KR930008245B1 - Improvements in/or relating to the disposal of waste material - Google Patents

Abstract

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Description

Waste disposal plant

1 is a cutaway perspective view of a packaging facility.

FIG. 2 is a cutaway perspective view of a powerful compactor used in the packaging facility illustrated in FIG.

3 is a cutaway perspective view of a waste disposal plant.

4a or a top plan view of a packaging module.

4b is a side cross-sectional view of the module.

4c or bottom view of the module.

5a or top view of the module cap.

5b is a partial side cross-sectional view of the cap illustrated in FIG. 5a.

6 is a perspective view of a packaged and sealed module.

7 is a cutaway perspective view of a packaged module.

* Explanation of symbols for main parts of the drawings

1: Packing facility 3: Remote control unit

85: contact adjustment unit 110: powerful compactor

150: treatment plant 200: module

The present invention relates to a treatment plant for toxic substances or nuclear wastes having a cap supported by a rigidly packaged arrangement of waste-containing modules that is flexibly arranged in response to changes in the shape of the terrain caused by earthquakes or other natural disasters.

Burial systems for depositing nuclear waste are well known. In these early systems, such waste was packaged in only 55 gallon steel drums and simply dropped into underground trenches by long-sized cranes. Unfortunately, such "kick and roll" store systems have proved generally unsatisfactory for the underground treatment of nuclear waste. Loose soil filled in these trenches permeates more water than dense compacted soil that forms the size of the trench or dense rock strata that usually form the bottom of the trench. In addition, the relatively loose, water-soaking soil surrounding the drum causes these trenches to collect a significant amount of static water known as the "bathtub effect." These stops eventually cause the steel walls of the drums buried in the trenches to corrode and collapse. The density of collapsed drums and soils causes the soil to sink in downward motion over time, making it difficult to form trench governments. This sedimentation collects surface water, which worsens the trench maintaining a pool of static water on the drum. Eventually, the increase in the number of stops would still cause more soil to sink and accelerate the corrosion and collapse of the drum embedded in it. In such areas, the erosion and collapse of the drums caused problems of radioactive contamination of groundwater flowing through it.

Various burial systems have been developed to address soil sinking and water accumulation problems in the "kick and roll" treatment area. These include container burial areas where the space between the waste container and the underground storage cell with structurally rigid walls is filled with concrete or some other hardenable grout. These various systems would certainly be more advanced than the trenches used in simple "kick and roll" handling systems, but several drawbacks were also found. For example, underground storage rooms are used in combination with structurally rigid walls, but such walls are prone to breakage and breakage in the event of an earthquake. Once the integrity of the cellar is lost, groundwater flows in and accumulates around waste packages. If these paving plants were metal walls, the static water around them eroded the walls, causing radioactive waste to enter the groundwater. Since such underground storage rooms typically have only one access opening, the recovery capacity of one leak pavement is nearly sparse. Buried areas, where the curable material is poured over a large group of waste containers to form a solid monolith, have a higher resistance to cracking or breaking in the event of an earthquake, but this particular type of treatment plant can There is a tendency to apply very high local stresses on waste containers located in the passage of failure. Moreover, this type of treatment plant has a problem in recoverability when only some or one of the grout-encapsulated containers is destroyed by the earthquake. Relocation of the treatment plant would be the only solution in case of breakage or breakage of inaccessible containers.

Thus, there is a need for a treatment plant that is structurally stable but flexible due to earthquakes or other natural disasters, so that no local container failure stresses can occur. In addition, if several or only one of the containers buried in an earthquake or other natural disaster is destroyed, it is desirable to be able to easily and conveniently recover individual containers buried in such a treatment plant to eliminate the hassle of moving the entire area. . The burial area should also have a device to prevent the buildup of static water around the arrangement of the containers in order to extend the life of the buried containers. Finally, it is desirable that such a plant be easily made of inexpensive materials.

According to the present invention, a treatment plant for the treatment of toxic waste materials includes a cap in which non-rigid water is superimposed on an impregnated ground formed of an impregnated ground and a hard material, and an encapsulation of the waste in the impregnated ground and the non-rigidity of the impregnated ground. It is characterized by consisting of a plurality of modules installed under the cap to structurally support the cap.

The present invention also includes a treatment plant for the treatment of radioactive waste, the treatment plant comprising: a radiation shielding cap in which trenches in the ground and non-rigid water overlapping the trenches flow; It consists of an array of modules installed under the cap to encapsulate and support the non-rigid cap on the trench. The cap preferably has a natural silt layer to allow surface water to flow away from the trench to prevent water from accumulating around the modules buried in the treatment plant. In addition, a layer of coarse grain material having high water conductivity may be located between the top of the module and the bottom of the silt layer to prevent water from leaking into the module through the silt layer by capillary action. In a preferred embodiment, the coarse particulate material used in the layer is gravel. A tidal layer is also placed on the silt surface of the silt layer to protect the silt from wind and water corrosion, providing a radiation barrier and an intrusion barrier for waste-containing modules contained within the treatment plant.

The trench in the ground has a flat bottom and the bottom of the trench contains a layer of water-conductive material of coarse particles such as gravel to prevent water from leaking into the module by capillary action. In addition, multiple lymeters are distributed at the bottom of the trench at locations below the gravel layer to collect samples of water that will later be used to measure radioactive leakage from the module.

The module used in the treatment plant of the present invention is preferably in the form of a right-angle prism that is tightly stacked in layers that can slide with each other, as well as in which each column is stacked in a column type that can slide in a vertical direction with respect to another column. Do. This tightly packed arrangement provides a non-depressed structure that can support the non-rigid cap of the plant, but is flexible as the terrain changes caused by earthquakes or other natural disasters.

Finally, the present invention relates to a method for depositing nuclear waste contained in a plurality of modules that can be tightly packed in a uniform shape, digging a trench, and tightly packing the modules that can be tightly packed one by one in the trenches. In order to minimize the exposure of the surrounding area with radiation emitted from the module, a non-rigid, water-blocking cap formed of a rigid material that can flow when the trench is filled with a rigid array of such modules is placed on top of the module. Characterized in that it is located.

