JP2022009513A - Method for calcining pollution material, calcination pollution material, and incineration ash - Google Patents

Abstract

PROBLEM TO BE SOLVED: To prevent a crustal composition from becoming fragile due to generation of gas from organic matters contained in pollution materials containing radioactive substances.

SOLUTION: A pollution material containing a radioactive substance at a radioactive concentration exceeding a lower limit of measurement is calcined at a temperature lower than a vaporization temperature of the radioactive substance. Here, the pollution material contains, for example, an organic matter, and the organic matter is carbonized and/or gasified by calcination at a temperature lower than the vaporization temperature of the radioactive substance, and the pollution material after the calcination treatment does not contain the organic matter. The calcination treatment is performed, for example, in an oxygen atmosphere or in a closed space. The pollution material mainly contains one or more of mud, soil, sand and debris. Also, the present invention is a calcination pollution material and incineration ash obtained by such a calcination method.

SELECTED DRAWING: Figure 15

COPYRIGHT: (C)2022,JPO&INPIT

Description

The present invention relates to a method for calcining a pollutant containing a radioactive substance at a radioactive concentration exceeding the lower limit of measurement, a calcining contaminant, and an incinerated ash.

In Japan, after the great earthquake on March 11, 2011, there was an accident at a nuclear power plant, and as shown in Fig. 44, it is thought that more than 850,000 terabecquerels of radioactive material 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 contaminants are found in the incineration ash of the garbage incinerator and the sludge of the sewage treatment plant that accumulate daily, and the radioactive contaminants are also found in the rubble of the disaster area. Has been confirmed. Radioactive contaminants have also been confirmed in rivers and the ocean.

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, which prohibits the dumping of radioactive materials into the ocean. In addition, a clearance system has been introduced, where the clearance level for radioactive waste is set.

For the final disposal of radioactive waste, at present, high-level radioactive waste is to be geologically disposed of vitrified waste, and low-level radioactive waste is to be disposed of at a marginal depth, in shallow pits, or in shallow ground. It is supposed to be disposed of in the trench. For geological disposal, the management period is tens of thousands of years or more, for marginal depth disposal is several hundred years, for shallow underground pit disposal is about 300 years, and for shallow underground trench disposal is about 50 years. Such a disposal method requires extremely high technology, is costly, and must be managed for an extremely long period of time. It is extremely difficult to dispose of and manage the radioactive waste that will increase in the future in this way.

The present invention has been made based on the above background, and incinerates a contaminant containing a radioactive substance at a radioactive concentration exceeding the lower limit of measurement, and the generated calcined contaminant and incinerated ash are effective. It is an object of the present invention to provide calcination methods, calcination contaminants, and incineration ash that can be used.
Further, the present invention is a method for firing a pollutant, which prevents an organic substance contained in a pollutant containing a radioactive substance from being fragile due to spoilage, gasification, or swelling of the crustal-like composition. The purpose is to provide calcined contaminants and incinerated ash.

The crustal-like composition according to the present invention includes a water-hard composition, animals and plants containing radioactive substances at a radioactive concentration exceeding the lower limit of measurement, incineration ash, sludge sludge, marine mud, river mud, lake mud, and streets. A fired pollutant containing a radioactive substance obtained by firing a pollutant containing any one or more of trees, debris, contaminated water, and earth and sand at a temperature lower than the vaporization temperature of cesium and / or strontium contained as the radioactive substance. It is obtained by kneading with water, and the radioactive concentration is set to a predetermined value or less as a whole.

Here, for example, the water-hardening composition includes a calcium carbonate composition containing calcium carbonate as a main component and a silicic acid composition containing silicate as a main component, wherein at least one of them is derived from a radioactive contaminant. , Consists of an iron oxide composition containing an iron oxide-based substance as a main component.

Further, for example, as a hydraulic composition, a pulverized material obtained by finely pulverizing a solid phase composition obtained by firing the calcium carbonate composition, a silicic acid composition, and an iron oxide composition is kneaded. is doing.

A reaction rate adjusting material for adjusting the curing rate and / or the hydration reaction rate, a fine aggregate, a coarse aggregate, or a treated material in which a radioactive substance is carried on a supporting material may be kneaded.

The paste-like composition according to the present invention is a water-hard composition, animals and plants containing radioactive substances at a radioactive concentration exceeding the lower limit of measurement, incineration ash, sludge sludge, marine mud, river mud, lake mud, and streets. A fired pollutant containing a radioactive substance obtained by firing a pollutant containing any one or more of trees, debris, contaminated water, and earth and sand at a temperature lower than the vaporization temperature of cesium and / or strontium contained as the radioactive substance. It is made by kneading with water.

Here, for example, the water-hardening composition includes a calcium carbonate composition containing at least one of radiation-derived calcium carbonate as a main component, a silicic acid composition containing a silicate as a main component, and oxidation. It consists of an iron oxide composition containing an iron-based substance as a main component. Further, for example, as a hydraulic composition, a pulverized material obtained by finely pulverizing a solid phase composition obtained by firing the calcium carbonate composition, a silicic acid composition, and an iron oxide composition is kneaded. is doing.

A reaction rate adjusting material for adjusting the curing rate and / or the hydration reaction rate, a fine aggregate, a coarse aggregate, or a treated material in which a radioactive substance is carried on a supporting material may be kneaded.

In the present invention, the contaminant containing the radioactive substance at a radioactive concentration exceeding the lower limit of measurement is fired at a temperature lower than the vaporization temperature of the radioactive substance. Can be free of organic matter.
The fired contaminants obtained by firing are a calcium carbonate composition containing calcium carbonate as a main component, a silicic acid composition containing silicate as a main component, and iron oxide containing an iron oxide-based substance as a main component. A paste-like composition can be produced by kneading a pulverized material obtained by finely pulverizing a solid phase composition obtained by firing the composition with water. Then, by adjusting the amount of the calcined contaminants and the incinerated ash added, the radioactivity concentration of the paste-like composition shall satisfy the legally set legal standard value and also satisfy the clearance level. Can be done. As described above, in the present invention, a fired contaminant containing a radioactive substance at a radioactive concentration exceeding the lower limit of measurement can be effectively used for a paste-like composition or a crustal-like composition obtained by solidifying the paste-like composition.
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. Can be done. Further, since the crustal-like composition does not contain an organic substance, it is prevented that the organic substance is swelled or decomposed to generate gas or the like to be fragile.

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 composition of the crustal-like composition. It is a figure which shows the relationship between the shielding wall pressure, the radiation intensity, and the radioactivity concentration when the amount of radioactive substances is constant. (A) is a cross-sectional view of a crustal-like composition in which radioactive substances are 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 crustal-like composition which arranged the radioactive substance inside and made the inside satisfy a predetermined value. It is a cross-sectional view of a crustal-like composition in which radioactive substances are arranged inside so as to satisfy a predetermined value as a whole. It is sectional drawing of the crustal-like composition which made the layer containing a radioactive substance into a multi-layer structure. It is a cross-sectional view of a crustal-like composition provided with an outer layer, in which the density gradually decreases as the radioactive material goes outward. It is sectional drawing of the crustal-like composition that the density gradually becomes lower as a radioactive substance goes to the outside. It is a manufacturing process diagram of the composition containing the radioactive substance used for the crustal-like composition. It is a figure which shows the raw material process of the composition containing the radioactive substance used for the crustal-like composition. FIG. 12 is a continuation of FIG. 12 and is a diagram showing a firing process. FIG. 13 is a continuation of FIG. 13 and is a diagram showing a finishing process. It is a figure which shows the firing process of a contaminated material. It is a figure which shows the mixing process of a contaminated material and a low melting point substance. It is a figure which shows the treatment process of contaminated water. It is sectional drawing which shows the manufacturing method of the crustal-like composition in which a radioactive substance is uniformly dispersed. (A)-(E) is a method for producing a crustal-like composition in which a radioactive substance is arranged inside, and is a cross-sectional view showing an example in which production is started from the outer layer side. (A)-(E) is a method for producing a crustal-like composition in which a radioactive substance is arranged inside, and is a cross-sectional view showing another example in which production is started from the outer layer side. (A) and (B) are sectional views showing a molded body arranged inside a crustal-like composition. (A)-(C) is a method for producing a crustal-like composition in which a radioactive substance is arranged inside, and is a cross-sectional view showing an example in which production is started from the inside. (A) and (B) are methods for producing a crustal-like composition in which radioactive substances are arranged inside, and examples of installing an internal molded body on a temporary table in an outer formwork and starting production from the inside. It is sectional drawing which shows. (A) and (B) are methods for producing a crustal-like composition in which radioactive substances are arranged inside, and the internal molded body is suspended by a wire and installed in an outer formwork to start production from the inside. It is sectional drawing which shows an example. (A) and (B) are methods for producing a crustal-like composition in which a radioactive substance is arranged inside, and are cross-sectional views showing an example in which an inner molded body is settled in a paste-like composition poured into an outer formwork. Is. (A) is a bottom view of a hopper, and (B)-(E) is a method for producing a crustal-like composition in which a radioactive substance is arranged inside, and shows an example in which an outer layer and an inner layer are simultaneously produced. It is a sectional view. (A)-(E) is a cross-sectional view showing another example of a method for producing a crustal-like composition in which a radioactive substance is arranged inside, which does not use an inner formwork for simultaneously producing an outer layer and an inner layer. .. It is sectional drawing which shows the centrifugal separation apparatus, (A) shows the state before rotation, (B) shows the state after centrifugal force is applied. It is sectional drawing which shows the formwork pressurizing apparatus, (A) shows the state before pressurization, (B) shows the state after pressurization. It is sectional drawing which shows the modification of the form pressurizing apparatus, (A) shows the state before pressurization, (B) shows the state after pressurization. (A) and (B) are the figure which shows the processing process of the crushed aggregate, and (C) is a figure which shows the state which provided the covering layer in the crushed aggregate. It is a cross-sectional view of a general road. It is sectional drawing which shows the state which pavement is provided on the steep ground. It is a perspective view of a ballast track. It is a figure which shows the trans-sea crustal reduction method. (A)-(C) is a figure which shows the shape of the crustal-like composition used for the trans-sea crustal reduction method. It is a figure which shows the ship which carries the crustal-like composition. It is a figure which shows the catamaran which carries the crustal-like composition. It is a figure which shows the pontoon which carries a crustal-like composition. It is sectional drawing which shows the installation state of a caisson. It is sectional drawing of the crustal-like composition provided with the impermeable layer on the outside. It is a figure which shows the backfill process of a tunnel. It is a figure which shows the utilization method of the crustal-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, the crustal-like composition and the method for producing the crustal-like composition according to the present invention will be described with reference to the drawings. The description of the present invention will proceed in the following order.

