JP2013213701A - Processing method for contaminated water, processing material, manufacturing method for crustal composition, paste crustal composition, and crustal composition - Google Patents

Abstract

PROBLEM TO BE SOLVED: To effectively use a processing material produced by a processing method for a contaminated water containing a radioactive material.SOLUTION: A contaminated water containing a radioactive material and a carrier material for carrying the radioactive material are mixed together so as to allow the carrier material to carry the radioactive material in the contaminated water. Here, when a fine particulate soil having a layer structure is used for the carrier material, the fine particulate soil having a diameter of, for example, 0.075 mm or less can be used. The fine particulate soil is constituted by including one or more selected from among, for example, vermiculite, bentonite, and asbestos. Further, adsorbent can be also used as the carrier material. As adsorbent, for example, a porous material is available. The porous material is constituted by including one or more selected from among, for example, white sand porous glass and amorphous carbon. From the processing method for such contaminated water, the processing material which allows the carrier material such as the fine particulate soil and the porous material to carry the radioactive material is produced.

Description

  The present invention relates to a method for treating contaminated water containing a radioactive substance, a treatment material produced by this treatment method, a method for producing a crust-like composition using this treatment material, and a paste-like crust-like composition. The present invention relates to a body and a crust-like composition.

  In Japan, after the great earthquake of March 11, 2011, there was an accident at a nuclear power plant, and as shown in FIG. 44, it is considered that radioactive materials of 850,000 terabecquerel or more were scattered. Since then, not only high-level radioactive waste, but also low-level radioactive waste and waste associated with decontamination have been generated in large quantities and are still increasing. Specifically, as shown in Fig. 45, radioactive waste is found in radioactive incineration ash and sludge in sewage treatment plants that accumulate daily. Has been confirmed. Radioactive pollutants have also been identified in rivers and oceans.

  Regarding the treatment of radioactive waste, as shown in FIG. 46, there is a nuclear policy outline enacted before the earthquake, and the Reactor Regulation Law and the Radiation Hazard Prevention Law have been enacted. Internationally, Japan is a member of the London Convention, and the dumping of radioactive material into the ocean is prohibited. In addition, a clearance system has been introduced, in which the radioactive waste clearance level is set.

  At the time of final disposal of radioactive waste, high-level radioactive waste is currently subject to vitrification of vitrified solids, while low-level radioactive waste is disposed at a shallow depth, in a shallow pit or in a shallow area. The trench will be disposed of. As for geological disposal, the management period is more than tens of thousands of years, hundreds of years for marginal depth disposal, about 300 years for shallow pit disposal, and about 50 years for shallow underground trench disposal. Such a disposal method requires very high technology, is expensive, and must be managed for a very long period of time. It is very difficult to dispose of radioactive waste that will increase in the future in this way.

  The present invention has been made based on the above background, and an object thereof is to provide a method for treating contaminated water containing a radioactive substance, and a treatment material produced by this treatment method. .

  The present invention also provides a method for producing a crust-like composition, a paste-like crust-like composition, and a crust-like composition that can effectively use the treatment material produced by the method for treating contaminated water. With the goal.

  In the method for treating contaminated water according to the present invention, contaminated water containing a radioactive substance and a support material supporting the radioactive substance are mixed, and the radioactive substance in the contaminated water is supported on the support material. Here, when a fine soil having a layered structure is used as the support material, for example, one having a particle size of 0.075 mm or less can be used, and the fine soil is selected from, for example, vermiculite, bentonite, and asbestos It is comprised including the above. An adsorbent can also be used as the support material. Examples of the adsorbent include a porous material, and the porous material includes, for example, at least one selected from a glass of porous glass and amorphous carbon.

  From the method for treating contaminated water as described above, a treatment material is produced in which the radioactive substance is carried on a carrier material such as the finely divided soil or porous material. The treatment material thus produced includes a calcium carbonate composition containing calcium carbonate as a main component, a siliceous composition containing silicate as a main component, and an iron oxide composition containing an iron oxide-based substance as a main component. Can be used in a method for producing a crust-like composition in which a solid composition obtained by firing is kneaded with a pulverized material obtained by finely pulverizing and a paste-like composition. The paste-like composition can be kneaded with a reaction rate adjusting material, fine aggregate or coarse aggregate for adjusting the curing rate and / or hydration reaction rate. In addition, the paste-like composition is made of incinerated ash containing a radioactive material obtained by firing a pollutant containing a radioactive material at a radioactivity concentration exceeding the measurement lower limit value below the vaporization temperature of the radioactive material. Can be kneaded.

  Here, the radioactivity concentration of the paste-like composition is set to a predetermined value or less. Here, the predetermined value is a legal standard value that is legally set and is a clearance level, and the radioactive concentration of the paste-like composition satisfies such a predetermined value.

  Further, the present invention calcinates a calcium carbonate composition containing calcium carbonate as a main component, a siliceous composition containing silicate as a main component, and an iron oxide composition containing an iron oxide-based substance as a main component. The pulverized material obtained by finely pulverizing the solid phase composition obtained by mixing the contaminated water containing the radioactive substance and the supporting material supporting the radioactive substance, and supporting the radioactive substance on the supporting material. A paste-like crust-like composition obtained by kneading a treated material with water.

  Further, the present invention calcinates a calcium carbonate composition containing calcium carbonate as a main component, a siliceous composition containing silicate as a main component, and an iron oxide composition containing an iron oxide-based substance as a main component. Then, the pulverized material obtained by finely pulverizing the solid phase composition obtained, the contaminated water containing the radioactive substance, and the support material supporting the radioactive substance are mixed, and the radioactive substance is supported on the support material. A crust-like composition obtained by solidifying a paste-like composition obtained by kneading a treatment material with water.

  In the present invention, the contaminated water containing the radioactive substance and the support material supporting the radioactive substance can be mixed, and the support material can support the radioactive substance in the contaminated water. From such a contaminated water treatment method, a treatment material in which a radioactive substance is supported on a support material such as a fine soil material or a porous material can be generated. Such a treatment material comprises a calcium carbonate composition mainly composed of calcium carbonate, a siliceous composition mainly composed of silicate, and an iron oxide composition mainly composed of an iron oxide-based substance. It can be used in a method for producing a crust-like composition in which a solid composition obtained by firing is kneaded with a pulverized material obtained by pulverization and water to produce a paste-like composition. And by adjusting the addition amount of a processing material, the radioactive density | concentration of a paste-form composition can be made to satisfy the legally set legal reference value, and can satisfy a clearance level. As described above, in the present invention, while removing the radioactive substance from the contaminated water, the generated treatment material containing the radioactive substance is effectively used for the pasty crust-like composition and the crust-like composition obtained by solidifying the paste. I can do it.

  Such a paste-like composition having a predetermined value or less can be reduced to the crust as a paste-like crust-like composition, and the crust-like composition obtained by solidifying the paste-like crust-like composition is reduced to the crust. I can do it.

It is a figure which shows the structure of this invention. It is a figure which shows the structure of this invention. It is a figure which shows the structure of a crust-like composition. It is a figure which shows the relationship between the shielding wall pressure, the radiation intensity, and the radioactive concentration when the amount of radioactive substance is constant. (A) is a cross-sectional view of a crust-like composition in which a radioactive substance is uniformly dispersed, and (B) is a cross-sectional view of an example in which an outer layer is provided. It is sectional drawing of the crust-like composition which distribute | arranged the radioactive substance inside so that the inside might satisfy | fill predetermined value. It is sectional drawing of the crust-like composition which distribute | arranged the radioactive substance inside and was made to satisfy | fill predetermined value as a whole. It is sectional drawing of the crust-like composition which made the layer containing a radioactive substance the multilayered structure. FIG. 4 is a cross-sectional view of a crust-like composition in which the density gradually decreases as the radioactive substance goes outward, and an outer layer is provided. It is sectional drawing of the crust-like composition in which a density becomes low gradually as a radioactive substance goes outside. It is a manufacturing-process figure of the composition containing the radioactive substance used for a crust-like composition. It is a figure which shows the raw material process of the composition containing the radioactive substance used for a crust-like composition. FIG. 13 is a continuation of FIG. 12 showing a firing step. FIG. 14 is a diagram showing a finishing process following FIG. 13. It is a figure which shows the baking processing process of a pollutant. It is a figure which shows the mixing process of a pollutant and a low melting-point substance. It is a figure which shows the process of contaminated water. It is sectional drawing which shows the manufacturing method of the crust-like composition in which the radioactive substance was disperse | distributed uniformly. (A)-(E) is a manufacturing method of the crust-like composition which arranged a radioactive substance inside, Comprising: It is sectional drawing which shows the example which starts manufacture from the outer layer side. (A)-(E) is a manufacturing method of the crust-like composition which arranged the radioactive substance inside, Comprising: It is sectional drawing which shows the other example which starts manufacture from the outer layer side. (A) And (B) is sectional drawing which shows the molded object arrange | positioned inside a crust-like composition. (A)-(C) is a manufacturing method of the crust-like composition which arranged the radioactive substance inside, Comprising: It is sectional drawing which shows the example which starts manufacture from the inside. (A) and (B) are methods for producing a crust-like composition in which radioactive materials are arranged, and an example in which the internal molded body is installed on a temporary base in an outer mold and production is started from the inside. It is sectional drawing shown. (A) and (B) are methods for producing a crust-like composition in which a radioactive substance is disposed inside, and the inner molded body is suspended with a wire and installed in an outer mold, and production is started from the inside. It is sectional drawing which shows an example. (A) And (B) is a manufacturing method of the crust-like composition which arranged a radioactive substance inside, Comprising: Sectional drawing which shows the example which settles an internal molded object to the paste-like composition poured into the outer mold frame It is. (A) is a bottom view of a hopper, and (B)-(E) are methods for producing a crust-like composition in which a radioactive substance is arranged inside, and show an example in which an outer layer and an inside are produced simultaneously. It is sectional drawing. (A)-(E) is a manufacturing method of the crust-like composition which arranged the radioactive substance inside, Comprising: It is sectional drawing which does not use the inner formwork which manufactures an outer layer and the inside simultaneously. . It is sectional drawing which shows a centrifuge, (A) is before rotation, (B) shows the state after centrifugal force is applied. It is sectional drawing which shows a formwork pressurization apparatus, (A) is before pressurization, (B) shows the state after pressurization. It is sectional drawing which shows the modification of a mold pressurization apparatus, (A) is before pressurization, (B) shows the state after pressurization. (A) And (B) is a figure which shows the process process of an aggregate, (C) is a figure which shows the state which provided the coating layer in the aggregate. It is sectional drawing of a general road. It is sectional drawing which shows the state which provides a pavement in the steep ground. It is a perspective view of a ballast track. It is a figure which shows the transsea crust reduction method. (A)-(C) is a figure which shows the shape of the crust-like composition used for the transoceanic crust reduction method. It is a figure which shows the ship which carries a crust-like composition. It is a figure which shows the catamaran which conveys a crust-like composition. It is a figure which shows the trolley which conveys a crust-like composition. It is sectional drawing which shows the installation state of a caisson. It is sectional drawing of the crust-like composition in which the impermeable layer was provided outside. It is a figure which shows the backfilling process of a tunnel. It is a figure which shows the utilization method of a crust-like composition. It is a figure explaining the background of this invention. It is a figure explaining the background of this invention. It is a figure explaining the background of this invention.

  Hereinafter, a crust-like composition according to the present invention and a method for producing the crust-like composition will be described with reference to the drawings. Hereinafter, the description of the present invention proceeds in the following order.

1. 1. Radioactivity disabling system 2. Predetermined value of concentration (density) of radioactive material and radioactive material 3. Density distribution of radioactive material Constitution of the crust-like composition 4-1. Example of uniform radioactive material 4-2. Example in which radioactive material is placed inside and the inside satisfies the specified value 4-3. Example in which radioactive material is placed inside to satisfy the specified value as a whole 4-4. Example in which a layer containing a radioactive substance has a multilayer structure and satisfies a predetermined value as a whole 4-5. 4. Example where the radioactive substance concentration (density) decreases as it goes to the outside. Method for producing crust-like composition 5-1. Description of the entire manufacturing process 5-2. Explanation of pretreatment process 5-2-1. Explanation of baking treatment of pollutant 5-2-2. Explanation of chemical fixation (wrapping treatment) of radioactive material 5-2-3. Explanation of pretreatment of contaminated water 5-3. Explanation of other processing 5-4. Explanation of molding method 5-4-1. Description of production method of crustal-like composition in which radioactive material is uniform throughout 5-4-2. Description of manufacturing method of crust-like composition with radioactive substance inside (1) Example starting from outer layer (2) Example starting from inside (3) Example starting simultaneously 5-4-3. Description of production method of crust-like composition using centrifugal force 5-4-4. Description of production method of crust-like composition using pressure 5-5. Explanation of crushing process 5-6. Explanation of use process 5-6-1. Explanation of transoceanic crust reduction method 5-6-2. Description of the shaft crustal reduction method 5-6-3. Explanation of other usage

[1. Radioactivity deactivation system]
As shown in FIG. 1, the present invention is a crust-like composition 20 of the present invention in which radioactive contaminants are disabled by a radioactive disabling treatment system 10 so that the concentration of the radioactive material is within the domestic and international reference values. Manufacturing. More specifically, as shown in FIG. 2, the radioactive disabling treatment system 10 includes, for example, debris containing radioactive pollutants, organic substances contained together with radioactive substances by incinerating sludge, sand, sludge and the like. The crust-like composition 20 having the radioactive substance concentration within the reference value is manufactured by mixing and diluting the mineralized radioactive substance with other substances, for example, at the same time. The crust-like composition 20 can shield the radioactive material from being released to the outside by fixing, confining, and enclosing the radioactive substance. In other words, by using an inorganic substance having radiation attenuation as a mixed material to be diluted, it is possible to effectively attenuate radiation emitted from the radioactive substance. Furthermore, it is desirable that the solid is solidified physically and chemically and becomes a stable solid phase, which can confine radioactive substances in the long term and substantially disable the radioactivity. It becomes like this.

