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.

Description:
BACKGROUND OF THE INVENTION 
     The present invention relates to a method of handling a nuclear reactor and an apparatus used in the handling method and in particular to a handling technique of an internal structure of a nuclear reactor with which a taking-out working of the internal structure of the nuclear reactor to an outside of a nuclear reactor building or containment is provided. 
     In the nuclear reactor building or containment of an atomic power plant station, a nuclear reactor pressure vessel is received and in this nuclear reactor pressure vessel a shroud for surrounding a reactor core of a nuclear reactor and an upper portion lattice plate and a reactor supporting plate etc. exist as an internal structure. 
     In the nuclear reactor internal structure of the atomic power plant station, a damage state of the nuclear reactor internal structure is carried out to inspect and mend during every regular inspection time, however from the aspects of a conservation performance, an economic performance and a prevention preservation in a midway of durable years the nuclear reactor internal structure is exchanged over and renewed with a new nuclear reactor internal structure. 
     In a renewal working or processing of the nuclear reactor internal structure according to the prior art, in a nuclear reactor well pool, an upper portion lattice plate, an upper portion shroud and a reactor core supporting plate etc. are cut roughly and taken out in advance. In a nuclear reactor building using a previous-established ceiling crane, the roughly cut-down upper portion lattice plate, the roughly cut-down upper portion shroud and the roughly cut-down reactor core supporting plate etc. are temporally placed in a dry separator (herein, it is called as “DS”). 
     Further, in DS pool, a decomposition taking-out working and a fine cutting working for the roughly cut-down upper portion lattice plate, the roughly cut-down upper portion shroud and the roughly cut-down reactor core supporting plate etc. are performed with a remote control in the water. Accordingly, the upper portion lattice plate, the upper portion shroud and the reactor core supporting plate etc. are converted to waste materials. 
     Accordingly, so as to isolate the nuclear reactor well pool and DS pool, a DS pool gate is newly established. Further, the fine cut waste materials (the small chips of the nuclear reactor internal structure) are received in plural receptacles such as container or casks and on occasion the fine cut waste materials are transferred and kept on the premises to a sight bunker or a solid waste material reservoir. 
     Accordingly, in accordance with the working for cutting roughly in the nuclear reactor well pool, the working for cutting finely in DS pool, the supplementary working for increasing the storage containers and the supplementary material amount increase, since the above stated workings extend over a long period, there is problems from the aspects of the cost and radiation exposure etc. Further, a long period for a plant stop period in a total becomes a big burden economically to an electric power company from a reduction in an operation of rate of an equipment. 
     On the other hand, when the nuclear reactor pressure vessel is exchanged over, as described in Japanese application patent laid-open publication No. Hei 8-285981 and Japanese application patent laid-open publication No. Hei 8-262190, a technique has known in which the nuclear reactor pressure vessel is drawn in in a transfer receptacle or container which has waited on a roof of a nuclear reactor building by a crane and the nuclear reactor pressure vessel with the transfer container is transferred to a desired point of the nuclear reactor building. 
     In the above stated prior art example, the nuclear reactor pressure vessel with the transfer container is moved at an upper portion to the roof by performing an uncover to the nuclear reactor pressure vessel and by lifting the nuclear reactor pressure vessel with the transfer container in the nuclear reactor building. Accordingly, an exposure reduction countermeasure against to working men in the nuclear reactor building who relates to radiation from the nuclear reactor pressure vessel is insufficient. 
     Taking into consideration about the exposure reduction countermeasure against to the working men in the nuclear reactor building, as disclosed in Japanese application patent laid-open publication No. Hei 9-145882, a techniques has known in which plural divided shield bodies are assembled so as to surround the nuclear reactor pressure vessel in the nuclear reactor building and the reduction of the radiation and the diffusion of the radioactivity are shielded by the shield bodies and as a result the nuclear reactor pressure vessel is taken out from the roof of the nuclear reactor building. 
     However, in the above stated prior art method, since the assembling working of the shield body in the nuclear reactor building equipment is accompanied with, such an assembling working requires the labor time and accordingly it takes the time for carrying out the shield bodies to an outside of the nuclear reactor building. 
     To avoid the labor time for requiring the assembly of the shield bodies in the nuclear reactor building, a technique described in Japanese application patent laid-open publication No. Sho 62-285100 has known. The contents described in this patent publication will be shown as follows. 
     Namely, a cask for storing the radioactive waste material is lifted by a crane which is provided at an outside of the nuclear reactor building and the cask is passed through a provisional opening which is provided with an opening and closing state on the roof of the nuclear reactor building and further the cask is lifted in the nuclear reactor building. 
     After that, the cask is separated once from the crane and the cask is placed on a floor of the nuclear reactor building and further the cask is moved in a horizontal direction at a position in which the radioactive waste material to be subjected to the carry-out exists. 
     Next, the radioactive waste material (in concretely, an upper portion cover of the nuclear reactor pressure vessel) is lifted in the cask using a lifting machine in the cask and after that a bottom portion of the cask is closed according to an opening and closing door. 