1. 1. Radioactivity incapacity treatment system 2. Predetermined value of concentration (density) of radioactive material and radioactive material 3. Density distribution of radioactive materials 4. Composition of crustal-like composition 4-1. Example of uniform radioactive material 4-2. Example of arranging radioactive substances inside and satisfying the specified value inside 4-3. Example of arranging radioactive substances inside and satisfying the specified value as a whole 4-4. An example in which a layer containing radioactive substances has a multi-layer structure and satisfies a predetermined value as a whole 4-5. Example where the concentration (density) of radioactive substances decreases toward the outside. Method for Producing Crust-like Composition 5-1. Explanation of the entire manufacturing process 5-2. Explanation of pretreatment process 5-2-1. Explanation of firing treatment of contaminants 5-2-2. Explanation of chemical fixation (wrapping treatment) of radioactive substances 5-2-3. Explanation of pretreatment of contaminated water 5-3. Explanation of other processing 5-4. Explanation of molding method 5-4-1. Explanation of the method for producing a crustal-like composition having a uniform radioactive substance as a whole 5-4-2. Explanation of the method for producing a crustal-like composition in which radioactive substances are arranged inside (1) Example of starting from the outer layer (2) Example of starting from the inside (3) Example of starting at the same time 5-4-3. Explanation of the method for producing a crustal-like composition using centrifugal force 5-4-4. Explanation of the method for producing a crustal-like composition using pressure 5-5. Explanation of crushing process 5-6. Explanation of usage process 5-6-1. Explanation of transsea crust reduction method 5-6-2. Explanation of the method of reducing the crustal crust 5-6-3. Explanation of other usage

[1. About radioactivity incapacity treatment system]
As shown in FIG. 1, the present invention is the crustal-like composition 20 of the present invention in which the radioactive contaminants are incapacitated by the radioactive incapacitating treatment system 10 and the concentration of the radioactive substances is within the domestic and foreign standard values. To manufacture. More specifically, as shown in FIG. 2, the radioactive incapacitating treatment system 10 contains organic substances together with radioactive substances by, for example, incineration of debris, sludge, sand, sludge and the like containing radioactive contaminants. The crustal-like composition 20 in which the concentration of the radioactive substance is within the reference value is produced by, for example, simultaneously mixing and diluting the radioactive substance treated with the inorganic substance with other substances. The crustal-like composition 20 can shield the radioactive material from being released to the outside by fixing, confining, and containing the radioactive substance. That is, by using an inorganic substance having a radiation-attenuating property as a mixing material to be mixed for dilution, it is possible to effectively attenuate the radiation emitted from the radioactive substance, and this mixing material can be used. Furthermore, it is desirable that the solidification is physically and chemically stable to form a stable solid phase, which can trap radioactive substances for a long period of time and substantially incapacitate the radiation. It will be like.

In this way, the crustal-like composition 20 produced by the radioactive incapacitating treatment system 10 is obtained by physically confining and fixing the radioactive substance and / or by chemically confining and fixing the radioactive substance. It is possible to prevent the movement and elution of radioactive substances, and further, by making the radioactive substances ultra-low density, the absolute amount of radiation can be significantly reduced. Further, by shielding the radiation, the radiation level can be reduced, and further, by lowering the heat density, overheating can be prevented. If overheating is not prevented, the controllability of the water-hardening reaction, which is one reaction for obtaining a solid-phase crustal composition, deteriorates, and there is a fear that the solidified body becomes embrittled due to the excessive progress of the water-hardening reaction.

[2. Predetermined value of concentration (density) of radioactive material and radioactive material]
Here, the standard value of the concentration (density) of radioactive materials is the interim storage necessary for dealing with environmental pollution caused by radioactive materials due to the accident at the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company, dated October 29, 2011 by the Ministry of the Environment. According to the document "About the basic concept of facilities, etc.", it is 8,000 Bq / kg or less. Therefore, it is suitable and preferable to prepare the crustal structure so as to comply with this. In addition, this standard is also a legal standard value set legally. In addition, according to the document "Clearance system under the Reactor Regulation Law" of the Radioactive Waste Regulation Division of NISA, the following standards are used. Therefore, it is preferable to prepare a crustal composition so as to comply with this because it is also suitable under international rules. The predetermined value of the present invention is a value that satisfies this statutory standard value and / or clearance level.

Specifically, the clearance level is the ratio of the concentration (density) of the radionuclide to be evaluated contained in the object to the clearance level of the nuclide in order to consider the superposition when multiple radionuclides are present in the object. The standard is that the total 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 contaminants are typically fish and shellfish, vegetables, incinerator ash (derived from a garbage incinerator or a thermal power plant, etc.), sludge sludge, marine mud and river mud. , Lake sludge, street trees, debris (concrete, wood, glass, metal, plastic), contaminated water, earth and sand, etc. These pollutants can be classified as shown in Table 2 below.

[3. Density distribution of radioactive materials]
Here, the relationship between the density distribution of radioactive materials and the radiation intensity will be considered. Here, first, the radiation emitted by all the radioactive substances in the distribution system in which the radioactive substances are dispersed in the medium having the attenuation coefficient μ, which is uniquely determined by the substance, is one point on the surface of the medium (hereinafter, this point is 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 uniform and homogeneous, the distance (position) from the origin to a certain point in the medium is _xj , and the density distribution of the radioactive substances distributed in the medium is a one-dimensional density distribution function ρ. Let it be (x _j ). That is, ρ (x _j ) represents the density of radioactive material at the position x _j .

From this, the radiation intensity ΔI _0j at the position x _j emitted from the radioactive substance existing in the minute region Δx _j represented by the position x _j in the medium is expressed as ΔI _0j ∝ρ (x _j ) Δx _j . To. 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 as. Here, κ is a proportionality constant peculiar to radioactive substances and is a strength coefficient. If the effect of radiation emitted from the radioactive substance existing in this minute region Δx _j on the measurement point, that is, if the minute radiation intensity is ΔI _j , the minute radiation intensity ΔI _j is.

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

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

And from this,

Can be obtained.

The above is a consideration of the one-dimensional model, but when this is extended to the three-dimensional model, the three-dimensional density distribution function is extended 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 linear path in the medium from the position r to the measurement point emitted is given by the norm ∥r∥ of the position vector r. Therefore, the radiation intensity at the measurement point in the two-dimensional distribution system can be integrated with a minute volume dv over the entire region of the two-dimensional distribution system.

Here, for the sake of simplicity, the radiation intensities of each of the following four cases are obtained by giving specific radioactive material density distribution functions ρ (x) using a one-dimensional model.
(Case I ... Refer to the crustal-like composition 20a in FIG. 1)
ρ (x) = c: const
An example in which radioactive substances are uniformly dispersed as a whole.
(Case II ... Refer to the crustal-like composition 20b in FIG. 1)
ρ (x) = kx: k = proportionality constant An example in which the density of radioactive substances increases proportionally toward the center.
(Case III ... Refer to the crustal-like composition 20b in FIG. 1)
ρ (x) = sin (gx): g = constant of proportionality An example in which the density of radioactive substances increases toward the center, as in a sine curve.
(Case IV ... Refer to the crustal-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 present 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,

Satisfy.

(Case I ... Refer to the crustal-like composition 20a in FIG. 1)

Therefore, the above equation is

Will be. Here, if X is sufficiently large, c = N / X = const from the 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 the end point depends on the size and the total amount of radioactive substances, the properties of the medium, the types of radioactive substances contained in the medium, and the radioactivity. It shows that it is a constant value determined only by the concentration.

(Case II ... See Fig. 1 Mid-Crust-like Composition 20b)

By definition, k = 2N / X ² , so the radiation intensity _{II II} is

Will be. Here, if X is sufficiently large, the radiation intensity _{II II} will be

Will converge to. In other words, it is shown that when the distribution system exceeds a certain size, the radiation intensity _{II II} at the end point becomes constant regardless of the size and the total amount of radioactive substances. Furthermore, this result shows that the radiation intensity on the surface of the distribution system is lower in Case II than in Case I for the same size and the same total amount of substance.

(Case III ... See Fig. 1 Medium Crust-like Composition 20b)

To get. Here, it is assumed that the sine curve as the density distribution function ρ of the radioactive material forms a distribution for half a wavelength from the origin to X in the one-dimensional distribution system. That is, it is assumed that the abundance of radioactive substances is 0 at both ends, the amount is gradually increased toward the center of the distribution system, and the amount is distributed so as to be the largest amount at the center. Then, from this condition, g = π / X (π here is the pi). According to this, the radiation intensity I _III is

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

Converge on. Here, if μ and π / X are about the same, this convergence value is

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

Will be. In any case, if X is made 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 reciprocal of the magnitude X, the magnitude of X is set. It can be seen that the radiation intensity I _III decreases in inverse proportion to.

(Case IV ... See Fig. 1 Mid-Crust-like Composition 20c)

It is assumed that the measurement point is located at the end point of one of the radioactive substance 0 distribution regions. Then, if the radiation intensity from the c distribution area side at the boundary point between this 0 distribution region and the region of the uniform homogeneous distribution c adjacent to it is _{I'IV, the radiation intensity I IV is}

It is expressed as. Here, μ is the attenuation coefficient of the medium constituting the 0 distribution region. Radiation intensity _I'IV is given as an integral form for x between a and X-a. That is,

Will be. Since c = N / (X-2a) by definition, the radiation intensity _IIV is

It is expressed as. This indicates that no matter what size of X is set, it is a monotonous decrease with respect to a satisfying 0 <a <X / 2. In addition, the behavior of the radiation intensity _IIV with respect to the increase of X when X is sufficiently large with respect to a also becomes monotonously decreased. Therefore, in the limit of X at this time, the value of the radiation intensity _IIV converges to 0.

From this, in Case IV, it is shown that when the size X is fixed, the intensity of the radiation intensity I _IV can be reduced by increasing the size of the wall thickness a closer to X / 2. ing. However, if the wall thickness a is increased and the amount of radioactivity N is constant, the radioactivity concentration ρ becomes higher.

Since it is given by, the value of ρ increases endlessly as a approaches X / 2. That is, the radioactivity concentration cannot be kept below a predetermined value. Therefore, the surface radiation intensity is set to be below the clearance level or government standard value (also referred to as the legal standard value or predetermined value including the clearance level and government standard value) as described above while setting the density ρ of the c distribution region as necessary. Is preferably set to be less than or equal to the desired value, preferably less than or equal to the natural radiation level, and is a balance between minimizing the radiation intensity in the equation as much as possible and the legal standard that regulates the radioactivity concentration. It is preferable to take it.

For example, FIG. 4 plots the radiation intensity at the corresponding measurement point while continuously changing the thickness a (shielding wall thickness) of the 0 distribution region while keeping the total amount of radioactive substances contained in the distribution system constant. , This graph is overlaid with a graph that gradually increases the concentration by taking the radioactivity concentration that changes with the change of the thickness a of the 0 distribution region on the vertical second axis, and superimposes the wall thickness a, the radiation intensity, and the radiation. The relationship of the ability 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, monotonically 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 0 distribution region becomes thicker, the radioactivity concentration is initially slowly and gradually increased, and from a certain point, it is rapidly increased to an ultra-high concentration. I understand. Here, with respect to the concentration curve shown by line B, the legal standard concentration, which is an element that can change depending on the demands of the times and social conditions, is crossed by a line C parallel to the horizontal axis, and the vertical axis is from the intersection to the horizontal axis. A line D parallel to is drawn to obtain an intersection with the horizontal axis.

Then, the intersection with this horizontal axis is the thickness a _max of the maximum 0 distribution region capable of achieving the legal standard concentration, and is the thickness conforming to the legal standard concentration. Further, this line D is extended upward and intersects with the intensity curve shown by the line A, and a line E is drawn from the intersection point in parallel with the horizontal axis toward the vertical axis to obtain an intersection point with the vertical axis. Then, the intersection of the line E and the vertical axis becomes the radiation intensity corresponding to the legal standard concentration conforming thickness a _max , that is, the intensity corresponding to the legal standard concentration conforming thickness. The strength corresponding to the thickness conforming to the legal standard concentration is not always the minimum value or the minimum value in the strength curve, or the value near the minimum value, but rather it is higher than the minimum value and the thickness conforming to the legal standard concentration. The corresponding intensity does not always meet 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 above distribution system or increasing the size of the entire distribution system, the radioactivity concentration of the entire system is diluted and the surface radiation is applied. It is desirable to reduce the strength.