  In this way, the crust-like composition 20 produced by the radioactive disabling treatment system 10 can physically confine and fix radioactive substances and / or chemically confine and fix radioactive substances. The migration and elution of radioactive materials can be prevented, and the absolute amount of radiation can be greatly reduced by reducing the density of the radioactive materials to an ultra-low density. Further, by shielding the radiation, the radiation level can be reduced, and further, by reducing the heat density, overheating can be prevented. If overheating is not prevented, the controllability of the hydraulic reaction, which is one reaction for obtaining a solid phase crust composition, is deteriorated, and the solidified body may become brittle due to the excessive progress of the hydraulic reaction.

[2. About the predetermined value and concentration of radioactive material]
Here, the standard value for the concentration (density) of radioactive material is “Interim storage required for coping with environmental pollution caused by radioactive material associated with the accident at TEPCO's Fukushima Daiichi NPS” dated October 29, 2011. According to the document “Basic concept of facilities, etc.”, it is 8,000 Bq / kg or less. Therefore, it is preferable that the crustal structure is produced so as to comply with this and suitable for domestic law. This standard is also the legal standard value set legally. In addition, according to the document “Regarding the clearance system in the Reactor Regulation Law” by NISA radioactive waste regulation section, the following standards are set. Therefore, it is preferable to produce a crust composition so as to comply with this because it is suitable in accordance with international rules. The predetermined value of the present invention is a value that satisfies this legal standard value and / or clearance level.

  Specifically, when there are multiple radionuclides in the object, the clearance level is the ratio of the concentration (density) of the evaluation target radionuclide contained in the object to the clearance level of the nuclide in consideration of the overlap. The total sum is 1 or less. The formula is as follows.

i: Radionuclide to be evaluated i
D (i): Concentration (density) of nuclide i contained in the object
C (i): clearance level of nuclide i (see Table 1 below)

  By the way, as shown in FIG. 3, the radioactive pollutants typically include fish and shellfish, vegetables, incineration ash (from refuse incineration plant or thermal power plant, etc.), sludge sludge, marine mud sand, river mud sand. , Lake mud, roadside trees, debris (concrete, wood, glass, metal, plastic), contaminated water, earth and sand, etc. These contaminants can be classified as shown in Table 2 below.

[3. Regarding the density distribution of radioactive materials]
Here, the relationship between the density distribution of the radioactive substance and the radiation intensity will be considered. Here, first, radiation emitted from all radioactive materials in a distributed system in which radioactive materials are dispersed in a medium having an attenuation coefficient μ that is specific to the material with respect to radiation attenuation is a point on the surface of the medium (hereinafter referred to as this point). Consider the radiation intensity created at the measurement point or origin).

First, consider a one-dimensional medium system. Here, it is assumed that the medium is uniformly homogeneous, the distance (position) from the origin to a certain point in the medium is x _j, and the density distribution of the radioactive substance distributed in the medium is a one-dimensional density distribution function ρ. Let (x _j ). That is, ρ (x _j ) represents the density of the radioactive substance at the position x _j .

Accordingly, the radiation intensity ΔI _0j at the position x _j emitted from the radioactive substance existing in the minute region Δx _j having the position x _j in the medium as a representative point is expressed as ΔI _0j ∝ρ (x _j ) Δ _xj. The This is evident from the fact that the radiation intensity depends on the amount of radioactive material and the inherent radiation intensity it emits, and therefore

It is expressed. Here, κ is a proportionality constant inherent to the radioactive substance, and is an intensity coefficient. Effects of radiation emitted from a radioactive substance present in this small region [Delta] x _j is on the measurement point, i.e., if a small radiation intensity and [Delta] I _j, the small radiation intensity [Delta] I _j,

It is expressed. If this distribution system is divided into n minute regions, the total radiation intensity I for the measurement points by the radiation emitted from the entire distribution system is a superposition over the entire _j of the minute radiation intensity ΔI _j. . Therefore,

If the small region Δx _j is made as small as possible, that is, if ρ can be defined in the positive limit of n,

  And from this,

  Can be obtained.

  The above has been a discussion of the one-dimensional model. When this is expanded to a three-dimensional model, the three-dimensional density distribution function is expanded to ρ (r) using the position r on the three-dimensional coordinates. . That is, the density distribution function ρ is defined as a function of coordinates. Further, the distance of the straight path in the medium from the position r to the measurement point is given by the norm ‖r 位置 of the position vector r. Therefore, the radiation intensity at the measurement point in the two-dimensional distribution system can be integrated with the minute volume dv over the entire region of the two-dimensional distribution system.

Here, for simplicity, a specific radioactive substance density distribution function ρ (x) for the following four cases is given by a one-dimensional model, and each radiation intensity is obtained.
(Case I: See crust-like composition 20a in FIG. 1)
ρ (x) = c: const
An example in which radioactive materials are uniformly dispersed as a whole.
(Case II: See crust-like composition 20b in FIG. 1)
ρ (x) = kx: k = proportional constant An example in which the density of the radioactive material increases proportionally toward the center.
(Case III: See crust-like composition 20b in FIG. 1)
ρ (x) = sin (gx): g = proportional constant An example in which the density of the radioactive substance increases like a sin curve toward the center.
(Case IV: See crust-like composition 20c in FIG. 1)
ρ (x) = 0: 0 ≦ x ≦ a
c (const): a <x ≦ X−a
0: X−a <x ≦ X
Example of radioactive material existing only in the center

  However, in the radioactivity concentration distribution function ρ (x), when N is the total amount of radioactive substances in the distribution system and the length of the distribution system is X,

  Shall be satisfied.

(Case I: See crust-like composition 20a in FIG. 1)

  Therefore, the above formula is

It becomes. Here, if X is sufficiently large, c = N / X = const by definition, so that the radiation intensity I _I is

Will converge to. In other words, if the distribution system exceeds a certain size, the radiation intensity I _I at its end points regardless of the amount of the size and radioactive materials, and the nature of the medium, the type of radioactive substance contained in a medium and radioactivity It shows a constant value determined only by the concentration.

(Case II: See crust-like composition 20b in FIG. 1)

By definition, since it is k = 2N / ^{X 2,} the radiation intensity _{I II} is

It becomes. Here, if X is sufficiently large, the radiation intensity I _II is

Will converge to. That is, if the distribution system exceeds a certain size, the radiation intensity I _{II at the} end point becomes constant regardless of the size or the total amount of radioactive material. Furthermore, this result shows that the radiation intensity on the surface of the distribution system is lower in the case II than in the case I if the total amount is the same size.

(Case III: See crust-like composition 20b in FIG. 1)

Get. Here, it is assumed that the sin curve as the density distribution function ρ of the radioactive material forms a half-wavelength distribution from the origin to X in a one-dimensional distribution system. That is, the amount of radioactive substance present at both ends is zero, and the amount is gradually increased toward the center of the distribution system and distributed so as to be the largest amount in the center. Then, from this condition, g = π / X (where π is the circumference). According to this, the radiation intensity I _III is

It becomes. Here, if X is sufficiently large, the radiation intensity I _III is

  Converge to. Here, if μ is equal to π / X, this convergence value is

If the same degree expressed as μ ² >> (π / X) ² , this convergence value is

It becomes. In any case, if X is sufficiently large, it means that the radiation intensity I _III converges to a constant value, and in particular, since the constant g is set to be proportional to the inverse of the magnitude X, the magnitude of X It can be seen that the radiation intensity _IIII decreases in inverse proportion.

(Case IV: See crust-like composition 20c in FIG. 1)

It is assumed that there is a measurement point at the end point of one radioactive substance 0 distribution region. Then, if the radiation intensity from the c distribution region side at the boundary point between the zero distribution region and the region of the uniform homogeneous distribution c adjacent thereto is I ′ _IV , the radiation intensity I _IV is

It is expressed. Here, μ is an attenuation coefficient of a medium constituting the 0 distribution region. The radiation intensity I ′ _IV is given as an integral form for x between a and X−a. That is,

It becomes. Since c = N / (X−2a) by definition, the radiation intensity I _IV is

It is expressed. This indicates that no matter what size X is set, it is monotonically decreasing with respect to a satisfying 0 <a <X / 2. In addition, the behavior of the radiation intensity I _Iv with respect to an increase in X when X is sufficiently large with respect to a also monotonously decreases. Accordingly, the value of the radiation intensity I _Iv converges to 0 in the limit of X at this time.

Therefore, in case IV, when the size X is fixed, the intensity of the radiation intensity I _Iv can be decreased as the wall thickness a is made closer to X / 2. ing. However, if the wall thickness a is increased, the radioactivity concentration ρ is

 Therefore, the value of ρ increases indefinitely as a is made closer to X / 2. That is, it becomes impossible to keep the radioactivity concentration below a predetermined value. Accordingly, the surface radiation intensity is set while setting the density ρ of the c-distribution region to a clearance level or government standard value (also referred to as a legal standard value or a predetermined value including the clearance level or government standard value) as described above if necessary. Is preferably set below the desired value, preferably below the natural radiation level, and the balance between minimizing the radiation intensity in the equation as much as possible and the legal standards governing the radioactivity concentration. It is preferable to take.

  For example, FIG. 4 plots the radiation intensity at the corresponding measurement point while continuously changing the thickness a (shielding wall thickness) of the zero distribution region while keeping the total amount of radioactive material contained in the distribution system constant. This graph is overlaid with a graph in which the radioactivity concentration that changes with changing the thickness a of the zero distribution region is taken as the second vertical axis, and the concentration is gradually increased, and the wall thickness a, radiation intensity, and radiation The relationship of active concentration is shown.

  As shown by the line A in FIG. 4, it can be seen that the radiation intensity becomes weaker as the wall thickness a becomes thicker, monotonously decreases toward a = X / 2, and the radiation intensity level gradually decreases. On the other hand, as shown by the line B, as the thickness a of the zero distribution region becomes thicker, the radioactive concentration is gradually increased at the beginning and gradually increased to a very high concentration from a certain point. I understand. Here, the concentration curve shown by line B is crossed by a line C parallel to the horizontal axis, which is a factor that may vary depending on the demands of the times and social circumstances, and the vertical axis from the intersection to the horizontal axis. A line D parallel to is drawn to obtain the intersection with the horizontal axis.

Then, the intersection with the horizontal axis is the maximum thickness a _max of the 0 distribution region that can achieve the legal standard concentration, and is the legal standard concentration conformity thickness. Further, the line D is extended upward to intersect with the intensity curve indicated by the line A, and a line E is drawn in parallel to the horizontal axis from the intersection to the vertical axis to obtain an intersection with the vertical axis. Then, the intersection between the line E and the vertical axis is the radiation intensity corresponding to the legal standard concentration conforming thickness a _max , that is, the legal standard concentration conforming thickness corresponding strength. The strength corresponding to the legal standard concentration conformity thickness is not necessarily the minimum value or minimum value in the intensity curve, or a value near the minimum value, but rather is higher than the minimum value, and the legal standard concentration conformity thickness. The corresponding intensity does not necessarily satisfy the natural radiation level or the desired radiation level. Therefore, in such a case, by reducing the total amount of radioactive substances contained in the distribution system or increasing the size of the entire distribution system, the radioactivity concentration of the entire system is diluted and surface radiation is increased. It is desirable to reduce the strength.

  By the way, considering what kind of distribution system can be used to minimize the intensity of the radiation that is exposed to the outside is very meaningful in safely and effectively performing the disabling process. Therefore, in the following, it will be examined what density distribution function ρ is used to determine whether the radiation intensity emitted from the surface of the distribution system is a certain value or less.

First, the depth (distance) from one end of the distribution system is D, and the depth (distance) from one end of the distribution system to the center (or the other end side) is D _max , that is,

Assuming that the depth to a certain depth point between ₀ and D _max is D ₀ . At this time, for all D satisfying D ₀ <D,

  It is preferable from the viewpoint of efficient distribution. This is because the thicker the medium is, the more effective it is to attenuate the radiation intensity. For comparison, it is possible to reduce the radiation intensity by distributing the high concentration on the deep side rather than the high concentration distribution on the near side. It is.

