TWI760749B - Use of silicon-aluminum oxide composite as hardening agent of radioactive phosphoric acid decontamination waste liquid and method for processing radioactive phosphoric acid decontamination waste liquid - Google Patents

Use of silicon-aluminum oxide composite as hardening agent of radioactive phosphoric acid decontamination waste liquid and method for processing radioactive phosphoric acid decontamination waste liquid Download PDF

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TWI760749B
TWI760749B TW109116448A TW109116448A TWI760749B TW I760749 B TWI760749 B TW I760749B TW 109116448 A TW109116448 A TW 109116448A TW 109116448 A TW109116448 A TW 109116448A TW I760749 B TWI760749 B TW I760749B
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phosphoric acid
radioactive
waste liquid
silicon
acid
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TW202144310A (en
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莊禮璟
林國明
鍾人傑
謝賢德
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行政院原子能委員會核能研究所
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Abstract

The method for processing radioactive phosphoric acid decontamination waste liquid includes mixing radioactive phosphoric acid decontamination waste liquid with first water to form pre-treating slurry, wherein the solidified radioactive phosphoric acid waste is 100wt%, the radioactive phosphoric acid decontamination waste liquid is ≧ 60 wt%, the first water is ≦30wt%; mixing the pre-treating slurry with silicon-aluminum oxide composite for a first time to form hardening slurry, wherein the solidified radioactive phosphoric acid waste is 100wt%, the silicon-aluminum oxide composite is ≧ 30 wt%, the ratio of the weight of water in the pre-treating slurry to the weight of the silicon-aluminum oxide composite is 0.5-1, the ratio of the mole number of the phosphoric acid in the pre-treating slurry to the mole number of the silicon-aluminum oxide composite is 1-1.9; and standing the hardening slurry for a second time at a first temperature to form solidified radioactive phosphoric acid waste.

Description

矽鋁氧複合物作為放射性磷酸除污廢液的固化劑的用途以及放射性磷酸除污廢液之處理方法Application of silico-alumino-oxygen compound as curing agent of radioactive phosphoric acid decontamination waste liquid and treatment method of radioactive phosphoric acid decontamination waste liquid

本發明關於矽鋁氧複合物作為放射性磷酸除污廢液的固化劑的用途以及放射性磷酸除污廢液之處理方法。The present invention relates to the use of a silicon-alumina-oxygen compound as a curing agent for the radioactive phosphoric acid decontamination waste liquid and a method for treating the radioactive phosphoric acid decontamination waste liquid.

放射性汙染金屬廢棄物除了不銹鋼為大宗外,碳鋼亦為常用之核能建廠材料;因應核設施除役之放射性汙染金屬及老舊管件更換,因而產生大量需除汙之放射性金屬廢棄物須待處理。為解決上述之大量放射性金屬廢棄物問題,化學除污法針對不同金屬材質與除污技術之應用受到研究機構廣泛的注意。其中,針對不銹鋼,可使用磷酸、硫酸與硝酸混合應用於化學除污法,除污後可達到極低放射性廢棄物之標準。In addition to stainless steel being the bulk of radioactively contaminated metal waste, carbon steel is also a commonly used material for nuclear power plant construction; due to the replacement of radioactively contaminated metals and old pipe fittings in decommissioned nuclear facilities, a large amount of radioactive metal waste that needs to be decontaminated has to be deal with. In order to solve the above-mentioned problem of a large amount of radioactive metal waste, the application of chemical decontamination methods for different metal materials and decontamination technologies has received extensive attention from research institutions. Among them, for stainless steel, phosphoric acid, sulfuric acid and nitric acid can be used in the chemical decontamination method, which can reach the standard of extremely low radioactive waste after decontamination.