By the way, it is probably meaningful to consider what kind of distribution system can be constructed to minimize the radiation intensity emitted to the outside in order to safely and effectively perform the incapacity treatment. Therefore, in the following, it will be examined what kind of density distribution function ρ the radiation intensity emitted from the surface of the distribution system becomes below a certain value.

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

Let D ₀ be the depth to a certain depth point of 0 or more and D _max or less. At this time, for all Ds satisfying D ₀ <D,

Satisfying is preferable in terms of efficient distribution theory. This is because the thicker the medium, the more effective it is to attenuate the radiation intensity, and for comparison, it is possible to reduce the radiation intensity by distributing the high concentration on the deep side rather than distributing the high concentration on the front side. Is.

Here, we introduce an arbitrary function f (D) in which the limit of D _max is bounded upward in the integral value from 0 to D _max for D. in short,

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 _ID below a certain radiation intensity I _η (reference intensity). The condition to be satisfied is for all Ds.

Will be.

Therefore, when the density distribution satisfies the above condition, it is realized that the intensity of the 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 amount of radioactive substances while suppressing the surface radiation intensity to a constant value. Of course, in that case, note that the size of the distribution system is also infinite.

By the way, if the half-life of j kinds of radioactive substances (nuclides) R _j distributed in the distribution system and the abundance ratios of nuclides in the distribution system are τ _j and σ _j , respectively, then the total of all the radioactive substances R _j of the nuclides The half-life τ _ζ (not constant with respect to the elapsed time t) can be expressed by the following equation. That is,

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

Is. Using this, the total remaining amount N (t) of radioactive material after t hours can be calculated.

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

Will be expressed as.

[4. About the composition of the crustal-like composition]
[4-1. Example of overall uniformity]
The crustal-like composition 20 can be configured as shown in FIG. 5, according to the example of Case I above. That is, the crustal-like composition 20a shown in FIG. 5A is formed in a block shape, and the radioactive substance 19 is uniformly dispersed and solidified throughout. Here, the shape of the block-shaped object is not particularly limited. The crustal-like composition 20a is a solidifying binder obtained by adding a reaction rate adjusting material such as gypsum for adjusting the curing rate and / or the hydration reaction rate of the primary composition to the primary composition shown in Table 1 above. The block may be a tertiary composition obtained by further adding water to the next composition and kneading and solidifying the mixture, or further adding fine aggregate (sand) and appropriately adding water and kneading. It 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 kneaded and solidified by adding coarse aggregate (sand) as appropriate and adding water as appropriate. May be. In the case of these compositions, the primary composition may contain radioactive substances 19, contaminated water of radioactive substances 19 may be used as water, and radioactive substances may be used for fine aggregates and coarse aggregates. Although 19 may be contained, the concentration (density) of the radioactive substance 19 in the molded product as a finished product is adjusted to be equal to or less than the above-mentioned predetermined value. Here, the predetermined value means a standard value that is set by the society from time to time depending on the social situation, economic situation, radiological knowledge, radiobiology, radioecology, and radiation environmental knowledge. Currently, the radiation level is 8,000 Bq / kg or less in Japan, and the clearance level shown in Table 1 is adopted as the clearance system.

In addition, the crustal-like composition 20a is a molded product in which the radioactive substance 19 is kneaded with resin, tar, pitch, polyacrylonitrile heat-treated material, asphalt, etc., and the radioactive substance 19 is uniformly dispersed throughout. Is also good. Further, the radioactive material 19 chemically or physically coated may be uniformly dispersed in the finished block. Further, the radioactive substance 19 is preferably uniformly dispersed throughout, but may be a non-uniform substance in which a portion where the radioactive substance 19 is unevenly distributed is present. In this case, the density of the radioactive substance 19 may be higher than a predetermined value in the portion where the radioactive substance 19 is unevenly distributed, but it is preferable that the radioactive substance 19 is not exposed on the surface. Further, as shown in FIG. 5B, the crustal-like composition 20a may be provided with an outer layer 17, and the outer layer 17 may be a layer having a radiation concentration lower than a predetermined value, for example, a layer containing no radioactive substance 19. ..

In the crustal-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 submerged in the ocean. Further, the crustal-like composition 20a can be settled in the ocean as a paste-like crustal-like composition in a paste-like state. Further, it can be arranged in a tunnel and used as a floor and / or a wall and / or a ceiling of the tunnel. Furthermore, it can be used as a material for backfilling the tunnel. Further, the crustal-like composition 20a may be used as a crushed aggregate (crusher run) by crushing a block-shaped molded product. This crushed aggregate can also be used, for example, as a substitute material for roadbed materials and soft ground, soil materials, and ballast used for ballast tracks, which will be described in detail later.

[4-2. An example in which radioactive substances are placed inside and the inside meets the specified value]
Further, the crustal-like composition 20 can be configured as shown in FIGS. 6 and 7 according to the example of Case 4. Explaining from the example of FIG. 6, in this crustal-like composition 20c-1, the inner layer 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 inner 18. The concentration (density) is set, and the radioactivity concentration (density) of the internal 18 is set to a predetermined value or less. Specifically, the crustal-like composition 20c-1 is formed into a block shape, in which the radioactive substance 19 is arranged inside 18, and the outer layer 17 is a barrier layer containing no radioactive substance 19. Here, the predetermined value means a standard value that is set by the society from time to time depending on the social situation, economic situation, radiological knowledge, radiobiology, radioecology, and radiation environmental knowledge. Currently, the radiation level is 8,000 Bq / kg or less in Japan, and the clearance level shown in Table 1 is adopted as the clearance system. Further, the outer layer 17 may have at least the radioactivity concentration set to be at least the lower limit of measurement. The crustal-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 layer 18 is exposed, the above predetermined value is exceeded. It is possible to prevent the radiation from being adversely affected by the surrounding environment.

The crustal-like composition 20c-1 can be produced, for example, as follows, although details are omitted. For example, first, the inside 18 is kneaded by adding water as appropriate to the secondary composition which is 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) is added, water is appropriately added, and the mixture is kneaded and solidified to be produced as a quaternary composition. Further, a coarse aggregate (sand) is added, water is appropriately added, and the mixture is kneaded and solidified to be produced as a quintic composition. In these cases, the primary composition may contain radioactive substances 19, contaminated water containing radioactive substances 19 may be used as water, and radioactive substances 19 may be used for fine aggregates and coarse aggregates. However, the concentration (density) of the radioactive substance 19 inside 18 of the molded product as a finished product is adjusted to be equal to or less than the above-mentioned predetermined value.

The inner 18 containing the radioactive substance 19 produced as described above is placed in, for example, the central part of the mold, and around the inner 18, for example, a quaternary composition or a quintic kneaded with water containing no radioactive substance 19. It can be produced by pouring the composition and molding and solidifying it.

The crustal-like composition 20c-1 as described above can be used as a fish reef or a coastal marine structure, or can be submerged in the ocean. Further, it can be arranged in a mine shaft and can be used for a floor portion and / or a wall portion and / or a ceiling portion of the mine shaft. Further, the crustal-like composition 20c-1 is a block that does not exceed the above-mentioned predetermined value even when the outer layer 17 serving as the barrier layer is damaged due to aged deterioration or the like. Therefore, the crustal-like composition 20c-1 can be used as a crushed aggregate (crusher run) by crushing a block-shaped molded product in the same manner as the crustal-like composition 20a.

[4-3. Example of arranging radioactive substances inside and satisfying the specified value as a whole]
Further, the crustal-like composition 20 can be configured as shown in FIG. 7, according to the example of Case 4. In this crustal-like composition 20c-2, the inner layer 18 is set to a finite radioactivity concentration, the outer layer 17 is set to a radioactivity concentration (density) lower than the radioactivity concentration (density) of the inner layer 18, and the inner layer 18 is set to a lower radioactivity concentration (density). The radioactivity concentration (density) is set to be larger than the predetermined value. Specifically, the crustal-like composition 20c-2 is formed into a block shape, in which the radioactive substance 19 is arranged inside 18, and the outer layer 17 is a barrier layer containing no radioactive substance 19. The outer layer 17 may have at least the radioactivity concentration set to be at least the lower limit of measurement. Here, the density of the radioactive substance 19 in the inner 18 is set to be equal to or higher than the above-mentioned predetermined value, and the density of the radioactive substance 19 is set to be equal to or lower than the predetermined value in the whole including the inner 18 and the outer layer 17. In this crustal-like composition 20c-2, rubble or the like having a relatively high density of radioactive substances 19 above a predetermined value can be efficiently used as a raw material for the inner portion 18.

The crustal-like composition 20c-2 can be produced by the same production method as that of the crustal-like composition 20c-1 shown in FIG. The crustal-like composition 20c-2 as described above can be used as a fish reef or a coastal marine structure, or can be submerged in the ocean. Further, it can be arranged in a mine shaft and can be used for a floor portion and / or a wall portion and / or a ceiling portion of the mine shaft. Furthermore, it can be used as a material for backfilling the tunnel.

[4-4. An example in which a layer containing radioactive substances has a multi-layer structure and meets the specified values as a whole]
Further, the crustal-like composition 20 can be configured as shown in FIG. 8 with reference to the examples of cases 2 and 3 above. That is, in the crustal-like composition 20b-1 shown in FIG. 8, the inside 18 has a multi-layer structure. The inner 18 is a layer containing the radioactive substance 19, for example, the concentration (density) of the radioactive substance 19 in the central portion 18a is greater than or equal to or less than the above-mentioned predetermined value, and as it goes outward from the central portion 18a. The concentration (density) of the radioactive substance 19 in the intermediate layer 18b is configured to be gradually lowered. In this example, the number of intermediate layers 18b is not particularly limited. Here, the concentration (density) of the radioactive substance 19 may be proportionally lowered from the central portion 18a toward the outer layer 17, as in case 2 above, or may be distributed like a sine curve. The outer outer layer 17 of the intermediate layer 18b is a barrier layer that does not contain the radioactive substance 19. The outer layer 17 may also have at least the radioactivity concentration (density) set to be at least the lower limit of measurement.

The crustal-like composition 20b-1 can be produced by the same production method as the crustal-like compositions 20c-1 and 2 shown in FIGS. 6 and 7. That is, a multilayer structure can be obtained by forming the central portion 18a and then sequentially forming the inner intermediate layer 18b. In the crustal-like composition 20b-1 as described above, the molded product can be used as a fish reef or a coastal marine structure, or can be submerged in the ocean. Further, it can be arranged in a mine shaft and can be used for a floor portion and / or a wall portion and / or a ceiling portion of the mine shaft. Furthermore, it can be used as a material for backfilling the tunnel. Further, when the concentration (density) of the radioactive substance 19 in the central portion of the inner portion 18 having the highest density of the radioactive substance 19 is set to a predetermined value or less, the block-shaped molded product is crushed in the same manner as the crustal-like composition 20a. It can be used as a crushed aggregate (crusher run).