     After that, the cask is moved toward a horizontal direction at just an under portion of the provisional opening which has provided with the opening and closing state on the roof of the nuclear reactor building equipment. The cask is connected together with the crane and this cask is lifted up by the crane and further the cask is passed through the provisional opening of the cask and is carried out to the outside of the nuclear reactor building. 
     In the prior art technique described in Japanese application patent laid-open publication No. Sho 62-285100, it takes no labor time for requiring the assembly of the shield bodies in the nuclear reactor building, however it is effective to the reduction of radiation exposure and the diffusion of the radioactivity. However, in this prior art technique, the cask is separated once on the floor of the nuclear reactor building equipment from the crane and the cask is placed and after that the cask is moved toward the horizontal direction. 
     Accordingly, from the lift-in of the cask in the nuclear reactor building equipment until the lift-out of the cask, however since the working of the horizontal movement of the cask and the working of the connection and the separation of the cask and the crane are accompanied with, it takes the labor time yet. 
     In a case of the requirement of the above stated labor time, since the exchange-over of the internal structure is delayed, and further since also a re-operation time period of the atomic power plant station after the exchange-over of the internal structure is delayed, an operation efficiency of the atomic power station becomes worse. 
     Further, in a case of the decomposition of the atomic power plant station, there is a problem about a long-pending of the decomposition working. 
     SUMMARY OF THE INVENTION 
     An object of the present invention is to provide to a method of handing a nuclear reactor and an apparatus used in this handling method wherein it can be compatible with a speedy handling being accompanied with a carry-out for an internal structure of a nuclear reactor from a nuclear reactor building and a handling by reducing an exposure amount which is received by the working men from the radioactive internal structure. 
     For attainment the above stated object according to the present invention, it employs a method of handling an internal structure of a nuclear reactor, comprising the steps of lifting in a container in a nuclear reactor building from an outer side of the nuclear reactor building through an opening which is opened at an upper portion of the nuclear reactor building, maintaining the container under a condition in which the container is lifted at an upper portion of the internal structure of a nuclear reactor pressure vessel, storing the internal structure in the container which is maintained under the lifted condition, and lifting out the container which stores the internal structure toward an outside of the nuclear reactor building through the opening. 
     Further, it employs a method for exchanging over an internal structure of a nuclear reactor, comprising the steps of, taking out the internal structure through the opening which is opened at the upper portion of the nuclear reactor building in accordance with the above stated handing method of the internal structure, lifting up a new internal structure in the nuclear reactor building from the outside of the nuclear reactor building through an opening which is opened at an upper portion of the nuclear reactor building, installing the new internal structure in the nuclear reactor pressure vessel of the nuclear reactor building, and restoring the opening which is opened at the upper portion of the nuclear reactor building. 
     As an apparatus to realize the above stated methods, according to the present invention, it employs a handling apparatus of an internal structure of a nuclear reactor, comprising an opening opened at a portion of a nuclear reactor building which is positioned at an upper portion of a nuclear reactor well pool, a cask for storing the internal structure which has taken off from a nuclear reactor pressure vessel in the nuclear reactor building, a crane for lifting out and lifting in the cask from an outer side of the nuclear reactor building through the opening, and a hoisting device lifted up together with the cask according to the crane and for drawing in the internal structure in the cask. 
    
    
     BRIEF DESCRIPTION OF DRAWINGS 
     FIG. 1 is an outline longitudinal cross-sectional view of a nuclear reactor building or containment of an atomic power plant station of one embodiment according to the present invention; 
     FIG. 2 is an outline longitudinal cross-sectional view of a nuclear reactor pressure vessel shown in FIG. 1; 
     FIG. 3 is a longitudinal cross-sectional view showing a transfer and exchange working in a nuclear reactor building in a vapor-liquid separation apparatus in the nuclear reactor building shown in FIG. 1 and a vapor drying means to DS pool; 
     FIG. 4 is a longitudinal cross-sectional view in the nuclear reactor pressure vessel showing a state in which a shroud is lifted up from the nuclear reactor pressure vessel shown in FIG. 3; 
     FIG. 5 is a squint view showing a relationship between a cask during the lift-up state shown in FIG.  4  and the shroud; 
     FIG. 6 is a view showing a hole enclosing working according to a first embodiment and FIG.  6 ( a ) is a longitudinal cross-sectional view showing a relationship between the cask and a bottom plate of the cask and FIG.  6 ( b ) is an upper plan view showing a relationship between a bougie car and the bottom portion of the cask; 
     FIG. 7 is a view showing a hole enclosing working according to a second embodiment of the present invention, and FIG.  7 ( a ) is a longitudinal cross-sectional view showing a relationship between the cask and a bottom plate of the cask, and FIG.  7 ( b ) is an upper plan view showing a relationship between a bougie car and the bottom portion of the cask; 
     FIG. 8 is a view showing a hole enclosing working according to a third embodiment of the present invention, and FIG.  8 ( a ) is a longitudinal cross-sectional view showing a relationship between the cask and a bottom plate of the cask and FIG.  8 ( b ) is an upper plan view showing a relationship between a bougie car and the bottom portion of the cask; 
     FIG. 9 is a view showing a carry-in working state of the cask according to a first embodiment of the present invention, and FIG.  9 ( a ) is a longitudinal cross-sectional view showing a relationship between the cask and an opening and FIG.  9 ( b ) is A—A arrow mark direction of FIG.  9 ( a ); 
     FIG. 10 is a view showing a carry-in working state of the cask of a second embodiment according to the present invention, and FIG.  9 ( a ) is a longitudinal cross-sectional view showing a relationship between the cask and an opening and FIG.  10 ( b ) is A—A arrow mark direction shown in FIG.  10 ( a ); 
     FIG. 11 shows a longitudinal cross-sectional view showing after a state of a carry-out of the cask by lifting up the cask toward an upper portion of the nuclear reactor building; 
     FIG. 12 is a squint view showing a positional relationship between the cask immediately after a taking-out of the nuclear reactor building and an underground reservoir; 
     FIG. 13 is view showing a sequence of carry-out and carry-in of the nuclear reactor internal structure; and 
     FIG. 14 is an enlargement view of a receiving table of the bougie car. 