BRIEF DESCRIPTION OF THE DRAWINGS Preferred embodiments thereof will be described with reference to the accompanying drawings in order to more clearly understand the present invention.

Like reference numerals in the drawings indicate like parts. In FIG. 1, the packaging facility 1 of the system according to the present invention includes a remote control waste packing unit 3 on the left side of a building, a module loading and transport unit 60 in the center of the building, and a contact control waste unit on the right side of the building ( 85 It is comprised of four isolation walls 2a, 2b, 2c, and 2d which are enclosed. The remote and contact waste fractions 3, 85 each comprise drive passages 7, 87. In these driveways 7,87 the trucks 13,95 are relatively lightweight shipping containers (i.e. liners, 55-gallon drums, and so on) in remotely generated waste areas for encapsulation into relatively heavy and rigidly packed modules. Deliver remote and contact controlled nuclear waste into an LSA container. In a preferred embodiment, the final treatment plant 150 of the module 200 packaged by the packaging facility 1 is equipped with a facility 1 to minimize the distance the packaged module 200 (which weighs more than 30,000 pounds) is transported. It is located very close to). First, it should be noted that there is at least three important advantages for facilities that are located far away from the waste generating area, but which are surrounded by isolated walls in the final treatment plant 150. Firstly, the relatively heavy module 200 does not need to be transported to the waste generating area, and secondly, if the waste generating area is not likely to be contaminated from pavement accidents, and thirdly, the separating walls 2a, 2b, 2c, and 2d are treated with a treatment plant ( 150) minimizes the possibility of contamination from any packaging accident.

Returning now to a more detailed description of the remotely controlled waste portion 3 of the plant 1, the portion 3 has a driveway 9 having an inlet (not shown) and an outlet 11 for receiving the transport truck 13. ) Is included. Such a truck 13 will carry a load of nuclear waste in a reusable, shielded shipping cask 15 of the type permitted by the United States Department of Transportation or the Nuclear Regulatory Commission. Installed in this shielded shipping cask 15 are metal or plastic liners (not shown) that will retain waste. The waste part 3 of the installation 1 also comprises a treatment platform 18 at the same height as the bed of the truck 13, a shielding bell 19 with a hook assembly 21, and a remotely controlled traveling crane ( 23) and so on. The shielding bell 19 is preferably formed of a steel shell with a lead liner having a thickness sufficient to reduce the amount of radiation generated from the non-contact waste to an acceptable level. The crane 23 comprises a primary hoist 25 which is removably connected to the hook assembly 21 of the shielding bell 19 via a pulley assembly 27 which is operated by an electric motor. In addition, the traveling crane 23 is the carriage 29 and the "Y" direction (equipment for moving the primary hoist 25 in the "X" direction (direction parallel to the drive path 9 of the drive passage 7). And a trolley 33 for moving the primary hoist 25 in a direction parallel to the front surface of the front side (1). The pulley assembly 27, operated with a vertically adjustable electric motor together with the carriage 29 and the trolley 33, adjusts the traveling crane 23 to the chapebell over the loading cask 15 of the transport truck 13. Swing 19, take out the liner containing waste out of the cask 15, and place the liner in the required position on the treatment platform 18.

Although a remote control traveling crane 23 operated via a T.V monitor is used in this embodiment, other types of existing remote control crane mechanisms may be used to implement the present invention, regardless of the number. In addition to the primary hoist 25, a secondary hoist 35 is also connected between the traveling crane 23 and the shielding bell 19. The secondary hoist 35 controls the position of the cables and hooks (not shown) in the shielding bell 19 that can bind the waste containing liner installed in the shielded shipping cask 15.

The remote control waste part 3 of the building installation 1 is equipped with a variety of radiometers 39 and ultrasonic meters 41 to ascertain whether the contents of the liner in the shipping cask 15 comply with the requirements. Area 37 is included. Radiation meter 39 is used to measure the intensity of radiation emitted from waste contained in the liner and to examine the radiation spectrum “symbol” of the waste to ensure that it meets the requirements for loading. Ultrasonic meter 41 is used to determine what radioactive liquid is present with the liner or not. Federal regulatory provisions strictly forbid the burial of radioactive waste in liquid form, so the information provided by the ultrasonic meter 41 is of considerable importance. The radiation meter 39 and the ultrasonic meter 41 are electrically connected to the bank of the read dial 45 by a cable installed in the groove 43 in the processing platform 18. Although not shown exactly in any of the figures, the outputs of the radiation meter 39 and the ultrasonic meter 42 indicate how many specific types of waste material are for record keeping purposes and before the surface radiation of the module 200 exceeds the set limits. It is fed to a central computer to determine if it is loaded into a particular module. The central computer can also calculate how much grout should be put into a specific loading module to properly encapsulate the waste, and the ultrasonic meter 41 indicates that the waste contained in the liner is in an unacceptable percentage of liquid form. Has the ability to activate an alarm circuit when

In a preferred embodiment the height of the treatment platform 18 is approximately equal to the bed height of the trailer truck 13 so that any worker who may be on the platform 18 when the cover is removed from the cask 15 is removed. Do not expose to radiation emitted from governments of India. During operation, the shield bell 19 descends into the open cask 15 to bind the liner therein and then swings over the meter 39, 41 in the specific area 37 and reflects off the platform 18. Quickly descend within a few inches from these meters to minimize the exposure of waste 3 to any radiation emitted from the bottom of (19). Down quickly. In a preferred embodiment, the treatment platform 18 is formed entirely of solid slab of concrete for structural rigidity of the installation 1 and for shielding purposes as a whole. The shielding purpose will become clearer after the structure and function of the rack storage well 50 is described. Although the specific area 37 of the preferred embodiment includes only the radiometer 39 and the ultrasound meter 41, other types of metering devices (such as remote TV monitors for visually identifying waste) may be included if desired. .