[4-5. An example in which the density gradually decreases as the radioactive material goes outward]
Further, the crustal-like composition 20 can be configured as shown in FIG. 9 with reference to the examples of cases 2 and 3 above. In the crustal-like composition 20b-2 shown in FIG. 9, the concentration (density) of the radioactive substance 19 in the central portion of the inner portion 18 is equal to or lower than the above-mentioned predetermined value, and is radioactive as it goes outward from the central portion. It is configured so that the density of the substance 19 gradually decreases. Here, the concentration (density) of the radioactive substance 19 may be proportionally lowered from the central portion 18 toward the outer layer 17, as in case 2 above, or may be distributed like a sine curve. The outer layer 17 on the outer side of the inner 18 is a barrier layer that does not contain the radioactive substance 19. The outer layer 17 may also have at least the radioactivity concentration (density) set to be at least the lower limit of measurement.

Although the details of the crustal-like composition 20b-2 will be described later, the radioactive substance 19 is adsorbed on a plurality of substances having a relatively low specific gravity, the paste-like composition is accommodated and rotated, and the central portion thereof is subjected to centrifugal force. It can be produced by distributing a substance having a low specific gravity including the radioactive substance 19 on the side and distributing a substance having a low density of the radioactive substance 19 on the outside. The outer layer 17 to be the barrier layer may be formed, for example, by molding the inner layer 18 and then using a formwork.

The crustal-like composition 20b-2 as described above can be used as a fish reef or a coastal marine structure, or can be submerged in the ocean. Further, it can be arranged in a tunnel and used as a floor material and / or a wall material of the tunnel. Further, when the density of the radioactive substance 19 in the central portion of the inner portion 18 having the highest density of the radioactive substance 19 is set to a predetermined value or less, the block-shaped molded product is crushed and crushed aggregate as in the crustal-like composition 20a. It can be used as a (crusher run).

As shown in FIG. 10, the crustal-like composition 20 does not have an outer layer 17 as a barrier layer in the outermost layer, and the density of the radioactive substance 19 gradually or gradually decreases from the central portion to the outside. Further, the crustal-like composition 20e having a predetermined value or less as a whole may be used.

[5. Method for producing crustal-like composition]
[5-1. Explanation of the entire manufacturing process]
The raw material containing the radioactive substance 19 used in the crustal-like composition 20 shown in FIG. 5-10 as described above is specifically produced through the steps shown in FIG. As shown in Table 2 above, radioactive contaminants include fish and shellfish, vegetables, incineration ash, sludge sludge, marine mud, river mud, lake mud, street trees, and debris (concrete, wood, glass, metal, plastic). ), Contaminated water, earth and sand, road surface materials, etc. In the pretreatment step 1001, for example, these contaminants are fired to mineralize the contaminants. The details of this pretreatment step 1001 will be described later.

In the raw material step 1002, as shown in FIG. 12, the calcium carbonate composition produced from fish and shellfish, animal carcasses, meat bones, animals and plants such as vegetables, etc., which became radioactive contaminants, became radioactive contaminants. Prescribed constituents centered on fine geological compositions such as incinerated ash, sludge sludge, and lake mud sand, siliceous compositions such as marine mud sand, river mud sand, and lake mud sand that have become radioactive contaminants, and iron oxide raw materials. A powder raw material with stable components is produced by crushing, drying, and mixing so as to become. For the fine-grained geological composition and silicic acid composition, incineration ash from a thermal power plant may be used, or debris (concrete, wood, glass, metal, plastic) that has become a radioactive contaminant may be used. 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 so as to be a water-hard compound. For example, after reaching the maximum temperature and completing a predetermined chemical reaction, the mixture 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 contaminated substance or a non-radioactive contaminated material may be used, but fuel raw materials such as waste plastic, waste oil, waste white clay, wood chips, meat-and-bone meal, and recycled oil are added to fire the powder raw material.

In the primary composition which is this solid phase composition, the concentration (density) of the radioactive substance is adjusted in advance for each of the calcium carbonate composition, the fine geological composition, the silicic acid composition, the iron oxide raw material, and the fuel raw material. The concentration (density) of the radioactive substance as a whole can be adjusted to a predetermined value or less or more by using the above-mentioned material. The primary composition, which is a solid phase composition, uses a radioactive contaminant as one or more of a calcium carbonate composition, a fine-grained geological composition, a siliceous composition, an iron oxide raw material, and a fuel raw material. The concentration (density) of the radioactive substance can be set to a predetermined value equal to or higher than the above-mentioned predetermined value by adjusting the amount of the non-radioactive contaminated material. In addition, these primary compositions may be those which do not contain radioactive substances.

Further, in the finishing step 1004, as shown in FIG. 14, for adjusting the curing rate and / or the hydration reaction rate of the primary composition, which is the solid phase composition obtained in the firing step, to the primary composition. Reaction rate modifiers such as gypsum are added, which are ground to a fine powder, which completes the secondary composition which is the solidifying binder. By using the above-mentioned primary composition as the secondary composition as the solidifying binder, the concentration (density) of the radioactive substance as a whole can be adjusted to a predetermined value of a predetermined value or more. ..

The secondary composition serving as the solidifying binder is kneaded with an appropriate amount of water to become a paste-like composition or a tertiary composition which is a solid phase product. This tertiary composition is hydrated and / or polymerized and solidified by kneading with water. The water used here may be fresh water such as tap water, river water, lake water, etc., as well as water other than fresh water such as seawater, contaminated water which is a radioactive contaminant, or non-fresh water. It may be water as a radioactively contaminated material. In particular, when seawater is used and the treatment is performed by transsea crustal reduction, it is preferable that the osmotic pressure between the crustal composition and the seawater in contact with the transsea can be adjusted in advance. In the tertiary composition, the concentration (density) of the radioactive substance as a whole can be adjusted to a predetermined value or less or a predetermined value depending on what kind of water is used. In such a tertiary composition, the concentration (density) of the radioactive substance as a whole is set to a predetermined value or more in the state of the paste-like composition or the state of the cured crustal-like composition.

Further, the secondary composition to be a solidifying binder becomes a paste-like composition or a quaternary composition which is a solidified product thereof by adding a fine aggregate (sand) and kneading with an appropriate amount of water. .. The quaternary composition is hydrated and / or polymerized and solidified by kneading with water. The water used here may be seawater, contaminated water which is a radioactive contaminant, or water which is a non-radioactive contaminated material, in addition to fresh water. In particular, when seawater is used and transsea crustal reduction is performed, it is preferable that the osmotic pressure between the crustal composition and the seawater in contact with the transsea can be adjusted 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 a non-radioactive pollutant material may be used. In the quaternary composition, the concentration (density) of the radioactive substance as a whole can be adjusted to a predetermined value of a predetermined value or more, depending on what kind of water or fine aggregate (sand) is used. In such a quaternary composition, in the state of a paste-like composition or the state of a cured crustal-like composition, the concentration (density) of the radioactive substance as a whole is set to a predetermined value of a predetermined value or more. ..

Further, the secondary composition serving as a solidifying binder is a quintic composition which is a paste-like composition by adding fine aggregate (sand) and coarse aggregate (gravel) and kneading with an appropriate amount of water. Will be. This quintic composition is hydrated and / or polymerized and solidified by kneading with water. The water used here may be seawater, contaminated water which is a radioactive contaminant, or water which is a non-radioactive contaminated material, in addition to fresh water. There may be. In particular, when seawater is used and transsea crustal reduction is performed, it is preferable that the osmotic pressure between the crustal composition and the seawater in contact with the transsea can be adjusted 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 a non-radioactive pollutant material may be used. In the quaternary composition, the concentration (density) of the radioactive substance as a whole can be adjusted to a predetermined value of a predetermined value or more, depending on what kind of water or fine aggregate (sand) is used. In such a quintic composition, in the state of a paste-like composition or the state of a cured crustal-like composition, the concentration (density) of the radioactive substance as a whole is set to a predetermined value of a predetermined value or more. ..

The tertiary composition, the quaternary composition, and the quintic composition as described above are molded into a block shape by pouring the paste-like composition into a mold, which will be described later, in the molding step 1005. In the utilization step 1007, the tertiary composition, the quaternary composition, and the quintic composition formed into the block shape have the configuration as shown in FIGS. 5 to 10 above, and the molded product is used as a fish reef or a coastal ocean. It can be used as a structure or can be submerged in the ocean. In addition, the tertiary composition, quaternary composition, and quintic composition should be settled in the ocean as a paste-like crustal-like composition in a paste-like state when the concentration (density) of the radioactive substance is equal to or less than a predetermined value. Can be done. Further, the molded crustal-like composition 20 can be placed in the tunnel and can be used for the floor and / or the wall and / or the ceiling of the tunnel. Further, even the paste-like crustal-like composition can be poured or sprayed on the floor portion and / or the wall portion and / or the ceiling portion. Further, it can be used as a material for backfilling floors and / or walls and / or ceilings or tunnels. Further, the crustal-like composition 20 may be used as a crushed aggregate (crusher run) by crushing a block-shaped molded product in the crushing treatment step 1006 when the concentration (density) of the radioactive substance is equal to or less than a predetermined value. This crushed aggregate can be used in the utilization step 1007, for example, as a substitute material for roadbed materials and soft ground, earth materials, and ballast used for ballast tracks, which will be described in detail later.

[5-2. Explanation of pretreatment process]
[5-2-1. Explanation of firing treatment of contaminants]
As shown in Table 2 above, the radioactive contaminants are fish and shellfish, vegetables, incineration ash, sludge sludge, marine mud, river mud, lake mud, street trees, and debris (concrete, wood, glass, metal, plastic). , Contaminated water, earth and sand, road surface materials, etc. As the radioactive contaminants used here, the radioactive concentration (density) may be the lower limit of measurement, but a contaminant containing radioactive substances at the radioactive concentration (density) exceeding the lower limit of measurement can also be used. .. When an organic substance is contained in such a contaminant, after the crustal-like composition 20 is formed, the organic substance swells, decomposes, or generates gas with the lapse of time, and the crustal-like composition 20 becomes. There is a risk of becoming vulnerable. Therefore, in the pretreatment step 1001, as shown in FIG. 15, before the contaminated material is used as a raw material for the crustal-like composition 20, the contaminated material is fired. The firing temperature here is set to be lower than the vaporization temperature of the radioactive substance, and the radioactive substance and the ash content remain as a residue so that the radioactive substance is not vaporized and released into the atmosphere. In this way, the contaminated material can be vaporized or mineralized as an organic substance by being calcined.

Table 3 above 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 set to less than 671 ° C., it is possible to prevent most of the radioactive substances from being vaporized. When the contaminated material is fired in a closed space, the organic substance can be changed into a gas such as carbon dioxide gas and an inorganic substance such as water or ash by supplying oxygen.

The calcined contaminated material and incinerated ash obtained by the calcining treatment of the contaminated material as described above are put into a raw material crusher together with a calcium carbonate composition, a silicic acid composition, an iron oxide composition and the like in, for example, in the raw material step 1002. Then, the crushed raw material may be obtained. Further, the fired contaminated material and the incinerated ash can be used as an additive when the tertiary composition, the quaternary composition or the quaternary composition is kneaded with water or contaminated water to form a paste-like composition, and the curing rate and / or water. It may be mixed with a reaction rate adjusting material for adjusting the sum reaction rate, fine aggregate or coarse aggregate. By adding the calcined contaminants and incinerator ash in this way, the concentration (density) of the radioactive substance 19 as a whole of the crustal-like composition 20 can be adjusted.

