JPS6182199A - Method and device for manufacturing radioactive waste intermediate store - Google Patents

Abstract

(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a method for producing an intermediate storage body for intermediate to low level radioactive waste generated from radioactive material intake facilities such as nuclear power plants and nuclear fuel reprocessing facilities; Regarding the manufacturing equipment.

[Technical background of the invention and its problems] Conventionally, IIA handling of radioactive materials at nuclear power plants, etc.
Methods for volume reduction and solidification of radioactive waste, such as radioactive liquid waste and used ion exchange resin, generated in facilities include the following methods: Assimilation method, beretization method, Yaki JJI method,
Wet decomposition methods are known.

(a) Cement assimilation method This method is a method of cement assimilation.
After condensing and drying the monolithic waste to form a powder containing sodium chloride (M), or by drying the used ion exchange resin (, this is a method of solidifying using cement as a solidifying agent.

This cement assimilation method has the advantage of producing an assimilated material with poor fire resistance and high mechanical strength, but it also increases the weight of the assimilated material, making it difficult to handle.
The disadvantage is that a large amount of solidified material is generated.

(b) Assuffuult assimilation method This method involves condensing and drying liquid radioactive waste to form a powder containing sodium latinate, or after drying used ion exchange resin. Assimilate Ruto as a solidifying agent 5! ! This is the method to do it immediately.

This method has the advantage of being able to form a solidified material at a low cost, but has the disadvantage that the resulting assimilated material has poor fire resistance and is susceptible to mechanical shock since the assimilated material is flammable.

(c) Plastic solidification method This method involves concentrating and drying liquid plastic waste to form a 1'I) compound containing sodium sulfate, or drying used ion exchange resin, followed by thermosetting. This is a method of C solidification using a carbonaceous plastic as a solidifying agent.

In this method, water is not solidified as well as in the cement assimilation method, and the amount of solidified material generated can be reduced to 17'5 h2 compared to the cement assimilation method.
■Although there are 111 points that indicate that it is steeped in mechanical properties, etc., many of the monomers used in Plus Bootsque are volatile at room temperature, so there is a real risk of fire due to overassimilation processing. ,
In addition, since the assimilating agent has a special property, there is a drawback that the solidified material obtained by the process becomes poor in fire resistance.

(d) Making pellets This method involves concentrating and drying 1 part of liquid waste, making 1 part of powder, 1 part of water, and making it into 1 part of pellet, and then storing it for intermediate storage. This is a method of redirecting.

According to this /j method, /If (the amount of machinable waste generated is 111 points smaller than the amount generated by the plus one solidification method (January), but the ion exchange resin history filter As in (i), there are many disadvantages in applying things to things.

(e) Incineration u1 method This incineration method involves sending air to dispose of waste! 01 Power is incinerated 11'
l! There are two methods: carbonizing the waste and burning the gas generated by pyrolysis.

These methods are methods that reduce the volume of waste materials such as ion exchange resins and filters that are generated in large rivers at nuclear power plants by decomposing them at high temperatures. There are advantages to being there.

However, in these methods, C in the former category is used for ion exchange resins, especially powdered ion exchange resins with a particle size of several tens of thousands.
At the 13th stage, when waste of about 0 μm is incinerated, the air promotes the scattering of waste, and the waste flows into the off-gas system, which has a capacity of 1.
However, the latter method has the disadvantage of increasing air entrapment and placing a heavy burden on the filter.Also, in the latter method, the scattering of radioactivity is greatly reduced because no air is sent into the processed material. Compared to the previous method, there is a large amount of unburned residue, and especially in the case of ion exchange resins, coke remains in the carbonization process, so
Although the volume of the car can be reduced, it has the disadvantage that the volume cannot be reduced as much.

(f) Wet fraction FLY method This method uses a material such as a radioactive ion exchange resin.
; J', 1: T radioactive waste is immersed in water by applying active oxygen generated during the decomposition of hydrogen peroxide or high pressure.
8 This is a method in which the volume is reduced by decomposing the arsenic using dissolved oxygen.

With this V%, it is possible to significantly reduce the volume of ion exchange resin without the release of A4 activity, but it takes a long time to process, and there is a concern that Ling Mlli will need a lot of help. There is.

