Shah 2011
Shah 2011
Shah 2011
Abstract--This paper reviews fault detection and diagnosis Before we begin further on discussing diagnostic
techniques and their application in nuclear power plant. Fault is approaches, let us see few of the terminologies which are
an unexpected change or malfunction in the system.Fault widely used in literature:
occurring at a point in the plant may propagate further in the -Failure: Permanent disruption of the system in performing its
system. It is necessary to arrest fault propagation for economy
and safety of plant. For this purpose quick detection of an
desired function
unexpected deviation of process variableis necessary. This -Disturbance: An unknown input adversely affecting
function is achieved with the help of Fault detection and operation
diagnosis unit. Diagnostic unit also assists operators in retaining - Irregularity: Intermittent departure from normal response of
normal and safe state of the system. In this paper,I have the system
mentionedthe characteristic requirements of Fault detection and -Abnormality: Fault or failure constitutes an abnormal event
diagnosis unit and the classification of diagnostic methods. With
the help of Fault detection and diagnosis, it is possible to realize
The rest of the paper is organized as follows: Section II
continuous monitoring of plant which enables diagnosis of describes fundamentals of FDD unit, Section III shows
incipient faults and thus prevents unexpected operational requirements of FDD in NPP and various diagnostic
upsets.Here, I have done case study for two approaches, and I approaches employed in NPP and Section IV concludes the
have observed that use of hybrid approaches for Fault detection paper.
and diagnosis yields quick and accurate assistant to the
operators compared to conventional approaches.
II. FAULT DETECTION AND DIAGNOSIS
Index Terms—Fault detection, Fault identification, Fault A. Classification of faults
isolation, Fault diagnosis, Nuclear power plant
Figure 1.1Classification of Diagnostic methods Based on the statistics from World nuclear association,
INSTITUTE OF TECHNOLOGY, NIRMA UNIVERSITY, AHMEDABAD – 382 481, 08-10 DECEMBER, 2011 3
nuclear power plants are delivering about 6% of world energy processes. Firstly linearization of nonlinear models is done.
and about 15% of world electricity. NPPcan be seen as a Secondly kalman filters are used on these linear models.
thermal power station in which the heat source is one or more General problem with model based methodology is the
nuclear reactors. As in a conventional thermal power station modeling uncertainties due to deviations in the
the heat is used to generate steam which drivessteam turbine parameters,linear approximations achieved for nonlinear
connected to a generator which produces electricity. models can be poor over the wide range andwe need to model
The heart of a NPP is the Nuclear reactor. In its central faults specifically for novelty identifiability.
part, the reactor core‟s heat is generated by controlled nuclear Diagraphs, fault tree, structural and functional methods are
fission. Coolant circuit removes heat energy from the reactor. used forqualitative model based approaches[10]-[15]. Signed
diagraphs represents the cause-effect relations. Arc is directed
Since nuclear fission creates radioactivity, the reactor core is
from cause node to effect node[1]. In case of fault tree, layers
surrounded by a protective shield. This containment absorbs
of nodes exist. Fault tree is constructed by using logic gate
radiation and prevents radioactive material from being
symbols[16]. This method is top down, deductive method
released into the environment. In addition, many reactors are
aimed at analyzing the effects of initiating faults and events
equipped with a dome of concrete to protect the reactor
on a complex process system. Structural approach specifies
against external impacts.
the connectivity information of a system and subsystem while
Apart from NPP and its facilities, health care facilities,
functional approach specifies the output of a unit as a
research institutes, natural sources like civil aircrew, mines,
function of its inputs. Disadvantage with use of qualitative
etc. also suffers from radiation exposure. Data from
models is the generation of spurious solutions. Considerable
International atomic energy agency shows that, for nuclear
work has been done so for reducing spurious solutions like
reactor annual average effective dose for an individual is
generation of latent constraints in signed directed graphs.
