Kabushiki Kaisha Toshiba

Naotaka Oda

Toshifumi Sato

Tadashi Miyazaki

Mikio Izumi

Toshiaki Ito

Hirotaka Sakai

Toshifumi Hayashi

Hideyuki Kitazono

Shigeru Odanaka

Makoto Ueda

Tatsuyuki Maekawa

Teruji Tarumi

Hiroaki Kenjyo

Makoto Yasuoka

Hironori Kumanomido

Yutaka Tokiwa

The power monitoring system has: a local power range monitor (LPRM) unit that has a plurality of local power channels to obtain local neutron distribution in a nuclear reactor core; an averaged power range monitor (APRM) unit that receives power output signals from the LPRM unit and obtains average output power signal of the reactor core as a whole; and an oscillation power range monitor (OPRM) unit that receives the power output signals from the LPRM unit and monitors power oscillations of the reactor core. The output signals from the LPRM unit to the APRM unit and the output signals from the LPRM unit to the OPRM unit are independent.

Power monitoring system

A reactor core coolant temperature measuring apparatus for measuring the temperature of the coolant flowing in the reactor core of a nuclear reactor comprises a &#x3b3;-ray thermometer having a temperature measuring section arranged below the bottom of the reactor core and a &#x3b3;-ray heat generation detecting section arranged between the bottom and the top of the reactor core, a cable for transmitting the signal output from the temperature measuring section and an output signal processing means for receiving the signal and computationally determining the local temperature of the coolant at the position of placement of the temperature measuring section.

Apparatus and method for measuring a temperature of coolant in a reactor core, and apparatus for monitoring a reactor core

To provide a rod block monitor in which irrespective of the selection or non-selection of a control rod, such a process is repeatedly executed that gain adjustment is performed at fixed intervals at all times to match a local area average value of signals of neutron detectors surrounding the control rod with a nuclear reactor average power and a block level appropriate to the local area average value of the neutron detector signals after the gain adjustment is set.

Rod block monitor

An upper detector and a lower detector that face at least one side of a fuel assembly, on which neutrons are irradiated in a nuclear reactor, and detect radiation are set at a predetermined interval in an axial direction of the fuel assembly. Distributions of radiation signals are measured by the upper detector and the lower detector while the fuel assembly and the upper detector and the lower detectors are relatively moved along the axial direction of the fuel assembly. Soundness of radiation signals measured by the upper detector and the lower detector is determined in every measurement by comparing radiation signal distributions obtained by measuring the same portion in the axial direction of the fuel assembly in a multiplexed manner with the upper detector and the lower detector. Thereafter, relative burn-up is calculated by utilizing the measured radiation signals to measure a burn-up profile. According to the present invention, it is possible to measure a burn-up profile of the fuel assembly while securing reliability of a measurement result.

Burn-up profile measuring method, burn-up profile measuring apparatus, radiation signal distribution measuring apparatus, and burn-up profile measuring program

Each of APRM units equipped for each of the diversity channels has printed circuit boards having circuit patterns thereon and a circuit description elements installed on the printed circuit board. The circuit description elements are FPGA elements manufactured by mutually different providers for example and implemented an electric circuit described in a hardware description language by a configuration tool. The circuit description elements can be implemented mutually different descriptions of the electric circuit, or can be implemented the electric circuit by mutually different configuration tools. Also, the printed circuit boards for the diversity channels can be different from each other.

Diversity signal processing system and a producing method thereof

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.

Safety protection instrumentation system and method of operating the system

An apparatus for verifying a custom IC including a test pattern generating unit for generating a test pattern for verifying a function of the custom IC. The test pattern is output to a master IC and a test IC. The apparatus further includes a comparing unit connected to receive operation signals output from the master IC and the test IC for comparing the operation signals to see if the operation signals are agreed with each other and for generating a comparison signal based on a comparison result, a judging unit connected to receive the comparison signal for judging if there is any abnormality in the test IC and for outputting a judged signal based on a judged result, and a computer connected to receive the judged signal for displaying the judged result of the test IC.

Apparatus and method for verifying custom IC

A verification method is provided for verifying a safety apparatus including a programmable logic device having a plurality of functional elements. The verification method includes the steps of exhaustively verifying the plurality of functional elements on actual hardware, generating a functional element that is the same as one of the functional elements verified on the actual apparatus using a predetermined hardware description language, independently logic-synthesizing each generated functional element into a plurality of first net lists, generating a connection function between the functional elements using the predetermined hardware description language, logic-synthesizing the generated connection function into a second net list corresponding to the connection function, synthesizing the first net lists with the second net list to generate a third net list, writing a logic circuit into the programmable logic device on the basis of the third net list, and verifying the actual programmable logic device.

Method for verifying safety apparatus and safety apparatus verified by the same

An apparatus for measuring the power of a nuclear reactor having a sensor assembly disposed in a core section inside the nuclear reactor. The sensor assembly includes a cover tube made of metal and press-fitted on the outer surface of a rod-shaped core tube made of metal, a plurality of annular gaps defined between the cover tube and the core tube at different positions spaced from each other in the axial direction of the core tube, a plurality of axial grooves formed in the core tube while opening on the outer surface of the core tube and extending in the axial direction of the core tube, and a plurality of temperature sensors individually guided in the axial grooves and disposed on the core tube. The temperature sensors of the sensor assembly detect temperature distribution in portions of the core tube which face the annular gaps so as to measure the power of the nuclear reactor. By virtue of the above construction, the apparatus can be manufactured easily, has high precision of temperature measurement, and has a sufficiently high reliability for reducing problems such as disconnection and insulation failure.

Apparatus for measuring power of nuclear reactor and method for

A start-up range neutron monitor system for monitoring neutrons generated from a neutron source comprises a neutron detector disposed in a non-earthed state and adapted to detect neutrons generated from the neutron source, a coaxial cable for externally transmitting a detection signal from the neutron detector, the coaxial cable being composed of a core and an outer sheath, a preamplifier incorporated on a way of the coaxial cable for amplifiying the detection signal, and a signal processing unit connected to the preamplifier through the coaxial cable to process the amplified detection signal amplified. The coaxial cable is composed of a first cable portion connecting the neutron detector and the preamplifier on an input side thereof and a second cable portion connecting the preamplifier and the signal processing unit on an output side of the preamplifier. A cable shield is further disposed so as to cover the first cable portion of the coaxial cable, wherein an earth side circuit on the signal processing unit is earthed and the cable shield is connected to an earth side circuit of the preamplifier, thus constituting the entire system as one point earth structure. A coil assembly including including first and second coils are also incorporated in the core and outer sheath of the first cable portion of the coaxial cable respectively alone or together with the cable shield. The first and second coils have the same inductance and are arranged so as to generate magnetic fluxes in directions reverse to each other.

Growing community of inventors

Kanagawa, Japan

Naotaka Oda