Kabushiki Kaisha Toshiba

Koji Hirukawa

Shungo Sakurai

Kazuki Hida

Takafumi Naka

Kouji Hiraiwa

Teruji Tarumi

Tsuyoshi Nakajima

Yoshihira Ando

Yasushi Hirano

Yuki Narawa

Nobuaki Oono

A nuclear reactor instrumentation system including a plurality of incore nuclear instrumentation assemblies arranged in a gap between a number of fuel assemblies charged in a reactor core. The incore nuclear instrumentation assemblies each include a fixed type neutron detector having a plurality of fixed type neutron detectors dispersively arranged in a core axial direction and a fixed type gamma thermometer assembly having a plurality of fixed type gamma ray heat detectors arranged at least in a same core axial direction as the fixed type neutron detectors. A power range detector signal processing device operatively connected to the fixed type neutron detector assemblies through signal cables. A gamma thermometer signal processing device is operatively connected to the fixed type gamma thermometer assembly of the incore nuclear instrumentation assembly through a signal cable.

Nuclear reactor power distribution monitoring system and method including nuclear reactor instrumentation system

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.

Neutron flux measuring apparatus

In an in-core fixed nuclear instrumentation system for a reactor, each of a plurality of in-core nuclear instrumentation assemblies has a nuclear instrumentation tube. LPRM detectors are housed in the nuclear instrumentation tube for detecting LPRM signal in a core of the reactor. A GT assembly is housed in the tube. The GT assembly has fixed GT detectors for detecting &ggr;-ray heating values and a built-in heater therein for calibrating the fixed GT detectors. The fixed GT detectors are arranged at least close to the fixed LPRM detectors, respectively. GT signals by the detected &ggr;-ray heating values of the fixed GT detectors of each GT assemblies are processed by a GT signal processing unit. The heater in each GT assemblies is electrically energized by a GT heater control unit. Predetermined time intervals are stored in a memory unit. One of the predetermined time intervals for specified &ggr;-ray thermometer assemblies, respectively is selected so that the GT heater control unit controls an electrical energy supplied to the heater by the selected interval so as to heat the heater, thereby executing a heater calibration of output voltage sensitivities of the fixed GT detectors of the GT assembly.

In-core fixed nuclear instrumentation system and power distribution monitoring system

A nuclear reactor instrumentation system including a plurality of in core nuclear instrumentation assemblies arranged in a gap between a number of fuel assemblies charged in a reactor core. The income nuclear instrumentation assemblies each include a fixed type neutron detector assembly having a plurality of fixed type neutron detectors dispersively arranged in a core axial direction and a fixed type gamma thermometer assembly having a plurality of fixed type gamma ray heat detectors arranged at least in a same core axial direction as the fixed type neutron detectors. A power range detector signal processing device is operatively connected to the fixed type neutron detector assemblies through signal cables. A gamma thermometer signal processing device is operatively connected to the fixed type gamma thermometer assembly of the in core nuclear instrumentation assembly through a signal cable.

A moderator rod provided with a burnable poison and disposed in a fuel assembly of a reactor core comprises an outer tube, an inner tube disposed in the outer tube, the outer and inner tubes constituting a double tube structure between which an annular section is formed, and a burnable poison charged in said annular section. A containing amount of the burnable poison per unit area of the annular section is distributed at least one of peripheral direction and axial direction of the double tube structure of the inner and outer tubes. A fuel assembly of a nuclear reactor comprises an upper tie plate, a lower tie plate, a number of fuel rods supported at their upper ends by the upper tie plate and at their lower ends by the lower tie plate and filled up in their inner spaces with a plurality of fuel pellets, at least one of moderator rods containing burnable poison in various states and a channel box. The moderator has an outer tube and an inner tube disposed coaxially in the outer tube. An area of a metal, ceramics or thermet containing the burnable poison is formed at a portion except for portions having axial length corresponding to 1/24 to 1/12 length of the fuel effective length from the upper and lower ends thereof.

Moderator rod containing burnable poison and fuel assembly utilizing same

A fuel assembly for a boiling water reactor comprising an upper and lower tie plates, a plurality of fuel rods filled therein with a plurality of fuel pellets, a fuel bundle comprising the fuel rods retained with a plurality of spacers in spaced relation and disposed between the upper and lower tie plates, and a polygonal tube-like channel box which encloses the fuel bundle and constitutes flow paths for coolant. The fuel rods comprise long fuel rods and short fuel rods which are each shorter in the effective portion than each of the long fuel rods. The concentration of fissile material in each of the short fuel rods is lower than the mean concentration of fissile material in the cross section of the fuel bundle. In the case the fuel bundle is vertically subdivided into two regions, an upper and lower one, with the upper end of the effective portion of each of the short fuel rods as a border, the mean concentration of fissile material in the cross section of the fuel bundle in the region lower than the border is lower than that in the cross section of the fuel bundle in the region above the border.

Fuel assembly for boiling water reactor and core

A fuel spacer for a fuel assembly comprises a plurality of tubular ferrules each forming a fuel rod insertion passage, a belt-like support member for supporting the tubular ferrules bundled in a lattice arrangement and a spring member for axially supporting the fuel rods disposed in the ferrules. The adjoining ferrules are joined together horizontally, each of the ferrules has at least one end to which a plurality of cutout portions are formed circumferentially of the end portion and at least one flat portion is formed between adjoining petal portions at which the adjoining ferrules are spot welded. Each of the cutout portions and petal portions of the tubular ferrule has various shapes such as trapezoidal, rectangular, triangular, V or M shape. The cutout portions and petal portions may be formed at both axial ends of the tubular ferrule. The adjoining ferrules are joined together such that an end portion of one ferrule to which the cutout portions are formed is spot welded to an end portion of another ferrule to which any cutout portion is not formed. The petal portions formed on a downstream side with respect to a coolant flow in a fuel assembly is twisted outward to provide revolutional flow and an opened end of the ferrule.

Fuel spacer for fuel assembly

A fuel assembly having a water cross or water rod arranged between the fuel rods, an inside of the water cross or water rod being divided into a coolant rising passage and a coolant lowering passage, and a control guide tube disposed inside the water cross or water rod and extending along an axial direction of the water cross or water rod. The coolant rising passage has a coolant inlet port formed to a portion above or under a portion at which the fuel rods are supported by the lower tie plate. The control element guide tube has a coolant outlet port formed at that portion so that a coolant introduced into the coolant rising passage flows vertically upwardly, then turns and flows downwardly along the control element guide tube, and flows into an inside thereof through the coolant outlet port. A reactor core comprises a plurality of fuel assemblies each having a structure described above, a control rod and a control element operated in association with the control rod.

Growing community of inventors

Kanagawa-ken, Japan

Koji Hirukawa