Here, an arbitrary function f (D) in which the limit of D _max is bounded above is introduced in the integrated value of D from 0 to D _max . That means

And However, K is a constant value. Then, if the radiation attenuation coefficient of this medium is μ _D , the density distribution function ρ (D) that makes it possible to suppress the surface radiation intensity I _D below a certain radiation intensity I _η (reference intensity). The condition to be satisfied is for all D

  It becomes.

  Therefore, when the density distribution satisfies the above conditions, it is realized that the intensity of radiation emitted from the surface does not exceed a certain value regardless of the size of the distribution system. Therefore, as long as this condition is satisfied, it can be said that it is theoretically possible to treat an infinite radioactive substance while keeping the surface radiation intensity at a constant value. Of course, note that the size of the distribution system is infinite in that case.

By the way, if the half-life of j kinds of radioactive substances (nuclide) R _j distributed in the distribution system and the abundance ratio of the nuclides in the distribution system are τ _j and σ _j , respectively, the total over all radioactive substances R _j of all nuclides The half-life τ _ζ (which is not constant with respect to the elapsed time t) can be expressed as: That is,

However, since σ _j is the abundance ratio of nuclides,

  It is. If this is used, the total remaining amount N (t) of the radioactive substance after time t is

  It is expressed. Here, assuming that the intensity of radiation such as γ rays emitted from each nuclide is substantially constant, the surface radiation intensity I (t) of the distribution system after t time is

  Will be expressed.

[4. Constitution of crust-like composition]
[4-1. Uniform example]
The crust-like composition 20 can be configured as shown in FIG. 5 according to the case I. That is, the crust-like composition 20a shown in FIG. 5A is formed into a block shape, and the radioactive substance 19 is uniformly dispersed and solidified as a whole. Here, the shape or the like is not particularly limited as an object formed in a block shape. The crust-like composition 20a is a solidified binder obtained by adding a reaction rate adjusting material such as gypsum to adjust the curing rate and / or hydration reaction rate of the primary composition to the primary composition shown in Table 1 above. The secondary composition may be a block that is a tertiary composition that is appropriately kneaded and solidified by adding water to the subsequent composition, and fine aggregate (sand) is further added and water is appropriately added and kneaded. The block may be a block that is a quaternary composition that has been molded and solidified, or a block that is a quaternary composition that has been coarsely aggregated (sand), added with water, kneaded, and molded and solidified. May be. In the case of these compositions, the primary composition may contain the radioactive substance 19, the contaminated water of the radioactive substance 19 may be used as the water, and the radioactive substance is used in the fine aggregate and coarse aggregate. 19 may be included, but the concentration (density) of the radioactive substance 19 of the molded product as a finished product is adjusted to be equal to or less than the predetermined value described above. Here, the predetermined value means a reference value that is determined by the society from time to time based on the state of society, economic conditions, radiological knowledge, radiation biology, radiation ecology, and radiation environmental knowledge. In Japan, the clearance level is 8,000 Bq / kg or less, and the clearance level shown in Table 1 is adopted as the clearance system.

  In addition, the crust-like composition 20a is a molded product in which the radioactive substance 19 is kneaded with resin, tar, pitch, polyacrylonitrile heat treatment, asphalt, etc., and the radioactive substance 19 is uniformly dispersed throughout. Also good. Further, the radioactive material 19 that is chemically or physically coated may be uniformly dispersed in a block that is a finished product. Moreover, it is preferable that the radioactive substance 19 is dispersed uniformly throughout, but it may be a non-uniform substance in which a part where the radioactive substance 19 is unevenly distributed exists. In this case, the location where the radioactive substance 19 is unevenly distributed may have a density of the radioactive substance 19 larger than a predetermined value, but is preferably not exposed on the surface. Further, as shown in FIG. 5B, the crust-like composition 20a may be provided with an outer layer 17, and the outer layer 17 may be a layer that does not contain a radiation concentration lower than a predetermined value, for example, the radioactive substance 19. .

  In the crust-like composition 20a shown in FIGS. 5A and 5B, the molded product can be used as a fish reef or a coastal marine structure, or can be settled in the ocean. In addition, the crust-like composition 20a can be deposited in the ocean as a pasty crust-like composition in a pasty state. Moreover, it can arrange | position to a mine shaft and can be used as a floor part and / or wall part, and / or a ceiling part of a mine shaft. Furthermore, it can be used as a material for refilling the tunnel. The crust-like composition 20a may be a crushed aggregate (crusher run) by pulverizing a block-shaped molded product. For example, although this will be described in detail later, this crushed aggregate can also be used for a road base material, a soft ground replacement material, a soil material, and a ballast used for a ballast track.

[4-2. Example in which radioactive material is placed inside and the inside meets the specified value]
The crust-like composition 20 can be configured as shown in FIGS. 6 and 7 according to the case 4 example. Explaining from the example of FIG. 6, in this crust-like composition 20 c-1, the inside 18 is set to a finite radioactivity concentration (density), and the outer layer 17 has a radioactivity lower than the radioactivity concentration (density) of the inside 18. The concentration (density) is set, and the radioactive concentration (density) in the interior 18 is set to a predetermined value or less. Specifically, the crust-like composition 20c-1 is formed in a block shape, and the radioactive substance 19 is arranged in the inside 18, and the outer layer 17 is a barrier layer that does not contain the radioactive substance 19. Here, the predetermined value means a reference value that is determined by the society from time to time based on the state of society, economic conditions, radiological knowledge, radiation biology, radiation ecology, and radiation environmental knowledge. In Japan, the clearance level is 8,000 Bq / kg or less, and the clearance level shown in Table 1 is adopted as the clearance system. Moreover, the outer layer 17 should just set the radioactivity density | concentration below to a measurement lower limit. The crust-like composition 20c-1 can shield radiation by the outer layer 17 serving as a barrier layer, and even if the outer layer 17 is damaged due to aging or the like and the inner 18 is exposed, it exceeds the predetermined value. Can be prevented, and adverse effects on the surrounding environment can be prevented.

  Although details are omitted, the crust-like composition 20c-1 can be manufactured, for example, as follows. For example, first, the interior 18 is further kneaded by appropriately adding water to the secondary composition to be a solidifying binder obtained by adding a reaction rate adjusting material such as gypsum to the primary composition shown in Table 1 above. It can be molded and solidified to produce a tertiary composition. Further, a fine aggregate (sand) can be added, and water can be added as appropriate, kneaded and molded and solidified to produce a quaternary composition. Furthermore, a coarse aggregate (sand) can be added, and water can be added as appropriate, kneaded and molded and solidified to produce a quaternary composition. In these cases, the radioactive material 19 may be contained in the primary composition, contaminated water containing the radioactive material 19 may be used as water, and the radioactive material 19 is contained in the fine aggregate and coarse aggregate. However, the concentration (density) of the radioactive substance 19 in the interior 18 of the molded product as a finished product is adjusted to be equal to or lower than the predetermined value described above.

  The interior 18 containing the radioactive substance 19 manufactured as described above is arranged in the center of the mold, for example, and the quaternary composition or the quinary is mixed around the inside 18 with, for example, water not containing the radioactive substance 19. It can be produced by pouring the composition and molding and solidifying it.

  The crust-like composition 20c-1 as described above can use the molded product as a fish reef or a coastal marine structure, or can be settled in the ocean. Moreover, it can arrange | position to a tunnel and can be used for the floor part and / or wall part, and / or ceiling part of a tunnel. The crust-like composition 20c-1 is a block that does not exceed the predetermined value even when the outer layer 17 serving as the barrier layer is damaged due to deterioration over time. Therefore, like the crust-like composition 20a, the crust-like composition 20c-1 can be used as a crushed aggregate (crusher run) by pulverizing a block-shaped molded product.

[4-3. Example of satisfying the specified value as a whole by arranging radioactive materials inside]
The crust-like composition 20 can be configured as shown in FIG. 7 according to the case 4 example. In this crust-like composition 20c-2, the inside 18 is set to a finite radioactive concentration, the outer layer 17 is set to a radioactive concentration (density) lower than the radioactive concentration (density) of the inside 18, The radioactivity concentration (density) is set larger than the predetermined value. Specifically, the crust-like composition 20c-2 is formed in a block shape, in which a radioactive substance 19 is arranged in the inside 18, and the outer layer 17 is a barrier layer that does not contain the radioactive substance 19. In addition, the outer layer 17 should just set the radioactivity density | concentration below to a measurement lower limit. Here, the density of the radioactive substance 19 in the interior 18 is set to be equal to or higher than the predetermined value described above, and the density of the radioactive substance 19 is set to be equal to or lower than the predetermined value as a whole including the inner 18 and the outer layer 17. In the crust-like composition 20c-2, rubble or the like in which the density of the radioactive substance 19 is relatively higher than a predetermined value can be efficiently used as a raw material for the interior 18.

  This crust-like composition 20c-2 can be produced by the same production method as the crust-like composition 20c-1 shown in FIG. The crust-like composition 20c-2 as described above can be used for a molded product as a fish reef or a coastal marine structure, or can be settled in the ocean. Moreover, it can arrange | position to a tunnel and can be used for the floor part and / or wall part, and / or ceiling part of a tunnel. Furthermore, it can be used as a material for refilling the tunnel.

[4-4. Example where the layer containing radioactive material has a multi-layered structure and satisfies the specified value as a whole]
Furthermore, the crust-like composition 20 can be configured as shown in FIG. 8 by referring to the cases 2 and 3 described above. That is, in the crust-like composition 20b-1 shown in FIG. 8, the inside 18 has a multilayer structure. The inside 18 is a layer containing the radioactive substance 19, and for example, the concentration (density) of the radioactive substance 19 in the central part 18a is greater than or less than the predetermined value described above, and as it goes outward from the central part 18a. The concentration (density) of the radioactive substance 19 in the intermediate layer 18b is configured to decrease stepwise. In this example, the number of intermediate layers 18b is not particularly limited. Here, the concentration (density) of the radioactive substance 19 may decrease proportionally as in the case 2 or may have a distribution like a sin curve as it goes from the central portion 18a to the outer layer 17. The outer layer 17 outside the intermediate layer 18 b is a barrier layer that does not contain the radioactive substance 19. The outer layer 17 may also have at least a radioactivity concentration (density) set to a measurement lower limit value or less.

  The crust-like composition 20b-1 can be produced by the same production method as the crust-like compositions 20c-1 and 2 shown in FIGS. That is, after forming the center portion 18a, a multilayer structure can be formed by sequentially forming the inner portion 18b in order. The crust-like composition 20b-1 as described above can use the molded product as a fish reef or a coastal marine structure, or can sink into the ocean. Moreover, it can arrange | position to a tunnel and can be used for the floor part and / or wall part, and / or ceiling part of a tunnel. Furthermore, it can be used as a material for refilling the tunnel. Further, when the concentration (density) of the radioactive substance 19 in the center of the interior 18 where the density of the radioactive substance 19 is the highest is set to a predetermined value or less, the block-shaped molded product is crushed in the same manner as the crust-like composition 20a. It can be used as a crushed aggregate (crusher run).

[4-5. Example of progressively lower density as the radioactive material goes outward]
Furthermore, the crust-like composition 20 can be configured as shown in FIG. 9 by referring to the cases 2 and 3 described above. In the crust-like composition 20b-2 shown in FIG. 9, the concentration (density) of the radioactive substance 19 in the central portion of the interior 18 is greater than or less than the predetermined value described above, and the radioactive material 19 is radioactive as it goes outward from the central portion. The density of the substance 19 is configured to gradually decrease. Here, as it goes from the central portion 18 toward the outer layer 17, the concentration (density) of the radioactive substance 19 may be reduced proportionally as in the case 2 or may be distributed like a sin curve. The outer layer 17 outside the inner portion 18 is a barrier layer that does not contain the radioactive substance 19. The outer layer 17 may also have at least a radioactivity concentration (density) set to a measurement lower limit value or less.

  As will be described in detail later, the crust-like composition 20b-2 is formed by adsorbing the radioactive substance 19 to a plurality of substances having a relatively low specific gravity, rotating the paste-like composition therein, and rotating the central part by centrifugal force. It can be manufactured by distributing a substance having a low specific gravity including the radioactive substance 19 on the side and a substance having a low density of the radioactive substance 19 on the outside. The outer layer 17 serving as a barrier layer may be molded using a mold after the inner 18 is molded, for example.

  In the crust-like composition 20b-2 as described above, the molded product can be used as a fish reef or a coastal marine structure, or can be settled in the ocean. Moreover, it can arrange | position to a mine shaft and can be used as a floor material and / or wall material of a mine shaft. Further, when the density of the radioactive substance 19 in the center of the interior 18 where the density of the radioactive substance 19 is the highest is set to a predetermined value or less, the block-shaped molded product is pulverized and crushed aggregate like the crust-like composition 20a. It can be used as (crusher run).