1.4mSv; while in civil aircrew effective dose is 3mSv and in
Process history method develops model in terms of
metal mines effective dose is 2.7mSv. Still in NPP,
quantitative or qualitative nature from available data[4], [8],
safety focuses on unintended conditions or events which may
[16]-[19]. Qualitative models are realized using expert
lead to radiological release from authorized activities. In
systems and Qualitative trend analysis (QTA) while
other words, operational safety is a prime concern for those
quantitative models are realized using principle component
working in nuclear plants. These are supported by continuous
analysis (PCA)/partial least square, neural networks,
monitoring of individual doses and of the work environment
etc.[10],[20]. Indevelopment of expert system, we have ease
to ensure very low radiation exposure compared with other
in development process, transparent reasoning and the ability
industries.So early detection and quick diagnosis of a fault is
to provide explanations for the solutions provided. With
of paramount importance for NPP.
QTA, we can achieve process monitoring, malfunction
The complexity and voluminous nature of NPP make it a
diagnosis and prediction of future states. This method
very difficult task to ascertain whether the plant is operating
provides valuable information that explains the process
within acceptable limits. Furthermore, when plant is not
behavior. PCA is based on an orthogonal decomposition of
operating within acceptable limits, it is difficult to determine
the covariance matrix, i.e. data set are reduced to lower
what has gone wrong. With use of FDD determination of,
dimensions which can still describe the major trends in the
part of the system which is failing and which kind of fault it
original data set.NN refers to the network of biological
is facing would be accurate.In addition, operator‟s task of
neurons. Modern usage refers to artificial neural networks
handling plant becomes easy.
(ANN). ANN can be realized using supervised learning
B. FDD in NPP strategy or unsupervised learning strategy. They mainly
consist of three layers. First layer is input, then hidden layer
All model based diagnostic methods rely on an explicit and finally an output layer. ANN being process historybased
model of the plant, under observation. Model based method approach has minimal modeling requirements. Once network
consists of two steps: is trained, on-line computation complexity is minimal. ANN
1) Residual generation: Generating inconsistencies between does not possess an explanation facility for its actions and
the actual and expected behavior also its underlying structure is difficult to understand.
2) Selection of decision rule We have seen in this sectionvarious approaches used for
Quantitative model based approaches can be realized by diagnosis. These methods individually satisfy few of the
analytical redundancy, i.e. observer,extended kalman filters, above listed characteristics requirements of FDD unit while
parity relation, etc., [6]-[9].In analytical redundancy unlike still lacks in few other qualities. Different approaches
physical redundancy (measurements from multiple sensors employed for diagnosis purpose has relative strengths and
are compared to each other), sensor measurements are weaknesses. Also some of these methods can complement
compared to values computed analytically. Observer based one another[1]-[3].Hybrid techniques combine two or more
method develops a set observers, each of which is sensitive to standard techniques with the aim to provide accurate
a subset of faults and insensitive to the remaining diagnosis to the system over the wide range of operational
faults.Kalman filters, a recursive algorithm for state conditions. In next section, we look upon few of the
estimation, in state space model is equivalent to an optimal hybridtechniques proposed or used in NPP for diagnostic
predictor for input output model. Extended kalman filters are purpose.
widely used in non-linear systems by employing two step
4 INTERNATIONAL CONFERENCE ON CURRENT TRENDS IN TECHNOLOGY, „NUiCONE – 2011‟
C. Case study: Diagnosis techniques used in NPP 2) Monitoring system for NPP
1)Identification of transients in NPP An on-line monitoring system for the NPP has been
developed using the neural networks and the expert system
Identification of transients for timely monitoring of nuclear [21]. With conventional monitoring methods in NPP,
plants operation is of fundamental importance. A fuzzy-logic detecting anomalies can be achieved. But detecting symptoms
based method for the identification of transients is being of anomalies is difficult because of wide error boundary
proposed[17]. This approach uses if-then rules, which covering power level operation from zero to full[21].
constitutes the heart of the approach, developed from the Neural network can detect deviation from the normal state
available input-output signal data. Marzio uses Quandry of operation, while interpretation of the deviation by an
based reactor kinetics code (QUARK) for simulation, to expert system is performed to diagnose the cause. Neural
obtain necessary data for the identification. networks lacks in interpreting the cause of deviation while
QUARK is being used to model the operations of the use of expert systems alone for the plant monitoring is too
Westinghouse Advanced Pressurized water reactor, AP600. much computational complexity.
