Abstract: A method of treating a large scale structural body is provided in which when carrying out and in the large scale structural body such as nuclear reactor pressure vessel and an internal reactor structural body from and to a nuclear reactor building, a used fuel pool and fuels stored inside thereof can be protected even if the large scale structural body drops by some cause. In the method of treating a large scale structural body in which an opening portion is provided at a roof of the nuclear reactor building and the large scale structural body is carried out/in through the opening portion; the carrying out/in of the large scale structural body is performed under a condition that a protective measure for the used fuel pool is provided in a nuclear reactor well.

Abstract: A method of treating a large scale structural body is provided in which when carrying out and in the large scale structural body such as nuclear reactor pressure vessel and an internal reactor structural body from and to a nuclear reactor building, a used fuel pool and fuels stored inside thereof can be protected even if the large scale structural body drops by some cause. In the method of treating a large scale structural body in which an opening portion is provided at a roof of the nuclear reactor building and the large scale structural body is carried out/in through the opening portion; the carrying out/in of the large scale structural body is performed under a condition that a protective measure for the used fuel pool is provided in a nuclear reactor well.

Abstract: When carrying the large structure out through an aperture portion provided at a roof of a reactor building, a chamber for covering the aperture is provided at the roof so that work of providing the chamber for covering the aperture portion can be performed independent of other work performed in the reactor building, before at least a part of work of using a roof crane and at least a part work of handling fuel assemblies in the reactor building.

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 multilayer ceramic substrate having improved mechanical and electrical properties and suitable for use to form a hybrid integrated circuit and a process for the manufacture thereof. The multilayer ceramic substrate has at least one layer of a first conductor based on a refractory metal as an internal conductor layer and at least one layer of a Cu-based second conductor as a surface conductor layer, wherein the second conductor layer is connected to the first conductor layer through a metallic layer formed by coating with a metalloorganics paste containing one or more metals selected from the group consisting of Pt, Pd, Ni, Cu, Au, Rh, Ru, Re, Co, and Ir followed by firing in an inert or reducing atmosphere.

Abstract: A pressure vessel of a nuclear reactor is bodily enclosed by an inner layer made of a heat insulating material and an outer layer made of a radiation shielding material, and a nozzle joined by welding to the pressure vessel and a pipe joined by welding to the nozzle projected outwardly from the pressure vessel to extend through openings formed in the two layers. A removable heat insulator detachably attached to an edge of the inner layer defining the opening is disposed in a manner to surround the nozzle. A shielding frame is secured to walls defining the opening in the outer layer, to provide a manhole through which the nozzle and the pipe extend. A plurality of radiation shielding blocks are hingedly supported by an outer end of the shielding frame which is remote from the pressure vessel, while a plurality of radiation shielding plates are hingedly supported by an inner end of the shielding frame which is near to the pressure vessel.