    
    
     DESCRIPTION OF THE INVENTION 
     Hereinafter, as one embodiment of a method of handling a nuclear reactor and an apparatus used in the handling method according to the present invention, an atomic power plant station having a boil water type nuclear reactor will be explained by taking as an exemplified example. However, the present invention will be applied to an atomic power plant station having another type of nuclear reactor. 
     In a nuclear reactor building  11  of an atomic power plant station having a boil water type nuclear reactor shown in FIG. 1, a nuclear reactor pressure vessel  3  is provided and this nuclear reactor pressure vessel  3  is stored by a nuclear reactor storing vessel  21 . 
     In the nuclear reactor pressure vessel  3 , as shown in FIG. 2, as an internal structure a steam dryer  5  and a vapor-liquid separator  8  and a shroud  1  etc. are provided. 
     In a space of an operation floor  9  of the nuclear reactor building or containment  11 , an overhead crane  8  is provided, and the overhead crane  8  is used in the working of the operation floor  9 . 
     In the operation floor  9 , a dryer separator pool  7  which is abbreviated as “DS pool” and a nuclear reactor well pool  10  which communicates to an interior portion of the nuclear reactor pressure vessel  3  are provided. 
     Among the internal structures, since the shroud  1  is a component which surrounds a reactor core of the nuclear reactor, among the internal structures the shroud  1  most strongly recieves the radiation. 
     In this embodiment according to the present invention, the working for exchanging over the shroud  1  will be explained. 
     The nuclear reactor pressure vessel  3  in the nuclear reactor building  11  of the atomic power plant station receives the fuels of the nuclear reactor and is a vessel to which a primary cooling member comprised the liquid is inserted. 
     The reactor core to which the fuels of the nuclear reactor are mounted is surrounded by the shroud  1 , and this shroud  1  is formed with a stainless steel cylindrical structure which isolates a flow in the cooling member which raises in the nuclear reactor and a re-circulation flow which descends a ring shape portion between an inner wall of the nuclear reactor pressure vessel  3 . 
     In this embodiment according to the present invention, the shroud  1  which is a subject of a carry-in working and a carry-out working between the inside and the outside of the nuclear reactor building  11  is a main large weight product among the machines and the apparatuses for constituting the atomic power plant station and has 70 tons weight. 
     The internal structure receives the high concentration radioactive rays because the internal structure is a machinery product which is passed through a primary system coolant and this internal structure is covered by a reinforce concrete shielding wall or a steel plate concrete shielding wall. 
     Further, a surrounding of the internal structure is stored in a steel shape nuclear reactor storing container  21  and this internal structure works a role of the prevention of the leakage of the radiation. 
     These atomic power plant stations, during a periodic inspection a damage state of the internal structure of the nuclear reactor is inspected, according to the demand, the internal structure is mended, however from the aspects of the economical performance and the prevention preservation, even in a midway of the durable years, there is a case over which the internal structure is exchanged. 
     To carry out the exchange-over for the internal structure, first of all to a sealing roof of the nuclear reactor building  11  which is positioned at a just above of the well pool  10  an opening  61  is formed as shown in FIG.  12 . The opening portion  61  is closed once according to a curing sheet  63  or a rolling system shutter  62 . In a case where an outside shielding wall  31  is installed at a roof portion of the nuclear reactor building  11 , the carry-in and carry-out use opening  61  is provided at the outside shielding wall  31  and this opening  61  has a size in which a cask  41  is enable to pass through. 