[Objective 1 of the Invention] The present inventors have devised a revec S5 that eliminates such conventional drawbacks.
The result of pursuing dual-purpose research is nuclear power? , h'l of electric stations etc.
For river use C1 handling/ll! Radioactive 11! containing salts generated in stage i is dried and heated together with vitrification agent and solid radioactive waste of lfM 7'[.
By melting B, right) one purchase of solid radioactive waste and inorganic j7. ; The i! It has been found that 1q of non-scattering cullet-like intermediate storage bodies can be obtained by rapidly cooling the melt of '+U.

In other words, by drying the liquid radioactive waste generated at the 1ζ1e tit B W R Hara Ryoki Photoelectric Plant,
Sodium chloride is one of the materials used in the glass industry and melts at temperatures above 884°C. In the molten salt of sodium sulfate, ion exchange resins and other 4-i substances are thermally decomposed without scattering and turned into coke at °C, and this coked carbon component and vitrification agent react with sodium sulfate to form Co, The volume reduction progresses further by vitrification while generating gases such as GO2 and 802.

The present invention was made based on this knowledge, and the present invention eliminates the drawbacks of conventional radioactive waste solidification methods and ion exchange resin incineration methods. It is an object of the present invention to provide a method for manufacturing a bundle intermediate storage body and an apparatus for manufacturing the same.

SUMMARY OF THE INVENTION 1 In other words, the method for producing an intermediate storage body for HK off-river waste according to the present invention is a method for producing an intermediate storage body for HK non-river waste,
Dry and powder the waste, heat this dry powder and a vitrification agent, and treat the generated pyrolysis gas! ! I! L
, 81 pieces of glass remained after being discharged from the system (
It is characterized by rapid cooling of 7C cullet and 1 heat, and the intermediate storage facility ¥J Zosokyo dries the contents of liquid radioactive waste containing inorganic salts generated at nuclear facilities. A liquid synthetic waste pretreatment device for converting it into a dry powder, and the drying process 1't! Equipment: A glass melting furnace that heats and melts the mixture of the dry powder obtained in step 6 and the vitrifying agent, and a glass melting furnace that processes the pyrolysis gas generated in the glass melting furnace and discharges lJ+ from the system.
Coming out of the A fugas place! l! The present invention is characterized in that it is equipped with a cullet production apparatus that rapidly cools the high temperature molten material lath-formed in the IY1 gutter glass melting furnace and converts it into J-let.

Hereinafter, the method for producing one radioactive waste and one interim storage according to the present invention will be further explained in detail.

According to the manufacturing method A'27jθ of the intermediate storage body of the present invention, used-(71-ton cross-ground resin, filter sludge, paper, Tri
, solid radioactive waste such as polyolefin sheets has a volume reduction and solidification IQ of 19! You can.

In the present invention, in one evening, a liquid α1-produced waste material containing, for example, sodium sulfate generated at a nuclear facility is dried and powdered by a conventional method, and this dry powder and a vitrifying agent are used. and solid FFE waste such as ion exchange resins and filters are mixed and heated at high temperature.

The dry powder obtained by drying the above liquid radioactive waste containing sodium chloride contains ion exchange resins and filters that were dispersed in the form of slurry in the liquid radioactive waste. may be included and also separately these right one
j, l 11 solid ffi! You may also add Tomotsu to make the match α immediate.

As the vitrifying agent, any glass-forming substance that improves the water resistance and mechanical strength of sodium sulfate can be used, but silicon dioxide is suitable for fi. Note that boric acid, aluminum hydroxide, lucium carbonate, etc. may be used in combination with silicon dioxide.

Generally, when sodium sulfate and silicon dioxide are heated, they melt and form a vitrified product with high strength. However, as the reaction progresses, the soda glass component increases, and as a result, the viscosity of the melt increases. In order to maintain the molten state Qji of the treated material at a temperature of 1500° C., it is necessary to heat the material to a temperature of about 1400° C. Add 1 part of boric acid as a vitrifying agent.
1 (The viscosity of the used glass melt decreases significantly 12
Even at a temperature of about 00°C, it can be kept in a molten state for tll.