Finally, the remote control waste 3 of the plant 1 comprises a repair work chamber 53 which is formed of four rack storage wells 50 and a shielding wall 54 and accessible through the shielding door 55. Doing. Each rack storage well 50 includes a cylindrical well covered with a disc shaped cover. The rack storage well 50 inspects a particular area 37 for excessive amounts of liquid or other unacceptable conditions and then provides a safe and convenient storage area for nuclear waste shipments. Additionally, rack storage wells may be used to temporarily store remote control waste when grouting area 118 is filled. The material and thickness of the disk-shaped cap on top of the well 50 is selected to reduce the amount of radiation emitted from the remotely controlled waste that can be stored therein to the working area of the waste section 3 to within a safe level. The maintenance workshop provides a separate area within the remote control waste section 3 of the installation 1, where the broken liner (or liquid containing liner) is located in the entire installation 1 or remote control waste section 3. It is properly repaired or disposed of without risking contamination of the main parts. As will be described more clearly below, the installation of a separate work chamber 53 for repairing a broken wall of the liner results in three radiations in which the wall of the liner is in module 200 when the liner is grouted in one module 200. And water barriers. When free liquid is found in the waste liner, the repair shop 53 provides an area where the liquid can be mixed with a suitable absorbent or other solidifying media, allowing the liquid to be buried within the limits of current federal regulations. In solid form. Under normal circumstances, rack storage wells 50 or maintenance rooms 53 are not used to handle remote control waste. Instead, after a particular test is completed, these wastes are usually remotely hoisted to pass through the maze exit 56 formed by the shielding walls 57a and 57b, which form the back side of the waste portion 3, The waste is placed in module 200 on rail car art 64 on the passageway to grouting area 118.

The module loading and transporting unit 60 is located in the center of the facility 1 between the remote control unit 3 and the contact control unit 85. Positioning the module loading and transporting unit 60 in the center makes it possible to conveniently perform operations of the remote and contact control units 3 and 85 of the plant 1.

In general, the module loading and transporting unit 60 is a conventional traveling crane 62 (which is the driving crane 23 described above) for loading the modules 200 stacked on the rail car art 64 outside the facility 1. Has all parts and abilities). The rail car 64 is free to move along a pair of parallel loading rail assemblies 66a, 66b. The beds 70a and 70b, on which the tracks 68a and 68b are installed to allow the rail car art 64 to move freely, are slightly inclined so that the tracks 68a and 68b of the loading rail assemblies 66a and 66b are bound. The car art 64 is allowed to roll the track freely by gravity. Although not shown in the figures, each of the loading rail assemblies 66a, 66b is operated with multiple pneumatics to stop the rail carart 64 in the loading grouting and capping positions along the loading rail assemblies 66a, 66b. It includes stop mechanisms. The module loading and transporting unit 60 includes a return rail assembly 74 having a bed 78 inclined in a direction opposite to the beds 70a and 70b of the loading rail assemblies 66a and 66b. Since the bed 78 of the return rail assembly 74 is inclined in the opposite direction, the rail carart is free to move on the track 76 freely by gravity, grouted, and the capped module 200 falls off and then loads and It is possible to return to the loading position in the transport section 60. Finally, the shielding wall 79 (preferably formed of a solid concrete wall having a thickness of at least 12 inches) is provided in the shielding bell 19 as the remote control waste is loaded and grouted into one module 200. It is located between the rail assembly 66a and the return rail assembly 74 to prevent exposure of the contact 85 from the included remote control waste. The shielding wall 79 generally has two functions, one of which allows the contact control waste part 85 to be sealed in the same facility as the remote control waste part 3, and the other is remote of the facility 1. And the use of the common module loading and transporting unit 60 for the contact adjustments 3, 85. This last function has the advantage of eliminating the need to install two redundant loading and transport systems.

Returning to the now-controlled waste section 85, this part of the plant 1 contains a number of identical parts present in the remote control section 3. For example, the contact portion 85 has a drive passage 87 comprising a drive passage 89, an inlet 90 and an outlet (not shown) of the same kind as described above with respect to the drive passage 7. . The contact 85 also includes a treatment platform 93, which is preferably formed from a rigid slab of concrete raised to approximately the same height as the bed of the truck to facilitate the unloading of the packaged waste from the transport truck 95; have. The contact portion 85 also has a pair of specific regions 107a and 107b and a rack storage will 113. Finally, contact 85 includes a repair workshop 112 to repair broken containers and to convert liquid and other improperly packaged waste into a solid form suitable for burial.

However, despite the common parts with these remote parts 13, the contact part 85 contains several other parts that are unique within the plant 1. For example, a relatively lightweight jib crane 99 with a magnetic or vacuum hoist 101 is used instead of the relatively heavy traveling crane 23 of the remote part 3. Since the waste treated at the contact 85 has a sufficiently low radiation level and can be in direct contact with the worker, there is no need for a crane to lift the heavy shielding bell 19 used at the remote part 3. Also, the crane used for the contact 85 only needs to be able to lift the lightly packed nuclear waste arriving at the plant 1 with the 55 gallon steel drum 97. Several light shields have been used for the contact 85 of the installation 1, but the low radiation level of the waste being processed in this area eliminates the need to heavy shield each steel drum 97 containing waste.

Accordingly, the conveyor system 103 formed from the roller is provided to facilitate the handling of the drum 97 containing waste. Finally, the powerful compactor 110 condenses the waste into smaller volumes and the drum around it so that during grouting the waste is below the point at which the waste is above the inelastic limit of steel that cannot be "spring back" in the volume. It is provided to squeeze. This is a very important advantage and will be described in detail later in this specification.

