The paper is devoted to solution of some problems in nuclear power station generating unit intellectual control systems using genetic algorithms on the basis of control system model development, optimizations methods of their direct quality indices and improved integral quadratic estimates. Some mathematical vector models were obtained for control system multicriterion quality indices with due ...

the paper is devoted to solution of some problems in nuclear power station generating unit intellectual control systems using genetic algorithms on the basis of control system model development, optimizations methods of their direct quality indices and improved integral quadratic estimates. some mathematical vector models were obtained for control system multicriterion quality indices with due ...

Poor control of the nuclear steam generator (SG) water level of pressurized Water Reactor can lead to frequent reactor shutdowns. In addition, the steam generator is a highly complex, nonlinear and time-varying system and its parameters vary with operating conditions. The dynamics of a nuclear steam generator is very different according to the power levels and changes as time goes on. Therefore...

Poor control of steam generator water level is the main cause of unexpected shutdowns in nuclear power plants. Such shutdowns are caused by violation of safety limits on the water level and are common at low operating power where the plant exhibits strong nonminimum phase characteristics. In addition, the steam generator is a highly complex, nonlinear and time-varying system and its parameters ...

In early February 2000, primary-to-secondary tube leakage ranging from one to four gallons per day (gpd) was detected in steam generator (SG) No. 24. On February 15, 2000, while the unit was operating at 99% power, SG leakage rapidly increased from 4 gpd to greater than 75 gallons per minute (gpm). The reactor was manually tripped 13 minutes later, and the faulted steam generator was isolated o...

After the nuclear accidents of Three Mile Island and Chernobyl the world nuclear community made great efforts to increase research on nuclear reactors and to develop advanced nuclear power plants with much improved safety features. Following the successful construction and a most gratifying operation of the 10MWth high-temperature gas-cooled test reactor (HTR-10), the Institute of Nuclear and N...

Abstract In developing the PeLUIt 150 MW nuclear power plant based on High Temperature Gas-cooled Reactor (HTGR) technology, with helium-coolant and output thermal of MW, simulator is also developed for training operators educating other technical personnel. Referred to balance (BOP) design PeLUIt, utilized vPower simulation platform simulate secondary loop generation a water-steam Rankine cycl...

1. Steam Generation 1.1. General Characteristics 1.2. Circulation in Boiling Water Reactors 1.3. Steam Generation in CANDU Reactors 1.4. Steam Generators 1.5. Steam Generator for PWR and CANDU Systems 1.6. Heat Transfer 2. Steam Generator Operation 2.1. Swelling and Shrinking 2.1.1. Steady State Swelling and Shrinking 2.1.2. Transient Swelling and Shrinking 2.2. Level Control 2.3. Carryover 2.4...