Control of Nuclear Reactor Power Level

Abstract

When building nuclear reactors the most important part that must be observed and verified is controlled in a nuclear reactor operation and representing the safety of nuclear plant and workers and an environmental. An important consideration in the design of a control system for a nuclear reactor is provision for safe operation. The main objective of this study is control of the nuclear reactor power level, to transition from one power level to another. Problem statement of study determines and evaluates the control variables from nuclear reactor system at 100% of the power and comparison with control variables at 90% of the power. Use dynamic programming technique of the optimal control theory for solute the problem of the study, The formulation of the optimal control problem, to facilitate the synthesis, a simplified reactor model is adopted such as to permit application of the one group delayed-neutron, the aim of control used in the present study is to minimize the core average temperature deviations from a given reference temperature during the transition from one power level to another. The reactor system model adopted here is a three-dimensional nonlinear discrete-time system of about twenty sampling intervals, which makes it impracticable to apply the conventional dynamic programming method, on account of the excessive demands on computer time and core memories. In this study use the simulations of the International Atomic Energy Agency (IAEA) development of nuclear plant simulators for operational and control of advanced Pressurized Water Reactor to shows all control variables to transition from 100% of the power to 90% .