System science and control techniques for harnessing nuclear energy

Abstract

Scientists and researchers are optimistic about safe usage of nuclear power even after several accidents. The control system is a crucial subsystem of the reactor, and accounts for its safe operation. In this review article, several types of control problems in nuclear reactors are presented and discussed, particularly the direct and indirect effects of temperature changes on the reactivity. The first part of the article describes the architecture for instrumentation and control, and outlines various reactivity feedback. Nuclear fuel handling control and turbine speed control are illustrated. The second part considers simulation techniques used in practice, including simulations of the effects of internal feedback and external reactivity perturbations, simulation techniques used to model the different types of problems, and the control schemes used to control reactor parameters. The paradigm of each control algorithm is explained. Techniques to simulate or to model a reactor coupled with different types of loads are explained.

Nuclear policy-nuclear fuels for peaceful, safer co-generation and environmentally benign applications

“…The chronological sequence of events for the accident at Chernobyl has been explained (Fig. 2) in details by Kushal [2]. Some of the peculiar facts that lead to Chernobyl accident are mentioned below:…”

“…(2) would be K 0 = $1.2 which is close to the estimate of K 0 = $1.5by H. Mochizuki' [5] analysis. By integrating equation (2) over the period of reactivity excursion, the total energy released after the power excursion can be estimated as,…”

“…mol .Consider the Zion PWR plant parameters. The total surface area of fuel cladding is 5400m 2 . Assuming that the total surface area is exposed to steam for 5 minutes, will yield W=0.322 kg/m 2 , i.e.…”

An improved control rod selection algorithm for core power control at TRIGA PUSPATI Reactor

“…As the movement of the control rod at nuclear reactor is mechanically limited, the acceptable ranges for velocity and delay time of the control rod movement must be considered at the design stage [5]. One of the key challenges in core power control is to control the displacement of the control rod accurately using CRDM [6]. In general, the manual controlling system has been used for controlling and tuning control rods in the nuclear reactor by the operator at low power (startup) and automatic controlling system with minimal supervision by operator most of the time at a high-power level for safety purpose.…”