摘要:
A nuclear reactor control system is provided in a nuclear reactor having a core operating in the fast neutron energy spectrum where criticality control is achieved by neutron leakage. The control system includes dual annular, rotatable reflector rings. There are two reflector rings: an inner reflector ring and an outer reflector ring. The reflectors are concentrically assembled, surround the reactor core, and each reflector ring includes a plurality of openings. The openings in each ring are capable of being aligned or non-aligned with each other. Independent driving means for each of the annular reflector rings is provided so that reactor criticality can be initiated and controlled by rotation of either reflector ring such that the extent of alignment of the openings in each ring controls the reflection of neutrons from the core.
摘要:
A coupling device between a nuclear reactor control rod and an actuating mechanism has a gripper body having resilient gripping fingers, belonging to the mechanism and, on the bar, a terminal pommel for engagement by the fingers and a shoulder directed towards the pommel. The coupling device comprises an additional member, such as a sleeve, movable with respect to the gripper body between a position in which it allows resilient fingers to be released from the pommel and another position in which it locks the resilient fingers onto the pommel. The sleeve has an end face bearing on the shoulder of the pommel. A prestressed spring exerts a force tending to move the sleeve away from the fingers so as to hold the end face of the sleeve firmly applied against the shoulder when the fingers are locked on the pommel.
摘要:
A method of operating a gas-cooled nuclear reactor having graphite fuel elements in which, to reduce the reactor, a quenching element is introduced which takes a particle of a reaction-reducing substance in a sheath which will melt or release the substance in vapor form so that the substance can penetrate in gaseous form through the surrounding graphite body and deposit upon fuel elements.
摘要:
An operating method for a nuclear reactor power plant having control rods for controlling the power level thereof, upon an occurrence of a failure, comprising the steps of: determining the type of failure; selecting control rods from the outermost peripheral region of said nuclear reactor; selecting control rods from those control rods in the region inside the outermost peripheral region which are in a fully withdrawn position during normal operation of said nuclear reactor power plant; subjecting the control rods selected from the outermost peripheral region and the region inside the outermost peripheral region to a scram process, whereby the power level of said nuclear reactor power plant is controlled in accordance with the type of failure.
摘要:
In a process for running a nuclear reactor cooled with light water, by displacing control rods and modifying the physical and/or chemical state of the coolant, the value of the running parameters of the reactor are continuously measured and recorded and the parameters describing the state of the reactor core are calculated for each substantial modification of the running parameters. The parameters describing the state of the core are measured at defined intervals of time and the calculated parameters are replaced by the measure parameters. The modified parameters resulting from predetermined sequences of action taken on the control rods or the coolant, and the action which must be taken on the running parameters in order to comply with a given program, are calculated by way of predictions. Action is taken on the control rods and the coolant in accordance with the results of the calculation.
摘要:
An improved method and apparatus for operating magnetic stepping-type mechanisms. The current flowing in the coils of magnetic stepping-type mechanisms of the kind, for instance, that are used in control-element drive mechanisms is sensed and used to monitor operation of the mechanism. Current waveforms that characterize the motion of the mechanism are used to trigger changes in drive voltage and to verify that the drive mechanism is operating properly. In addition, incipient failures are detected through the observation of differences between the observed waveform and waveforms that characterize proper operation.
摘要:
A core reactor and method of operating same, according to which fuel elems, preferably of ball shape, are provided with an envelope of graphite and are passed in downward direction through reflector means of graphite which is simultaneously passed through by a heat transfer means and includes a ceiling reflector, a side reflector and a bottom reflector so that the fuel elements after once passing through the reactor core have reached the desired end burn-off conditions. Within or in the vicinity of that portion of the wall of the ceiling reflector and/or of the upper portion of the wall of the side reflector there are provided neutrons absorbing substances or additional substances reducing the speed of the neutrons.
摘要:
The control rods of the different zones of the plant are moved simultaneously with or independently of the control rods of the other zones. Control of the rod movements is made dependent on the pressure of the working medium of the plant as well as the outlet temperature of the reactor coolant. Additionally, a control of the live steam mass flow of the plant is achieved by comparison between the live steam mass flow and the overall neutron flux of the nuclear reactor.
摘要:
869,560. Nuclear reactor control rods. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Feb. 12, 1960 [Feb. 26, 1959], No. 6802/59. Class 39(4). A reactor control member comprises an elongated casing 6, a movable member 12 at the bottom of the casing, a lifting cable 5 the tension in which normally holds the member 12 to close the casing, and a mass of particulate neutron absorbers in the casing; if the control member becomes jammed the tension in the cable is relaxed and the neutron absorbers are able to fall out of the casing into the control rod channel. The member 12 carries a shock absorber 16. The channel contains a tube 3 at the bottom of which is a grid which allows passage of coolant but prevents loss of absorber partides; this tube can be discharged from the reactor. The absorber may be boron steel balls. Specifications 813,584, 816,157 and 857,432 are referred to.