The conveyor system 103 includes a pair of continuously arranged compactor conveyor belts 105a and 105b and a maintenance work conveyor belt 106. The effector conveyor belt 105a forces the 55 gallon drum 97 containing contact conditioning waste from the jib crane 99 through a first specific region 107a including an ultrasonic and radiometer (not shown). It moves to the loading mechanism 110.1 of the compactor 110. The powerful compactor 110 applies a pressure between 500 and 1100 tons to a 55 gallon drum container to reduce them to a high density "puck" 117 with a density between 60-70 pounds / cubic feet.

In the preferred embodiment, a compression force of 600 tonnes is usually used. The high density puck 117 exits the powerful compactor 110 and slides down the lamp 111.2 on the compactor conveyor belt 105b, thus similarly equipped with a second specific equipped with an ultrasonic and radiometer (not shown). It facilitates movement of the puck 117 through area 107b. The conveyor belt 105b then moves the high density puck 117 to the magnetic or vacuum hoist 116 of the jib crane 114 to swing the puck 117 into the module 200 on the way to the grouting area 118. . The maintenance work conveyor belt 106 has a specific area 107a in which (a) the drum 97 contains liquid, (b) the wall of the drum 97 is broken, or (c) the drum 97 It starts to run when the waste contained in) is measured, for example, that it cannot be compressed.

If any one of the above three situations has been measured, an operator (not shown) simply slides the drum 97 from the compactor conveyor belt 105a onto the repair conveyor belt 106 so that the drum 97 can be repaired. 112, where the working chamber 112 has a suitable wall-repairing liquid solidification or grouting process in a separate drum such that the drum 97 and its contents are encapsulated within the module 200. Is performed. The drum 97 may be temporarily stored in the rack storage well 113 of the contact adjuster 85 when the maintenance work chamber 112 is in the filled state.

Looking closely at FIG. 2, the powerful compactor 110 of the present invention has a loading mechanism 110.1 having a drum scoop 110.2 at the end side of the arm assembly 110.3 that can be articulated as shown. It is included. The drum 97 which slides down into the chute at the end of the compactor conveyor 105a is supplied to the drum scoop 110.2 by a worker. The arm assembly 110.3, which can then be articulated, loads the drum 97 into the loading cradle 110.4.

The compactor 110 also includes a loading ram 110.5, which ram 110.5 is capable of moving between the outer position of the main ram 110.8 and the government of the discharge lamp 111.2 to allow the water-adhesive contact cylinder 110.6. The drum 97 is fed into the drum). In FIG. 2 the contact cylinder 110.6 is marked in the extended position adjacent to the top of the discharge ramp 111.2 away from the main ram 110.8. After the drum 97 is loaded into the tight cylinder 110.6, the cylinder 110.6 is retracted into the main ram 110.8 such that the drum 97 is ram piston 110.9 (not shown) and the main ram 110.8. Is squeezed between the beds.

As described above, an adhesion force between 500 and 1,100 tons is applied to the drum 97. The use of such strong adhesion has three significant advantages.

Firstly, the drum 97 and its contents volume is reduced to allow more drums to be packed in one module 200. Obviously using such high adhesion, 35 to 84 drums 97 can be packaged inside one module 200 instead of fourteen. Secondly, using such high adhesion forces deforms the waste contained in the drum and the steel of the drum 97 beyond the inelastic limits of the material so that the last high density puck is ejected from the discharge ramp 111.2 in a larger form after the "spring bag." "It eliminates the possibility of trying to be. Removing such a "spring bag" eliminates the possibility that an internal crack or cavity is formed in the cured grout in the module 200 after the module 200 has loaded and grouted the puck 117.

The final high density puck 117 forms a strong incompressible reinforcement structure inside the module 200 when it is covered with grout, separate from the "spring bag", which is made of a trench cap made of dirt applied over the waste disposal plant 150 ( 164 to support the module when performing another function as the structural support member. Finally, the compression of waste inside such extreme drums 97 (usually rag paper and contaminated uniforms) makes it resistant to absorbing water.

This, of course, makes them less likely to filter out radioactive material when they get wet. Such resistance to the absorption of water also results in less degradation that meets the full functionality of the module 200 in encapsulating the waste since the decomposition "hollows out" containers that contain excessive waste, causing sedimentation problems. do.

It should be noted that the compactor 110 includes an air filtration system 111.4 having a filter 111.5, a blower assembly 111.6, an exhaust stack 111.7, and the like. The air filtration system 111.4 discharges any radioactive air particles resulting from applying 660-1,100 tons of force on the drum 97 holding the contact waste.

Returning back to the first road, the contact portion 85 of the installation 1 is connected to the rail assembly 66a (adjacent to the remotely controlled waste 3) or the rail assembly 66b (adjacent to the contacted regulated waste 85). And a grouting area 118 having a stretchable trough 120 that can pour grout into the module 200 on the rail car art 64. Using one grouting area 118 for the module 200 loaded in the non-contact and contact adjustments 3, 85 avoids the redundant installation of expensive components in the overall system. Immediately past the grouting area 118 is a capping sub-region 122 having a traveling crane 126, which crane 126 hoists to lift the lid 220 above the government of the module 200 to undergo a capping process. Has 128. A more detailed description of the capping process will be given when the structure of the module 200 is related in detail.

The modules 200 are typically filled with waste, grouted in the grouting area 118 and capped at the waste packaging facility 1 located near the waste disposal plant 150, but they are also processed at the facility that generates the waste. Since the surface radiation of the last module is low enough for contact handling, the waste in the module 200 is conveniently stored in the forest using the processing space. When the processing space is available, the module 200 is transported to the treatment plant 150 remotely controlled waste within a reusable transport overpack (not shown) and stacked directly in the trench 152. This method is not preferred, but cheaper than using log waste storage facilities.

3 illustrates a treatment plant 150 used in connection with a packaging facility 1. Treatment plant 150 generally includes a trench 152 (or a number of parallel trenches) having a flat impact bottom 154. Before the trench is loaded into the capped module with the cured grout, a number of water collection locators 155 are positioned uniformly through the bottom 154 to measure the radiation level of the water in the trench. The lysimeter 155 is positioned in the trench bottom 154 by drilling a hole in the bottom to insert the long body of the lysimeter 155. A network of plastic tubes (not shown) operates the plant 150 to periodically drain the water collected in the cups of the lysimeter 155.

