 2013
Subject
Nuclear Engineering
Bioengineering
Inductors
Fuels
Neutrons
Temperature measurement
Coolants
Observers
Robustness
Delayed neutron precursor group
pressurized water reactor (PWR)
reactivity
second order sliding mode (SOSM)
uniform robust exact differentiator (URED)
Language
ISSN
0018-9499
1558-1578
Abstract
This paper is about development of a uniform robust exact differentiator observer for estimation of the change in reactivity and average fuel temperature of a pressurized water reactor. The change in reactivity and average fuel temperature are important parameters in a nuclear power reactor, but there is no physical sensor available to measure these parameters directly. Therefore an observer is needed to estimate these parameters. There are different linear and non linear techniques to estimate the parameters with their own benefits and drawbacks. We have used uniform robust exact differentiator observer which is based on second order sliding mode and remains independent of initial conditions. This estimation is done under varying load conditions so that the estimated change in reactivity has the effect of control rod motion, coolant temperature and fuel temperature. For the proposed estimation scheme the measurement data of an actual plant is used. These measurements include normalized neutron density, coolant temperature and control rod position.