Advanced heavy water reactor control with the aid of adaptive second-order sliding mode controller

2019 ◽  
Vol 37 (4) ◽  
pp. 1237-1259 ◽  
Author(s):  
Rupam Gupta Roy ◽  
Dibyendu Ghoshal

Purpose Advanced heavy water reactor (AHWR) is a pressure tube type of heavy water reactor. It eliminates high-pressure heavy water coolant resulting in a reduction of heavy water leakage losses and eliminating heavy water recovery system. It recovers the heat generated in the moderator for feed water heating. However, it requires a satisfactory technological response to develop an effective controller that attains the challenges of the very high-level safety system. Hence, they require application-specific improvement for better controlling performance. Design/methodology/approach The purpose of this study intends to propose a system for controlling state vectors v1 and v2and in AHWR using Grey Wolf second-order sliding mode control (GW-SoSMC) technique. The main aim of the paper is to minimize the errors between the predicted and desired azimuthal angles of the system. With this proposed method, it is possible to mitigate both the chattering phenomenon and controlling performance of AHWR system. It implements a SoSMC controller based on GWO algorithm for the purpose of controlling the state vectors in the AHWR system. It aims to accomplish a controller for improving the performance of the AHWR system. Findings Through the performance analysis, the efficiency of the proposed GW-SoSMC technique was verified by comparing it with various conventional algorithms, such as GW-SMC, FF-SoSMC, ABC-SoSMC, GS-SoSMC and GA-SoSMC. From the analysis, it was obtained that the implemented GW-SoSMC technique was 65.3 per cent superior to GW-SMC, 65.32 per cent superior to both FF-SoSMC and 65 per cent superior to ABC-SoSMC, 65.8 per cent superior to the GS-SoSMC and 58 per cent superior to the GA-SoSMC methods. Thus, the effectiveness of the proposed method in controlling the state vectors in AHWR was obtained. Originality/value This paper presents a technique for controlling the state vectors in the AHWR system using GWO algorithm. This is the first work that uses GWO-based optimization for controlling state vectors in the AHWR system.

2013 ◽  
Vol 60 (4) ◽  
pp. 3040-3050 ◽  
Author(s):  
R. K. Munje ◽  
B. M. Patre ◽  
S. R. Shimjith ◽  
A. P. Tiwari

2008 ◽  
Vol 41 (2) ◽  
pp. 8648-8653 ◽  
Author(s):  
G. Datatreya Reddy ◽  
Y.J. Park ◽  
B. Bandyopadhyay ◽  
A.P. Tiwari

2020 ◽  
Vol 67 (6) ◽  
pp. 1076-1085 ◽  
Author(s):  
R. J. Desai ◽  
B. M. Patre ◽  
R. K. Munje ◽  
A. P. Tiwari ◽  
S. R. Shimjith

Author(s):  
B. Chatterjee ◽  
A. Srivastava ◽  
D. Mukhopadhyay ◽  
P. Majumdar ◽  
H. G. Lele ◽  
...  

Advanced Heavy Water Reactor is natural circulation light water cooled and heavy water moderated pressure tube type of reactor. Changes in heat removal by primary heat transport system of a reactor have significant impact on various important system parameters like pressures, qualities, reactor power and flows. Increase in heat removal leads to Cooldown of the system subsequently reducing pressure, void increase and changes in power and flows of the system. Decrease in heat removal leads to warm-up of the system subsequently raising pressure, void collapse, and changes in power and flows of the system. The behaviour is complex as system under consideration is natural circulation system. Causes for events under category of increase in heat removal are mainly malfunctioning of feed water heaters, Isolation Condensers (IC) inlet valves and controllers. These events lead to cooldown of system and addition of positive reactivity addition due to void collapse. Various events considered are Feed Water System malfunctions that result in decrease in feed water temperature, inadvertent opening of IC valve, Failure of PHT Pressure Control System and Decrease in pressure controller set point to 67 bars. Causes for events under category of decrease in heat removal are mainly malfunctioning of controllers, feedwater valves and operating events like turbine trip. Functioning of passive cooling system and different valves play important role for these events. These events lead to increase in system pressure. Various events considered are Loss of normal feed water flow (multiple trains), Turbine trip without bypass without IC, Turbine trip without bypass with IC, Turbine trip with bypass without IC, Increase in PHT pressure controller set point, Decrease in level controller set point, Turbine Trip with setback, Decrease in steam flow and Class IV power failure. Changes in the system voids and pressures as a result of change in the heat removal leads to complex reactivity feedback due to coolant temperatures, void fraction and fuel temperatures. These changes in the reactor power together with void distribution change affect two-phase natural circulation flow. This paper brings out these aspects. It discusses descretisation of the system and brings out various design aspects. In this paper summary of analysis for each event is presented, various modeling complexities are brought out, evaluation of acceptance criteria is made and design implications of each event is discussed.


Author(s):  
Manish Sharma ◽  
D. S. Pilkhwal ◽  
P. K. Vijayan ◽  
D. Saha

The proposed Advanced Heavy Water Reactor (AHWR) is a light water cooled and heavy water moderated pressure tube type boiling water reactor based on natural circulation. AHWR adopts several passive concepts with a view to simplify the design and to enhance safety and public acceptability. One such feature is passive decay heat removal using isolation condenser (IC) system during a station blackout. A scaled Integral Test Loop (ITL) was set up in BARC to simulate the overall system behavior studies for Advanced Heavy Water Reactor (AHWR). This facility simulates the Main Heat Transport System (MHTS), Emergency Core Cooling System (ECCS) and Isolation Condenser system (ICS) system, Feed Water System (FWS) and the associated controls. Power to volume scaling philosophy has been adopted for the design of the ITL systems. To evaluate the performance of IC, experiments have been carried out in ITL. The test results have been simulated using RELAP5/ MOD3.2. This paper deals with the experiments conducted, nodalization scheme adopted for ITL in RELAP5/MOD 3.2 simulation, transient predictions made and the results obtained in detail.


2016 ◽  
Vol 24 (1) ◽  
pp. 357-364 ◽  
Author(s):  
Ravindra K. Munje ◽  
Balasaheb M. Patre ◽  
Akhilanand P. Tiwari

Sign in / Sign up

Export Citation Format

Share Document