     At the same time, a large scale lifting machine  91  which is a large scale crawler crane is installed at a vicinity of the nuclear reactor building  11 . In a case of the installation of the large scale lifting machine  91 , as shown in FIG. 12, the ground for an operation area of the large scale lifting machine  91  is strengthened as an establishment ground  71 . 
     Further, as shown in FIG. 12, at the ground within a loading working radius range of the large scale lifting machine  91 , an underground reservoir  81  is formed and an inlet port of this underground reservoir  81  is opened upwardly. 
     Next, the carry-out working of the shroud  1  to the nuclear reactor building is carried out and in this carry-out working the cask  41  is used. 
     The cask  41  is pulled up and supported by a wire rope  12  from the lifting balance  51 , as shown in FIG.  5 . The cask  41  is constituted by a lower portion opened container having an inlet port at a lower portion. And at the ceiling portion of this cask  41 , a penetrating hole  54  is provided and in this penetrating hole  54  a wire rope  13  of a hoisting device  52  is passed through. This hoisting device  52  is installed to the lifting balance  51  and then the wire rope  13  is wounded up or paid out according to a remote operation. A hook  14  is provided to this wire rope  13 . 
     The lifting balance  51  and a hook block  93  of the large scale lifting machine  91  are connected by a wire rope  28  and the lifting balance  51  is pulled up and supported by the large scale lifting machine  91  to lift up and lift down freely. 
     The combination equipment of the above stated lifting balance  51 , the hoisting device  52 , and the cask  41  is prepared at the outer side of the nuclear reactor building  11 . 
     As shown in FIG.  6 ( a ) and FIG.  6 ( b ), to close the inlet port  27  provided at a bottom portion of the cask  41 , at an outer periphery of a cask bottom plate  42 , mail screws  42   a  of the cask bottom plate  42  is provided to engage with female screws  42   b  which are processed at an inner wall face of the lower portion of the cask  41 . The cask bottom plate  42  is mounted to the bougie car  43  through a receiving table  46 . The bougie car  43  is stridden over the well pool  10  and DS pool  7  and is installed to run freely on a rail  15  which is laid along to the well pool  10  and DS pool  7 . 
     The construction of the receiving table  46  is as following. Namely, as shown in FIG. 14, the receiving table is constituted by a rotary table  17  which is mounted on the bougie car  43  to rotate freely toward a horizontal direction through a thrust bearing  16 , an ascend and descend table  19  which is mounted on the rotary table  17  through an air pressure cylinder apparatus  18 , an inner gear  20  which is fixed to the above stated rotary table  17 , and a motor  23  for rotating and driving a pinion  22 . The manner for extending and contracting a piston rod of the air pressure cylinder apparatus  18  and the drive control of the motor  23  can be carried out from a remote place. 
     Accordingly, when the pinion  22  is rotated and driven by the motor  23 , the inner gear  20  and the rotary table  17  are rotated at the same time at a horizontal face. Further, by extending and contracting the piston rod of the air pressure cylinder apparatus  18  the ascend and descend table  19  can be moved toward the upward and downward direction, and then the ascend and descend table  19  can give the rotation operation and the ascending and descending operation to the cask bottom plate  42 . 
     In place of the respective screws  42   a  and  42   b  of the cask  41  to the cask bottom plate  42 , as shown in FIG.  7 ( a ) and FIG.  7 ( b ), faucet structures  44   a  and  44   b  can be employed. Further, as shown in FIG.  8 ( a ) and FIG.  8 ( b ), a bolt  24  is passed through a flange  45   b  which is fixed to the cask  41 , and a structure can be employed in which the cask bottom plate  42  is fastened to the cask according to the bolt  24  which is passed through a bolt passing-through hole  45   a  and a nut  25 . 
     As stated in above, the preparation of the exchangeover working is carried out, the exchange-over working is carried out as following. 
     FIG.  3  and FIG. 4 show an outline exchange-over working procedure in which the shroud  1  being the internal structure of the nuclear reactor is an object for exchanging over. 
     To exchange over of the shroud  1 , firstly a working for taking out the already established shroud  1  in the nuclear reactor pressure vessel  3  precedes. As the taking-out procedure, a cover  4  of the nuclear reactor pressure vessel  3  is released and the water is filled in the nuclear reactor pressure vessel  3  and in the well pool  10  to shield the radioactive rays and to prevent the diffusion of the radioactivity to the operation floor  9 . 
     After that, the steam dryer  5  and the vapor-liquid separator  6  are lifted out from the nuclear reactor pressure vessel  3  according to the overhead crane  8  and are laid in the water in DS pool  7 . Further, the steam dryer  5  and the vapor-liquid separator  6  are provided temporally and are stored. In this case, the vapor-liquid separator  6  and a shroud head are formed as one body and are lifted out. Further, the vapor-liquid separator  6  and the shroud head are laid in the water in DS pool  7  and are stored. 
     Next, the fuels in the nuclear reactor pressure vessel  3  are taken out from the nuclear reactor pressure vessel  3  to a suitable place and are stored. 
