Abstract:
An ultrasonic measurement method and an ultrasonic measurement apparatus are capable of performing an inspection for a short time with a high SN ratio and a small variation (that depends on an inspection direction) in sensitivity in a process for detecting a defect in all directions at 360 degrees using a matrix array sensor without performing mechanical scanning in all directions, while reducing noise that is caused by a bottom surface echo. An element selecting circuit selects a group of a plurality of ultrasonic transducer elements for transmission from among ultrasonic transducer elements that constitute a two-dimensional array sensor so that the ultrasonic transducer elements for selected for transmission are arranged in line symmetry with respect to a first line symmetric axis to set the group selected for transmission. The element selecting circuit selects a group of a plurality of ultrasonic transducer elements for reception so that the ultrasonic transducer elements selected for reception are arranged in line symmetry with respect to a second line symmetric axis that is perpendicular to the first line symmetric axis to set the group selected for reception. A transmitting element selector selects, as transmitting elements, the ultrasonic transducer elements set by the element selecting circuit. A receiving element selector selects, as receiving elements, the ultrasonic transducer elements set by the element selecting circuit.
Abstract:
A method for forming a ferrite film onto surface of structural member composing a plant, comprises steps of forming a ferrite film onto the wetted surface of the structural member by making contact with a film forming solution containing iron (II) ions, an oxidant for oxidizing the iron (II) ions, and a pH adjustment agent; measuring the amount of the formed ferrite film; and determining completion of the ferrite film formation based on the measured amount of the formed ferrite film. The method for forming the ferrite film onto the surface of the structural member, can shorten the time required for completing the ferrite film forming operations.
Abstract:
The ultrasonic probe of the ultrasonic inspection apparatus, which is pushed onto the outer surface of the reactor pressure vessel, transmits and receives an ultrasonic wave to and from a penetration having a welded portion while changing an incident angle of the ultrasonic wave. Based on a result of reception of an echo obtained by the reflection of the ultrasonic wave on the inner surface of the penetration, an inclination angle of the penetration relative to a wall surface of the reactor pressure vessel is measured. A circumferential direction position of the penetration, which corresponds to the inclination angle, is calculated based on the relationship of an inclination angle and a circumferential direction position, which have been calculated in advance. Then, the circumferential direction position can be obtained as information on the inspection position.
Abstract:
A reactor containment vessel of the present invention has a primary reactor containment vessel disposing a dry well for storing a reactor pressure vessel, a wet well for storing a pressure suppression pool, and an equipment room disposing below said pressure suppression pool inside thereof. Further, the primary reactor containment vessel includes an outer cylindrical wall reaching to a base mat from a top slab of the primary reactor containment vessel and facing the drywell, the pressure suppression pool and the equipment room respectively, an inner cylindrical wall facing the pressure suppression pool and the equipment room respectively, and a pressure suppression pool floor partitioning among the pressure suppression pool and the equipment room, and an outside portion of the outer cylindrical wall, an inside portion of the inner cylindrical wall, an outside portion of the ceiling and a lower portion of the pressure suppression pool floor are formed of a steel plate reinforced concrete respectively.The reactor containment vessel can contribute to shorten construction period and thereby improve economic efficiency of nuclear power generation facilities.
Abstract:
A method for generating data of plant construction simulation, in which a scheduling system and a CAD system are used to prepare a construction plan, comprises steps of:managing a construction work managed by said scheduling system and a plant part used in the construction work and managed by the CAD system in association with each other; andperforming processing for associating the plant part with each of a plurality of lower construction work constituting the construction work, which are produced when the construction works are broken down.
Abstract:
An adjustable speed drive system for a primary loop recirculation pump capable of keeping a PLR pump operating even if a single malfunction occurred in a main adjustable speed drive circuit portion. The drive system for the primary loop recirculation pump has a backup main adjustable speed drive circuit portion, and a breaker for switching between an incoming destination and an outputting destination of the backup main adjustable speed drive circuit portion. A control signal of an inverter control portion is switched to control an inverter included in the backup main adjustable speed drive circuit portion, and when a malfunction occurred in the adjustable speed drive main circuit, by switching to the backup main adjustable speed drive circuit portion, the primary loop recirculation pump of a nuclear reactor is continuously controlled and operated.
Abstract:
A nuclear power plant and method of operation for augmenting a second reactor thermal power output in a second operation cycle to a level larger than a first reactor thermal power output in the previous operation cycle. The plant is equipped, for example, with a reactor; a steam loop comprising high and low pressure turbines; a condenser for condensing steam discharged therefrom the low pressure turbine; a feedwater heater for heating feedwater supplied from the condenser; and a feedwater loop for leading feedwater discharged from the feedwater heater to the reactor. The operation method includes decreasing a ratio of extraction steam which is led to the feedwater heater from a steam loop in the second operation cycle.
Abstract:
The supply amount of reactive power can be expanded while the soundness of a nuclear reactor and a BOP. A control apparatus of a power generation plant connected to a power system including a power system stability degree previous evaluation unit that evaluates a stability degree at the time of the predicted failure of the power system, a nuclear power safety evaluation unit, and a current day power generation control instruction unit that corrects a required power supply amount given from the outside according to the evaluation result of the power system stability degree previous evaluation unit and the evaluation result of the nuclear power safety evaluation unit, in which the generated power of the power generation plant is adjusted by a signal from the current day power generation control instruction unit.
Abstract:
A pipe inspection method includes a first process of disposing an outside coil and a camera outside a thermal insulator, a second process of measuring the thickness of a pipe at a position of an ultrasonic sensor fixed in advance to an inside of the thermal insulator and to the outer surface of the pipe, by using the ultrasonic sensor, an inside coil, the outside coil, and a controller, a third process of photographing the thermal insulator with the camera, a fourth process of removing the thermal insulator from the pipe when judging an abnormality in the thickness of the pipe at the position of the ultrasonic sensor or in the appearance of the thermal insulator, a fifth process of disposing another ultrasonic sensor on the outer surface of the pipe, and a sixth process of measuring the thickness of the pipe at the position of the other ultrasonic sensor.
Abstract:
In a steam separator including a plurality of stages of separating mechanisms, a separating mechanism in a second or subsequent stage includes vertical plates and that divide a second stage annular flow passage or a third stage annular flow passage in a circumferential direction, and eliminate a swirl component of a mixed flow continuously occurring from a second stage inner cylinder or a third stage inner cylinder to the second stage annular flow passage or the third stage annular flow passage.