[5-2-2. Explanation of chemical fixation (wrapping treatment) of radioactive substances]
Further, as shown in FIG. 16, radioactive contaminants such as mud, soil, sand, debris, incinerated ash, and sludge containing radioactive substances 19 exceeding the lower limit of measurement are chemically stable as shown in FIG. Is preferable. Therefore, the contaminated material is dissolved or mixed with a low melting point substance that melts at a temperature lower than the boiling point of the radioactive substance 19 after being crushed and / or fired and / or dried, and solidified and solidified. It is good to crush the body into crushed aggregate. The paste-like melting point substance mixed with the contaminant is preferably kneaded so that the contaminant is uniformly dispersed in the low melting point substance. This crushed aggregate is mixed with the secondary composition as a fine aggregate or a coarse aggregate in the finishing step 1004, for example, when producing a quaternary composition or a quintic composition which is a paste-like composition. Can be done. Further, it can be mixed with the above-mentioned calcining contaminants and incinerator ash. By adding the crushed aggregate in this way, the concentration (density) of the radioactive substance 19 as a whole of the crustal-like composition 20 can be adjusted. The solidified body solidified by this wrapping treatment can then be treated as an incapacitating composition without being crushed, but in the case of the composition at this stage, chemical stability can be obtained. , There is a risk that the shielding property that attenuates radiation will be insufficient.

As the low melting point substance, for example, low melting point glass having a boiling point lower than the boiling point 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 the main components, are arranged in a network through oxygen, and the radioactive substance 19 in the vitrified body. Can be uniformly and stably incorporated into the network structure. By crushing the vitrified body in which the radioactive substance 19 is incorporated in this way, it can be made into a crushed aggregate.

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 radioactive substance 19 can be used as an aggregate, mixed with tar, pitch, polyacrylonitrile, asphalt, etc., and pulverized to produce a crushed aggregate. Even in such a crushed aggregate, as described above, when producing a quaternary composition or a quaternary composition which is a paste-like composition, a secondary composition is used as a fine aggregate or a coarse aggregate. Can be mixed with. Of course, this crushed aggregate may be used as a road paving material as a mixture with asphalt or the like.

[5-2-3. Explanation of pretreatment of pollutants]
Contaminants containing radioactive material 19 include contaminated water contaminated with radioactive material 19. The contaminated water containing a radioactive substance is mixed with a supporting material that carries the radioactive substance to support the radioactive substance on the supporting material, and this is used as a contaminant as a raw material for the crustal-like composition 20 for treatment. Can be done. That is, as shown in FIG. 17, the carrier material and the contaminated water contaminated with the radioactive substance 19 are mixed in the container.

Examples of the supporting material used here include fine-grained soil having a layered structure having properties such as adsorptivity, cohesiveness and coagulability such as vermiculite, bentonite and asbestos, alkali metals such as cesium, and alkaline soil such as strontium. Includes substances having compounding properties that react with cationic substances such as similar metals to form stable solid compounds.

The inventor of the present invention has obtained the finding that most of cesium is found in fine-grained sand and ultra-fine-grained sand of 0.075 mm or less in the classification by Wentworth particle size classification by classifying the components of the topsoil. The carrier used here adsorbs cesium on fine-grained soil having a layered structure having a particle size of 0.075 mm or less. When the fine-grained soil having a layered structure and the contaminated water are mixed, the pollutant-carrying material adsorbing and holding the radioactive substance 19 forms a paste. This pasty-like contaminant supporting material is used in the finishing step 1004 when the tertiary composition, the quaternary composition, or the fifth-order composition, which is the paste-like composition, is produced. It can be mixed with materials, fine aggregates, coarse aggregates, and the like. Of course, the paste may not be used as it is, but may be dried into a powder.

Further, a porous material can be used instead of the fine-grained soil having a layered structure. For example, as a porous material, there is Shirasu Porous Glass. Since the pore size of Shirasu porous glass can be freely controlled in the range of 1 nm to 50 μm by adjusting the heat treatment conditions, the pore size can be 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 with the primary to quintic compositions and used as a primary contaminant, and the filtered water can also be used as a paste-like composition in the finishing step 1004, such as a tertiary composition or a quaternary composition. It can be used in the production of compositions and quintic compositions. That is, it is possible to determine and mix the amount of the supporting material mixed according to the contaminated concentration of the contaminated water, and use the filtered water and the contaminated supporting material as a raw material of the crustal composition in a mixed state without separation. You can. The porous material may be an amorphous carbon material.

[5-3. Explanation of other processing]
When a tertiary composition, a quaternary composition or a quaternary composition is kneaded with water or contaminated water to form a paste-like composition, a high-density substance having low reactivity is added as an additive to shield the radioactivity. Can be improved. Examples of high-density substances include barium and lead glass pieces. As shown in FIGS. 6 to 10, these high-density substances can be particularly distributed in the outer layer 17 of the crustal-like composition 20 to enhance the barrier performance. Further, when treating a contaminant-carrying material or contaminated soil in which a radioactive substance is carried on the above-mentioned supporting material, these contaminants have a lower specific density than an additive having a high specific density, and therefore, for example, will be described later. When molding using centrifugal force, a large amount of high-density substances are distributed on the outside, contaminants are distributed on the inside, and radioactive substances are not distributed on the outside, so the barrier performance of the outer layer 17 Can be enhanced.

Further, when the tertiary composition, the quaternary composition or the quaternary 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 are used. By adding the metal fiber as an additive, the physical strength of the crustal-like composition 20 can be increased.

Further, when the tertiary composition, the quaternary composition or the quaternary composition is kneaded with water or contaminated water to form a paste-like composition, an inexpensive and basic substance such as soda glass is crushed and added. May be. Further, glass fiber may be added. This makes it possible to prevent the neutralization of the crustal-like composition 20.

Further, when the tertiary composition, the quaternary composition or the quintic composition is kneaded with water or contaminated water to form a paste-like composition, titanium oxide may be added. Titanium oxide has high hydrophilicity, enhances the water retention effect, and can prevent deterioration due to lack of water during a water-hard reaction.

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

[5-4-1. Explanation of the method for producing a crustal-like composition in which radioactive substances are uniformly uniform]
The crustal-like composition 20a shown in FIG. 5 is formed into a block shape in which the radioactive substance 19 is uniformly dispersed and solidified throughout. As shown in FIG. 18, in order to form the crustal-like composition 20a, first, a tertiary composition or a fourth is applied to an outer formwork 101 having a predetermined shape made of a material such as steel, wood, resin, or glass. The next composition or the fifth composition is kneaded with water or contaminated water, the paste-like composition 102 is driven in, compaction is performed 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. Further, in the paste-like composition 102, the concentration (density) of the radioactive substance is set to a predetermined value of a predetermined value or less. Thus, the crustal-like composition 20a is formed as a block in which the concentration (density) of the radioactive substance as a whole is set to a value of a predetermined value or less.

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

[5-4-2. Explanation of the method for producing a crustal-like composition with radioactive substances inside]
The crustal-like composition 20c-1 shown in FIG. 6 is formed into a block shape, a radioactive substance 19 is arranged inside 18, and the outer layer 17 is set to have a radioactivity concentration below the lower limit of measurement or relatively low. The barrier layer is formed so that the concentration (density) of the radioactive substance 19 inside 18 is equal to or less than the above-mentioned predetermined value. In the example here, the outer layer 17 is prevented from containing the radioactive substance 19. Further, the crustal-like composition 20c-2 shown in FIG. 7 is formed into a block shape, and the radioactive substance 19 is arranged in the inner layer 18, and the outer layer 17 is a barrier layer containing no radioactive substance 19 and is referred to as the inner layer 18. The concentration (density) of the radioactive substance 19 as a whole including the outer layer 17 is larger than the above-mentioned predetermined value. The crustal-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7 may be molded from the outer layer 17 or from the inner layer 18, and methods for producing these will be described next.

(1) Example of starting from the outer layer The crustal-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7 can be manufactured by the procedure shown in FIG. 19 when molding from the outer layer 17 side. .. Specifically, as shown in FIG. 19A, first, an inner 18 including a radioactive substance 19 is further formed on an outer form 111 having a predetermined shape made of a material such as steel, wood, resin, or glass. The inner formwork 112 is supported and arranged at a position on the bottom surface of the outer formwork 111 at a predetermined interval by a mounting portion (not shown). Further, the height of the opening surface of the inner formwork 112 is set lower than that of the opening surface of the outer formwork 111 so that the paste-like composition 113 of the non-radioactive substance can be driven onto the inner part 18. ..

For example, when the inner 18 is provided in the center of the block, the inner form 112 is arranged in the center of the outer form 111. That is, in FIG. 19A, the inner formwork 112 has a distance a1 between the side wall of the outer formwork 111 and the side wall of the inner formwork 112 and a distance a2 between the bottom surface of the outer formwork 111 and the bottom surface of the inner formwork 112. Is arranged in the outer mold 111 so that the distance a3 between the opening surface of the outer mold 111 and the opening surface of the inner mold 112 is equal to each other. Then, the paste-like composition 113, which is a non-radioactive substance such as mortar or concrete, is driven into the space between the outer formwork 111 and the inner formwork 112 up to the height of the opening surface of the inner formwork 112. The paste-like composition 113 may be made of resin, tar, pitch, polyacrylonitrile heat-treated material, asphalt, or the like. Further, here, compaction may be performed with a vibrator or the like.

Next, as shown in FIG. 19B, the tertiary composition, the quaternary composition, and the quintic composition are kneaded with water or contaminated water into the inner mold 112, and the paste-like composition 114 is driven into the inner mold 112. Here, in the paste-like composition 114, when the crustal-like composition 20c-1 in which the density of the radioactive substance 19 in the inner portion 18 shown in FIG. 6 is formed is formed into a predetermined value or less, the density of the radioactive substance 19 is adjusted to the predetermined value or less. The paste is used. Further, when the crustal-like composition 20c-2 in which the density of the radioactive substance 19 in the inner 18 shown in FIG. 7 is larger than the predetermined value is formed, the density of the radioactive substance 19 is larger than the predetermined value, and the outer layer 17 and the inner 18 are preferable. The radioactivity level for the total mass of, that is, the radioactivity concentration adjusted to meet the reference value is used. Then, the paste-like composition 114 is driven up to the opening surface of the inner mold 112. Also here, the paste-like composition 114 in the inner mold 112 may be compacted.

Next, as shown in FIG. 19C, the paste-like composition 113 of the non-radioactive substance was poured 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. Is done. Also here, the paste-like composition 114 in the inner mold 112 may be compacted. Thus, in the crustal-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7, the concentration (density) of the radioactive substance inside 18 is set to a predetermined value or less or a large value, and the concentration of the radioactive substance as a whole ( It is molded as a block whose density) is less than or equal to a predetermined value. The outer formwork 111 may be left instead of being removed and used as a protective layer of the crustal-like compositions 20c-1 and 20c-2 or a barrier layer against radiation.

As shown in FIGS. 19A and 19D, the paste-like composition 113 of the non-radioactive substance was poured into the outer mold 111 and solidified in a pre-shaped state, and then the inner mold 112 was 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 form 112. After that, as shown in FIG. 19E, the paste-like composition 113 of the non-radioactive substance is driven into the entire surface including the upper side of the paste-like composition 114 poured into the recess 115 up to the opening surface of the outer mold 111. Is done. As a result, the interface between the outer layer 17 and the inner layer 18 comes into 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. 19 (E). The physical strength of the interface can be increased as compared with the case where there is a separator such as a formwork.

Further, the crustal-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7 can be manufactured by the procedure shown in FIG. 20 when molding from the outer layer 17 side. Specifically, as shown in FIG. 20A, the outer mold 111 further has 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. It is supported and arranged by a mounting portion (not shown) at the position of. The inner formwork 112a is set so that the height of the opening surface is aligned with the opening surface of the outer formwork 111.