In addition, the glass formed by the present invention has a high soda content in order to increase volume reduction properties, and therefore has low water resistance, but boric acid and aluminum hydroxide improve the water resistance of the glass. It has a soothing effect. 1 Furthermore, calcium carbonate also reduces the viscosity of glass and improves its water resistance.
In addition to being effective, it also has a 1'F function that decomposes minute amounts of sodium sulfate contained in the dry powder.

In the present invention, the combination of the dry powder and the vitrifying agent is preferably in the following range, for example.

Dry powder of solid waste liquid...20-55%
Silicon dioxide ・・・・・・・・・・・・Go to 25・
65% phosphoric acid
・・・ ・・・ ・・・ ・・・ Go to 1・ 2
0% aluminum hydroxide ・・・・・・・・・・・・
1-5% calcium carbonate ・・・・・・・・・・・・
... 1 to 15% In this heating process, solid particles such as ion-prone resins (IJ wastes are easily thermally decomposed and turned into coke.The remaining carbon components are expressed as shown in equation (1). It is oxidized with sodium sulfate and released as carbon oxide.

Furthermore, in the presence of silicon dioxide, 1-lium sulfite is decomposed to generate sulfur dioxide, as shown by equation (2), and becomes vitrified into soda/guiric acid glass.

Na2SO4+C-1 → Ni1zSO3+CO↑・(1) Na2SO3+Si 02---1Na z 0-
3i 02 +SO2↑-(2) As is clear from the above formula, in the present invention, sodium sulfate itself is decomposed to release two components, resulting in a significant reduction in the amount of the product. However, the release of 1. The IJ active components and the carbonaceous components that have not been gasified are turned into coke and trapped in the vitrified material.

Therefore, place 1! I! The decontamination coefficient of the q] function is extremely high, and the volume reduction treatment of ion exchange resins etc. is performed under conditions F, which are similar to the wet firing method described above. ! ! It is possible to do this.

J3, the pyrolysis gas generated in the above reaction tube is burned in a conventional manner, and after radioactivity is removed, it is released outside the system. It is immersed, rapidly cooled, and turned into cullet.

Next, an apparatus for manufacturing an intermediate storage body of the present invention will be explained. 1. The volume reduction and solidification treatment system of the present invention, as shown in FIG.
The main part is 471m long, consisting of Fugas Station 1 Armor 13 and Karen [- Manufacturing Equipment 4].

b father (II waste + Wr processing equipment F'? 1,
For example, the known vertical thin film dryer V(1, generally right lr&11(D'jet hI I, lJ
Although it is possible to immerse the glass melting furnace 2 without immersing it in the glass melting furnace 2 without doing any processing, it is possible to immerse the waste sludge 63 of ion exchange resins and the waste sludge 63 of ion-exchange resins. After the dl'!!f is dried here, it is put into the glass 78 melting furnace 2.

The glass melting furnace 2 contains dry powder containing fc sodium sulfate produced in the radioactive waste surface treatment equipment 1, paper, other large-sized miscellaneous waste materials, and a vitrification agent. i!'!
This is a device that heats it in an i-lagoon to cause thermal decomposition and vitrification. A high frequency heating device is suitable as a heat source for this glass melting furnace 2, and its electric frequency is 10 to 400 kllz when the inner diameter of the glass melting furnace 2 is in the range of 20 to 400 m. Appropriate.

Off-gas treatment equipment'in 3G (mainly glass)
γ; Burning the flammable thermal decomposition residue generated in the melting furnace 27. II
1. This is a device that removes radioactive q4 activity and releases it outside the system.

This A gas processing device 3 is a gas processing device that burns gas (1.
A high-performance 11-hiflutter made of refractory material to completely remove radioactivity from the off-gas generated from the combustion chamber, and a combustion chamber to confirm the presence of h(j) in the off-gas. It consists of a measurement system.