The radiation level of this sample of water is measured periodically to determine which radioactive material has been emitted from the module 200. After lysimeter 155 is properly buried through floor 154, floor 154 is covered with a two-galling layer 156 about 2 feet thick that submerges as a capillary barrier. Although the treatment plant 150 preferably selects an area of at least 80 feet below the trench bottom 154 where all the flow of groundwater is selected, the non-cemented gravel layer 156 is a module of capillary action in the trench bottom 154. It is located across the top of the bottom 154 to prevent groundwater from seeping into the stack arrangement 160 of 200.

Although all capillary barriers in the treatment plant 150 of the present invention are preferably formed of gravel, it should be appreciated that the present invention involves the use of any coarse cyclic material with high conductivity of water. The gravel layer 156 is covered with a sand block 158 about 4 inches thick. The sand block 158 serves as a path for the heavy forklift 185 and the wheels of the trailer 184 used to transport the module 200 to the trench 152. If the portion 158 is not present, the wheels of the vehicles 184 and 185 will sink into the gravel layer 156.

The next part of the processing plant 150 is a tightly packed arrangement 160 of the hexagonal module 200 shown in FIG. In a preferred embodiment, the modules 200 are preferably stacked in columns that are in contact with each other, and each hexagonal surface of each module 200 forms a pillar with hexagonal surfaces of two other modules. Arranging the modules 200 in columns that are adjacent to each other has at least four significant advantages.

First, the rigidly packed module 200 provides a support structure for the non-rigid trench cap 164 that is formed quickly and conveniently from natural materials such as soil, sand and gravel.

Secondly, such an arrangement almost completely eliminates the gap between the soil 200, the module 200 causing the settling problem described above.

Thirdly, such an arrangement is also capable of severe seismic disturbances since each module 200 can move separately along eight different sides (i.e., the six sides of the hexagonal prism that form the government, bottom and module 200). I can endure it.

Since no modules are rigidly coupled with other adjacent modules, each of them is capable of at least some vertical and horizontal sliding motion even in the event of an earthquake. This free movement of the eight faces is a function of local earthquakes that make the entire module array 160 flexible as the shape of the trench 152 changes, creating a local stress point within the array 160 sufficient to break individual container walls. Eliminate or at least minimize the possibility of interference.

Fourthly, if the arrangement 160 is columnar, it is easy to recover the special module 200 if necessary, which includes the necessary modules.

This is because a module 200 can be removed from the trench by digging a hole the size of only one module on a special column.

In a preferred embodiment, the module with the circumference and intermediate and government modules as the strongest or "hotist" module 200 is located at the bottom layer of the module back 160 and surrounded by weaker radiation modules. Will provide added shielding from radiation emitted from the material in the "hot" module.

Trench 152 also includes gravel capillary barriers 162a and 162b located between the sides of rigid module array 160 and the walls of trench 152.

The purpose of these barriers 162a and 163b is to prevent water from seeping into the side of the tightly packed arrangement 160 of the module 200 from the side of the trench 152.

In a preferred embodiment, each of these side capillary barriers 162a, 162a has a thickness of about 2 feet.

The trench cap 164 is preferably a non-rigid cap formed of natural materials such as soil, sand and gravel.

Such caps 164 are more resistant to earthquake disturbances than rigid, synthetic structures.

More specifically, the non-rigidity of the cap 164 acts to vertically switch the layers of the cap 164 a small distance from each other, at least in part to "self-healing" earthquake disturbances. do.

In addition, even in the event of severe earthquake disturbances that cause significant damage to the cap 164, the cap 164 is easily repaired by conventional road construction and dirt movement facilities.

As noted above, the tightly packed arrangement of module 160 provides all the structural support needed to build and maintain the various layers of trench cap 164.

The first layer of trench cap 164 is preferably an alluvial layer 166, with the range of layer 166 being between 4 feet of lateral thickness and 7 feet of median thickness.

As pointed out in FIG. 3, the alluvial layer 166 (preferably made of soil removed when making the trench 152) becomes thinner as it is separated from the centerline of the layer by about 4.5%.

This terrain allows the cap 164 to effectively run off the water that penetrates its outer layer, causing the water to flow to the side drains 178a and 178b.

After the alluvial layer 166 is applied to the top of the tightly packed module arrangement 160, the layer 166 is compacted before the remaining layers are placed thereon.

Such compaction may be performed by conventional road compaction equipment or by simply allowing the charges in the layer 166 to fully settle with natural forces.

It is preferable to use a road compaction apparatus among two methods of compacting the alluvial layer 166.

In the present invention, the natural settling time of the alluvial layer is very fast compared to the settling time of the soil used in the treatment plant of the prior art, but still within three months, depending on the characteristics of the soil forming the alluvial layer may take a year.

On the contrary, when the road compaction equipment is used, the settling time is reduced to several days.

It should be noted that the alluvial layer 166 is positioned over the tightly packed array 160 at a rate approximately equal to the rate at which the arrangement 160 is formed by accumulating the individual modules 200.

Positioning the alluvial layer 166 at the same time on the module array 160 minimizes the amount of radiation exposed to the trench workers as the treatment plant 150 is formed.

After the alluvial layer 166 is approximately compacted, a sand layer 168 about 4 inches thick is applied thereon.

Another layer of gravel capillary barrier 170, about 2 feet deep, is placed over sand layer 168 after sand layer 168 is fully applied over alluvial layer 166.

The sand layer 168 acts as a barrier invading between the relatively coarse gravel forming the gravel capillary barrier 170 and the relatively fine alluvial path in the alluvial layer 166.

Once the gravel capillary barrier 170 is placed, another sand layer 172 about 4 inches thick is applied over the gravel capillary barrier 170.

