Abstract: An RFID installation position planning technology according to the present invention is used for outputting an optimum RFID installation position, which facilitates access to an RFID tag, before construction with work pieces. Work pieces layout data storage device stores work piece layout data including shape and disposition data of a work piece. A working route data storage device stores working route data including position data of works involving communication with the RFID tag. RFID tag position planning means determines communication accessibility to each point on a surface of the work piece from a work position, based on a distance between the work position and the RFID tag, presence or absence of an obstacle there between, and a communicatable distance of the RFID tag. Moreover, the RFID tag position planning means determines and outputs an optimum RFID tag installation position.

Abstract: A structure in a reactor building to be transported is made small when the structure is carried out from the reactor building and/or when the structure is carried into the reactor building. A beam is used outside a building inside of which a reactor pressure vessel is installed. The beam passes above the reactor pressure vessel and crosses over the building. A lifting machine has a lifting device and is moved on the beam. A shield is provided for shielding radioactive rays radiated from the reactor pressure vessel into the building through an opening portion provided in a roof of the building. The reactor pressure vessel, is moved together with the shield upward through the opening portion using the lifting device.

Abstract: An electronic exposure dose meter and a radiation handling operation management system is capable of realizing real time exposure management. The radiation handling operation management system has monitoring unit receiving an exposure dose amount measured by an electronic exposure dose meter having a radiation detector, its counter circuit and a PHS transmission and reception antenna, from a plurality of transmission and reception base station installed in a radiation handling operation site through bidirectional communication with a central management section via an external management base station, and deriving position of user of the electronic exposure dose meter for collecting and displaying position and exposure dose amount of the user. The electronic exposure dose meter has a radiation detector, a counter circuit, a PHS antenna for bidirectional communication with a central management section.

Abstract: A structure in a reactor building to be transported is made small when the structure is carried out from the reactor building and/or when the structure is carried into the reactor building. A beam is used outside a building inside of which a reactor pressure vessel is installed. The beam passes above the reactor pressure vessel and crosses over the building. A lifting machine has a lifting device and is moved on the beam. A shield is provided for shielding radioactive rays radiated from the reactor pressure vessel into the building through an opening portion provided in a roof of the building. The reactor pressure vessel, is moved together with the shield upward through the opening portion using the lifting device.

Abstract: One of methods for carrying out a reactor vessel according to the present invention comprises the steps of removing an overhead traveling crane in a reactor containment vessel of a pressurized water reactor, or the steps of, in an area where an overhead traveling crane is installed, operating the overhead traveling crane to move aside for creating a space, through which the reactor vessel is able to pass, and then carrying out the reactor vessel through an opening provided in a top portion of the reactor containment vessel. With the present method, the reactor vessel of the pressurized water reactor can be carried out in a short time with high efficiency.

Abstract: A method of carrying out a reactor vessel according to the present invention includes removing an overhead traveling crane in a reactor containment vessel of a pressurized water reactor. Alternatively, in an area where an overhead traveling crane is installed, operating the overhead traveling crane to move aside for creating a space, through which the reactor vessel is able to pass. Then the reactor vessel is carried out through an opening provided in a top portion of the reactor containment vessel. With the present method, the reactor vessel of the pressurized water reactor can be carried out in a short period of time with high efficiency.

Abstract: One of methods for carrying out a reactor vessel according to the present invention comprises the steps of removing an overhead traveling crane in a reactor containment vessel of a pressurized water reactor, or the steps of, in an area where an overhead traveling crane is installed, operating the overhead traveling crane to move aside for creating a space, through which the reactor vessel is able to pass, and then carrying out the reactor vessel through an opening provided in a top portion of the reactor containment vessel. With the present method, the reactor vessel of the pressurized water reactor can be carried out in a short time with high efficiency.

Abstract: An electronic exposure dose meter and a radiation handling operation management system is capable of realizing real time exposure management. The radiation handling operation management system has monitoring unit receiving an exposure dose amount measured by an electronic exposure dose meter having a radiation detector, its counter circuit and a PHS transmission and reception antenna, from a plurality of transmission and reception base station installed in a radiation handling operation site through bidirectional communication with a central management section via an external management base station, and deriving position of user of the electronic exposure dose meter for collecting and displaying position and exposure dose amount of the user. The electronic exposure dose meter has a radiation detector, a counter circuit, a PHS antenna for bidirectional communication with a central management section.

Abstract: An electronic exposure dose meter and a radiation handling operation management system is capable of realizing real time exposure management. The radiation handling operation management system has monitoring unit receiving an exposure dose amount measured by an electronic exposure dose meter having a radiation detector, its counter circuit and a PHS transmission and reception antenna, from a plurality of transmission and reception base station installed in a radiation handling operation site through bidirectional communication with a central management section via an external management base station, and deriving position of user of the electronic exposure dose meter for collecting and displaying position and exposure dose amount of the user. The electronic exposure dose meter has a radiation detector, a counter circuit, a PHS antenna for bidirectional communication with a central management section.

Abstract: One of methods for carrying out a reactor vessel according to the present invention comprises the steps of removing an overhead traveling crane in a reactor containment vessel of a pressurized water reactor, or the steps of, in an area where an overhead traveling crane is installed, operating the overhead traveling crane to move aside for creating a space, through which the reactor vessel is able to pass, and then carrying out the reactor vessel through an opening provided in a top portion of the reactor containment vessel. With the present method, the reactor vessel of the pressurized water reactor can be carried out in a short time with high efficiency.

