Rod Group and Individual Control System

Nuclear Power Plant Instrumentation and Control Systems for Safety and Security - Advances in Environmental Engineering and Green Technologies ◽

10.4018/978-1-4666-5133-3.ch010 ◽

2014 ◽

pp. 320-351

Author(s):

Yuri Rozen ◽

Alexander Siora

Keyword(s):

Control System ◽

Remote Control ◽

Reactor Power ◽

Nuclear Safety ◽

International Standards ◽

Control Rod ◽

Individual Control ◽

Actuation System ◽

The Individual

Chapter 10 considers the Rod Group and Individual Control (RG&IC) system, which is one of the individual I&C systems and a part of the reactor control and protection system. RG&IC is an actuation system, which performs functions initiated by emergency and preventive reactor protection, reactor power control, unloading, limitation and accelerated preventive protection, and remote control rod position commands sent by the power unit personnel. The central part of RG&IC system consists of software-hardware complex SHC RG&IC-R based on the equipment family of the Research and Production Corporation “Radiy” (RADIY PLATFORM – see Chapter 1). The RG&IC system combines functions that belong to A and B categories according to safety impact (IEC, 2009), relates to safety class 2(A) and complies with the fundamental safety principles (IAEA, 1999), requirements that are set forth in international standards (IAEA, 2002, 2012; IEC, 2011), and Ukrainian nuclear safety rules and regulations (NP, 2000, 2008a, 2008b).

Download Full-text

RETRAN Application of Turbine Trip and Load Rejection of Startup Test Analysis for Lungmen ABWR

Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance ◽

10.1115/icone17-75401 ◽

2009 ◽

Author(s):

Chen-Lin Li ◽

Chiung-Wen Tsai ◽

Chunkuan Shih ◽

Jong-Rong Wang ◽

Su-Chin Chung

Keyword(s):

Control System ◽

Water Level ◽

Control Systems ◽

Nuclear Power ◽

Pressure Control ◽

Reactor Power ◽

Level Control ◽

Bypass Flow ◽

Control Rod ◽

Recirculation Flow

This study used RETRAN program to analyze the turbine trip and load rejection transients of Taiwan Power Company Lungmen Nuclear Power Plant’s startup test at 100% power and 100% core flow operating condition. This model includes thermal flow control volumes and junctions, control systems, thermal hydraulic models, safety systems, and 1D kinetics model. In Lungmen RETRAN model, four steam lines are simulated as one line. There are four simulated control systems: pressure control system, water level control system, feedwater control system, and speed control system for reactor internal pumps. The turbine trip event, at above 40% power, triggers the fast open of the bypass valves. Upon the turbine trip, the turbine stop valves close. To minimize steam bypassed to the main condenser, recirculation flow is automatically runback and a SCRRI (selected control rod run in) is initiated to reduce the reactor power. The load rejection event causes the fast opening of the bypass valves. Steam bypass will sufficiently control the pressure, because of their 110% bypass capacity. A SCRRI and RIP runback are also initiated to reduce the reactor power. This study also investigated the sensitivity analysis of turbine bypass flow, runback rate of RIPS and SCRRI to observe how they affect fuel surface heat flux, neutron flux and water level, etc. The results show that turbine bypass flow has larger impacts on dome pressure than RIPS runback rate and SCRRI. This study also indicates that test criteria in turbine trip and load rejection transients are met and Lungmen RETRAN model is performing well and applicable for Lungmen startup test predictions and analyses.

Download Full-text

Coordinated Control of a Small Pressurized Water Reactor

Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs ◽

10.1115/icone26-81156 ◽

2018 ◽

Author(s):

Peiwei Sun ◽

Chong Wang

Keyword(s):

Control System ◽

Reactor Core ◽

Reactor Power ◽

Pressurized Water Reactors ◽

Primary System ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Control Rod ◽

Average Temperature ◽

Water Reactors

Small Pressurized Water Reactors (SPWR) are different from those of the commercial large Pressurized Water Reactors (PWRs). There are no hot legs and cold legs between the reactor core and the steam generators like in the PWR. The coolant inventory is in a large amount. The inertia of the coolant is large and it takes a long time for the primary system to respond to disturbances. Once-through steam generator is adopted and its water inventory is small. It is very sensitive to disturbances. These unique characteristics challenge the control system design of an SPWR. Relap5 is used to model an SPWR. In the reactor power control system, both the reactor power and the coolant average temperature are regulated by the control rod reactivity. In the feedwater flow control system, the coordination between the reactor and the turbine is considered and coolant average temperature is adopted as one measurable disturbance to balance them. The coolant pressure is adjusted based on the heaters and spray in the pressurizer. The water level in the pressurizer is controlled by the charging flow. Transient simulations are carried out to evaluate the control system performance. When the reactor is perturbed, the reactor can be stabilized under the control system.

Download Full-text