     Next, the water in the well pool  10  and the nuclear reactor pressure vessel  3  is drawn out and the radioactivity cleaning working in the nuclear reactor pressure vessel  3  is carried out. 
     Next, the curing sheet  63  which has closed the opening  61  of the nuclear reactor building  11  and the rolling system shutter  62  are operated to close the opening  61  and the opening  61  is performed to have an opened state. After that, until the restoration of the opening  61 , the pressure in the space of the nuclear reactor building  11  at least the operation floor  9  is maintained to a negative pressure condition to have a lower pressure than the pressure in the outside of the nuclear reactor building  11 . The maintaining means is carried out using a ventilation apparatus which is arranged at the space of the operation floor  9 . 
     Next, the lifting balance  51  is lifted up according to the large scale lifting machine  91  and the hoisting device  52  and the cask  41  are lifted up at the same time, and further the lifting balance  51 , the large scale lifting machine  91  and the hoisting deice  52  are lifted from the opening  61  and to carry out to approach to the well pool  10 . 
     Accordingly, the pull-up supporting condition between the lifting balance  51  according to the large scale lifting machine  91  and the large scale lifting machine  91  and the hoisting device  52  is maintained. 
     For this reason, the working, in which the lifting balance  51 , the hoisting device  52 , and the cask  41  are separated from the large scale lifting machine  91  and are reached to the operation floor  9 , is not carried out. 
     With the above stated process, the carry-in of the empty cask  41  is performed. After the carry-in of the empty cask  41  has carried out, the opening  61  is performed to have a narrow opening in which the wire rope for lifting up the lifting balance  51  of the large scale lifting machine  91  can be passed through by closing the curing sheet  63  and the rolling system shutter  62 . 
     By combining the procedure for maintaining at the above stated negative pressure condition, the atmosphere in the nuclear reactor building  11  is prevented to the utmost from leaking to the outside of the nuclear reactor building  11 . 
     Next, the wire rope  13  is paid out according to the hoisting device  52  and the hook lifting down working is carried out to approach the hook  14  toward the shroud  1 . Further, the nuclear reactor internal structure slinging working is carried out, in such a nuclear reactor internal structure slinging working, the wire rope  26  is paid out between a unitary structure which is constituted by the hook  14 , the upper portion lattice plate and the shroud  1 . 
     Next, the lifting-up working for lifting up the wire rope  13  according to the hoisting device  52  is carried out and then the shroud  1  is pulled up and supported as shown in FIG. 5, and the shroud  1  is stored gradually to the inner side of the cask  41  and as a result the receipt in the cask working is carried out. 
     Next, the bougie car  43  is run along to the rail  15  and is stopped just above the well pool  10 . Then the cask bottom plate which is mounted on the bougie car  43  can be positioned just under the cask  41 . 
     Next, the ascend and descend table  19  of the receiving table  46  is pushed up according to the air pressure cylinder apparatus  18  and the ascend and descend table  19  is rotated toward the horizontal direction, then with the female screws  42   b  of the cask  41  the male screws  42   a  of the cask bottom plate  42  is engaged, the inlet port  27  of the cask  41  is closed, accordingly the cask hole enclosing working is finished. 
     To more ensure the closing condition of the cask hole, a boundary portion between the cask bottom plate  42  and the cask  41  is performed to weld and to fix according to the welding manner and to carry out the seal welding. Further, the shroud  1  is lifted down on the cask bottom plate  42  according to the hoisting device  52  and the respective wire ropes  13  and  26  are given a condition where the shroud  1  is given the tension where the shroud  1  is not failed down. 
     The construction to which the hole closing working about the cask  41  is employed are exemplified according to the two examples shown in addition to those shown in FIG.  6 ( a ) and FIG.  6 ( b ), however in the constructions shown in FIG.  7 ( a ) and FIG.  7 ( b ), the cask bottom portion is formed with the faucet system and the closed condition is shown. 
     The shroud  1  is lifted up to above from the floor of the operation floor  9 , and on the bougie car  43  the cask bottom portion having the faucet structure  44   a  through the receiving table  46  is mounted on and the shroud  1  is run and moved at just under the cask  41 . The cask bottom portion  42  is raised similarly to in the above, the faucet structure  44   a  is inserted into the cask  41  and after that the cask bottom portion  42  is rotated toward the horizontal direction. 
     Then the cask bottom portion  42  is aligned to the position where the faucet structure  44   b  is fitted into faucet structure  44   b  at the cask side in the cask  41  and the receiving table  46  is retarded toward the lower portion from the cask bottom portion  42  and even those faucet structures between the cask  41  and the cask bottom plate  42  are meshed and fixed. 
     According to the commands, the boundary portion between the cask  21  and the cask bottom plate  42  are fixed according to the welding manner or the sealing welding manner and then the closing condition of the inlet port  27  of the cask  41  is performed more surely. 