  In the crust-like composition 20, as shown in FIG. 10, the outer layer 17 serving as a barrier layer is not provided in the outermost layer, and the density of the radioactive substance 19 gradually decreases from the center toward the outside. In addition, it may be a crust-like composition 20e having a predetermined value or less as a whole.

[5. Method for producing crust-like composition]
[5-1. Description of the entire manufacturing process]
The raw material containing the radioactive substance 19 used for the crust-like composition 20 shown in FIGS. 5-10 as described above is specifically manufactured through the steps shown in FIG. As shown in Table 2 above, radioactive pollutants include fish and shellfish, vegetables, incinerated ash, sludge sludge, marine mud sand, river mud sand, lake mud sand, roadside trees, debris (concrete, wood, glass, metal, plastic) ), Contaminated water, earth and sand, and road surface materials. In the pretreatment step 1001, for example, these pollutants are fired to make the pollutants inorganic. Details of the pretreatment process 1001 will be described later.

  In the raw material process 1002, as shown in FIG. 12, calcium carbonate compositions and radioactive pollutants generated from fish and shellfish that have become radioactive pollutants, animal carcasses such as animal carcasses, meat and bones, vegetables, and the like. Fine-grained geological composition such as incinerated ash, sludge sludge, lake mud sand, etc., silicic composition such as marine mud sand, river mud sand, lake mud sand, etc. which became radioactive pollutants, iron oxide raw materials, etc. A powder raw material with stable components is produced by pulverizing, drying and mixing. The fine geological composition and siliceous composition may be incinerated ash from a thermal power plant, or debris (concrete, wood, glass, metal, plastic) that has become a radioactive pollutant. May be.

  Next, in the firing step 1003, as shown in FIG. 13, the powder raw material obtained in the raw material step is heated to a predetermined temperature and fired to become a hydraulic compound. For example, after reaching a maximum temperature and finishing a predetermined chemical reaction, it is cooled at once with an air quenching cooler to produce a primary composition which is a solid phase composition. At the time of firing, either a radioactive pollutant or a non-radioactive pollutant may be used, but a raw material for fuel such as waste plastic, waste oil, waste white clay, wood scrap, meat-and-bone meal, reclaimed oil, etc. is charged to fire the powder material.

  The primary composition, which is a solid phase composition, is prepared by adjusting the concentration (density) of the radioactive material in advance for each of the calcium carbonate composition, fine-grained geological composition, siliceous composition, iron oxide raw material, and fuel raw material. By using this, the concentration (density) of the radioactive substance as a whole can be adjusted to a predetermined value or less or higher. The primary composition which is a solid phase composition is a calcium carbonate composition, a fine-grained geological composition, a siliceous composition, an iron oxide raw material, one or a plurality of fuel raw materials, and a radioactive pollutant. By adjusting the amount of the non-radioactive material as a non-radioactive contaminant, the concentration (density) of the radioactive substance can be set to a predetermined value equal to or lower than the predetermined value described above. These primary compositions may be those that do not contain radioactive substances.

  Furthermore, in the finishing step 1004, as shown in FIG. 14, the primary composition, which is the solid phase composition obtained in the firing step, is adjusted to adjust the curing rate and / or hydration reaction rate of the primary composition. Reaction rate modifiers such as gypsum are added and they are pulverized to a fine powder, thereby completing a secondary composition that becomes a solidifying binder. The secondary composition used as the solidifying binder can also be adjusted to a predetermined value equal to or lower than the predetermined value or higher by using the above-described primary composition. .

  The secondary composition to be the solidifying binder is kneaded with an appropriate amount of water to become a paste-like composition or a tertiary composition that is a solid phase. This tertiary composition is hydrated and / or polymerized and solidified by being kneaded with water. The water used here may be tap water, river water, fresh water such as lake water, water other than fresh water such as seawater, contaminated water that is a radioactive pollutant, or non-water. It may be water of radioactive contamination material. In particular, when seawater is used and treatment by transoceanic crust reduction is performed, it is preferable because the osmotic pressure adjustment between the crust composition and seawater in contact with the sea can be performed in advance. Depending on what kind of water is used for the tertiary composition, the concentration (density) of the radioactive material as a whole can be adjusted to a predetermined value or lower or a predetermined value below. In such a tertiary composition, the concentration (density) of the radioactive substance as a whole is set to a predetermined value or less in the pasty composition state or the cured crust-like composition state.

  Further, the secondary composition to be a solidifying binder is a paste-like composition or a quaternary composition that is a solidified product by adding fine aggregate (sand) and kneading with an appropriate amount of water. . This quaternary composition is hydrated and / or polymerized and solidified by being kneaded with water. The water used here may be fresh water, seawater, contaminated water that is a radioactive pollutant, or non-radioactive contaminated water. In particular, when seawater is used and when transoceanic crust reduction is performed, it is preferable because the osmotic pressure adjustment between the crust composition and seawater in contact with the seatime can be performed in advance. Further, as the fine aggregate (sand), radioactive pollutants such as earth and sand, lake mud sand, marine mud sand and river mud sand may be used, or sand of non-radioactive pollutant material may be used. Depending on what kind of water or fine aggregate (sand) is used for the quaternary composition, the concentration (density) of the radioactive substance as a whole can be adjusted to a predetermined value or less. In such a quaternary composition, the concentration (density) of the radioactive material as a whole is set to a predetermined value equal to or lower than a predetermined value or higher in a paste-like composition state or a cured crust-like composition state. .

  Furthermore, the secondary composition to be a solidifying binder is a quinary composition which is a paste-like composition by adding fine aggregate (sand) and coarse aggregate (gravel) and kneading with an appropriate amount of water. It becomes. This quaternary composition is hydrated and / or polymerized and solidified by being kneaded with water. The water used here may be fresh water, seawater, contaminated water that is a radioactive pollutant, or non-radioactive polluted water. There may be. In particular, when seawater is used and when transoceanic crust reduction is performed, it is preferable because the osmotic pressure adjustment between the crust composition and seawater in contact with the seatime can be performed in advance. Further, as the fine aggregate (sand), radioactive pollutants such as earth and sand, lake mud sand, marine mud sand and river mud sand may be used, or sand of non-radioactive pollutant material may be used. Depending on what kind of water or fine aggregate (sand) is used for the quaternary composition, the concentration (density) of the radioactive substance as a whole can be adjusted to a predetermined value or less. In such a quintic composition, in the state of a paste-like composition or the state of a hardened crust-like composition, the concentration (density) of the radioactive material as a whole is set to a predetermined value equal to or lower than a predetermined value. .

  Although the tertiary composition, the quaternary composition, and the quinary composition as described above will be described later in the molding step 1005, the paste-like composition is poured into a mold and molded into a block shape. In the utilization process 1007, the tertiary composition, the quaternary composition, and the quaternary composition molded into the block shape are configured as shown in FIG. 5 to FIG. It can be used as a structure and can be submerged in the ocean. The tertiary composition, quaternary composition, and quinary composition should be deposited in the ocean as a pasty crust-like composition in a pasty state when the concentration (density) of radioactive material is below a predetermined value. I can do it. Moreover, the shape | molded crust-like composition 20 can be arrange | positioned in a tunnel, and can be used for the floor part and / or wall part, and / or ceiling part of a tunnel. Moreover, even if it is a paste-like crust-like composition, it can be poured or sprayed on a floor part and / or a wall part, and / or a ceiling part. Furthermore, it can be used for materials for backfilling floors and / or walls and / or ceilings or tunnels. Further, when the concentration (density) of the radioactive substance is equal to or less than a predetermined value, the crust-like composition 20 may be crushed into a block-shaped molded product in a crushing process step 1006 to obtain a crushed aggregate (crusher run). In the utilization step 1007, this aggregate can be used for, for example, a ballast used for a road material or a soft ground replacement material, a soil material, or a ballast track, which will be described later in detail.

[5-2. Explanation of pretreatment process]
[5-2-1. Explanation of baking treatment of pollutants]
As shown in Table 2 above, radioactive pollutants include fish and shellfish, vegetables, incinerated ash, sludge sludge, marine mud sand, river mud sand, lake mud sand, roadside trees, debris (concrete, wood, glass, metal, plastic) Contaminated water, earth and sand, road surface materials, etc. The radioactive pollutant used here may have a radioactivity concentration (density) at the measurement lower limit, but a pollutant containing a radioactive substance at a radioactivity concentration (density) exceeding the measurement lower limit can also be used. . When organic matter is contained in such a pollutant, the crust-like composition 20 is molded, and the organic matter swells or rots with time, or generates gas over time. There is a risk of weakening. Therefore, in the pretreatment step 1001, as shown in FIG. 15, before the contaminant is used as a raw material of the crust-like composition 20, the contaminant is fired. The firing temperature here is lower than the vaporization temperature of the radioactive substance, so that the radioactive substance or ash remains as a residue so that the radioactive substance is not vaporized and released into the atmosphere. In this manner, the contaminant can be vaporized or mineralized by being fired.

  Table 3 is a boiling point table of typical radioactive substances. Cesium-134 has a boiling point of 671 ° C. Therefore, for example, when the firing temperature is less than 671 ° C., most of the radioactive material can be prevented from vaporizing. Note that when the pollutant is baked in the sealed space, the organic substance can be changed into a gas such as carbon dioxide and an inorganic substance such as moisture and ash by supplying oxygen.

  For example, in the raw material process 1002, the fired pollutant and the incinerated ash obtained by the above-described pollutant firing process are put into a raw material crusher together with a calcium carbonate composition, a siliceous composition, an iron oxide composition, and the like. Thus, a pulverized raw material may be obtained. In addition, when the burned contaminants and incineration ash are kneaded with water or contaminated water from the tertiary composition, quaternary composition or quinary composition to form a paste-like composition, the curing rate and / or water is used as an additive. You may make it mix with the reaction rate adjusting material for adjusting the sum reaction rate, fine aggregate, and coarse aggregate. Thus, the concentration (density) of the radioactive substance 19 as a whole of the crust-like composition 20 can also be adjusted by adding a burning contaminant or incineration ash.

[5-2-2. Explanation of chemical fixation (wrapping treatment) of radioactive material]
In addition, radioactive contaminants such as mud, soil, sand, debris, incineration ash, and sludge containing radioactive material 19 that exceeds the measurement lower limit are chemically stable as shown in FIG. It is preferable. Therefore, after pulverizing and / or firing and / or drying, the pollutant is dissolved or mixed in a low-melting-point material that melts at a temperature lower than the boiling point of the radioactive material 19 and solidified. The body should be crushed into aggregate. The pasty melting point substance mixed with the pollutant is preferably kneaded so that the pollutant is uniformly dispersed in the low melting point substance. In the finishing step 1004, for example, this crushed aggregate is mixed with the secondary composition as a fine aggregate or a coarse aggregate when producing a quaternary composition or a quinary composition that is a paste-like composition. I can do it. Further, it can be mixed together with the above-mentioned fired contaminants and incineration ash. The concentration (density) of the radioactive substance 19 as a whole of the crust-like composition 20 can also be adjusted by adding the crushed aggregate. Note that the solidified body solidified by the lapping treatment can be handled as an incapacitated composition without pulverizing, but in the case of the composition at this stage, chemical stability is obtained. There is a possibility that the shielding property for attenuating radiation is insufficient.

  As the low melting point substance, for example, a low melting point glass having a boiling point lower than that of cesium-134 (boiling point 671 ° C.) can be used. In another example, for example, the chemical structure of borosilicate glass forms a structural network structure in which silicon and boron, which are main components, are arranged in a network via oxygen, and the radioactive material 19 in the glass solidified body. Can be uniformly and stably incorporated into the network structure. By crushing the vitrified body in which the radioactive substance 19 has been taken in this way, a crushed aggregate can be obtained.

  Further, as the low melting point substance, at least one of tar, pitch, polyacrylonitrile, asphalt and the like may be used. In this case, a contaminated material containing the radioactive substance 19 is used as an aggregate, mixed with tar, pitch, polyacrylonitrile, asphalt or the like, and pulverized to produce an aggregate. Even in such a crushed aggregate, as described above, when producing a quaternary composition or a quaternary composition that is a paste-like composition, a secondary composition is used as a fine aggregate or a coarse aggregate. Can be mixed. Of course, this crushed aggregate may be used as a road paving material as a composite material with asphalt or the like.

[5-2-3. Explanation of pretreatment of pollutants]
The pollutant containing the radioactive substance 19 includes contaminated water contaminated with the radioactive substance 19. The contaminated water containing the radioactive substance is mixed with the support material supporting the radioactive substance, thereby supporting the radioactive substance on the support material, and this is used as a raw material for the crust-like composition 20 as a contaminant. I can do it. That is, as shown in FIG. 17, the carrier and the contaminated water contaminated with the radioactive substance 19 are mixed in the container.

  Examples of the supporting material used here include a layered structure having a property of adsorbing, coagulating, and coagulating properties such as vermiculite, bentonite, and asbestos, an alkali metal such as cesium, and an alkaline earth such as strontium. Substances having a compounding property that reacts with a cationic substance such as a metal group to produce a stable solid compound are included.