The solid handling device 4 includes a device C that rapidly cools the vitrified molten material and turns it into cullet 1. be converted into

In the 1% J ; r2 device of the intermediate storage body of the present invention, liquid radioactive waste in the form of a solution or slurry is first transferred to the radioactive waste pretreatment I11! The drying process can be done with the first purchase. BW[? At the Atomic Tsuno Power Plant, the main component of the concentrated waste liquid was found (because it is acid gamma thorium, it was dried and produced25) and was found in the body. It contains a lot of sodium chloride.
11 is 3 times right. , this dry powder containing sodium triacetate is like 11 others! 1 lIh5t mouth/J waste d
3J and a vitrifying agent are charged into the glass melting furnace 2, where they are heated to produce pyrolysis gases such as G01CO2,802 and the like, and are vitrified.

', E rj3 When starting up, since the electrical conductivity of the glass is low, it is desirable to add a substance with high electrical conductivity, such as silicon carbide. Silicon carbide is 1111
Since the constituent elements are the same as those participating in the vitrification reaction, they are similarly thermally decomposed and the residue is incorporated into the molten glass. At the same time, in order to form a molten glass as much as possible, dry T containing 1Xt M"U sodium, which is a glass-forming substance of 1 waste from hk river, is added.
It is desirable to charge 100 liters of powder. The melting point of sulfuric acid is 884°C, and it is easily melted and vitrified at relatively low temperatures.

Next, the molten sodium chloride, which has a low electrical resistance, is further heated with a quotient frequency to heat it with light.
R4 is heated to 1,200℃, and in this state, flammable radioactive waste or miscellaneous radioactive waste such as ion exchange resin with a curved surface is put into the glass melter 2 and heated. Let it break down.

Here, the carbon in the coked waste Tomono decomposes sodium sulfate and reduces its volume by the reaction represented by the above-mentioned formula (1) and (2).

FIG. 2 is a sectional view schematically showing the state of the charge in the glass melting furnace 2.

As shown in the figure, organic solid radioactive rA Tomono such as sodium sulfate and ion exchange resin are charged from a hopper 28 installed at the upper part of the glass melting H1 furnace 2.
From b, a vitrifying agent of S i 02 ′:rg is charged. These charges are heated to 50% by pyrolysis gas flowing from the lower layer in the upper layer of AIK in the glass melting furnace 2.
It is heated to 0°C or above, and as it sequentially moves to the lower three layers, the main components are thermally decomposed to produce UCO, COz-only hydrocarbon gas, and at the same time, coke progresses. The volume is reduced.Furthermore, in the 0 layer, it melts to -14-,
rII! Sodium I acid decomposes over time to generate SO2, and as the reaction progresses, the specific gravity of C increases and settles to the bottom layer D and 7, resulting in stable molten glass)l)? becomes.

J3, the hk radioactive waste number in the Δ layer, acts as a filter for the pyrolysis gas containing the active substance rising from the 13th layer; 11 to prevent the release of lF, 5 (high frequency coil for heating).

Heat generated in sword lath melting furnace 2 F/? The gas is sent to A Fugas Station 1A Equipment 3, and first it is sent to 1 City U Gen! : :rl to J
, is added 111, and sent to: C'i:i'η. Here, the pyrolysis gas f is completely combusted; it is 1 Ued and the COz is converted to 150 to 120.
12. The gas is passed through a filter consisting of refractory iΔ, C/+Q (141iti is invaginated, and f1in I(<
Pass the high performance filter 1 through 11. Ta1su, firiQ'
J Noh's T-r'j! It is confirmed by the gas monitor and released from the stack to the outside of the system.

On the other hand, the vitrified material of layer D is poured from the lower outlet into a current production tank filled with cold IJI water of the cullet production apparatus, and subjected to n-speed IJ cooling to form cullet. This cullet 1- is stored in the cullet intermediate storage tank in the [12 water, dry 1 crotch night].

[Embodiments of the Invention] The present invention will be explained below by embodying the present invention and referring to one embodiment.

FIG. 3 shows the firing waste M<'J'm of one embodiment of the present invention.
FIG. 4 is a diagram schematically showing the configuration of an apparatus for manufacturing an inter-II storage body.

Is J3 in the diagram? 'T No. 11 indicates a vertical dryer 11r, which dries the liquid waste containing sodium sulfate supplied by the pump 12 and turns it into powder.