Abstract: The present invention provides a method of handling a structure and an equipment of handling the structure which can make swing of the structure to be transported small when the structure in a reactor building is curried out from the reactor building and/or when the structure is carried into the reactor building from the outside of the reactor building.

Abstract: A method of placing cranes 1 and 2 with a reactor pressure vessel 4 (load) on a turntable 41 in the solid ground 57, turning the turntable 41 together with the cranes 1 and 2, and thus moving the reactor pressure vessel 4 to a selected position. Transferring an object by turning around a crane with a load in a narrow area without operating the crane.

Abstract: A method for handling an equipment inside a building by a crane installed outside; the method being employed when leading the wire hanging from the boom of a crane installed outside of a building (nuclear reactor containment vessel, into the building through an opening provided on the building, and lifting up or down an equipment inside said building by said wire. The said method includes a process for measuring by a three-dimensional measuring device which is positioned apart from the crane the shift of the boom caused by transfer of dead load of the equipment to the wire, in the course of transferring dead weight of the equipment between the wire and a structure inside the building, and correcting the position of the boom, by moving said boom up or down, back to a direction opposite to the shift so as to lift up the equipment vertically.

Abstract: A cask is lifted from outside of a nuclear reactor building through an opening which is opened at a portion of the nuclear reactor positioned just above a nuclear reactor pressure vessel. By maintaining the cask under a lifted condition a shroud which is an internal structure of the nuclear reactor is transferred and inserted to the cask from the nuclear reactor vessel. After that, an inlet port of the cask is closed, and the cask together with the shroud is lifted outside of the nuclear reactor building through the opening. The internal structure of the nuclear reactor can be speedily carried from the nuclear reactor building with reduced exposure of operators to radioactivity from the radioactive internal structure.

Abstract: A method of handling an internal structure of a nuclear reactor utilizing a receptacle such as a container or a cask. A cask, for example, is lifted from outside of a nuclear reactor building through an opening which is opened at a portion of the nuclear reactor positioned just above a nuclear reactor pressure vessel. While maintaining the cask under a lifted condition, a shroud, which is an internal structure of the nuclear reactor, is transferred and inserted to the cask from the nuclear reactor vessel. Thereafter, an inlet port of the cask is closed so that the cask substantially surrounds the shroud and substantially prevents radiation from the shroud passing therethrough. The cask together with the shroud is lifted outside of the nuclear reactor building through the opening. The internal structure of the nuclear reactor can be speedily carried from the nuclear reactor building with reduced exposure of operators to radioactivity from the radioactive internal structure.

Abstract: A plate structure block for establishing a surface layer ground is formed integrally with an iron plate on an upper surface of a reinforced concrete member. A lift metal fittings for transporting the block is installed on the block. The surface layer ground establishment block has a large ground bearing pressure and is a portable block. This block is covered on the surface layer ground and establishes the ground for operating a heavy material machinery and/or for maintaining a heavy material member. By operating a mobile heavy crane on the established ground, the working for constructing a plant is carried out. The material for constructing the ground is reused, the shape of the ground site is easily changed, and the dismantling and removal of the ground is simplified.

Abstract: In a method of construction of a reinforced concrete diaphragm floor of a nuclear reactor reinforced concrete containment vessel, a bottom surface of the diaphragm floor is provided in the form of an iron plate. The iron plate, an iron bar beam portion for supporting the load provided by concrete during a concrete pouring time, and a reinforcing bar member to be buried in the concrete of the diaphragm floor are assembled outside of a building in which the nuclear reactor is to be embodied. The above members are carried using lifting machinery and are set in a permanent receiving member which is provided on both a main body of the nuclear reactor pressure vessel and a steel member serving as a concrete mold frame of an outer wall of the nuclear reactor reinforced concrete vessel. A concrete pouring is carried out in stages so as to form successive layers of concrete during plural pouring times.

Abstract: A plate structure block for establishing a surface layer ground is formed integrally with an iron plate on an upper surface of a reinforced concrete member. A lift metal fittings for transporting the block is installed on the block. The surface layer ground establishment block has a large ground bearing pressure and is a portable block. This block is covered on the surface layer ground and establishes the ground for operating a heavy material machinery and/or for maintaining a heavy material member. By operating a mobile heavy crane on the established ground, the working for constructing a plant is carried out. The material for constructing the ground is reused, the shape of the ground site is easily changed, and the dismantling and removal of the ground is simplified.

Abstract: A method of constructing a top slab to provide a containment roof over a nuclear-power generating building, in particular, a method for utilizing overhead spaces bounded by a wall of the containment building and a shielding wall of the pressure vessel building, wherein the sequential steps involve; erecting a plurality of paired support columns on tops of the wall and of the shielding wall; building upper structural components across said paired support columns; installing a slab liner equipped with slab anchors beneath said lower structural components by suitable joining means; constucting a reinforcing network above said lower structural components; encasing said lower structural components and said reinforcing network; and pouring concrete over the slab liner to a suitable depth.

Abstract: Radioactivity exposure amount of workcraftmen is obtained through simulation by using an operation processor when the workcraftmen carry out work operation within an area under controlled radioactivity. The movement of the workcraftmen carrying out work operation in the area under controlled radioactivity is simulated by making use of layout graphic data relating to the area. The radioactivity exposure amount of the workcraftmen is calculated in response to the simulated movement of the workcraftmen. The operation procedures of the target work operation for radioactivity exposure amount calculation is outputted from the operation processor, when the calculated radioactivity exposure amount satisfies a predetermined value.