  The inventor of the present invention classified the topsoil components and obtained the knowledge that a large amount of cesium was found in fine sand and ultrafine sand of 0.075 mm or less in classification by Wentworth particle size classification. The supporting material used here adsorbs cesium to finely divided soil having a layered structure having a particle size of 0.075 mm or less. When the layered structure of finely divided soil and contaminated water are mixed, the contaminant support material that adsorbs and holds the radioactive substance 19 forms a paste. This paste-like pollutant-carrying material is used in the finishing step 1004 when the tertiary composition, the quaternary composition, and the quinary composition, which are paste-like compositions, are produced. It can be mixed with wood, fine aggregate, coarse aggregate and the like. Of course, it is good also as a powder form by drying, without using it in paste form.

  Further, a porous material can be used in place of the finely divided soil having a layered structure. For example, as a porous material, there is Shirasu Porous Glass. Shirasu porous glass can freely control the pore size in the range of 1 nm to 50 μm by adjusting the heat treatment conditions, so the pore size is adjusted according to the size of the target radioactive substance, its compound or mixture, and the radioactive substance Can be adsorbed. Such a porous material becomes a filter medium and can separate water and the radioactive substance 19. This contaminant-carrying material can be mixed into the primary to quinary composition and used as a contaminant. The filtered water is also used in the finishing step 1004 as a tertiary composition or a quaternary which is a paste-like composition. It can be used when producing a composition or a quinary composition. That is, according to the contamination concentration of the contaminated water, the mixing amount of the carrier material is determined and mixed, and the filtered water and the contaminant carrier material can be mixed and used as a raw material of the crust composition without separation. I can do it. The porous material may be an amorphous carbon material.

[5-3. Explanation of other processing]
When a tertiary composition, a quaternary composition or a quinary composition is kneaded with water or contaminated water to make a paste-like composition, a high specific gravity material with low reactivity is added as an additive, and the radiation shielding function Can be improved. Examples of high specific gravity materials include barium and lead glass pieces. As shown in FIGS. 6 to 10, these high specific gravity substances can improve the barrier performance especially by being distributed in the outer layer 17 of the crust-like composition 20. Further, when processing the contaminant support material or the contaminated soil in which the radioactive material is supported on the support material described above, since these contaminants have a lower specific gravity than the high specific gravity additive, for example, described later. When molding using centrifugal force, a large amount of high specific gravity material is distributed on the outside, contaminants are distributed on the inner side, and radioactive materials are not distributed on the outer side. Can be increased.

  In addition, when a tertiary composition, a quaternary composition or a quinary composition is kneaded with water or contaminated water to form a paste-like composition, resin fibers such as unsaturated polyester, unsaturated polyethylene and unsaturated polypropylene, By adding metal fibers as an additive, the physical strength of the crust-like composition 20 can be increased.

  Furthermore, when a tertiary composition, a quaternary composition, or a quinary composition is kneaded with water or contaminated water to obtain a paste-like composition, an inexpensive and basic substance such as soda glass is crushed and added. May be. Moreover, you may add glass fiber. Thereby, neutralization of the crust-like composition 20 can be prevented.

  Furthermore, when the tertiary composition, the quaternary composition, or the quinary composition is kneaded with water or contaminated water to obtain a paste-like composition, titanium oxide may be added. Titanium oxide has high hydrophilicity, can enhance the water retention effect, and can prevent deterioration due to lack of moisture during the hydraulic reaction.

[5-4. Explanation of molding method]
Next, the case where the crust-like composition 20 shown in FIG. 5-10 described above is molded using the above-described tertiary composition, quaternary composition, or quinary composition will be described.

[5-4-1. Explanation of production method of crust-like composition with uniform radioactive material]
In the crust-like composition 20a shown in FIG. 5, the radioactive substance 19 is uniformly dispersed and solidified as a whole and is formed into a block shape. As shown in FIG. 18, in order to mold the crust-like composition 20a, first, a tertiary composition or a fourth composition is formed on an outer mold 101 having a predetermined shape made of a material such as steel, wood, resin, or glass. The next composition and the fifth composition can be kneaded with water or contaminated water, the paste-like composition 102 is driven in, compacted with a vibrator or the like, and then the outer mold 101 can be removed and molded. Here, the paste-like composition 102 is poured into the outer mold 101 in a state where the radioactive substance 19 is uniformly dispersed. In the paste-like composition 102, the concentration (density) of the radioactive substance is set to a predetermined value that is equal to or less than a predetermined value. Thus, the crust-like composition 20a is molded as a block in which the concentration (density) of the radioactive material as a whole is a value equal to or less than a predetermined value.

  The outer mold 101 may be used instead of being removed and used as a protective layer of the crust-like composition 20a or a barrier layer against radiation. Further, the radioactive substance 19 can be uniformly dispersed when the kneading time is increased and kneaded firmly, and when the kneading time is shortened, the radioactive substance 19 is unevenly distributed in a part of the molded product. Will be formed.

[5-4-2. Explanation of manufacturing method of crust-like composition with radioactive substance inside]
The crust-like composition 20c-1 shown in FIG. 6 is formed in a block shape, and a radioactive substance 19 is arranged in the interior 18, and the radioactivity concentration is set to be lower than the measurement lower limit value or relatively low in the outer layer 17. In this case, the concentration (density) of the radioactive substance 19 in the interior 18 is set to be equal to or less than the predetermined value described above. In this example, the radioactive material 19 is not included in the outer layer 17. Further, the crust-like composition 20c-2 shown in FIG. 7 is formed into a block shape, and the radioactive substance 19 is arranged in the interior 18, and the outer layer 17 is a barrier layer that does not contain the radioactive substance 19. The concentration (density) of the radioactive substance 19 as a whole including the outer layer 17 is larger than the predetermined value described above. Since the crust-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7 may be molded from the outer layer 17 and molded from the inner part 18, these manufacturing methods will be described next.

(1) Example starting from outer layer Such crust-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7 can be manufactured by the procedure shown in FIG. 19 when being molded from the outer layer 17 side. . Specifically, as shown in FIG. 19A, first, an inner 18 containing a radioactive substance 19 is further formed in an outer mold 111 having a predetermined shape made of a material such as steel, wood, resin, or glass. An inner mold 112 for supporting the position is supported by a mounting portion (not shown) at a predetermined distance from the bottom surface of the outer mold 111. In addition, the inner mold 112 is set to have a lower opening surface than the outer mold 111 so that the non-radioactive paste-like composition 113 can be driven onto the interior 18. .

  For example, when the interior 18 is provided at the center of the block, the inner mold 112 is disposed at the center of the outer mold 111. That is, the inner mold frame 112 has an interval a1 between the side wall of the outer mold frame 111 and the side wall of the inner mold frame 112 and a distance a2 between the bottom surface of the outer mold frame 111 and the bottom surface of the inner mold frame 112 in FIG. And the outer mold frame 111 are arranged in the outer mold frame 111 so that the distance a3 between the opening surface of the outer mold frame 111 and the opening surface of the inner mold frame 112 is equal. A paste-like composition 113 that is a non-radioactive material such as mortar or concrete is driven into the space between the outer mold 111 and the inner mold 112 to the height of the opening surface of the inner mold 112. The paste-like composition 113 may be a resin, tar, pitch, polyacrylonitrile heat treatment quality, asphalt, or the like. Here, compaction may be performed with a vibrator or the like.

  Next, as shown in FIG. 19 (B), a paste-like composition 114 is driven into the inner mold 112 by kneading the tertiary composition, the quaternary composition, or the quinary composition with water or contaminated water. Here, in the paste-like composition 114, when the crust-like composition 20c-1 in which the density of the radioactive substance 19 in the interior 18 shown in FIG. 6 is a predetermined value or less is formed, the density of the radioactive substance 19 is adjusted to be a predetermined value or less. Is used. When forming the crust-like composition 20c-2 in which the density of the radioactive substance 19 in the interior 18 shown in FIG. 7 is greater than a predetermined value, the density of the radioactive substance 19 is greater than the predetermined value, preferably the outer layer 17 and the interior 18 The radioactivity level with respect to the total mass, that is, the radioactivity concentration adjusted so as to meet the standard value is used. Then, the paste-like composition 114 is driven up to the opening surface of the inner mold 112. In this case, the paste-like composition 114 in the inner mold 112 may be compacted.

  Next, as shown in FIG. 19C, the non-radioactive material paste-like composition 113 is driven into the entire surface including the upper side of the paste-like composition 114 poured into the inner mold 112 up to the opening surface of the outer mold 111. It is. In this case, the paste-like composition 114 in the inner mold 112 may be compacted. Thus, in the crust-like compositions 20c-1 and 20c-2 shown in FIG. 6 and FIG. 7, the concentration (density) of the radioactive substance in the interior 18 is set to a predetermined value or less or a large value. Density) is formed as a block having a predetermined value or less. The outer mold 111 may be left instead of being removed and used as a protective layer of the crust-like compositions 20c-1 and 20c-2 or a barrier layer against radiation.

  In addition, as shown in FIGS. 19A and 19D, after the paste-like composition 113 of the non-radioactive material is poured into the outer mold 111 and solidified in a previously formed state, the inner mold 112 is removed, The paste-like composition 114 containing the radioactive substance 19 may be poured into the recess 115 formed by releasing the inner mold 112. That is, in this example, the recess 115 is used as the inner mold 112. Thereafter, as shown in FIG. 19 (E), the non-radioactive material paste-like composition 113 is driven up to the opening surface of the outer mold 111 entirely including the upper side of the paste-like composition 114 poured into the recess 115. It is. Thereby, the interface between the outer layer 17 and the inner part 18 is in contact with the paste-like composition 113 of the non-radioactive substance and the paste-like composition 114 containing the radioactive substance 19, as shown in FIG. The physical strength of the interface can be increased compared to the case where there is a separator such as a mold.

  Moreover, the crust-like composition 20c-1 and 20c-2 shown in FIG.6 and FIG.7 can be manufactured in the procedure shown in FIG. 20, when shape | molding from the outer layer 17 side. Specifically, as shown in FIG. 20A, the outer mold 111 further includes an inner mold 112a for molding the inner 18 containing the radioactive substance 19 at a predetermined distance from the bottom surface of the outer mold 111. Is supported by a mounting portion (not shown). The inner mold frame 112 a is set so that the height of the opening surface is aligned with the opening surface of the outer mold frame 111.

  For example, when the interior 18 is provided in the central portion of the block, the inner mold 112a is configured such that the space a1 between the side wall of the outer mold 111 and the side wall of the inner mold 112a and the bottom of the outer mold 111 in FIG. And the inner mold 112a are arranged in the outer mold 111 such that the distance a2 between the inner mold 112a and the bottom of the inner mold 112a is equal. A paste-like composition 113 that is a non-radioactive material such as mortar or concrete is driven into the space between the outer mold 111 and the inner mold 112 to the height of the opening surface of the outer mold 111. The paste-like composition 113 may be resin, tar, pitch, polyacrylonitrile, asphalt, or the like. Here, compaction may be performed with a vibrator or the like.

  Next, as shown in FIG. 20 (B), the paste-like composition 114 is driven into the inner mold 112 by kneading the tertiary composition, the quaternary composition, or the quinary composition with water or contaminated water. Here, in the paste-like composition 114, when the crust-like composition 20c-1 in which the density of the radioactive substance 19 in the interior 18 shown in FIG. 6 is a predetermined value or less is formed, the density of the radioactive substance 19 is adjusted to be a predetermined value or less. Is used. When forming the crust-like composition 20c-2 in which the density of the radioactive substance 19 in the interior 18 shown in FIG. 7 is greater than a predetermined value, the density of the radioactive substance 19 is greater than the predetermined value, preferably the outer layer 17 and the interior 18 The radioactivity level with respect to the total mass, that is, the radioactivity concentration adjusted so as to meet the standard value is used. Then, the paste-like composition 114 is driven to a predetermined height of the inner mold 112. That is, the paste-like composition 114 is driven into the inner mold 112 to a height at which the intervals a1, a2 and the distance a3 between the opening surface of the outer mold 111, the inner mold 112a and the upper surface of the paste-like composition 114 are equal. It is. In this case, the paste-like composition 114 in the inner mold 112 may be compacted.

  Next, as shown in FIG. 20C, a non-radioactive material paste-like composition 113 is driven up to the opening surface of the inner mold 112 on the upper side of the paste-like composition 114 poured into the inner mold 112. Here, the pasty composition 113 in the inner mold 112 may be compacted. Thus, the paste-like composition 114 containing the radioactive substance 19 is blocked by the non-radioactive substance-like paste composition 113. In the crust-like compositions 20c-1 and 20c-2 shown in FIG. 6 and FIG. 7, the concentration (density) of the radioactive material in the interior 18 is set to a predetermined value or less, or the concentration of the radioactive material as a whole. (Density) is formed as a block having a predetermined value or less. The outer mold 111 may be left instead of being removed and used as a protective layer of the crust-like compositions 20c-1 and 20c-2 or a barrier layer against radiation.