The vertical 74+1 thin film dryer 11 is connected via the conveyor line 13 to a drying body for dry concentrated waste liquid, a bar 14 and a
These small flanges 1/I, 1!5 are in contact with the masonry step 1] 17 where the glass melting takes place between 16-1 and 16-1. 'a has been,
.

, Sword Nose Melting Furnace 1G Shrine Increase: 1 Death ``117''
No. 1, A1 machine '71 Phase number q1 Small waste supply collar 18 J3 Output of small supply collar 19 for vitrification f1 (:1 connection τ:1 is also connected.

As shown in Fig. 4, a damper 21 is installed between the material input port 17 and the glass melting furnace 1G. Melting furnace 16
The release of UJ-related waste to the government is controlled. A heating high-frequency coil 22 is attached to the lower side of the glass melting furnace 16.

In addition, an outlet nozzle 23 is provided at the bottom of the glass;
One tube is wound around the thermal heater and the other. This exit, l
Below the slot 23, a 3° glass molten h1! is arranged where the cullet 1 to production head for converting the molten glass material into cullet are arranged. A pyrolysis gas outlet 2.1 is provided on a part of the side surface 1 of the furnace 16, and is connected to an off-gas treatment device. , 2 b L;L Detecting the liquid level of the molten glass layer I
This is a level meter consisting of n1 pairs of beams.

As shown in Figure 413, the device consists of a cullet tank 26 filled with cooling water, a dewatering tank 27, a dried sieve 28, and a cullet tank 26 filled with cooling water. 414 have been completed. The space between the cullet manufacturing tank 26 and the outlet nozzle 23 of the glass melting furnace 16 is covered with an airtight cover 268, and the water vapor and other gases generated by pouring the molten glass are sent to the A fugas treatment device via the condenser 2G. It is now possible to

A screw conveyor 26b is disposed at the bottom of the current production tank 2G, so that the current generated by quenching the molten glass is conveyed to the dewatering tank n27.

260 is a cooling machine for cooling cooling water, and is a cold 7J
I water is cooled 2J to the cullet production tank 26 by the pump 26d.
+i' precirculation 1) is carried out between 11 and 26C.

The drying step 1328 consists of a belt conveyor 28a and a micro)1ρ heating device 28b arranged with the same number on the belt conveyor 28a,
The dried cullet is continuously dried while being conveyed on the belt conveyor 28.1.

A fucus ash ready-equipped; 1″′1 is the pyrolysis gas combustion chamber 30;
Filter treasure 31 made of fireproof material, off-gas cooling rA H
Iqt 32, high performance filter 33, IIf21v
! t'R'iQ34, stack 35, high 1
Immediately after the 1 (1 hif C filter 33), a radial capacity monitor 3G is disposed.

Manufacturing of intermediate waste storage body of this example Ju'1
41 Blue C (, 艮, ;1su゛15:! Completed) J Facility C Mitsushishi Ikoh ((1.1 sex, 1st edition, 1st layer waste liquid L-una dissolution ift
Radioactive q4 ff! m i! 71 )' - (A'
Exchange tree 1117 J, eel slurry radioactive 1C
The waste is dried by drying and becoming a body.

This vertical B1++ 114th day'tl J'61! Support 11 is a general IL technology plant 1' /+i (Q-1 sex ff
5! f! 91 processing (f7 l f tsu'y l+'
il It, to L/ll-11; ) ″”i widely 1
Fumikawa is C there is b's C- there, the inside is 1°i'j C
P, Q is ≧ ku, and internal t14 i is also simple j de ape)! It has the advantage that decontamination, I3 and J:, and j are R11A. 1 N1 Ta 1 Hojrk Q'J Sex Abolition History 1h t;t 'vF
”':,', j711S!*2 Dry IX!! 11
(J) It is supplied from the inlet and heated and dried.

~, the song's stroke 1 high-quality solid body + 3. ``waste 37'' is luck V with drum fUj or other form 2:), good!X! 71 from 1 hopper for miscellaneous radioactive waste The material is charged into the material input port 17 of the glass melting furnace 16. At this time, ti fil 7'
If the pond contains large pieces of non-combustible waste, it will be removed in advance. 1 Next, these fixed f4, radioactive lJi! It is heated in the glass melting furnace 16, but when the glass melting furnace 16 is started, a vitrifying agent mixed with silicon carbide is charged.