For example, when the inner 18 is provided in the center of the block, the inner formwork 112a has the distance a1 between the side wall of the outer formwork 111 and the side wall of the inner formwork 112a and the bottom surface of the outer formwork 111 in FIG. 20A. It is arranged in the outer formwork 111 so that the distance a2 between the inner formwork 112a and the bottom surface of the inner formwork 112a is equal to each other. Then, the paste-like composition 113, which is a non-radioactive substance such as mortar or concrete, is driven into the space between the outer mold 111 and the inner mold 112 up 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. Further, here, compaction may be performed with a vibrator or the like.

Next, as shown in FIG. 20 (B), the tertiary composition, the quaternary composition, and the quintic composition are kneaded with water or contaminated water into the inner mold 112, and the paste-like composition 114 is driven into the inner mold 112. Here, in the paste-like composition 114, when the crustal-like composition 20c-1 in which the density of the radioactive substance 19 in the inner portion 18 shown in FIG. 6 is formed is formed into a predetermined value or less, the density of the radioactive substance 19 is adjusted to the predetermined value or less. The paste is used. Further, when the crustal-like composition 20c-2 in which the density of the radioactive substance 19 in the inner 18 shown in FIG. 7 is larger than the predetermined value is formed, the density of the radioactive substance 19 is larger than the predetermined value, and the outer layer 17 and the inner 18 are preferable. The radioactivity level for the total mass of, that is, the radioactivity concentration adjusted to meet the reference 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 distance a1 and a2, the opening surface of the outer mold 111 and the inner mold 112a, and the distance a3 between the upper surface of the paste-like composition 114 are equal to each other. Is done. Also here, the paste-like composition 114 in the inner mold 112 may be compacted.

Next, as shown in FIG. 20 (C), the paste-like composition 113 of the non-radioactive substance is poured onto the upper side of the paste-like composition 114 poured into the inner mold 112 up to the opening surface of the inner mold 112. Also here, the paste-like 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 paste-like composition 113 of the non-radioactive substance. In such crustal-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7, the concentration (density) of the radioactive substance inside 18 is set to a predetermined value or less or a large value, and the concentration of the radioactive substance as a whole is set. It is molded as a block having a (density) of a predetermined value or less. The outer formwork 111 may be left instead of being removed and used as a protective layer of the crustal-like compositions 20c-1 and 20c-2 or a barrier layer against radiation.

As shown in FIGS. 20A and 20D, the paste-like composition 113 of the non-radioactive substance was poured into the outer mold 111 and solidified in a pre-shaped state, and then the inner mold 112 was 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 form 112. After that, as shown in FIG. 20 (E), the paste-like composition 113 of the non-radioactive substance is driven into the upper side of the paste-like composition 114 poured into the recess 115 up to the opening surface of the outer mold 111. As a result, the interface between the outer layer 17 and the inner layer 18 comes into 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. 20 (E). The physical strength of the interface can be increased as compared with the case where there is a separator such as a formwork.

It should be noted that the crustal-like composition 20b-1 having a multi-layer 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 to the outside as shown in FIG. At that time, the inner mold 112 according to the number of layers may be arranged in the outer mold 111, and the paste-like composition may be poured into the inner mold 112 in the air order on the center side to form the inner mold 112.

(2) Example of starting from the inside The crustal-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7 can be manufactured by the procedure shown in FIG. 21 when molding from the inside 18 side. In this case, first, as shown in FIG. 21 (A), a paste containing the radioactive substance 19 obtained by kneading the tertiary composition, the quaternary composition or the quaternary composition with water or contaminated water with respect to the inner mold 112a. This is driven as the composition 114, compacted with a vibrator or the like, and molded. In the paste-like composition 114, when the crustal-like composition 20c-1 in which the density of the radioactive substance 19 in the inner portion 18 shown in FIG. 6 is formed into a predetermined value or less, the density of the radioactive substance 19 is adjusted to the predetermined value or less. Is used. Further, when the crustal-like composition 20c-2 in which the density of the radioactive substance 19 in the inner 18 shown in FIG. 7 is larger than the predetermined value is formed, the density of the radioactive substance 19 is larger than the predetermined value, and the outer layer 17 and the inner 18 are preferable. The radioactivity level for the total mass of, that is, the radioactivity concentration adjusted to meet the reference value is used. Then, the inner molded body 18c with the inner mold 112a shown in FIG. 21 (A) and the inner molded body 18d from which the inner mold 112a shown in FIG. 21 (B) is removed as the internal composition are next to the outer mold. It will be installed in the frame 111. In the inner molded body 18c with the inner mold 112a, the inner mold 112a can function as a protective layer of the inner 18 or a barrier layer against radiation. Further, the inner molded body 18d from which the inner mold 112a is removed can increase the physical strength with the paste-like composition 113 of the non-radioactive substance. In the following example, the internal molded body 18c from which the inner mold 112a has been removed will be described as an example.

Specifically, as shown in FIG. 22 (A), the paste-like composition 113, which is a non-radioactive substance such as mortar or 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, the paste-like composition 113 is provided with the internal molded product 18d. In the paste-like composition 113, the internal molded body 18d is installed after the internal molded body 18d is solidified to such an extent that it does not settle in the paste-like composition 113. At this time, the inner 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 inner molded body 18d is the same. After that, as shown in FIG. 22C, the paste-like composition 113, which is a non-radioactive substance, is poured into the outer mold 111 up to the opening surface. At this time, the inner molded body 18d has a distance a2 between the bottom surface of the outer mold 111 and the bottom surface of the inner molded body 18d, the opening surface of the outer mold 111, and the upper surface of the inner molded body 18d in the outer mold 111. The interval a3 is set to be equal to each other. That is, the internal molded body 18d is arranged at a position in the outer mold 111 where a1 = a2 = a3. Thus, in the crustal-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7, the concentration (density) of the radioactive substance inside 18 is set to a predetermined value or less or a large value, and the concentration of the radioactive substance as a whole ( It is molded as a block whose density) is less than or equal to a predetermined value. The outer formwork 111 may be left instead of being removed and used as a protective layer of the crustal-like compositions 20c-1 and 20c-2 or a barrier layer against radiation. Further, the paste-like composition 113 may be a resin, tar, pitch, polyacrylonitrile, asphalt or the like. Further, here, compaction may be performed with a vibrator or the like.

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

Thus, in the crustal-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7, the concentration (density) of the radioactive substance inside 18 is set to a predetermined value or less or a large value, and the concentration of the radioactive substance as a whole ( It is molded as a block whose density) is less than or equal to a predetermined value. In such a molding method, except for the portion of the temporary table 111a, the paste-like compositions 113 and 114 are in direct contact with each other, and the physical altitude at the interface is increased as compared with the case where there is a separator such as a mold. Can be done. The outer formwork 111 may be left instead of being removed and used as a protective layer of the crustal-like compositions 20c-1 and 20c-2 or a barrier layer against radiation. Further, the paste-like composition 113 may be a resin, tar, pitch, polyacrylonitrile, asphalt or the like. Further, here, compaction may be performed with a vibrator or the like.

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

Thus, in the crustal-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7, the concentration (density) of the radioactive substance inside 18 is set to a value equal to or higher than a predetermined value, and the concentration of the radioactive substance as a whole is set to a value equal to or higher than a predetermined value. It is molded as a block having a (density) of a predetermined value or less. In such a molding method, it is not necessary to install the temporary base 111a on the outer mold 111, and the manufacturing process can be simplified. In addition, the paste-like compositions 113 and 114 are in direct contact with each other, and the physical altitude at the interface can be increased as compared with the case where there is a separator such as a mold. The outer formwork 111 may be left instead of being removed and used as a protective layer of the crustal-like compositions 20c-1 and 20c-2 or a barrier layer against radiation. Further, the paste-like composition 113 may be a resin, tar, pitch, polyacrylonitrile, asphalt or the like. Further, here, compaction may be performed with a vibrator or the like.

Further, as shown in FIGS. 25 (A) and 25 (B), the paste-like composition 113 which is a non-radioactive substance is poured into the outer mold 111 up to the opening surface of the outer mold 111, and then the paste-like composition 113 is formed. Before solidification and when the hardness is appropriate, the internal molded body 18d may be submerged and positioned at a substantially central portion in the outer mold 111.

The crustal-like composition 20b-1 as shown in FIG. 8, in which the density of the radioactive substance 19 in the intermediate layer 18b gradually decreases toward the outside from the central portion 18a, is a radioactive substance on the surface of the internal molded body 18d. It can be formed by providing an intermediate layer 18b having a low concentration (density) of 19 and repeating this, and finally providing an outer layer 17 containing no radioactive substance 19.

(3) Example of starting at the same time Further, in the crustal-like compositions 20c-1 and 20c-2 shown in FIGS. 6 and 7, the inner layer 18 and the outer layer 17 can be manufactured at the same time. In this case, as shown in FIGS. 26A and 26B, the discharge port 113a for discharging the paste-like composition 113 of the non-radioactive substance and the discharge port 114a for discharging the paste-like composition 114 containing the radioactive substance 19 are discharged. A hopper 118 equipped with and is used. Of course, the discharge port 113a here is supposed to discharge the paste-like composition 113 of the non-radioactive substance, but it does not necessarily have to be the paste-like composition of the non-radioactive substance. The discharge port 114a for discharging the paste-like composition 114 containing the radioactive substance 19 is provided in the central portion and forms the inside 18, and the discharge port 113a for discharging the paste-like composition 113 of the non-radioactive substance is a discharge port. A plurality of them are provided around 114a to form an outer layer 17. An inner formwork 112 for forming the inner portion 18 is located below the discharge port 114a, and a region between the outer formwork 111 and the inner formwork 112 is located below the discharge port 113a.

Further, the paste-like composition 114 containing the radioactive substance 19 discharged from the discharge port 114a is used to form the crustal-like composition 20c-1 in which the density of the radioactive substance 19 inside 18 shown in FIG. 6 is equal to or less than a predetermined value. , The radioactive substance 19 whose density is adjusted to a predetermined value or less is used. Further, when the crustal-like composition 20c-2 in which the density of the radioactive substance 19 in the inner 18 shown in FIG. 7 is larger than the predetermined value is formed, the density of the radioactive substance 19 is larger than the predetermined value, and the outer layer 17 and the inner 18 are preferable. The radioactivity level for the total mass of, that is, the radioactivity concentration adjusted to meet the reference value is used.

As shown in FIG. 26C, first, the paste-like composition 113 of a non-radioactive substance is poured into the outer mold 111 from the discharge port 113a. Next, as shown in FIG. 26 (D), the paste-like composition 114 containing the radioactive substance 19 was poured into the inner mold 112 from the discharge port 114a, and as shown in FIG. 26 (E), the inner mold was formed. The paste-like composition 114 is poured up to the height of the opening surface of the frame 112. Then, the discharge from the discharge port 114a is stopped, and the paste-like composition 113 of the non-radioactive substance is poured from the discharge port 113a to the height of the opening surface of the outer mold 111. The flow velocity and flow rate of the paste-like composition 114 containing the non-radioactive substance paste-like composition 113 discharged from the discharge port 113a and the radioactive substance 19 discharged from the discharge port 114a are such that the inner mold 112 determines 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 filled with. 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 side. According to such a molding method, 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, so that the production efficiency can be improved. You can.