  As shown in FIGS. 20A and 20D, after the non-radioactive paste-like composition 113 is poured into the outer mold 111 and solidified in a pre-formed state, the inner mold 112 is removed, The paste-like composition 114 containing the radioactive substance 19 may be poured into the recess 116 formed by releasing the inner mold 112. That is, in this example, the recess 116 is used as the inner mold 112. Thereafter, as shown in FIG. 20E, the non-radioactive paste-like composition 113 is driven up to the opening surface of the outer mold 111 on the upper side of the paste-like composition 114 poured into the recess 115. As a result, the interface between the outer layer 17 and the inner part 18 is in contact with the paste-like composition 113 containing the non-radioactive substance and the paste-like composition 114 containing the radioactive substance 19, as shown in FIG. The physical strength of the interface can be increased compared to the case where there is a separator such as a mold.

  In addition, the crust-like composition 20b-1 having a multilayer structure as shown in FIG. 8 is formed in which the density of the radioactive substance 19 in the intermediate layer 18b gradually decreases from the central portion 18a toward the outside as shown in FIG. When doing so, the inner mold 112 corresponding to the number of layers is arranged in the outer mold 111, and the paste-like composition is poured into the inner mold 112 in the order of the center side in order.

(2) Example starting from inside The crust-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7 can be manufactured by the procedure shown in FIG. In this case, first, as shown in FIG. 21 (A), a paste-form containing a radioactive material 19 obtained by kneading a tertiary composition, a quaternary composition or a quinary composition with water or contaminated water with respect to the inner mold 112a. This is cast as a composition 114 and compacted with a vibrator or the like to be molded. Note that when the paste-like composition 114 is formed into a crust-like composition 20c-1 in which the density of the radioactive substance 19 in the interior 18 shown in FIG. 6 is equal to or lower than a predetermined value, the density of the radioactive substance 19 is adjusted to be equal to or lower than the predetermined value. Is used. When forming the crust-like composition 20c-2 in which the density of the radioactive substance 19 in the interior 18 shown in FIG. 7 is greater than a predetermined value, the density of the radioactive substance 19 is greater than the predetermined value, preferably the outer layer 17 and the interior 18 The radioactivity level with respect to the total mass, that is, the radioactivity concentration adjusted so as to meet the standard value is used. Then, the inner molded body 18c with the inner mold frame 112a shown in FIG. 21A and the inner molded body 18d from which the inner mold frame 112a shown in FIG. It will be installed in the frame 111. The inner molded body 18c with the inner mold 112a can function as a protective layer in the inner 18 or a barrier layer against radiation. In addition, the internal molded body 18d from which the inner mold 112a is removed can increase the physical strength of the non-radioactive material paste-like composition 113. In the following example, an internal molded body 18c from which the inner mold 112a is removed will be described as an example.

  Specifically, as shown in FIG. 22 (A), a paste-like composition 113, which is a non-radioactive material such as mortar and concrete before curing, is driven into the outer mold 111 to a predetermined height. Here, compaction may be performed with a vibrator or the like. Next, as shown in FIG. 22B, an internal molded body 18d is placed in the paste-like composition 113. In the paste-like composition 113, the internal molded body 18 d is installed after the internal molded body 18 d is solidified to such an extent that it does not settle in the paste-like composition 113. At this time, the internal molded body 18d is installed at a position where the distance a1 between the side wall of the outer mold 111 and the side wall of the internal molded body 18d is the same. Thereafter, as shown in FIG. 22 (C), a paste-like composition 113 that is a non-radioactive material is poured into the outer mold 111 up to the opening surface. At this time, the internal molded body 18d is formed in the outer mold frame 111 between an interval a2 between the bottom surface of the outer mold frame 111 and the bottom surface of the internal molded body 18d, an opening surface of the outer mold frame 111, and an upper surface of the internal molded body 18d. The interval a3 is set to be equal. That is, the internal molded body 18d is disposed in the outer mold 111 at a position where a1 = a2 = a3. Thus, in the crust-like compositions 20c-1 and 20c-2 shown in FIG. 6 and FIG. 7, the concentration (density) of the radioactive substance in the interior 18 is set to a predetermined value or less or a large value. Density) is formed as a block having a predetermined value or less. The outer mold 111 may be left instead of being removed and used as a protective layer of the crust-like compositions 20c-1 and 20c-2 or a barrier layer against radiation. The paste-like composition 113 may be a resin, tar, pitch, polyacrylonitrile, asphalt, or the like. Here, compaction may be performed with a vibrator or the like.

  Further, the outer mold 111 may be configured as shown in FIG. That is, as shown in FIG. 23A, the outer mold 111 is provided with a temporary table 111a having a first height on the bottom surface, and an internal molded body 18d is installed on the temporary table 111a. The The temporary table 111a is installed at a predetermined height by, for example, a plurality of support legs 111b, and the paste-like composition 113 flows into a space between the temporary table 111a and the bottom surface of the outer mold 111. When the internal molded body 18d is installed on the temporary base 111a, the outer mold 111 has an outer mold in which the paste-like composition 113, which is a non-radioactive substance, has a second height, as shown in FIG. It is poured into the opening surface of the frame 111. At this time, the internal molded body 18d is formed in the outer mold frame 111 between an interval a2 between the bottom surface of the outer mold frame 111 and the bottom surface of the internal molded body 18d, an opening surface of the outer mold frame 111, and an upper surface of the internal molded body 18d. The interval a3 is set to be equal. Moreover, it installs so that the space | interval a1 and the space | interval a2, a3 of the side surface of the outer mold 111 and the side surface of the internal molded object 18d may become equal.

  Thus, in the crust-like compositions 20c-1 and 20c-2 shown in FIG. 6 and FIG. 7, the concentration (density) of the radioactive substance in the interior 18 is set to a predetermined value or less or a large value. Density) is formed as a block having a predetermined value or less. In such a molding method, the paste-like compositions 113 and 114 are in direct contact except for the temporary table 111a, and the physical height at the interface is increased as compared with the case where there is a separator such as a mold. I can do it. The outer mold 111 may be left instead of being removed and used as a protective layer of the crust-like compositions 20c-1 and 20c-2 or a barrier layer against radiation. The paste-like composition 113 may be a resin, tar, pitch, polyacrylonitrile, asphalt, or the like. Here, compaction may be performed with a vibrator or the like.

  Furthermore, as shown in FIG. 24 (A), the outer mold 111 is suspended at a first height by a wire 111c, and as shown in FIG. 24 (B), a paste-like composition which is a non-radioactive material. The object 113 may be poured into the second height which is the opening surface of the outer mold 111. At this time, the internal molded body 18d is installed such that the distance a1 between the side surface of the outer mold 111 and the side surface of the internal molded body 18d is equal to the distances a2 and a3. In the outer mold 111, the distance a2 between the bottom surface of the outer mold 111 and the bottom surface of the internal molded body 18d and the distance a3 between the opening surface of the outer mold 111 and the upper surface of the internal molded body 18d are equal. Set to Of course, these intervals a1, a2, and a3 do not necessarily have to be equal to each other, and may be sufficient to sufficiently attenuate the radiation emitted from the inside to a desired value. As a result, the inner molded body 18d is disposed at the center of the outer mold 111. And the part exposed after the paste-like composition 113 solidified the wire 111c is cut | disconnected. Of course, the wire 111c does not necessarily need to be cut, and when the internal molded body 18d is embedded to some extent with the paste-like composition 113, the wire 111c can be removed or embedded together with the internal molded body 18d.

  Thus, in the crust-like compositions 20c-1 and 20c-2 shown in FIG. 6 and FIG. 7, the concentration (density) of the radioactive substance in the interior 18 is set to a value equal to or less than a predetermined value, and the concentration of the radioactive substance as a whole. (Density) is formed as a block having a predetermined value or less. Such a molding method does not require the provisional base 111a to be installed on the outer mold 111, and can simplify the manufacturing process. Further, the paste-like compositions 113 and 114 are in direct contact with each other, and the physical height at the interface can be increased as compared with the case where there is a separator such as a mold. The outer mold 111 may be left instead of being removed and used as a protective layer of the crust-like compositions 20c-1 and 20c-2 or a barrier layer against radiation. The paste-like composition 113 may be a resin, tar, pitch, polyacrylonitrile, asphalt, or the like. Here, compaction may be performed with a vibrator or the like.

  Further, as shown in FIGS. 25A and 25B, a paste-like composition 113 which is a non-radioactive material is poured into the outer mold 111 to the opening surface of the outer mold 111, and then the paste-like composition 113 is formed. The inner molded body 18d may be submerged before being solidified and positioned at a substantially central portion in the outer mold frame 111.

  Note that the crust-like composition 20b-1 as shown in FIG. 8 in which the density of the radioactive substance 19 in the intermediate layer 18b decreases stepwise from the central part 18a toward the outside is the radioactive substance on the surface of the internal molded body 18d. The intermediate layer 18b having a low concentration (density) of 19 is provided, this is repeated, and finally, the outer layer 17 not including the radioactive substance 19 is provided.

(3) Example of starting at the same time In addition, the crust-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7 can simultaneously produce the inner 18 and the outer layer 17. In this case, as shown in FIGS. 26A and 26B, a discharge port 113a for discharging the non-radioactive material paste-like composition 113 and a discharge port 114a for discharging the paste-like composition 114 containing the radioactive material 19 are discharged. A hopper 118 provided with Of course, the discharge port 113a here discharges the non-radioactive material paste-like composition 113, but is not necessarily a non-radioactive material paste-like composition. The discharge port 114a for discharging the paste-like composition 114 containing the radioactive substance 19 is provided at the center, forms the interior 18, and the discharge port 113a for discharging the paste-like composition 113 of the non-radioactive substance is the discharge port. A plurality of outer layers 17 are formed around 114a. An inner mold 112 for forming the interior 18 is positioned below the discharge port 114a, and an area between the outer mold frame 111 and the inner mold frame 112 is positioned below the discharge port 113a.

  Moreover, the paste-like composition 114 containing the radioactive substance 19 discharged | emitted from the discharge port 114a is a case where the density | concentration of the radioactive substance 19 of the inside 18 shown in FIG. 6 forms the crust-like composition 20c-1 below a predetermined value A material whose density of the radioactive substance 19 is adjusted to a predetermined value or less is used. When forming the crust-like composition 20c-2 in which the density of the radioactive substance 19 in the interior 18 shown in FIG. 7 is greater than a predetermined value, the density of the radioactive substance 19 is greater than the predetermined value, preferably the outer layer 17 and the interior 18 The radioactivity level with respect to the total mass, that is, the radioactivity concentration adjusted so as to meet the standard value is used.

  As shown in FIG. 26C, first, a paste-like composition 113 of a non-radioactive material is poured into the outer mold 111 from the discharge port 113a. Next, as shown in FIG. 26 (D), the inner mold 112 is poured with the paste-like composition 114 containing the radioactive substance 19 from the discharge port 114a, and as shown in FIG. Paste composition 114 is poured up to the height of the opening surface of frame 112. Then, the discharge from the discharge port 114a is stopped, and the non-radioactive paste-like composition 113 is poured into the height of the opening surface of the outer mold 111 from the discharge port 113a. The flow rate and the flow rate of the paste-like composition 114 including the non-radioactive material paste-like composition 113 discharged from the discharge port 113a and the radioactive material 19 discharged from the discharge port 114a are such that the inner mold 112 has the paste-like composition 114. It is preferable that the paste-like composition 113 is adjusted so as not to enter the inner mold 112 before being satisfied by the above. Further, it is desirable to adjust so that the paste-like composition 114 does not overflow from the inner mold 112 and flow into the outer mold 111. According to such a molding method, since the paste-like composition 113 of the non-radioactive substance and the paste-like composition 114 containing the radioactive substance 19 can be poured in parallel, the production efficiency can be improved. I can do it.

  Further, when the paste-like composition 113 of the non-radioactive material discharged from the discharge port 113a and the paste-like composition 114 containing the radioactive material 19 discharged from the discharge port 114a are poured simultaneously, the inner mold 112 is not used. Also good. That is, as shown in FIG. 27A, the inner mold 112 is not installed in the outer mold 111. In this state, the non-radioactive paste-like composition 113 is poured into the first height from the discharge port 113a. Next, as shown in FIG. 27B, the paste-like composition 114 containing the radioactive substance 19 is also poured from the discharge port 114a. Then, as shown in FIG. 27C, the paste-like composition 114 containing the radioactive substance 19 is poured into the central portion of the outer mold 111 from the discharge port 114a, and the paste of the non-radioactive substance is placed outside thereof. The composition 113 is poured. 27E by aligning the rising of the water surface of the non-radioactive material paste-like composition 113 from the discharge port 113a and the rising surface of the paste-like composition 114 containing the radioactive material 19 from the discharge port 114a. As shown in FIG. 3, the paste-like composition 114 can be distributed inside the outer paste-like composition 113. When the predetermined height is reached, the discharge of the paste-like composition 114 from the discharge port 114a is stopped, and only the paste-like composition 113 is discharged from the discharge port 113a, whereby the paste is placed on the paste-like composition 114. The composition 113 can be distributed. Then, the paste-like composition 113 is poured into the opening surface of the outer mold 111.

