Abstract: According to an embodiment, a power monitoring system for a nuclear reactor comprises at least a first system and second system. The first system and the second system respectively comprise a plurality of APRM units, a plurality of FLOW units, and a plurality of OPRM units. The APRM units respectively generate an LPRM signal that indicates the local output of neutrons by the reactor core, and generate an APRM signal indicating the average output of the reactor core, based on the LPRM signal. The FLOW units respectively generate a FLOW signal indicating the flow rate of reactor coolant. The OPRM units respectively are supplied with the LPRM signal and the APRM signal from at least two aforementioned APRM units and are supplied with the FLOW signal from at least one aforementioned FLOW unit; and, based on the supplied LPRM signals, APRM signals and FLOW signals, generate a trip signal for shutting down the reactor.

Abstract: A safety protection instrumentation system for a nuclear reactor is constructed by using digital logic. The digital logic includes functional units in which output logic patterns corresponding to all input logic patterns are verified in advance and a functional module formed by combining the functional units.

Abstract: A plant protection instrumentation equipment, comprises, a sensor that detects a process signal indicating a quantity of a state of a plant, a plurality of A/D converters, each of the A/D converters converts the process signal into a digital signal and outputs a value corresponding to the digital signal, a plurality of instrumentation circuits, each of the instrumentation circuits receives the value corresponding to the process signal and performs a logical operation using the value, and a judgment circuit that judges the state of the plant based on outputs of the plurality of instrumentation circuits and outputs an operation signal based on the process signal, wherein each of the instrumentation circuits comprises a logical integrated circuit including a set value comparator that compares the value corresponding to the process signal with a predetermined set value, and outputs a signal when the value corresponding to the process signal exceeds the set value.

Abstract: A radiation measurement device includes a radiation detector generating an analog signal containing pulse components, an A/D converter converting the analog signal into sampled data, an n-th power pulse discrimination unit calculating n-th power values of the sampled data to discriminate the pulse component, where n is two or more, and a pulse counter counting a number of the discriminated pulse components.

Abstract: A safety protection instrumentation system for a nuclear reactor is constructed by using a digital logic, in which the digital logic includes functional units in which output logic patterns corresponding to all input logic patterns are verified in advance and a functional module formed by combining the functional units.

Abstract: A radiation measurement device includes a radiation detector generating an analog signal containing pulse components, an A/D converter converting the analog signal into sampled data, an n-th power pulse discrimination unit calculating n-th power values of the sampled data to discriminate the pulse component, where n is two or more, and a pulse counter counting a number of the discriminated pulse components.

Abstract: A radiation measurement device includes a radiation detector generating an analog signal containing pulse components, an A/D converter converting the analog signal into sampled data, an n-th power pulse discrimination unit calculating n-th power values of the sampled data to discriminate the pulse component, where n is two or more, and a pulse counter counting a number of the discriminated pulse components.

Abstract: A radiation measurement device includes a radiation detector generating an analog signal containing pulse components, an A/D converter converting the analog signal into sampled data, an n-th power pulse discrimination unit calculating n-th power values of the sampled data to discriminate the pulse component, where n is two or more, and a pulse counter counting a number of the discriminated pulse components.

Abstract: A radiation measurement device includes a radiation detector generating an analog signal containing pulse components, an A/D converter converting the analog signal into sampled data, an n-th power pulse discrimination unit calculating n-th power values of the sampled data to discriminate the pulse component, where n is two or more, and a pulse counter counting a number of the discriminated pulse components.

Abstract: A plant protection instrumentation equipment, comprises, a sensor that detects a process signal indicating a quantity of a state of a plant, a plurality of A/D converters, each of the A/D converters converts the process signal into a digital signal and outputs a value corresponding to the digital signal, a plurality of instrumentation circuits, each of the instrumentation circuits receives the value corresponding to the process signal and performs a logical operation using the value, and a judgment circuit that judges the state of the plant based on outputs of the plurality of instrumentation circuits and outputs an operation signal based on the process signal, wherein each of the instrumentation circuits comprises a logical integrated circuit including a set value comparator that compares the value corresponding to the process signal with a predetermined set value, and outputs a signal when the value corresponding to the process signal exceeds the set value.

Abstract: A radiation measurement device includes a radiation detector generating an analog signal containing pulse components, an A/D converter converting the analog signal into sampled data, an n-th power pulse discrimination unit calculating n-th power values of the sampled data to discriminate the pulse component, where n is two or more, and a pulse counter counting a number of the discriminated pulse components.

Abstract: A neutron flux measuring apparatus, adapted to a boiling-water reactor (BWR) of a nuclear power plant and an advanced boiling-water reactor (ABWR) of a nuclear power plant, for measuring a neutron flux in a reactor pressure vessel, comprises a neutron flux detector assembly incorporating a local power range monitor detector assembly and a start-up range neutron monitor detector, a preamplifier amplifying a detector signal obtained from said start-up range neutron monitor detector, a start-up range neutron monitor operation unit operating, indicating and monitoring the amplified signal of the start-up range neutron monitor detector, and a local power range monitor operation unit operating, indicating and monitoring a signal obtained from the local power range monitor detector.

Abstract: A neutron flux measuring apparatus, adapted to a boiling-water reactor (BWR) of a nuclear power plant and an advanced boiling-water reactor (ABWR) of a nuclear power plant, for measuring a neutron flux in a reactor pressure vessel, comprises a neutron flux detector assembly incorporating a local power range monitor detector assembly and a start-up range neutron monitor detector, a preamplifier amplifying a detector signal obtained from said start-up range neutron monitor detector, a start-up range neutron monitor operation unit operating, indicating and monitoring the amplified signal of the start-up range neutron monitor detector, and a local power range monitor operation unit operating, indicating and monitoring a signal obtained from the local power range monitor detector.

Abstract: The reactor start-up monitoring apparatus is provided with an SRNM detector, an analog amplifier, an N/D converter, a pulse measurement system, a Campbell measurement system and reactor power monitoring means. The pulse measurement system is provided with pulse counting means for counting the pulse number of output pulses of the detector from the first digital data from the converter, and pulse measurement evaluating means for converting the measurement value to reactor power and evaluating the reactor power. The Campbell measurement system is provided with sum operating means for adding a plurality of sampling values forming the first digital data from the converter and acquiring the second digital data having accuracy of bits more than those of the first digital data, power operating means for obtaining mean square values based on the second digital data and Campbell measurement evaluating means for converting the mean square values to reactor power and evaluating the reactor power.