Code allows simulating the neutronic and thermal-hydraulic Compact simulator of Surry-I, U.S.A. helps in
transient behavior of a 3-D Light water reactor. simulating many kinds of malfunctions caused by equipment
In the QUARK, analytical nodal method is used to solve failure during steady state and transient operation for the
two-group neutron diffusion equation and the upgraded testing purpose. Time interval of the simulation is 2 seconds.
version of the COBRA code is used to develop the core Nabeshima has considered the Borssele NPP, a two loop
thermal-hydraulic model.The output of the code is taken as pressurized water reactor, with normal electric power output
the correct (pseudo) experimental values of the process of 477 MWe. On-line data acquisition system sends 72 plant
parameters, which are used in the fuzzy model training and signals to the neuro-expert system every two seconds. Of
identification tasks. these 21 most significant signals are selected for the inputs of
Possible four forcing functions considered by Marzio neural network. Others signals are considered to be
which can originate transients are: unchanged during controlled operation of power rise or fall,
- Primary pressure in the core (Pp) so that conventional monitoring method can detect anomaly
- Primary core inlet temperature (Tin) of these signals. Anomaly detection patterns by NNs are
- Core inlet flow rate (Γin) created using PWR simulator. In anomaly detection principle,
- Boron concentration (CB) measured sensor value is compared with predicted value for
Selection of forcing functions allows simulation of various checking fault level.
transients listed as: Software of NN and expert system are programmed in
- Leakage for the pressurizer (PP) FORTRAN and executed on the PC. The advisory displays
- Pressure increase (PP) show the status of NPP diagnosed by neuro-expert system.
- Increase of coolant inlet temperature (Tin) Java language based program is used in the graphical
- Decrease of coolant inlet temperature (Tin) advisory displays [21].
- Loss of coolant accident (Tin) NNs are trained by the current and past system input and
- Rise in boron concentration (CB) output for predicting next output of the system. This process
- Decrease in boron concentration (CB) of one-step-ahead prediction can be implemented by ANN,
The proposed approach by Marzio begins with and applied for dynamic tracking. Expert system use sensory
automatically generating the Fuzzy rule base (FRB) starting signals and outputs of the NNS along with information
from plant input/output data pairs. Set of rules designed maps provided from human operators as the input.
measured data to system behavior required for the system Few of malfunction cases considered by Nabeshima are
identification. listed below:
Each signal is characterized by a classificability threshold, - Small reactor coolant system leak
given as: - Leakage of atmospheric steam dump valve
- Partial loss of feed water
- Turbine governor valves fails
- Volume control tank level control fails
- Steam generator level control fails
Where, smax, smin and savg are the maximum, minimum and Last two malfunctions mentioned above are some kind of
average value of the signal in the transients. controller failures. With conventional alarm system detecting
FRB algorithm takes care of possible ambiguities in the those failures is possible. But with these systems identifying
classification. During simulation, the responsible forcing the cause of these anomalies is difficult. The neuro-expert
function is readily classified with small percentage of errors system in next time step can identify the failures for the failed
from signals measured within first 7s after the beginning of signals because the failed signals show deviations which are
the transients. Result by Marzio shows that by increasing the much larger than the others.
signal variation threshold classification accuracy can be The simple expert system called DISKET is compared with
increased. neuro-expert system by Nabeshima. DISKET diagnosis
process utilizes information obtained from the conventional
alarm system for knowing plant status. Neuro-fuzzy expert
INSTITUTE OF TECHNOLOGY, NIRMA UNIVERSITY, AHMEDABAD – 382 481, 08-10 DECEMBER, 2011 5
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