Further, when the paste-like composition 113 of the non-radioactive substance discharged from the discharge port 113a and the paste-like composition 114 containing the radioactive substance 19 discharged from the discharge port 114a are simultaneously poured, the inner mold 112 is not used. Is also good. That is, as shown in FIG. 27 (A), the inner form 112 is not installed in the outer form 111. In this state, the paste-like composition 113 of the non-radioactive substance is poured from the discharge port 113a to the first height. Next, as shown in FIG. 27 (B), the paste-like composition 114 containing the radioactive substance 19 is also poured from the discharge port 114a. Then, as shown in FIG. 27 (C), 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 poured on the outside thereof. The state composition 113 is poured. FIG. 27 (E) is made by aligning the way of raising the water surface of the paste-like composition 113 of the non-radioactive substance from the discharge port 113a and the way of raising the water surface of the paste-like composition 114 containing the radioactive substance 19 from the discharge port 114a. As shown in the above, the paste-like composition 114 can be distributed inside the outer paste-like composition 113. Then, when the height reaches a predetermined height, 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 pasted on the paste-like composition 114. The state composition 113 can be distributed. Then, the paste-like composition 113 is poured up to the opening surface of the outer mold 111.

According to such a molding method, 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, so that the production efficiency can be improved. You can. Further, since the inner form 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 will be disturbed. Therefore, it is preferable not to make these properties too different.

The crustal-like composition 20b-1 as shown in FIG. 8 in which the density of the radioactive substance 19 in the intermediate layer 18b gradually decreases toward the outside from the central portion 18a has the concentration (density) of the radioactive substance 19. The paste-like composition 114 containing different radioactive substances 19 can be molded by pouring it into the outer mold 111 so that the concentration (density) decreases toward the outer mold 111 side.

[5-4-3. Explanation of the method for producing a crustal-like composition using centrifugal force]
The interior 18 of the crustal-like composition 20b-2 shown in FIG. 9 is configured such that the density of the radioactive substance 19 gradually decreases toward the outside from the central portion. The crustal-like composition 20e shown in FIG. 10 is also configured such that the density of the radioactive substance 19 gradually decreases toward the outside from the central portion as a whole. Here, the two crustal-like compositions are collectively referred to simply as "crustal-like composition 20e and the like". As described above, the crustal-like composition 20e or the like in which the density of the radioactive substance 19 gradually decreases toward the outside from the central portion can be produced by utilizing centrifugal force.

FIG. 28 (A) shows the centrifuge device 121. The centrifuge device 121 includes a formwork 122 for forming the crustal-like composition 20e and the like, and the formwork 122 rotates at a high speed about the shaft 125. The centrifuge device 121 is provided with a hopper discharge port 123 and a discharge port 124. From the discharge port 123, the substance 19b corresponding to the high-density substance is poured into the mold 122, and from the discharge port 124, the substance 19a corresponding to the low-density substance is poured into the mold 122. Of course, the centrifuge does not necessarily have to be provided with a rotating formwork, and it is sufficient that the material material in a fluid state before solidification contained in the formwork can be rotated at high speed. ..

The high specific density substance 19b is a substance having a high specific density in which the radiation concentration is set to be below the lower limit of measurement or relatively low, and as described above, barium, lead glass pieces, etc., which have a high radiation shielding effect, and other fine substances. Examples include aggregate and coarse aggregate. Further, the low specific gravity substance 19a is a low specific gravity substance having a finite radioactive concentration, and examples thereof include soil containing radioactive substances, that is, contaminated soil, particularly fine-grained soil having a layered structure and other porous materials. , As described above, contaminated water and a contaminant-carrying material obtained by mixing them may be used (see FIG. 17). Specifically, as the fine-grained soil having a layered structure, for example, the main particle size is 0.075 mm or less, and there are vermiculite, bentonite, asbestos, etc., and as the porous material, shirasu porous glass, amorphous charcoal, etc. Materials and the like can be mentioned. Such a high-density substance 19b and a low-density substance 19a are mixed and kneaded from the discharge ports 123 and 124 into a paste-like composition such as a tertiary composition, a quaternary composition, or a quintic composition as an additive or an aggregate. do. Then, the low-density substance 19a containing the radioactive substance 19 and the high-density substance 20 as a non-radioactive substance are uniformly dispersed. Further, the centrifuge does not necessarily have to be provided with discharge ports 123 or 124, and the discharge does not have to be performed in a state where the high-density substance and the low-density substance are separated, and the high-density substance does not need to be discharged in advance. And a low-density substance may be mixed and housed in a mold.

Next, as shown in FIG. 28 (B), when the mold 122 is rotated at high speed, the high-density substance 19b is distributed in a large amount on the outside and the low-density substance 19a is distributed in a large amount on the inside due to the centrifugal force. As a result, it is possible to easily produce a crustal-like composition 20e or the like in which the density of the radioactive substance 19 gradually decreases toward the outside from the central portion. Further, the high specific density substance 19b has a high radiation barrier effect. By distributing a large amount of the high-density substance 19b to the outside, it is possible to form a crustal-like composition having a high radiation barrier effect. Further, as shown in FIG. 9, the outer layer 17 that does not contain the radioactive substance 19 can also be formed of a layer in which a large amount of high specific density substances are distributed. Further, the outer layer 17 can be thinned like the epidermis layer.

[5-4-4. Explanation of the method for producing a crustal-like composition using pressure]
As shown in Table 2 and FIG. 3, the radioactive contaminants include fish and shellfish, vegetables, incineration ash, sludge sludge, marine mud, river mud, lake mud, street trees, and debris (concrete, wood, glass, etc.). 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, etc. can be used as fine aggregate and coarse aggregate. Then, by adding a fine aggregate, a coarse aggregate, or the like to the secondary composition which is a solidifying binder obtained by adding gypsum or the like to the primary composition, the above-mentioned tertiary composition, quaternary composition, or quintic composition is added. The composition can be produced.

Then, as shown in FIGS. 9 and 10, in producing the crustal-like compositions 20b-2 and 20e in which the density of the radioactive substance 19 gradually decreases toward the outside from the central portion, the paste in the mold is formed. It can be produced by pressurizing the composition. Specifically, as shown in FIG. 29 (A), the outer formwork pressurizing device 131 includes a formwork 132 and a pressurizing member 133 for pressurizing the paste-like composition in the formwork 132. The formwork 132 includes, for example, a secondary composition 134 which is a solidifying binder obtained by adding gypsum or the like to a primary composition and does not contain a radioactive substance 19, and a fine aggregate or a coarse aggregate 135. Those containing radioactive material 19 are mixed and contained. Then, after the secondary composition 134 and the fine aggregate or the coarse aggregate 135 are kneaded in advance, the paste-like composition 136 housed in the mold 132 is placed in the mold 132 by the pressurizing member 133. It is pressurized. Then, as shown in FIG. 29 (B), the secondary composition 134 containing fine particles having a smaller particle size and higher fluidity than the fine aggregate or coarse aggregate 135 moves to the mold 132 side. As shown in FIG. 9, it is also possible to form a crustal-like composition 20e in which the density of the radioactive substance 19 gradually decreases as the composition of the inner layer 18 moves from the central portion to the outer side while forming the outer layer 17.

In the formwork pressurizing device 131, when the pressurizing pressure is low, the outer layer 17 is hardly formed, and the crustal-like composition 20a in which the radioactive substance 19 is uniformly dispersed as shown in FIG. 5 is formed. You can also do it. Further, when the pressurizing pressure is increased, the secondary composition 134 having a small particle size and high fluidity is distributed along the inner surface of the mold 132, and a thin outer layer 17 is distributed on the epidermis of the crustal-like composition 20a shown in FIG. Can also be formed. By distributing a large amount of the secondary composition 134 having high fluidity in the outer layer 17, the physical strength of the molded product can be increased. Further, as shown in FIG. 9, when the pressure is further increased, the density of the radioactive substance 19 gradually decreases as the composition of the inner 18 moves from the central portion to the outer side while forming the outer layer 17, and the crustal-like composition 20b- 2 can also be molded. Further, as shown in FIG. 10, it is also possible to form a crustal-like composition 20e in which the density of the radioactive substance 19 gradually decreases toward the outside from the central portion where the outer layer 17 is hardly formed. That is, what kind of crustal-like composition 20 is to be molded is determined by appropriately adjusting the composition of the secondary composition 134, water, the magnitude of pressure, the pressurizing 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 pressurizing member 137 during pressurization, the crustal-like composition 20 to be molded becomes fragile. .. Therefore, the pressure member 137 shown in FIG. 30 (A) is formed in a mountain shape so that the pressure surface at the tip portion is highest at the center portion. In this case, the pressurizing member 137 pushes the paste-like composition 136 away and enters the mold 132, thereby preventing air from entering the mold 132 during pressurization. Can be done.

[5-5. Explanation of crushing process]
The crustal-like composition 20a in which the radioactive substances 19 shown in FIGS. 5A and 5B are uniformly dispersed throughout, and the crustal-like composition 20c-1 containing the radioactive substances 19 in the inner 18 shown in FIG. 6 are radioactive. The density of the substance 19 is not more than a predetermined value, and it no longer falls under the definition of radioactive waste, but can be treated as general waste or simply a material or a resource. Therefore, in the crushing treatment step 1006 shown in FIG. 11, as shown in FIGS. 31 (A) and 31 (B), the crustal-like composition 20a and the crustal-like composition 20c-1 are crushed by a crusher or the like and coarsely crushed in the plant. The aggregate 150 can be artificially crushed by medium crushing and fine crushing. As shown in FIG. 31 (C), such a crushed aggregate 150 may be coated with at least one coating layer 151 of resin, tar, pitch, polyacrylonitrile heat-treated material, and asphalt. Resin, tar, pitch, polyacrylonitrile heat-treated material, and asphalt can not only function as a barrier layer against the radiation emitted by the radioactive substances contained in each crushed aggregate, but also enhance chemical stability, acid rain and acid rain. It is possible to prevent neutralization and elution due to carbon dioxide in the air.

Such a crushed aggregate 150 can be used as a roadbed material 201, for example, as shown in FIG. 32. In a general road 202 such as a national highway, a lower roadbed 204, an upper roadbed 205, a base layer 206, and a surface layer 207 are sequentially provided on the roadbed 203. For example, the roadbed material 201, which is the crushed aggregate 150, can be used for the lower layer roadbed 204 and the upper layer roadbed 205. That is, the portion where the roadbed material 201 is used is not the road surface but the roadbeds 204 and 205 of the lower layers of 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.

Further, the crushed aggregate 150 can be used as the embankment material 211 as shown in FIG. 33. When the original ground has a slope, the upper side of the pavement 212 is generally cut and the lower side is filled. The embankment material 211, which is a crushed aggregate, can be used for the embankment portion. In the portion of the pavement 212, the roadbed material 201 can be used on the roadbed. Further, although not shown, the crushed aggregate 150 can also be used as a substitute material for soft ground. Further, the crushed aggregate 150 can be used as the ballast 216 used for the ballast track 217, as shown in FIG. 34. Further, as shown in FIG. 40, the inside of the caisson 310 used for breakwaters, quays, seawalls, etc. can be filled with crushed aggregate.

[5-6. Explanation of usage process]
Further, the block-shaped crustal-like composition 20 shown in FIG. 5-10 can be further reduced to the crust as follows. Specifically, there are a method of reducing the crust via the ocean and a method of directly returning to the ground.