A silt 164 is then applied over the sand layer 172 across the gravel capillary barrier 170 to flow down the microlayers of water. Sand layer 172 serves as a barrier that penetrates between the silt in silt layer 174 and the gravel in gravel capillary barrier 170. The silt layer 174 is the main water flow layer of the trench cap 164, is about 2 feet thick, and is formed of a dense, uniformly sized material (preferably from elsewhere). There are at least two advantages to using the silt layer 174 in place of natural materials, such as clays that flow other water.

Firstly, silt is cheaper to obtain than clay.

Second, when the silt layer 174 is saturated with water and dried, it tends to crack or break like clay.

Not cracking or breaking like this helps maintain the overall strength of the trench cap 164.

Sides of the silt layer 174 terminate adjacent to a pair of French drains 178a and 178b located on both sides of the trench 12.

French drains 178a and 178b include trenches on which perforated pipes 182a and 182b are placed.

Water flowing down the sides of the silt layer 174 flows along the discharge trenches 180a and 180b through the holes in the pipes 182a and 182b to move away from the trenches 152.

If the silt layer 174 is completely saturated with water when the source of rain or other surface water is so large that the gravel capillary barrier flows any water from the saturated silt layer 174 into the module array 160 through capillary action Prevent it from going down.

The last stratum 176 of trench cap 164 is composed of tides, which are colloquially termed coarse gravel, roughly the size of a surface. The tidal layer 176 has at least three functions.

First, the silt layer 174 is isolated from potential corrosive winds and running water.

Second, it provides a lasting radiation barrier for the module arrangement 160 which should bring the radiation level of the treatment plant 150 within the range of normal background radiation.

Third, the ground above the module array 160 provides a barrier to intrusion that would cause fatal intrusions by humans or animals.

A preferred embodiment of the cap 164 as described above is for a dry area.

Another embodiment of the cap 164 in the wet zone includes a first water infiltration barrier of natural soil over the rigid arrangement 160 of the module 200.

The layer is covered with a sand and gravel capillary barrier similar to the layers 168, 170, 172 described above.

These sand and gravel capillary barriers are covered with a gravel invading layer and additional layers of sand and gravel to prevent the last layer of soil with vegetation cover.

In another such embodiment, the vegetation cover not only prevents erosion that may occur in the top layer of soil, but also removes water that penetrates the top layer of the cap.

The vegetation used is preferably superficial roots to ensure that the integrity of the cap 164 is not compromised.

In addition, such another embodiment has a steep slope of about 10 ° or more because of the significant amount of rainwater associated with that area.

Referring now to FIGS. 4A, 4B, 4C, and 5A, the module 200 of the present invention, after being filled with nuclear waste and properly grouted, includes a lid 220 and a reinforced concrete wall covering the container 201. It is comprised by the container 201 which has.

With particular reference to FIGS. 4A-4C, the container 201 of the module 200 is a hexagonal prism 201 having a cylindrical inner layer portion 216.

The corners 204 where the hexagonal walls abut each other cut sideways as appropriate so that a small gap is left between adjacent modules 200 when stacked in the module array 160 illustrated in FIG.

These small spaces should be large enough to accommodate a recovery tool if it is necessary to recover any of the modules 200, but a significant amount of soil will sink when the module 200 is arranged in the shape illustrated in FIG. It should not be small enough.

The cut shape of the corner 2034 also prevents forklift 185 from splitting or breaking as it occurs when the module 200 is pushed into the module array 160 according to the loading process.

Returning to the bottom and bottom of the container 201 of the module 200, the government 206 is now open for loading nuclear waste and grout as shown.

The government 206 includes three I-bolt anchors 208a, 208b, 208c that allow the container 201 to be handled by a grappling hook in the packaging 1 and stacked in the trench 164.

These anchors 208a, 208b, 208c also allow module 200 to be lifted out of trench 164 if retrieval is required.

The shanks of the anchors 208a, 208b, and 208c are deeply immersed into the concrete wall of the container 201 so as to be properly grasped, as indicated.

The bottom 209 of the container 201 has an outer surface 211 in the form of a bottom surface 210 and a groove 212 that is inside the container 201.

Each of these grooves 212 is slightly longer and wider than the forks of the shielded forklift 185, making it very easy for these grooves 212 to handle the module 200 by the forklift 185.

Each shape of groove 212 also allows such forklift to bind a particular module at various different angles. Reinforcing the container 201 bottom of the module and the concrete wall is a "basket" 215 made of a commercial steel-reinforced mesh. The basket 215 significantly increases the tensile strength of the bottom 209 and walls of the container 201 of the module 200.

In a preferred embodiment, the wall of container 201 is at least 3 inches thick.

In addition, the cylindrical inner side 216 of the container 201 has a diameter of at least 75 inches, such that 14 drums or seven high density puck 117 are stacked on the cylindrical inner side 216 of the container 201.

The top portion 206 of the container 201 is a plurality of grooves 214a, 214b for receiving the cap retaining rods 232a, 232b, 232c, 232d, 232e, 232f of the slab container lid 220, which will now be described in detail. , 214c, 214d, 214e, 214f).

Referring now to FIGS. 5A and 5B, the slab container lead 220 generally includes a disk-shaped lower portion 228 having a smaller diameter formed integrally with the disk-shaped upper portion 222.

The edges of the upper portion 222 are flattened into three portions 223.1, 223.2, and 223.3 spaced about 120 degrees from each other.

When the container lid 220 is properly positioned over the open top 206 of the container 201, the flat portions 22 1,223.2,223.3 are positioned at appropriate angles to space the crane hooks that restrain the I-bolt portion of the anchor. It is directly opposite the above-mentioned I-bolt anchors 208a, 208b, 208c to provide.

The top surface 224 of the top 222 of the lid 220 includes a radiation warning 226 specially cast on the surface of the lid 220.

In addition, a serial number for identification is cast on the top surface 224 of the lid 220 (as shown in FIG. 3) so that the module 220 can be easily identified if the module needs to be retrieved.

