摘要:
A feedwater control system considering a pressure drop of feedwater control valve in a nuclear power plant and a control method therefor are provided. In the feedwater control system, a first detection unit includes: a flow error signal generator for generating a flow error signal corresponding to a difference between a steam flow signal and a feedwater flow signal; and a water level correction error signal generator for generating a water level correction error signal corresponding to a sum of a water level measurement signal and the flow error signal. A second detection unit includes: a pressure drop sensor unit for detecting a pressure difference between front and rear portions of at least one feedwater control valve among the main feedwater control valves and the downcorner feedwater control valves and generating a pressure drop signal corresponding to the detected pressure difference; a pressure drop setup value signal generator for generating a pressure drop setup value signal corresponding to a previously set pressure drop setup value of the feedwater control valves; and a pressure drop error signal generator for comparing the pressure drop signal with the pressure drop setup value signal and generating a pressure drop error signal. A control unit controls the main feedwater pump based on a correction control signal output from the correction control signal generator.
摘要:
A method for modeling linear control systems that are asymptotically stable provided that any initial deviation is within a definite bound is described. The method includes the steps of generating a parametric model of the quasi steady state system, generating a time-invariant parametric mapping function, using the system model, to relate a system setpoint parameter at a system setpoint function to an input process parameter implicit in a system implicit parameter, and generating an interface protocol to adjust the time-invariant parametric mapping function to account for any time-dependent variations in the relative performance between the input process parameter and the implicit system parameter.
摘要:
A method for mitigating crack growth on the surface of stainless steel or other alloy components in a water-cooled nuclear reactor wherein a solution or suspension of a compound containing a noble metal is injected into the coolant water while the reactor is not generating nuclear heat, e.g., during shutdown or recirculation pump heatup. During shutdown, the reactor coolant water reaches temperatures as low as 120.degree. F., in contrast to the water temperature of 550.degree. F. during normal operation. During pump heatup, the water temperature reaches 400.degree.-450.degree. F. At these reduced temperatures, the rate of thermal decomposition of the injected noble metal compound is reduced. However, radiation-induced decomposition also occurs inside the reactor. In particular, the noble metal compound can be decomposed by the gamma radiation emanating from the nuclear fuel core of the reactor. The noble metal compound decomposes under reactor thermal and radiation conditions to release ions/atoms of the noble metal which incorporate in or deposit on the oxide film formed on the stainless steel and other alloy components. As a result, the electrochemical potential of the metal surface is maintained at a level below the critical potential in the presence of low levels of hydrogen to protect against intergranular stress corrosion cracking.
摘要:
An enhanced protection system for protecting against transient overpower in a boiling water nuclear reactor which automatically adjusts the reactor over-power protection trip setpoints to be a controlled margin above the operating power level, so that enhanced fuel and reactor protection is provided at all power levels.
摘要:
An apparatus for removing free hydrogen from a gas mixture containing essentially hydrogen, oxygen, and steam using a catalyst arrangement for catalytically supported oxidation of hydrogen and a hydrogen-storage apparatus for absorption of hydrogen by hydride formation. The catalyst arrangement and the hydrogen-storage apparatus are designed to operate in different temperature and pressure regions, and they are arranged to provide good heat conduction between them. In this manner, heat generated by hydride formation enhances catalytic oxidation.
摘要:
The invention is of a method for treating the primary cooling medium of a pressurized water nuclear reactor by controlling its efficiency through the H.sub.3 BO.sub.3 content in the cooling medium. Hydrazine hydrate (N.sub.2 H.sub.4 .multidot.H.sub.2 O) is continuously fed to the coolant of a reactor which is charged for energy generation, to such an extent that its content equals 5.10.sup.-6 to 5.10.sup.-2 g/kg coolant medium as well as KOH and/or LiOH which corresponds to the alkaline properties. KOH in an amount of 80 to 56 mg/kg cooling medium with respect to the amount of H.sub.3 BO.sub.3 in a range of 20 to 0 g/kg cooling medium and the excess hydrogen is removed from the system leaving a maximum amount of hydrogen in the coolant medium of 100 n.multidot.ml/kg.
摘要:
In a boiling water nuclear reactor, a reactor primary cooling water line is filled with water at the start-up time, and the inside of a pressure vessel is pressurized by a pressurized tank and at the same time control rods are withdrawn to thereby heat cooling water in a state of single-phase flow to high temperature. Succeedingly, the pressurization is released and the pressure of the pressure vessel is gradually approximated to the saturation pressure corresponding to the cooling water temperature to thereby make the cooling water transit into a state of two-phase flow, and thereafter the cooling water is heated by nuclear reaction in the state of two-phase flow to thereby obtain predetermined reactor running temperature and pressure. This prevents the flow fluctuation and the reduction of stability of core due to occurrence of unstable phenomena of low temperature two-phase flow at the start-up time of the reactor to thereby make it possible to perform stable starting-up of the reactor and to shorten the start-up time of the reactor to thereby realize improvement in economy as well as reliability.
摘要:
To ensure safe removal of flammable explosive gaseous mixtures, the flammable mixtures are burned and/or recombined in partial volumes of the container separated from the rest of the container by metal grilles (18,19). The combustion is thereby prevented from spreading by the principle of the Davy safety lamp. The combustion and/or recombination in the partial volumes is effected by means of ignition sources (20), such as electric sparks, hot surfaces, open flames and/or catalytic surfaces. The heat energy released during combustion is transferred by means of cooling devices such as heat pipes. The temperature of the grille is sued to control the energy supply of the ignition source(s) and should never exceed approximately 2/3 of the ignition temperature of the flammable gaseous mixture; when the temperature reaches 3/4 of the ignition temperature, a fuse cuts off the energy supply. If the grille suffers mechanical damage, it touches an electrically insulated internal grille. This spark-free contact triggers an electrical switch which cuts off the power supply to the ignition and/or glow plugs. Detonatable H2-air mixtures can thereby be removed without the risk of explosion.
摘要:
Water testing means for monitoring circulating water coolant in service within a water cooled nuclear reactor system is disclosed. The invention is an improvement in such water testing means and comprises a preconditioning of selected sample specimens of water with a pH adjustment for inhibiting unbalancing an equilibrium in solution of water coolant with ion solutes.
摘要:
An element (e.g., a sensor) has a fine-line thin film of a conductor formed on a non-conductive substrate, and a change of physical properties (e.g., deformation) of the substrate or the ambient environment is detected through a change in physical properties of the conductor. The element is manufactured by forming a layered film, composed of a semiconductor and a conductor, on the substrate, and forcibly diffusing part of this film, e.g., by selective irradiation with high-energy ions, to form this part into an alloy semi-conductor, thereby providing a two-dimensional pattern of the fine lines of the conductor and the semiconductor. By arranging a plurality of fine lines of a conductor transversely to a direction of growth of a crack in the substrate, crack in the substrate is detected through a change in electrical resistance of the fine lines. A dissolved oxygen sensor, a hydrogen sensor, and an electrical conductivity sensor (of an ambient medium) can also be provided. To control water chemistry of a reactor, an amount of a water chemistry improving agent injected is controlled in accordance with an output of a water chemistry measurement sensor provided in water in a pressure vessel of the reactor. One or more of a dissolved oxygen sensor, a hydrogen sensor and an electrical conductivity sensor are formed directly on a surface of a structural material of the reactor.