     In the examples shown in FIG.  8 ( a ) and FIG.  8 ( b ), similarly to the examples shown in FIG.  6 ( a ) and FIG.  6 ( b ), the cask bottom portion  42  is positioning aligned by aligning to just under of the inlet port  27  of the cask  41 . After that, at the position of the bolt  24  a bolt through-out hole  45   a  is rotated the cask bottom plate  42  toward the horizontal direction by the cask bottom plate  42  according to the receiving table  46  to coincide with the upward and downward directions. After that by the receiving table  46  the cask bottom plate  42  is arisen and the bolt  24  is passed through the bolt passing-through hole  45   a  and the screw portion of the bolt  24  which is come out toward the lower portion from the bolt passing-through hole  45   a  is engaged with the nut  25  and the nut  25  is tied up and then at the lower end of the cask  41  the cask  41  is adhered and accordingly the hole closing working is carried out. 
     In this case, according to the demands the boundary portion of the cask  41  and the cask b bottom plate  42  is fixed to and seal-welded according to the welding manner and then the sealing condition to the inlet port  27  of the cask  41  can be performed surely. 
     Further, when the sealing condition of the shroud  1  according to the cask  41  is performed surely to transfer, according to the hoisting device  52  the shroud  1  is received in the cask  41  and after the hole closing working of the inlet port  27  of the cask  41 , the wire rope  13  of the hoisting device  52  is pulled out and the shroud  1  is set down on the cask bottom plate  42 . 
     The the hook  14  and the wire rope  13  together is taken out from an upper portion passing-through hole  54  and then the hole closing working of the upper portion passing-through hole  54  is carried out. 
     The hole closing working may be the screw system in which the cover is screws to the upper portion passing through hole  54  or may be the welding system in which the cover is welded to the upper portion passing-through hole  54  or may be flange system in which using the bolt and the nut the cover is fastened to the cask  41 . With the above stated structure, now the element in which the atmosphere in the cask  41  leaks to the outside of the cask  41  become nothing. 
     When the cask hole closing working has finished, next, as shown in FIG.  9 ( a ) and FIG.  9 ( b ), a lifting rope  92  is wound out from a large scale lifting machine  91  according to the large scale lifting machine  91  and a hook block  93  of the large scale lifting machine  91  which is lifted to the lifting rope  92  is lifted near to the opening  61 . With this structure, further the lifting balance  51  which is lifted up from the hook block  93 , the hoisting device  52  and the cask  41  are lifted near to the opening  61 . 
     Next, it will enter the opening passing-through working, firstly the rolling system shutter  62  is opened and further the opening  61  is opened, next by the large scale lifting machine  91  the lifting rope  92  is wound up further from the large scale lifting machine  91  and to the opening  61  the lifting balance  51 , the hoisting device  52  and the cask  41  are passed through. As shown in FIG. 11, the rolling system shutter  62  is closed and further then the opening  61  is closed. 
     After that the above stated opening passing-through working is performed, the lifting balance  51 , the hoisting device  52  and the cask  41  are lifted up toward the upper portion from the nuclear reactor building  11  and then the lifting up working in which the lifting balance  51 , the hoisting device  52  and the cask  41  are carried out to the upper portion of the outside of the nuclear reactor building  11  is carried out. 
     In the condition in which the rolling system shutter  62  is opened, from the opening  61  the atmosphere in the nuclear reactor building  11  is tried to leak toward the outside of the nuclear reactor building  11 , however the pressure in the nuclear reactor building  11  is managed to a lower negative pressure condition than the pressure in the outside of the nuclear reactor building  11 . 
     Accordingly, the leakage of the atmosphere in the nuclear reactor building  11  is checked and the restraint of the radioactivity diffusion toward the outside of the atmosphere in the nuclear reactor building  11  can be strengthened. 
     This rolling system shutter  62  is formed by making the large scale of a construction of a diaphragm mechanism of a camera and the opening  61  can be opened according a move of four diaphragm blades toward a radial direction. 
     In place of the rolling system shutter  62 , as shown in FIG.  10 ( a ) and FIG.  10 ( b ), the shape of the opening  61  can be formed with a quadrangle shape and from four sides of the quadrangle shape directing toward a center of the opening  61 , four curing sheets  63  are spread by proceeding to the horizontal direction and the opening  61  is closed, in reversely by folding the four curing sheets  63  the opening is opened, according a construction for opening and closing the opening  61  can be employed. 
     Another means for preventing the leakage of the atmosphere to the minimum through the opening  61  from in the nuclear reactor building equipment  11 , there is a method for enclosing the cask  41 , as shown in FIG.  10 ( a ) and FIG.  10 ( b ). 
     Namely, in the above stated another method, firstly the cask  41  is lifted by approaching the cask  41  to the opening  61  through the large scale lifting machine  91  and holding under this condition the lifting balance  51 , the hoisting machine  52  and the cask  41  are enclosed by a sheet which is installed sealable to four sides of the opening  41  and between a space of the cask  41  from the sheet  64  and a space of the operation floor at an outside the communication of the atmosphere can be prevented. 