As best shown in FIG. 5A, the u-shaped transport lugs 227a, 227c, 227e are positioned around the circumference of the top 222 of the container lid 220 at intervals of about 120 ° from each other.

These lugs 227a, 227c, and 227e preferably intersect with the flat portions 223.1, 223.2, 223.3 along the circumference of the top 222.

The angular crossover between these lead transport lugs 227a, 227c, 227e and the flat portions 223.1, 223.2, 223.3 described above is accidentally lead to a crane hook that is about to engage with one of the I-bolt anchors of the module container 201. It minimizes the possibility of catching and tearing the transport lugs 227a, 227c or 227e.

As described above, the container lid 220 also includes a bottom 228 formed in a coinage with a diameter slightly smaller than the disk top 222.

The layer steel-reinforcing mesh 229 is cast in concrete forming the container lid 220 at the position shown in FIG. 5B.

Also cast in the lead are six equally spaced cap retaining rods 232a, 232b, 232c, 232d, 232e and 232f.

These rods slide into corresponding slots 214a, 214b, 214c, 214d, 214e and 214f after the container has been filled and grouted with nuclear waste.

The container lid 220 and the module container are preferably cast from nonporous commercial largecrete having a compression tolerance of about 4,000 psi.

The concrete is rigid and waterproof.

6 and 7 illustrate a module 200 that is filled, grouted and capped with a high density puck 117 formed from the powerful compactor 110.

In operation, seven high density puck 117 are located in the container 201 of the module 200 as shown in FIG.

The dense container covering the dense waste forms a barrier of added radiation and water between the waste and the outside of the module 200.

The extensible trough 120 of the grouting area 118 of the packaging facility 1 is then placed over seven puck 117 to form a rigid layer of grout between the inner surface of the container 201 wall and the puck 117. Pour grout 218.

In a preferred embodiment, the grout used to fill module 200 is 3,000 or 4,000 psi commercial concrete.

However, gypsum, volcanic ash, fly ash or other cement materials may be used for the grout.

The cured grout 218 forms a third radiation and water barrier between the outer surface of the container 200 and the waste in the puck 117 as is apparent from the figure.

In addition, the grout 218 serves to anchor the cap retaining rods 232a, 232b, 232c, 232d, 232e, and 232f into the body of the module 200, so that the container, 201, lid 220, and grout 218 are provided. And piles of puck 117 and the like into a single rigid structure with significant compressive and tensile strength.

The cured and completed module 200 is stacked in the rigid arrangement 160 illustrated in FIG. 3 by a forklift 185 that is transported from the packaging 1 by a drop-bed trailer 184 and shielded.

Although not shown in the figure, the module 200 may be modified to package special high strength nuclear waste, such as waste control rods.

More specifically, the module 200 is formed into a very thick wall so that a relatively small cylindrical space remains in the center of the module.

The control rods are then transported directly from the shielded transport cask 15 into the small cylindrical space in the already grouted module.

Such a modified module should be long to accommodate some complete control rods.

It is also possible to use already grouted modules 200 of normal height when the rods are cut to smaller lengths.

Claims (46)