Wake up again! During IJ, it is desirable to form molten glass as quickly as possible.
i/, [Dry powder containing a large amount of F.lium is 1
1 is loaded first.

After this, the dried waste sludge, ion exchange resin,
Other right 1; 1K solid release Q (HL containing appropriate amount of VIA acid sodium 11) Q1t!! It is charged into a glass melting furnace together with silicon and molten metal.The temperature inside the glass melting furnace is 8 molten layer
If it is 191 degrees below 1200 degrees Celsius, then the solid IA is released! 20 (1”Q
A temperature gradient is applied such that I'+', degrees and <r. Gogo 1 ice ho (Fl)
Most of the sexual waste is caused by the heat content at -FI'? temperature or higher (5
00℃ or higher), there is a large amount of flammable heat M gas.
Light occurs at 1, at B! i! Coking of the material takes place) 1 (row). Also, at 1°i of the glass melting hη, the right (
Eleven components are turned into coke, and the carbon component, vitrification agent, and 1AfiQ sodium are melted to begin vitrification. Vitrified tit molten FAf! Minute Rt from goods
L, because of its large ratio, tends to settle into the glass melt.

On the other hand, the pyrolysis gas generated by pyrolysis of the radioactive waste is led to the off-gas processing device from the pyrolysis gas outlet 24 installed at the i section of the side surface of the glass melting furnace 16. Nowadays, the hot FIY gas passes through 1 ft of solid waste in the glass melting furnace 16, heating it up and discharging the radioactive waste into the solid waste. It is removed by filtering the object.

Moreover, in the radioactive chamber 1'l' in the intermediate storage body manufacturing apparatus of the present invention, thermal decomposition occurs statically, and due to the filtering effect of the radioactive waste in the upper part of the glass melting furnace, Can be held low.

As the process progresses, the volume of molten glass increases and reaches a certain level, which is detected by the level meter 25 and an alarm is issued, and the molten glass is extracted from the outlet nozzle 2G of the glass melting furnace 16fc section. Current 'II-built 4th floor! 126.

The extraction of the molten glass is carried out by a method in which it is heated in a melting furnace for ordinary J-Las solidification processing.

In other words, during normal operation, the glass in the outlet nozzle 23 is solidified to block the outlet nozzle 23, and when taking out, the heater is energized to cool the glass in the outlet nozzle 23). The cullet is melted and the high-temperature molten material is poured into the cullet fixing layer 1a26.

The melt poured into the Karen production tank 26 is pulverized into a Karen shape by one blow of a thermometer, dried in a drier 28, and stored in an intermediate current storage tank 27.

In addition, the pyrolysis gas discharged from the glass melting furnace 16 is heated to about 800°C by the fuel burner 30a and burns the thermal molecule i7 scum? I'T L30'\ is sent there, where it is oxidized and turns into carbon dioxide gas.

) The filter chamber 31 is composed of a 1111-inch laminated ramic filter, which removes dust and particles contained therein from the high-temperature gas. The temperature of the filter chamber is 600-8
The temperature is kept at 00℃ and the pyrolysis gas is combusted with N2G.
The remaining combustible gas that has been converted into CI'i'F is also completely converted into n-wax.

The combustion residue leaving the filling chamber 31 is heated at a temperature of 3 to 411°2 in the 1afJI chamber 32, cooled to below 200°C, and passed through a high-performance filter 33 to remove radioactive particles. The light was measured by the 36-year-old Monique QJ.
It is confirmed that the Ill component does not contain L.

After that, the SO contained in the waste gas is sent to the desulfurizer 34.
2 is removed.

At this stage, the radioactivity is 41, so IBJ rlI!
As for I-434, it is possible to use commonly used T-shirts.

The secondary waste generated in 1ql of wastewater treatment can be treated as general waste.

The waste gas after the desulfurization process is discharged into the environment through the stack 35.