  According to such a molding method, since the paste-like composition 113 of the non-radioactive substance and the paste-like composition 114 containing the radioactive substance 19 can be poured in parallel, the production efficiency can be improved. I can do it. In addition, since the inner mold 112 is not used, the production process can be simplified. Here, if the fluidity and specific gravity of the paste-like composition 113 and the paste-like composition 114 are too different, the distribution is disturbed. Therefore, it is preferable that these properties are not too different.

  Note that the crust-like composition 20b-1 as shown in FIG. 8 in which the density of the radioactive substance 19 in the intermediate layer 18b decreases stepwise from the center part 18a toward the outside has a concentration (density) of the radioactive substance 19 as shown in FIG. A paste-like composition 114 containing a different radioactive substance 19 can be molded by pouring it into the outer mold 111 so that its concentration (density) decreases toward the outer mold 111.

[5-4-3. Explanation of manufacturing method of crust-like composition using centrifugal force]
The inside 18 of the crust-like composition 20b-2 shown in FIG. 9 is configured such that the density of the radioactive substance 19 gradually decreases from the center to the outside. The crust-like composition 20e shown in FIG. 10 is also configured such that the density of the radioactive substance 19 gradually decreases as it goes outward from the center. Here, the two crust-like compositions are also simply referred to as “crust-like composition 20e and the like”. Thus, the crust-like composition 20e etc. in which the density of the radioactive substance 19 gradually decreases from the central part toward the outside can be manufactured using centrifugal force.

  FIG. 28A shows a centrifuge 121. The centrifuge 121 is provided with a mold 122 for molding the crust-like composition 20e and the like, and the mold 122 is rotated at high speed around a shaft 125. The centrifuge 121 is provided with a hopper discharge port 123 and a discharge port 124. From the discharge port 123, a substance 19b corresponding to a high specific gravity material is poured into the mold 122, and from the discharge port 124, a substance 19a corresponding to a low specific gravity material is poured into the mold 122. Of course, the centrifuge does not necessarily have to have a rotating mold, and it is sufficient that the material substance in a flowable state before solidification accommodated in the mold can be rotated at high speed. .

  The high specific gravity substance 19b is a substance having a high specific gravity whose radioactivity concentration is set to be lower than the measurement lower limit value or relatively low. As described above, other than barium and lead glass pieces having a high radioactivity shielding effect, etc. Examples include aggregates and coarse aggregates. The low specific gravity material 19a is a low specific gravity material having a finite radioactivity concentration, and includes soil containing radioactive material, that is, contaminated soil, in particular, a layered structure of fine soil and other porous materials. As described above, it may be a contaminated water and a contaminant carrying material mixed with these (see FIG. 17). Specifically, the finely divided soil structure has a main particle size of 0.075 mm or less, for example, vermiculite, bentonite, asbestos, etc., and porous materials include shirasu porous glass, amorphous carbon, etc. Examples include materials. The high specific gravity material 19b and the low specific gravity material 19a are mixed and kneaded as additives and aggregates into the tertiary composition, the quaternary composition, and the quinary composition that are paste-like compositions from the discharge ports 123 and 124. To do. Then, the low specific gravity material 19a containing the radioactive material 19 and the non-radioactive high specific gravity material 20 are uniformly dispersed. In addition, the centrifugal separator does not necessarily have to be provided with the discharge ports 123 and 124, and it is not necessary to discharge the high specific gravity material and the low specific gravity material separately. And a low specific gravity substance may be mixed and accommodated in the mold.

  Next, as shown in FIG. 28 (B), when the mold 122 is rotated at a high speed, a large amount of the high specific gravity material 19b is distributed outside and a large amount of the low specific gravity material 19a is distributed inside due to the centrifugal force. Thereby, the crust-like composition 20e etc. in which the density of the radioactive substance 19 gradually decreases from the center toward the outside can be easily manufactured. The high specific gravity material 19b has a high radioactivity barrier effect. By distributing a large amount of the high specific gravity material 19b on the outside, a crust-like composition having a high radioactivity barrier effect can be formed. Further, as shown in FIG. 9, the outer layer 17 that does not contain the radioactive substance 19 can also be formed with a layer in which a high specific gravity substance is distributed a lot. The outer layer 17 can be made as thin as the skin layer.

[5-4-4. Explanation of manufacturing method of crust-like composition using pressure]
As shown in Table 2 and FIG. 3 above, radioactive pollutants include fish shellfish, vegetables, incinerated ash, sludge sludge, marine mud sand, river mud sand, lake mud sand, roadside trees, debris (concrete, wood, glass, Metal, plastic), contaminated water, earth and sand, road surface material, etc., and earth and sand, lake mud sand, marine mud sand, river mud sand, road surface material and the like can be used as fine aggregate and coarse aggregate. And to the secondary composition that becomes a solidifying binder obtained by adding gypsum and the like to the primary composition, the above-described tertiary composition, quaternary composition, and quintic are added by adding fine aggregate, coarse aggregate, etc. A composition can be produced.

  Then, as shown in FIG. 9 and FIG. 10, in producing the crust-like compositions 20 b-2 and 20 e in which the density of the radioactive substance 19 gradually decreases from the center to the outside, the paste form in the mold is used. It can be manufactured by pressurizing the composition. Specifically, as shown in FIG. 29A, the outer mold pressurizing apparatus 131 includes a mold 132 and a pressurizing member 133 that pressurizes the paste-like composition in the mold 132. In the mold 132, for example, as the secondary composition 134 which becomes a solidifying binder obtained by adding gypsum or the like to the primary composition, the one not containing the radioactive substance 19, and the fine aggregate and the coarse aggregate 135 are What contains the radioactive substance 19 is mixed and accommodated. Then, after the secondary composition 134 and the fine aggregate or coarse aggregate 135 are kneaded in advance, the paste-like composition 136 accommodated in the mold 132 is moved in the mold 132 by the pressing member 133. Pressurized. Then, as shown in FIG. 29B, the secondary composition 134 containing fine particles having a smaller particle size and higher fluidity than the fine aggregate and coarse aggregate 135 moves to the mold 132 side. As shown in FIG. 9, a crust-like composition 20 e in which the density of the radioactive substance 19 gradually decreases as the structure of the inner 18 is moved from the central part to the outer side while forming the outer layer 17 can be formed.

  In the mold pressurizing apparatus 131, when the pressurizing pressure is low, the outer layer 17 is hardly formed, and the crust-like composition 20a in which the radioactive substance 19 is uniformly dispersed as shown in FIG. 5 is formed. You can also Further, when the pressurizing pressure is increased, the secondary composition 134 having a small particle size and a high fluidity is distributed along the inner surface of the mold 132, and the thin outer layer 17 is formed on the skin of the crust-like composition 20a shown in FIG. Can also be formed. The outer layer 17 can increase the physical strength of the molded article because a large amount of the secondary composition 134 having high fluidity is distributed. Further, when the pressure is increased, as shown in FIG. 9, the density of the radioactive substance 19 gradually decreases as the structure of the inner part 18 moves outward from the central part while forming the outer layer 17. 2 can be molded. Furthermore, as shown in FIG. 10, a crust-like composition 20e in which the density of the radioactive substance 19 gradually decreases from the central portion where the outer layer 17 is hardly formed to the outside can be formed. That is, what kind of crust-like composition 20 is formed is determined by appropriately adjusting the composition of the secondary composition 134, water, the magnitude of pressure, the pressurization time, and the like.

  By the way, if air or the like is present between the mold 132, the paste-like composition 136, and the pressure member 137 during pressurization, the crust-like composition 20 to be molded becomes fragile. . Therefore, the pressurizing member 137 shown in FIG. 30A is formed in a mountain shape so that the pressurizing surface of the tip portion is highest at the center. In this case, the pressurizing member 137 moves into the mold 132 so as to push away the paste-like composition 136, so that air can be prevented from entering the mold 132 during pressurization. I can do it.

[5-5. Explanation of grinding process]
The crust-like composition 20a in which the radioactive substance 19 shown in FIGS. 5A and 5B is uniformly dispersed throughout and the crust-like composition 20c-1 containing the radioactive substance 19 in the interior 18 shown in FIG. The density of the substance 19 is equal to or lower than a predetermined value and no longer corresponds to the definition of radioactive waste, and can be treated as general waste or simply as a material or resource. Therefore, in the pulverization treatment step 1006 shown in FIG. 11, as shown in FIGS. 31A and 31B, the crust-like composition 20a and the crust-like composition 20c-1 are crushed with a crusher or the like, and coarsely crushed at the plant. Then, the aggregate 150 can be artificially formed by intermediate crushing or fine crushing. Such a crushed aggregate 150 may be coated with at least one coating layer 151 of resin, tar, pitch, polyacrylonitrile heat treatment quality, and asphalt as shown in FIG. Resin, tar, pitch, polyacrylonitrile heat treatment quality, asphalt can not only function as a barrier layer against radiation emitted by radioactive materials contained in each aggregate, but also increase chemical stability, acid rain and Neutralization and elution due to carbon dioxide in the air can be prevented.

  Such a crushed aggregate 150 can be used as a roadbed material 201 as shown in FIG. 32, for example. In a general road 202 such as a national road, a lower layer roadbed 204, an upper layer roadbed 205, a base layer 206, and a surface layer 207 are sequentially provided on a roadbed 203. For example, the roadbed material 201 that is the crushed aggregate 150 can be used for the lower layer roadbed 204 and the upper layer roadbed 205. That is, the portion using the roadbed material 201 is not the road surface but the roadbeds 204 and 205 below the base layer 206 and the surface layer 207. Therefore, the base layer 206 and the surface layer 207 also serve as a barrier layer against radiation.

  Moreover, the aggregate 150 can be used as the embankment material 211 as shown in FIG. When the original ground has a slope, generally, the upper side of the pavement 212 is cut and the lower side is filled. The embankment material 211 which is a crushed aggregate can be used for the embankment part. In the portion of the pavement 212, the roadbed material 201 can be used on the roadbed. Moreover, although not shown in figure, the crushed aggregate 150 can also be used as a substitute material for soft ground. Further, the aggregate 150 can be used as a ballast 216 used for the ballast track 217 as shown in FIG. Furthermore, as shown in FIG. 40, it is possible to fill the inside of a caisson 310 used for a breakwater, a quay, a revetment and the like with a crushed aggregate.

[5-6. Explanation of use process]
Furthermore, the crust-like composition 20 formed into a block shape shown in FIG. 5-10 can be further reduced to the crust as follows. Specifically, there are a method of reducing the crust through the ocean and a method of reducing directly to the ground.

[5-6-1. Explanation of the transoceanic crust reduction method]
As shown in FIG. 35, the crust-like composition 20 formed into a block shape shown in FIG. 5-10 is landed on the ocean 302, placed on the ocean floor 303, and reduced as a part of the crust on the ocean floor. I can do it. The crust-like composition 20 formed in the shape of a block disposed on the seabed is transported to the ocean 302 by a ship 301 and then input, thereby functioning as a fish reef 303a or the like on the seabed 303. When sinking into the deep sea, such as a subduction trench, it can sink into the crust on the seabed and disappear as the plate 304 moves.

  When sinking into the deep sea, in order to reduce the influence of the ocean current and the like, and to make the crust-like composition 20 settle at a predetermined position, for example, as shown in FIGS. It is preferable to provide a teardrop shape, a weight shape, a bullet shape, a streamlined shape, and the like, and a weight portion 307 having a weight from the other end side on one end side. Thereby, the crust-like composition 20 can be settled at a predetermined position on the seabed 303 in a stable posture.

  For example, as shown in FIG. 37, the ship 301 that transports the crust-like composition 20 to a predetermined place in the ocean is allowed to sink from the sea to the seabed 303 by using a conveyor 301 b from the hatch 301 a at the rear of the hull. I can do it. Of course, as shown in FIG. 35, the ship 301 may land on the sea surface from the sea using a crane or the like. FIG. 38 shows an example of a catamaran. In this catamaran, a large deck 301d can be provided between the two hulls 301c, and many crust-like compositions 20 can be loaded on the deck 301d. For example, the deck 301d is of an open / close type, and when opened, the crust-like composition 20a loaded on the sea surface at a time can be introduced. FIG. 39 shows an example of a trolley. In the case of a trolley, the block-shaped crust-like composition 20 is loaded on the deck 301 or the internal storage, and towed to a predetermined location, and settled in the ocean using a crane or a conveyor at the predetermined location. It can be made. Further, in the case of a trolley that does not include a propulsion engine, the trolley loaded with the crust-like composition 20 may be submerged and / or submerged in the ocean as it is by injecting seawater. The carriage may be provided with a propulsion engine.

  In the case of a ship such as a trolley, the crust-like composition 20 is formed into a shape such as a hull shape, a drooping shape, and a floating shape that can float, and this is towed and submerged directly in the ocean at a predetermined location. And / or sedimentation. Furthermore, the crust-like composition 20 may be towed in a submerged state and then separated from the towed ship at a desired position and allowed to sink. In this case, in order to reduce the water resistance, it is preferable to form a streamlined type such as a submarine craft or a submarine. The crust-like composition 20 may be used for ocean landfill.