In a treatment plant for treating toxic waste material, the non-rigid water superimposed on the impregnated ground formed on the impregnated ground and the hard material is encapsulated in the cam and the impregnated ground, and the non-rigid cap on the impregnated ground is structurally formed. A waste disposal plant comprising a plurality of modules installed under the cap for supporting. The waste treatment plant of claim 1 wherein the impregnated ground comprises a layer of a rigid material at its lower portion that cannot conduct water to prevent groundwater from flowing into the module by capillary action. 3. The waste disposal plant of claim 2 wherein the rigid material layer that is unable to conduct water through capillary action is a coarse particle material layer having high water conductivity. The process of claim 1, 2 or 3, wherein the treatment plant is packaged in a space between the walls of the impregnated ground and the side of the module to prevent water from flowing from the walls of the impregnated ground to the module by capillary action. Waste material, characterized in that it comprises a layer of hard material that cannot conduct water through capillary action. The waste treatment plant of claim 1 wherein the rigid material forming the cap comprises a silt layer such that surface water flows away from the impregnated ground. 6. The waste disposal plant according to claim 5, wherein the treatment plant includes a discharge device for allowing surface water to flow away from the impregnated ground, and the silt layer is inclined to allow the surface water to flow to the discharge device. 2. The waste disposal plant of claim 1, wherein the cap includes an alluvial layer for supporting a layer through which water formed of a rigid material flows. 8. The waste disposal plant of claim 7, wherein the alluvial layer directly covers the module. 9. The waste disposal plant of claim 8 wherein the water flowing layer is formed of a silt layer over the alluvial layer. 10. The waste treatment plant of claim 9, wherein the treatment plant comprises a rigid material layer that is unable to conduct water between the silt and alluvial layers to prevent water from seeping into the alluvial layer by capillary action. 11. The waste disposal plant of claim 10 wherein the rigid material layer between the silt layer and the alluvial layer is a coarse particle material layer having high water conductivity. 2. The waste disposal plant of claim 1, wherein the modules are adjacent to each other in a tightly packed arrangement. 13. The waste disposal plant of claim 12 wherein the tightly packed arrangement comprises at least one module layer formed by stacking modules in a row adjacent to each other. 14. The waste disposal plant of claim 13, wherein each module in the bed is capable of sliding in a vertical direction with respect to the bed. 14. The waste disposal plant of claim 13, wherein the rigidly packed arrangement includes modules stacked in a plurality of columnar shapes, each columnar pile being capable of sliding in a vertical direction with respect to the array. 15. The waste disposal plant of claim 14, wherein the tightly packed arrangement comprises at least two modular layers forming a plurality of column piles, each layer being slidable horizontally with respect to the arrangement. A treatment plant for the treatment of radioactive waste, comprising: a radioactive cap for allowing non-rigid water to flow over trenches in the ground and a trench formed of a rigid material; and encapsulating the cap to prevent water from entering the radioactive waste in the trench. A waste disposal plant comprising a rigidly packed module array installed under the cap for supporting. 18. The waste disposal plant of claim 17, wherein the rigid material forming the cap comprises a silt layer such that surface water flows away from the trench. 19. The waste treatment plant of claim 18, wherein the treatment plant also includes a discharging device such that surface water flows away from the trench and the silt layer is inclined to allow the surface water to flow into the discharging device. 19. The waste disposal plant of claim 18, wherein the cap includes a rigid material layer that permeates water over the silt layer to prevent weathering of the silt layer and to provide radiation tension between the module arrangement and the top surface of the cap. . 21. The waste disposal plant according to claim 20, wherein the layer on the silt layer is formed of tides. 22. A waste disposal plant as claimed in any one of claims 17 to 21, wherein the trench has a hard material layer at the bottom that cannot conduct water to prevent groundwater from flowing into the module by capillary action. 18. The process of claim 17 wherein the treatment plant is also packaged in a space between the walls of the trench and the sides of the module to prevent water from flowing into the module by capillary action and includes a layer of material that is not capable of conducting water. Waste treatment plant characterized in that there is. 23. The waste disposal plant of claim 22, wherein the hard material layer that is unable to conduct water by capillary action is a gravel layer. 18. The waste treatment plant of claim 17, wherein the treatment plant comprises at least one radiation measuring instrument positioned below the trench bottom to measure radiation levels in the trench bottom. 18. The waste disposal plant of claim 17, wherein the cap comprises an alluvial layer supporting a layer through which water formed of a rigid material can flow. 27. The waste disposal plant of claim 26, wherein the alluvial bed is retracting from the module arrangement and is reliefable to provide an inspection for the flowing layer of water supported by the alluvial bed. 28. The waste disposal plant of claim 27, wherein the water flowing layer is formed of a silt layer over the alluvial layer. 29. The waste material of claim 28, wherein the treatment plant also includes a rigid material layer that is unable to conduct water between the silt and impact layers to prevent water from seeping into the alluvial layer by capillary action. Treatment plant. 30. The waste disposal plant of claim 29, wherein the rigid material layer between the silt and alluvial layers is a gravel layer. 18. The waste disposal plant of claim 17, wherein the modules are adjacent to each other in a tightly packed arrangement. 18. The waste disposal plant of claim 17, wherein the tightly packed arrangement comprises at least one module layer formed by stacking modules adjacent to each other in the heat of the modules. 33. The waste disposal plant of claim 32, wherein each module in the bed is capable of sliding in a vertical direction with respect to the bed. 18. The waste disposal plant of claim 17, wherein the rigidly packed arrangement comprises a plurality of module stacks, each columnar stack slid vertically relative to the arrangement. 18. The rigidly packaged arrangement of claim 17, wherein the tightly packed arrangement comprises at least two modular layers forming a columnar stack of multiple modules, each columnar stack being slideable in a horizontal direction with respect to the array, wherein each layer is A waste treatment plant characterized by being capable of sliding in a horizontal direction with respect to the arrangement. A treatment plant for the treatment of radioactive waste, comprising: a trench in a ground having a flat bottom having a gravel layer disposed therein to prevent groundwater from flowing into capillary phenomena; First layer of alluvial soil, between the cap and alluvial layer, a second layer of gravel to prevent water from flowing into capillary phenomena, non-rigidity formed of tidal layer on the silt layer to protect the silt layer from saponification and to provide a radiation barrier Consisting of a radiation shielding cap, a tightly packed module array of uniform size and shape is encapsulated under the cap to encapsulate water into the radioactive waste in the trench and to structurally support the cap. Each module can slide in the vertical direction, the flexibility of the module arrangement according to the shape change of the bottom of the flat trench due to the earthquake, waste disposal facility characterized in that it facilitates the recovery capacity of the module. 37. The waste disposal plant of claim 36, wherein each module is shaped like a right angle prism with a plurality of flat surfaces having the same size and shape. 38. The waste disposal plant of claim 37, wherein the modules are stacked in a plurality of mutually adjacent columns, with the flat surfaces of each module arranged in a common plane with each other. 37. The waste disposal plant of claim 36, wherein each module is a hexagonal prism. 37. The waste disposal plant of claim 36, wherein the treatment plant comprises a discharge device, wherein the silt layer is inclined such that surface water flowing over the cap flows to the discharge device. A method for depositing nuclear waste contained in a number of uniformly packaged, tightly packaged modules, the method of digging a trench, packing the trenches tightly one by one into a tightly packaged module, and by radiation emitted from the module. A method of depositing nuclear waste, characterized by placing a non-rigid water-flowing radiation blocking cap formed of a rigid material on top of the module when the trench is filled with a rigid module array to minimize exposure to the surrounding area. 42. The method of claim 41, wherein the non-rigid water-flowing cap is formed including an alluvial layer on the module top, allowing the alluvial to settle, and placing a silt layer on which the water flows over the top of the submerged alluvial bed. How to bury nuclear waste 43. The method of claim 42, wherein the method further comprises placing a layer of coarse particle material with high water conductivity between the layer of flowing water and the settled layer of water to provide a capillary barrier between the layer of silt and the layer of cladding. How to bury nuclear waste. 44. The method of claim 43, wherein the method also includes covering the silt layer with a tidal layer to prevent weathering of the silt layer as well as provide a lasting radiation barrier between the module government and the surrounding area. Way. 45. The method of claim 44, wherein the method further comprises measuring the amount of radiation in the water present at the bottom of the trench. In a treatment plant for the treatment of radioactive waste, the treatment plant is provided with a rigidly packaged module arrangement formed of a plurality of adjacent columnar module stacks in the shape of a right prism and a non-rigid water on the module arrangement such that it is structurally supported by the module arrangement. A waste disposal plant comprising a flowing radiation shielding cap.

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