     After that, the curing sheet  63  is folded at a side of the four sides of the opening  41  and the opening  61  is opened and after the lifting balance  51 , the hoisting machine  52  and the cask  41  are lifted at a height of the cask  41  as shown in FIG. 11, and then the shroud  1  is stored from the nuclear reactor building  11  and are carried out the outside. 
     Even when the opening  61  is opened, since there is a possibility in which only the atmosphere at the space of the cask  41  side from the sheet is leaked at the maximum, a safety can be attained, and further in a case of the open of the opening  61 , even the rush-in matters from the outside of the nuclear reactor building  11  and the atmosphere are entered into the space of the operation floor  9 , the rush-in matters and the atmosphere are enclosed by the sheet  64 , accordingly the diffusion of the atmosphere in the space of the operation floor  9  can be prevented. 
     Next, after the lifting of the cask  41  which has stored the shroud  1  is carried out toward the upper portion of the nuclear reactor building  11 , by swirling the boom of the large scale lifting machine the cask  41  is positioned at the just upper portion of an underground reservoir  81 , accordingly the swirl working is carried out. 
     Next, the cask  41  is fixed in the underground reservoir  81  and then the storage storing and fixing working is carried out. 
     Next, the wire rope  12  is taken off from the cask  41  and the cask  41  is taken off from the lifting balance. Further, the wire rope  13  is cut off, for example, and the connection between the hoisting machine  52  and the shroud  1  is released, the slinging-out working is carried out, and next the inlet port of the underground reservoir  81  is covered and closed, then the carry-out working is finished. 
     In a case of the decomposition of the atomic power plant station, in place of the above stated carry-out working a newly shroud is carried in the nuclear reactor pressure vessel  3  and then in this case the installation working is not accompanied with. 
     However, in a case of the replace working of the shroud  1 , after the finish of the carry-out working, the carry-in working of a newly shroud in the nuclear reactor building equipment  11  is accompanied with. 
     The above stated carry-in working is carried out in accordance with the working process which is indicated as the carry-in working at a right side of FIG.  13 . Namely, first of all, the new shroud is transported at the goods receipt position where the new shroud can be lifted by a trailer etc., accordingly the nuclear reactor internal structure transportation working is carried out. 
     Next, between a hook block  93  of the large scale lifting machine  91  and the new shroud, the nuclear reactor internal structure slinging working for laying the wire rope is carried out. 
     Next, the new shroud is lifted up at the goods receipt position according to the large scale lifting machine  91  and by swirling the boom of the large scale lifting machine  91  toward the horizontal direction the new shroud is positioned just above of the opening  61 , according the lifting-up and swirling working is carried out. 
     Next, the opening  61  is opened by operating the rolling system shutter  62  or the curing sheet  63  and the new shroud is lowered according to the large scale lifting machine  91  and the opening  61  is passed through and entered into the nuclear reactor building  11 . 
     Next, the opening  61  is closed, except for a clearance in which the lifting rope  92  can be passed through, according to the rolling system shutter  62  and the curing sheet  63 , accordingly the lowering and opening passing-through working is carried out. 
     In this above stated case, since the pressure in the nuclear reactor building  11  is managed to have the lower negative pressure management condition than the pressure in the outside of the nuclear reactor building  11 , the leakage of the atmosphere in the nuclear reactor building equipment  11  can be checked and the radioactivity diffusion toward the outside of the atmosphere in the nuclear reactor building  11  can be prevented. 
     Next, the new shroud is lifted down further and entered into the nuclear reactor pressure vessel  3  and this new shroud is set at the position where the previous established shroud  1  has existed, accordingly the nuclear reactor internal structure installation and setting working is carried out. 
     Next, the wire rope which is laid out between the new shroud and the hook block  93  is taken out from the new shroud, accordingly the slinging-out working is carried out. 
     After that, the above stated hook block  93  is lifted out at the outside of the nuclear reactor building  11  and then the carry-in working is finished. 
     After that, the opening is restored to the original state, accordingly the carry-in and carry-out use opening restoration working is carried out. Next, the large scale lifting machine  91  is decomposed and withdrawn. 
     According to the invention, since the container which is lifted in the nuclear reactor building is positioned above the internal structure of the nuclear reactor pressure vessel under a lifted condition and the internal structure is inserted in the container under the lifted condition, and since in the nuclear reactor building, there are unnecessary to carry out an assembly of the container a lowering of the container to a floor in the nuclear reactor building, a horizontal move on the floor, a connection and a release to a lifting means of the container after the lowering, and a connection working during the lowering and further it can transfer to the lifting out working, leaving the container with the lifted condition the internal structure can be stored in the container and the internal structure can be carried out speedy at the outside of the nuclear reactor building, and further the container can be shield the diffusions of the radioactive rays and the radioactivity from the internal structure, as a result the effects of the diffusion of the radioactivity in the nuclear reactor building and the restraint of the radiation exposure can be attained. 