  Furthermore, the crust-like composition 20 can be used for a coastal marine structure as shown in FIG. For example, FIG. 40 shows a caisson 310 used as a breakwater, a quay, a seawall, etc. as one of the facilities of a port / fishing port. The caisson 310 is set on the seabed, for example. Thereafter, the crust-like composition 20 can be disposed in the caisson 310. Further, the caisson 310 may be filled with a crushed aggregate obtained by pulverizing the crust-like composition 20, and a paste-like composition using the crushed aggregate may be placed in the gap between the block-shaped crust-like composition 20. It may be filled or filled. Alternatively, the paste-like tertiary composition, quaternary composition or quaternary composition may be stored in a fluid state and solidified in the caisson. It can also be used as a coastal offshore structure for floating moored shores, floating breakwaters that wave off and wave break off the coast, swash plate dams for the purpose of coastal erosion prevention and multi-purpose use in coastal areas, etc. I can do it.

  By the way, as shown in FIG. 41, the crust-like composition 20 obtained by solidifying the quaternary or quaternary composition that is a paste-like composition has at least a surface selected from asphalt, tar, and glass. The impermeable layer 21 may be provided by one or more substances. When the impermeable layer 21 is provided, the crust-like composition 20 can be prevented from being exposed to seawater or the like and becoming brittle.

Furthermore, as a method for solidifying high-level radioactive substances and highly toxic radioactive substances, ores are artificially synthesized with titanate-based minerals such as hollandite, perovskite, and zirconolite as main components, and molybdenum, Co-fixed transuranium element nuclides such as technetium, ruthenium, plutonium, etc., and co-fixed the fixing material 22 with the primary to quinary composition and the impermeable layer 21 to have a high degree of confinement effect You may do it. For example, the fixing material 22 can be mixed before the kneading with water. In the synthesis of the above artificial ore, for example, rutile (TiO ₂ ) and zircon (ZnO ₂ ) among the precursors are prepared from titanium alkoxide and zirconium alkoxide. All the remaining components are prepared by treating with an alkaline solution and coprecipitating as a mixed solution of nitrate solution. These precursors are mixed with high-level radioactive or highly toxic radioactive liquid waste to form a slurry, which is dried and calcined in a reducing atmosphere at 800 ° C., which is enclosed in a vessel together with titanium powder and heated. It can also be pressed and fired.

  In addition, the crust-like composition 20a in which the radioactive substance 19 shown in FIGS. 5A and 5B is uniformly dispersed throughout and the crust-like composition 20c-1 containing the radioactive substance 19 in the interior 18 shown in FIG. When the concentration (density) of radioactive material 19 is below the specified value and no longer falls under the definition of radioactive waste, it becomes a general waste or simply a material or resource that can be treated as a transcrust crust. Easy to use. Of course, the crust-like composition 20 as shown in FIG. 7 having a portion (density) of the radioactive substance 19 in the interior 18 higher than a predetermined value may be used for transoceanic crust reduction when forming a block shape.

[5-6-2. Description of the shaft crustal reduction method]
As shown in FIG. 42, the crust-like composition 20 formed into a block shape shown in FIG. 5-10 can be used for backfilling the closed mine shaft 401 to reduce the crust. For example, in the mine shaft 401, invert concrete 403 is placed on a support mine 402 that prevents collapse of the mine. The block-shaped crust-like composition 20 is disposed on the invert concrete 403, for example. At this time, the above-described quaternary composition or quinary composition in which the density of the radioactive substance 19 is not more than a predetermined value may be injected into the space between the crust-like compositions 20. Further, the back end material 404 can be filled on the top end side. Even in the backfill material 404, for example, a fluid-treated soil in which the density of the radioactive substance 19 in which the secondary composition serving as the solidifying binder is poorly mixed is not more than a predetermined value may be used. Thus, the closed mine shaft 401 is backfilled by efficiently using the paste-like composition or the crust-like composition 20 in which the density of the radioactive substance 19 is not more than a predetermined value. Of course, the paste-like crust-like composition 20 can also be used for the floor portion and / or the wall portion and / or the ceiling portion of the mine shaft 401 by using it for the support mine 402 and the invert concrete 403.

  In addition, you may make it spray the paste-form composition in which the density of the radioactive substance 19 is below a predetermined value on the floor surface or wall surface of the mine shaft 401. The pasty composition for spraying may be used as invert concrete during tunnel excavation. In addition, backfilling as shown in FIG. 42 may be performed in a mine that is currently used in order to prevent collapse.

[5-6-3. Explanation of other usage methods]
As shown in FIG. 43 (A), the crust-like composition 20 as described above has a block-like crust-like composition in a trench 501a in a shallow ground 501 that is not provided with an artificial structure as a conventional disposal method of radioactive materials. 20 may be disposed, or a paste-like composition in which the density of the radioactive substance 19 is a predetermined value or less may be placed. Further, the crust-like composition 20c-2 shown in FIG. 7 in which the density of the radioactive substance 19 is partly greater than a predetermined value may be in the shallow ground 501, but as shown in FIG. It may be arranged in the pit 502a at a depth (50 to 100 m underground) 502 having a sufficient margin for general underground use. Further, the pasty crust-like composition 20 can be used in place of ordinary concrete to form the trench 501a and the pit 502a.

10 Radioactive deactivation processing system, 17 outer layer, 18 inside, 18a center part, 18b intermediate layer, 18c, 18d internal molded body, 19 radioactive material, 19a low specific gravity material, 19b high specific gravity material, 20 (20a, 20b, 20c) 20c-1, 20c-2, 20e) Crust-like composition, 21 impervious layer, 22 fixing material, 101 outer mold, 102 paste-like composition, 111 outer mold, 111a temporary base, 111b support leg, 111c Wire, 112 inner mold, 112 inner mold, 112a inner mold, 113,114 paste composition, 113a outlet, 114a outlet, 115,116 recess, 118 hopper, 121 centrifuge, 122 mold, 123, 124 outlet, 125 shaft, 131 mold pressurizer, 132 mold, 133 pressurizing member, 134 secondary Composition, 135 coarse aggregate, 136 paste composition, 137 pressure member, 137 paste composition, 150 crushed aggregate, 151 coating layer, 201 roadbed material, 202 general road, 203 roadbed, 204 lower layer roadbed 205 Upper layer, 206 Base layer, 207 Surface, 211 Filling material, 212 Pavement, 216 Ballast, 217 Ballast track, 301 Ship, 301 Deck, 301a Hatch, 301b Conveyor, 301c Deck, 301d Deck, 302 Ocean, 303 Seabed, 303a fish reef, 304 plate, 307 weight, 310 caisson, 401 closed mine, 401 mine, 401 closed mine, 402 support mine, 403 invert concrete, 404 backfill material, 1001 pretreatment process, 1002 raw material process, 1003 firing process, 1004 finishing Upper process, 1005 molding process, 1006 pulverization process, 1007 utilization process

Claims (38)

Mixing the contaminated water containing the radioactive substance and the support material supporting the radioactive substance,
A method for treating contaminated water, characterized in that the radioactive material in the contaminated water is supported on the support material.   The method for treating contaminated water according to claim 1, wherein the support material is a fine soil having a layered structure.   The method for treating contaminated water according to claim 2, wherein the fine soil has a main particle size of 0.075 mm or less.   4. The method for treating contaminated water according to claim 2, wherein the fine soil material includes at least one selected from vermiculite, bentonite, and asbestos. 5.   The method for treating contaminated water according to claim 1, wherein the carrier is an adsorbent.   The method for treating contaminated water according to claim 1, wherein the support material is porous.   The method for treating contaminated water according to claim 6, wherein the porous material includes one or more selected from among a porous glass and amorphous carbon. Mixing the contaminated water containing the radioactive substance and the support material supporting the radioactive substance,
A treatment material, wherein the radioactive material is supported on the support material.   The treatment material according to claim 8, wherein the support material is a fine soil having a layered structure.   The treated material according to claim 9, wherein the fine soil has a main particle size of 0.075 mm or less.   11. The treatment material according to claim 9, wherein the fine soil material includes one or more selected from vermiculite, bentonite, and asbestos.   The treatment material according to claim 8, wherein the support material is an adsorbent material.   The treatment material according to claim 8, wherein the support material is porous.   The processing material according to claim 13, wherein the porous material includes one or more selected from a glass of porous glass and amorphous carbon. Solid phase obtained by firing a calcium carbonate composition containing calcium carbonate as a main component, a siliceous composition containing silicate as a main component, and an iron oxide composition containing iron oxide as a main component A pulverized material obtained by pulverizing the composition;
Mixing a contaminated water containing a radioactive substance and a support material supporting the radioactive substance, and kneading the support material supporting the radioactive substance with water to produce a paste-like composition; A method for producing a characteristic crust-like composition.   The method for producing a crust-like composition according to claim 15, wherein the paste composition is kneaded with a reaction rate adjusting material for adjusting a curing rate and / or a hydration reaction rate.   The method for producing a crust-like composition according to claim 15 or 16, wherein the paste-like composition is kneaded with fine aggregate.   The method for producing a crust-like composition according to any one of claims 15 to 17, wherein a coarse aggregate is kneaded in the paste-like composition.   The paste-like composition is kneaded with incinerated ash containing a radioactive material obtained by firing a pollutant containing a radioactive material at a radioactivity concentration exceeding the lower limit of measurement below the vaporization temperature of the radioactive material. The method for producing a crust-like composition according to any one of claims 15 to 18, wherein:   The method for producing a crust-like composition according to any one of claims 15 to 19, wherein the radioactive concentration of the paste-like composition is set to a predetermined value or less.   The method for producing a crust-like composition according to claim 20, wherein the predetermined value is a legal standard value set legally.   The method for producing a crust-like composition according to claim 20 or 21, wherein the predetermined value satisfies a clearance level. Solid phase obtained by firing a calcium carbonate composition containing calcium carbonate as a main component, a siliceous composition containing silicate as a main component, and an iron oxide composition containing iron oxide as a main component A pulverized material obtained by pulverizing the composition;
A paste-like crust obtained by mixing contaminated water containing a radioactive substance and a support material supporting the radioactive substance, and kneading the support material with the treatment material supporting the radioactive substance with water. Like composition.   The paste-like crust-like composition according to claim 23, wherein the paste-like crust-like composition is obtained by kneading a reaction rate adjusting material for adjusting a curing rate and / or a hydration reaction rate.   The pasty crust-like composition according to claim 23 or 24, wherein the pasty crust-like composition is obtained by kneading fine aggregate.   The pasty crust-like composition according to any one of claims 23 to 25, wherein the pasty crust-like composition is obtained by kneading coarse aggregate.   In the paste-like crust-like composition, incinerated ash containing a radioactive material obtained by firing a pollutant containing a radioactive material at a radioactivity concentration exceeding the lower limit of measurement below the vaporization temperature of the radioactive material. The paste-like crust-like composition according to any one of claims 23 to 26, which is kneaded.   28. The pasty crust-like composition according to claim 23, wherein the pasty crust-like composition has a radioactivity concentration of a predetermined value or less.   The paste-like crust-like composition according to claim 28, wherein the predetermined value is a legal standard value set legally.   The pasty crust-like composition according to claim 28 or 29, wherein the predetermined value satisfies a clearance level. Solid phase obtained by firing a calcium carbonate composition containing calcium carbonate as a main component, a siliceous composition containing silicate as a main component, and an iron oxide composition containing iron oxide as a main component A pulverized material obtained by pulverizing the composition;
A paste-like composition obtained by mixing contaminated water containing a radioactive substance and a supporting material supporting the radioactive substance and kneading the supporting material supporting the radioactive substance with water is solidified. A crust-like composition characterized in that it is obtained.   The paste-like composition is obtained by kneading a reaction rate adjusting material for adjusting a curing rate and / or a hydration reaction rate, and is obtained by solidifying the paste-like composition. The crust-like composition as described.   The crust-like composition according to claim 31 or 32, wherein the paste-like composition is obtained by kneading fine aggregates and solidifying the paste-like composition.   The crust-like composition according to any one of claims 31 to 33, wherein the paste-like composition is obtained by kneading coarse aggregate and solidifying the paste-like composition.   The paste-like composition is kneaded with incinerated ash containing a radioactive material obtained by firing a pollutant containing a radioactive material at a radioactivity concentration exceeding the lower limit of measurement below the vaporization temperature of the radioactive material. 35. The crust-like composition according to any one of claims 31 to 34, which is obtained by solidifying the paste-like composition.   36. The radioactivity concentration of the paste-like composition is made to be a predetermined value or less, and the paste-like composition is solidified so that the radioactivity concentration is made to be the predetermined value or less. Crust-like composition.   37. The crust-like composition according to claim 36, wherein the predetermined value is a legal standard value set legally.   38. The crust-like composition according to claim 36 or 37, wherein the predetermined value satisfies a clearance level.

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