[5-6-1. Explanation of transsea crust reduction method]
As shown in FIG. 35, the block-shaped crustal-like composition 20 shown in FIG. 5-10 is landed on the ocean 302, placed on the seabed 303, and reduced to the crust as a part of the crust on the seabed. Can be done. The block-shaped crustal-like composition 20 arranged on the seabed functions as a fish reef 303a or the like on the seabed 303 by being transported to the ocean 302 by a ship 301 and thrown into the ocean 302, and also serves as a continental plate or an ocean plate. When it is submerged in the deep sea such as a subducted trench, it can be submerged in the crust of the seabed and disappear in accordance with the movement of the plate 304.

When submerging in the deep sea, in order to reduce the influence of ocean currents and settle the crustal-like composition 20 at a predetermined position, for example, as shown in FIGS. 36 (A)-(C), it looks like a weight as a whole. It is preferable to have an outer shape such as a teardrop shape, a weight shape, a bullet shape, a streamline shape, etc., and to provide a weight portion 307 on one end side, which is heavier than the other end side. As a result, the crustal-like composition 20 can be landed at a predetermined position on the seabed 303 in a stable posture.

As shown in FIG. 37, for example, the ship 301 that carries the crustal-like composition 20 to a predetermined place in the ocean is sequentially submerged from the sea to the seabed 303 by using the conveyor 301b from the hatch 301a at the rear of the hull. Can be done. Of course, as shown in FIG. 35, the ship 301 may be made to land on the sea surface from the sea by using a crane or the like. Further, FIG. 38 shows an example of a catamaran. In this catamaran, a large deck 301d can be provided between the two torso 301c, and many crustal-like compositions 20 can be loaded on the deck 301d. For example, the deck 301d is openable and closable, and when opened, the crustal-like composition 20a loaded on the sea surface at one time can be charged. Further, FIG. 39 shows an example of a pontoon. In the case of a pontoon, a block-shaped crustal-like composition 20 is loaded on the deck 301 or an internal storage, towed to a predetermined place, and settled in the ocean at a predetermined place using a crane, a conveyor, or the like. Can be made to. Further, in the case of a pontoon without a propulsion engine, the pontoon loaded with the crustal-like composition 20 may be submerged and / or submerged in the ocean as it is by injecting seawater into the pontoon. The pontoon may be equipped with a propulsion engine.

In the case of a ship such as a pontoon, the crustal-like composition 20 is formed into a hull shape, a raft shape, and a floating shape that can float, towed, and submerged in the ocean as it is at a predetermined place. And / or may be settled. Further, the crustal-like composition 20 may be towed in a submerged state and then separated from the towed vessel and settled at a desired position. In this case, in order to reduce the water resistance, it is preferable to form a streamlined shape such as a submersible, a submarine, or the like. Further, the crustal-like composition 20 may be used for landfill in the ocean.

Further, the crustal-like composition 20 can be used for coastal marine structures as shown in FIG. 40. 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 sunk, for example, on the seabed. After this, the crustal-like composition 20 can be disposed in the caisson 310. Further, the caisson 310 may be filled with a crushed aggregate obtained by crushing the crustal-like composition 20, or a paste-like composition using the crushed aggregate may be placed between the gaps of the block-shaped crustal-like composition 20. It may be packed or filled. Alternatively, the paste-like tertiary composition, quaternary composition or quintic composition may be contained in a state of having fluidity and solidified in the caisson. In addition, as a coastal marine structure, it can also be used for floating mooring shores, floating breakwaters that float offshore for wave-dissipating and wave-breaking, and sloping embankments for the purpose of preventing coastal erosion and multipurpose use of coastal areas. You can.

By the way, as shown in FIG. 41, the crustal-like composition 20 in which the quaternary or quaternary composition, which is a paste-like composition, is solidified, has at least one selected from asphalt, tar, and glass on its surface. The impermeable layer 21 may be provided by one or more substances. When the impermeable layer 21 is provided, it is possible to prevent the crustal-like composition 20 from becoming fragile due to exposure to seawater or the like.

Furthermore, as a method for solidifying high-level radioactive substances and highly toxic radioactive substances, ore is artificially synthesized mainly from titanate-based minerals such as horandite, perovskite, and zirconolite, and molybdenum is used at that time. The fixing material 22 which is co-fixed by co-fixing transuranium element nuclides such as technetium, ruthenium, and plutonium with the primary to fifth-order composition and the impermeable layer 21 has a high confinement effect. You may do so. For example, the fixing material 22 can be mixed before kneading with water. The above-mentioned artificial ore synthesis is carried out, for example, of the precursors, rutile (TiO ₂ ) and zircon (ZnO ₂ ) are prepared from titanium alkoxide and zirconium alkoxide. All the remaining components are prepared by treating with an alkaline solution as a mixed solution of nitrate solutions and coprecipitating them. These precursors are mixed with high-level radioactive or highly toxic radioactive waste liquid to form a slurry, which is dried and calcined in a reducing atmosphere at 800 ° C., sealed in a vessel together with titanium powder, and heated. It can also be pressed and fired under pressure.

The crustal-like composition 20a in which the radioactive substances 19 shown in FIGS. 5 (A) and 5 (B) are uniformly dispersed throughout, and the crustal-like composition 20c-1 in which the radioactive substances 19 are contained in the inner 18 shown in FIG. , When the concentration (density) of radioactive material 19 is less than a predetermined value and no longer falls under the definition of radioactive waste, it becomes general waste or a material that can be treated simply as a material or resource, and trans-sea crustal reduction is performed. Easy to use. Of course, the crustal-like composition 20 as shown in FIG. 7, which has a portion in the inner portion 18 in which the concentration (density) of the radioactive substance 19 is higher than a predetermined value, may be used for trans-sea crustal reduction when forming a block.

[5-6-2. Explanation of the method of reducing the crustal crust]
As shown in FIG. 42, the block-shaped crustal-like composition 20 shown in FIG. 5-10 can be used for backfilling of the closed tunnel 401 and can be reduced to the crustal. For example, in the tunnel 401, invert concrete 403 is placed on a support shaft 402 that prevents collapse in the tunnel. The block-shaped crustal-like composition 20 is arranged, for example, on the invert concrete 403. At this time, the above-mentioned quaternary composition or quintic composition having a density of the radioactive substance 19 of a predetermined value or less may be injected into the filling of the crustal-like composition 20. Further, the top end side can be filled with the backfill material 404. Even in the backfill material 404, for example, fluid treated soil having a density of the radioactive substance 19 in which the secondary composition serving as a solidifying binder is poorly blended may be used. Thus, the closed tunnel 401 is backfilled by efficiently using the paste-like composition or the crustal-like composition 20 in which the density of the radioactive substance 19 is equal to or less than a predetermined value. Of course, the paste-like crustal-like composition 20 can be used for the support pit 402 and the invert concrete 403, and can also be used for the floor portion and / or the wall portion and / or the ceiling portion of the mine shaft 401.

The paste-like composition having a density of the radioactive substance 19 of a predetermined value or less may be sprayed on the floor surface or the wall surface of the tunnel 401. The paste-like composition for spraying may be used as invert concrete during tunnel excavation. Further, in the tunnel still in use, backfilling as shown in FIG. 42 may be performed in order to prevent the collapse.

[5-6-3. Explanation of other usage methods]
As shown in FIG. 43 (A), the crustal-like composition 20 as described above is a block-shaped crustal-like composition in a trench 501a of a shallow ground 501 in which no artificial structure is conventionally provided as a method for disposing of radioactive substances. 20 may be disposed, or a paste-like composition having a density of the radioactive substance 19 of a predetermined value or less may be cast. Further, the crustal-like composition 20c-2 shown in FIG. 7, in which the density of the radioactive substance 19 is higher than a predetermined value, may be 501 in shallow ground, but as shown in FIG. 43 (B), it is generally used. It may be arranged in the pit 502a at a depth (50 to 100 m underground) 502 having a sufficient margin for underground use. Further, the paste-like crustal-like composition 20 can be used in place of ordinary concrete for forming the trench 501a and the pit 502a.

10 Radioactive neutralization treatment system, 17 outer layer, 18 inner, 18a center, 18b intermediate layer, 18c, 18d inner molding, 19 radioactive material, 19a low specific weight material, 19b high specific weight material, 20 (20a, 20b, 20c) , 20c-1, 20c-2, 20e) Crust-like composition, 21 impermeable layer, 22 fixing material, 101 outer formwork, 102 paste-like composition, 111 outer formwork, 111a temporary stand, 111b support legs, 111c Wire, 112 inner formwork, 112 inner formwork, 112a inner formwork, 113,114 paste-like composition, 113a outlet, 114a outlet, 115,116 recesses, 118 hopper, 121 centrifuge, 122 formwork, 123, 124 Outlet, 125 axis, 131 formwork pressurizer, 132 formwork, 133 pressurizing member, 134 secondary composition, 135 coarse aggregate, 136 paste-like composition, 137 pressurizing member, 137 paste-like Composition, 150 crushed aggregate, 151 covering layer, 201 roadbed material, 202 general road, 203 roadbed, 204 lower roadbed, 205 upper roadbed, 206 base layer, 207 surface layer, 211 filling material, 212 pavement, 216 ballast, 217 Formwork, 301 Ships, 301 Deck, 301a Hatch, 301b Conveyor, 301c Body, 301d Deck, 302 Ocean, 303 Submarine, 303a Fish Reef, 304 Plate, 307 Weight, 310 Cason, 401 Closed Tunnel, 401 Tunnel, 401 Closed Tunnel, 402 support pit, 403 invert concrete, 404 backfill material, 1001 pretreatment process, 1002 raw material process, 1003 firing process, 1004 finishing process, 1005 forming process, 1006 crushing process, 1007 utilization process.

Claims (8)

Any one or more of animals and plants containing radioactive substances at a radioactive concentration exceeding the lower limit of measurement, incineration ash, sludge sludge, marine mud, river mud, lake mud, street trees, debris, contaminated water, and earth and sand. A method for firing a pollutant, which comprises firing the pollutant contained at a temperature lower than the vaporization temperature of cesium contained as the radioactive substance. The pollutant contains an organic substance, and the organic substance is carbonized and / or gasified by firing at a temperature lower than the vaporization temperature of the radioactive substance.
The method for firing a contaminated material according to claim 1, wherein the contaminated material after the firing treatment does not contain the organic matter. The method for firing a contaminant according to claim 1 or 2, wherein the firing treatment is performed in an oxygen atmosphere. The method for firing a contaminant according to any one of claims 1 to 3, wherein the firing treatment is performed in a closed space. Any one or more of animals and plants containing radioactive substances at a radioactive concentration exceeding the lower limit of measurement, incineration ash, sludge sludge, marine mud, river mud, lake mud, street trees, debris, contaminated water, and earth and sand. A fired pollutant containing a radioactive substance obtained by firing the pollutant contained at a temperature lower than the vaporization temperature of cesium contained as the radioactive substance. The fired contaminant according to claim 5, wherein the contaminant after the firing treatment contains an ash containing the radioactive substance. The pollutant contains an organic substance, and the organic substance is carbonized and / or gasified by firing at a temperature lower than the vaporization temperature of the radioactive substance.
The fired contaminant according to claim 5 or 6, wherein the contaminant after the firing treatment does not contain the organic substance. Any one or more of animals and plants containing radioactive substances at a radioactive concentration exceeding the lower limit of measurement, incineration ash, sludge sludge, marine mud, river mud, lake mud, street trees, debris, contaminated water, and earth and sand. An incineration ash containing a radioactive substance obtained by firing a pollutant containing the pollutant at a temperature lower than the vaporization temperature of cesium contained as the radioactive substance.

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