磷酸除污劑對於多種放射性金屬廢棄物具有良好之除污效果,其中磷酸與硝酸混合液適合銅與鋁材金屬廢棄物之除污,磷酸、硫酸與硝酸混合液適合於不銹鋼金屬廢棄物之電化學除污。當除污過程中金屬離子逐漸累積於除污劑中,達到一特定飽和濃度後,產生金屬鹽類之沉澱,其係影響除污效率或受核種污染而放射性增高,需進行再生。用過之磷酸除污劑可用草酸選擇性沉澱法、電解回收法與陽離子交換法,以去除金屬離子而達到除污劑回收再利用之目的。磷酸除污劑於回收再利用數次而不能再用之後,即為放射性磷酸除污廢液而被汰換下來。Phosphoric acid decontamination agent has a good decontamination effect on various radioactive metal wastes. Among them, the mixed solution of phosphoric acid and nitric acid is suitable for the decontamination of copper and aluminum metal wastes, and the mixed solution of phosphoric acid, sulfuric acid and nitric acid is suitable for the electrification of stainless steel metal wastes. Learn to decontaminate. During the decontamination process, metal ions gradually accumulate in the decontamination agent, and after reaching a certain saturation concentration, the precipitation of metal salts occurs, which affects the decontamination efficiency or is polluted by nuclear species and increases the radioactivity, and needs to be regenerated. Used phosphoric acid decontamination agent can use oxalic acid selective precipitation method, electrolytic recovery method and cation exchange method to remove metal ions and achieve the purpose of recycling and reuse of decontamination agent. After the phosphoric acid decontamination agent is recycled and reused several times and cannot be reused, it is the radioactive phosphoric acid decontamination waste liquid and is replaced.

習知放射性磷酸除污廢液之後處理方法包含選擇性沉澱法、直接中和沉澱法與水泥固化法等,然而以上處理技術具有缺點例如中和劑大量使用而提高二次廢棄物體積、水泥固化過程中大量放熱而無法大量處理廢液等。因此,有需要對以上缺點進行改進,以增進放射性磷酸除污廢液的處理效果。Conventional radioactive phosphoric acid decontamination waste liquid post-treatment methods include selective precipitation, direct neutralization precipitation and cement solidification, etc. However, the above treatment technologies have disadvantages such as the use of a large amount of neutralizer to increase the volume of secondary waste, cement solidification. A large amount of heat is released during the process, and a large amount of waste liquid cannot be processed. Therefore, it is necessary to improve the above shortcomings to improve the treatment effect of radioactive phosphoric acid decontamination waste liquid.

本發明之目的在於提供一種矽鋁氧複合物作為放射性磷酸除污廢液的固化劑的用途,可增進放射性磷酸除污廢液的處理效果。The purpose of the present invention is to provide the use of a silicon-alumina-oxygen compound as a curing agent for the radioactive phosphoric acid decontamination waste liquid, which can improve the treatment effect of the radioactive phosphoric acid decontamination waste liquid.

本發明之另一目的在於提供一種放射性磷酸除污廢液之處理方法,可減少廢棄物的體積。Another object of the present invention is to provide a method for treating waste liquid of radioactive phosphoric acid decontamination, which can reduce the volume of waste.

本發明放射性磷酸除污廢液之處理方法,供由放射性磷酸除污廢液製備形成放射性廢酸固化體,包含:將放射性磷酸除污廢液與第一水分混合攪拌以形成前置漿料,其中放射性廢酸固化體為100wt%,放射性磷酸除污廢液為60 wt%以上,第一水分為30wt%以下;將前置漿料與矽鋁氧複合物混合攪拌第一時間以形成固化漿料,其中放射性廢酸固化體為100wt%,矽鋁氧複合物為30wt%以上,且使前置漿料中水的重量與矽鋁氧複合物的重量兩者比值介於0.5~1,前置漿料中磷酸的莫耳數與矽鋁氧複合物中氧化鋁的莫耳數兩者比值介於1~1.9;將固化漿料於第一溫度以上靜置第二時間以形成放射性廢酸固化體。The method for treating the radioactive phosphoric acid decontamination waste liquid of the present invention is for preparing the radioactive waste acid solidified body from the radioactive phosphoric acid decontamination waste liquid, comprising: mixing and stirring the radioactive phosphoric acid decontamination waste liquid and the first moisture to form a pre-slurry, The radioactive waste acid solidified body is 100 wt%, the radioactive phosphoric acid decontamination waste liquid is more than 60 wt%, and the first moisture is less than 30 wt%; the pre-slurry and the silicon-aluminum-oxygen compound are mixed and stirred for the first time to form a solidified slurry material, wherein the radioactive waste acid solidified body is 100wt%, the silicon-aluminum-oxygen compound is more than 30wt%, and the ratio between the weight of water in the pre-slurry and the weight of the silicon-alumina-oxygen compound is between 0.5 and 1. The ratio between the molar number of phosphoric acid in the slurry and the molar number of alumina in the silicon-alumina-oxygen composite is between 1 and 1.9; the solidified slurry is allowed to stand above the first temperature for a second time to form radioactive waste acid solidified body.