Experimental example: Using the above-mentioned apparatus, heat R1.1 waste and a vitrification agent having the following composition; The heat treatment was performed by adding 10 (8 parts) of the mixture.

/IS[Ql l! 1i1J degeneration: k 92 dry costume...
・45~・55% silicon dioxide ・・・・・・・・・
・35-45% boric acid ・・・・・・・・・
...1096J3 After about 1 hour, it was confirmed that a glass melt was formed.

The cullet made from this glass melt was a small fire-resistant case (n2 sorter glass C), and its physical properties were as follows.

Glass transition point 510°C Softening point 610°0°C Business point 950°C Specific gravity 2.51 Oxide [-lium elution fn (25'l: ;l', oral tradition) G, 8x 10' Q 7'cll' dayIc
In the above, an example using a 1-sulfur 1-sulfur solution containing sodium sulfate generated at the 7LZ of 1-1-1 was described, but the present invention is not limited to such an example. 6rj generated at a nuclear fuel reprocessing facility
t)iil
There is no ability. The main component of the pyrolysis gas in this case is CO2
, N2, so in the above example, jj31, n<2, y7, and OJO, since L is omitted.

[Effects of the Invention] As explained above, the manufacturing method and solidification process of the intermediate radioactive waste storage body of the present invention are as follows. If you use J as an accessory, you can eliminate C1J with a high volume reduction ability! The cullet produced has excellent water resistance and heat resistance, and can be used to process liN particles.
71L "CJ3" has less deterioration due to changes in chemical properties, and has no scattering properties, making it more suitable for use as an intermediate storage medium than pellets using conventional binders. In addition, the use of a vitrifying agent lowers the maximum processing temperature of the glass melting furnace, improves the air resistance of the glass (a) melting furnace, and improves the water resistance of the cullet.
Improves strong IJ.

[Brief explanation of the drawing]

Fig. 1 is a block diagram schematically showing the structure of the manufacturing apparatus for intermediate waste storage bodies of the present invention, Fig. 2 is a diagram showing the process of the glass melting furnace, and Fig. 3 is a block diagram schematically showing the structure of the production apparatus for intermediate waste storage bodies of the present invention. FIG. 4 is a cross-sectional view showing the structure inside lf and IJ3u of the intermediate storage body of this embodiment, and FIG. 4 is a cross-sectional view of the glass melting furnace.

Claims (8)

[Claims] (1) Dry and powder liquid radioactive waste containing inorganic salts generated at nuclear facilities, heat this dry powder and vitrification agent, process the generated pyrolysis gas, and discharge it outside the system. A method for producing an intermediate storage body for radioactive waste, comprising the steps of rapidly cooling the remaining high-temperature molten material and turning it into cullet. (2) The method for manufacturing a radioactive waste intermediate storage body according to claim 1, wherein the inorganic salt is sodium sulfate. (3) The method for manufacturing a radioactive waste intermediate storage body according to claim 1, wherein the inorganic salt is sodium nitrate. (4) Any one of claims 1 to 3, wherein the vitrifying agent is a mixture of silicon dioxide and boric acid.
A method for manufacturing a radioactive waste intermediate storage body as described in 2. (5) The radioactive waste intermediate storage body according to any one of claims 1 to 4, wherein the liquid radioactive waste contains a used ion exchange resin or other organic solid radioactive waste. Production method. (6) Production of an intermediate storage body for radioactive waste according to any one of claims 1 to 5, in which the dry powder and the vitrification material are heated together with other organic solid radioactive waste. Method. (7) A drying device that dries liquid radioactive waste containing inorganic salts generated at nuclear facilities into a dry powder, and heats a mixture of the dry powder obtained by the drying device and a vitrifying agent. A glass melting furnace for melting, an off-gas processing device for treating pyrolysis gas generated in the glass melting furnace and discharging it outside the system, and rapidly cooling the high-temperature molten material vitrified in the glass melting furnace to form cullet. 1. An apparatus for manufacturing a radioactive waste intermediate storage body, comprising: a cullet manufacturing apparatus. (8) The apparatus for manufacturing a radioactive waste intermediate storage body according to claim 7, wherein the glass melting furnace uses a high-frequency heating device as a heat source.