     According to the invention, as the container the cask is used. 
     According to the invention, by accompanying the cask with the hoisting device the cask and the hoisting device are lifted in the nuclear reactor building, after the lifting-in according to the hoisting device which is arranged at the outer side of the cask the internal structure can be lifted up from the nuclear reactor pressure vessel and the internal structure can be stored in the cask and the internal structure can be carried out more speedy at the outside of the nuclear reactor building and the radioactive rays in the cask from the internal structure can be shielded according to the cask, as a result the effects can be obtained such effects are that the hoisting device which is arranged at the outer side of the cask does not strongly recieve radiation and it may be dispensed with to make little a part which becomes to a radioactive waste material. 
     According to the invention, since the cask bottom portion member is carried in to the lower portion of the inlet port of the cask according to the bougie car and the inlet port of the cask is closed by the cask bottom portion member and the move of the cask bottom portion member is carried out according to the bougie car and further the cask is lifted up always and the space for enable to carry in the cask bottom portion to the lower portion of the inlet port of the cask is obtained easily, as a result the closure working can be carried out speedy, and also the inlet port of the cask can be closed at the height near to the operation floor, the effects in which the diffusion of the radioactivity into the nuclear reactor building and the restraint of radiation exposure can be attained more effectively. 
     According to the invention, using the same crane since the lifting-out of the cask from the nuclear reactor building to the lifting-in to the reservoir can be carried out consistently, the carry-in working of the internal structure to the reservoir can be speedy by lessening the intermittent working. 
     According to the invention, by limiting to the passing-through of the cask to the opening, the opening is opened widely according to the opening and closing apparatus and the leakage of the atmosphere in the nuclear reactor building to the outside of the nuclear reactor building which occurs by the open of the opening can be restrained and further the inside of the nuclear reactor building is formed to the negative pressure in comparison with the outside of the nuclear reactor building and the occurrence of the flow of the atmosphere from the opening to the outside of the nuclear reactor building can be deprived of and then the leakage of the atmosphere in the nuclear reactor building to the outside of the nuclear reactor building can be restrained from an aspect of the pressure, and further employing a complex means of the opening and closing apparatus and the pressure adjustment the leakage of the atmosphere in the nuclear reactor building to the outside of the nuclear reactor building can be deprived of, and as a result an effect in which the discharge of the radioactivity to the outside portion can be avoided at the utmost. 
     According to the invention, in a case where the cask is lifted out to the outside of the nuclear reactor building through the opening, since the leakage of the atmosphere in the nuclear reactor building from the opening is shielded according to a sheet for enclosing the cask and since the leakage of the atmosphere in the nuclear reactor building from the opening is prevented, as a result an effect in which the discharge of the radioactivity to the outside portion can be avoided at the utmost. 
     According to the invention, an effect in which the shroud as the internal structure is handled collectively and effectively by not subdividing the shroud can be obtained. 
     According to the invention, since the internal structure in the nuclear reactor can be exchanged speedy and as a result an effect in which the time of the re-operation of the nuclear reactor using the renewed internal structure of the nuclear reactor can be hastened. 
     According to the invention, in addition to the effect of the invention defined in claim  9 , the shroud as the internal structure is carried out collectively from the nuclear reactor building by not subdividing the shroud and as a result an effect in which the shroud is exchanged speedy can be obtained. 
     According to the invention, the cask which is lifted by the crane from the outside of the nuclear reactor building equipment is lifted together with the hoisting device in the nuclear reactor building from the opening of the nuclear reactor building, and the cask which is lifted in the nuclear reactor building and the hoisting device are held by chinning the crane and the hoisting device which is lifted up according to the crane lifts the internal structure and then the internal structure carried out the double chinning state, and the internal structure is lifted up further according to the hoisting device and drawn in the cask, after the internal structure is drawn in and stored, under the stored condition of the internal structure the internal structure and the cask are passed through together with the opening of the nuclear reactor building according to the crane and is lifted up, then the operation for carrying out the nuclear reactor building to the outside can be obtained. 
     According to this operation, since the internal structure is stored in the cask and is treated, the scattering of the radioactive and the radioactivity material from the internal structure can be restrained according to the cask and under the chinning condition of the hoisting device and the cask according to the crane the storing working of the internal structure in the cask can be carried out, and as a result an effect in which the internal structure can be treated speedy without the accompanying of the attachment and detachment working of the cask to the crane in the nuclear reactor building can be attained. According to the invention, since the inlet port of the lower end of the cask is closed according to the cask bottom plate, the radiation ray exposure of the operators and the diffusion of the radioactive material from the internal structure can be restrained. 
     According to the invention, since the working for closing the inlet port of the cask is carried out speedy using the boggier car, an effect for providing the handling apparatus of the internal structure of the nuclear reactor in which the more speedy carry-out of the internal structure of the nuclear reactor can be provided. 
     According to the invention, an effect in which the shroud as the internal structure can be handled speedy by not subdividing the shroud can be obtained.