在本發明的實施例中,放射性磷酸除污廢液中磷酸的含量為40wt%以上,水的含量為60wt%以下。In the embodiment of the present invention, the content of phosphoric acid in the radioactive phosphoric acid decontamination waste liquid is more than 40wt%, and the content of water is less than 60wt%.

在本發明的實施例中,矽鋁氧複合物選自包含偏高嶺土、Al2 O4 ‧SiO2 及其組合的群組。In an embodiment of the present invention, the silicon-alumina-oxygen composite is selected from the group comprising metakaolin, Al 2 O 4 ·SiO 2 and combinations thereof.

在本發明的實施例中,第一時間為10分鐘以上。In the embodiment of the present invention, the first time is more than 10 minutes.

在本發明的實施例中,第二時間為7天以上。In the embodiment of the present invention, the second time period is more than 7 days.

在本發明的實施例中,第一溫度介於25~45℃。In the embodiment of the present invention, the first temperature is between 25 and 45°C.

在本發明的實施例中,放射性廢酸固化體的體積與該放射性磷酸除污廢液的體積兩者比值1.1以下。In the embodiment of the present invention, the ratio between the volume of the solidified radioactive acid and the volume of the radioactive phosphoric acid decontamination waste liquid is 1.1 or less.

在本發明的實施例中,放射性廢酸固化體的強度為50kgf/m2 以上。In the embodiment of the present invention, the strength of the solidified body of radioactive waste acid is 50 kgf/m 2 or more.

本發明放射性磷酸除污廢液之處理方法,供由放射性磷酸除污廢液製備形成放射性廢酸固化體。如圖1所示的實施例流程示意圖,處理方法包含例如以下步驟。The method for treating radioactive phosphoric acid decontamination waste liquid of the present invention is for preparing a radioactive waste acid solidified body from the radioactive phosphoric acid decontamination waste liquid. As shown in the schematic flowchart of the embodiment shown in FIG. 1 , the processing method includes, for example, the following steps.

步驟1000,將放射性磷酸除污廢液與第一水分混合攪拌以形成前置漿料,此步驟可稱為前置漿料形成步驟。其中,放射性廢酸固化體為100wt%,放射性磷酸除污廢液為60 wt%以上,第一水分為30wt%以下。進一步而言,若放射性磷酸除污廢液不足60 wt%,將使得最終製備形成的放射性廢酸固化體的機械強度大幅降低。以較佳實施例而言,放射性磷酸除污廢液中磷酸的含量為40wt%以上,水的含量為60wt%以下,藉以確保原磷酸除污劑的除污效果以及最終製備形成的放射性廢酸固化體的機械強度。此外,原磷酸除污劑中可視需求添加例如硫酸、硝酸等,因此放射性磷酸除污廢液中可包含硫酸、硝酸等,而硫酸、硝酸等的含量較佳為5 wt%以下。另一方面,在一實施例中,第一水分可為0,亦即不加入第一水分,純粹以放射性磷酸除污廢液攪拌形成前置漿料。In step 1000, the radioactive phosphoric acid decontamination waste liquid and the first moisture are mixed and stirred to form a pre-slurry, and this step may be referred to as a pre-slurry forming step. Wherein, the solidified body of radioactive waste acid is 100wt%, the radioactive phosphoric acid decontamination waste liquid is more than 60wt%, and the first moisture is less than 30wt%. Furthermore, if the radioactive phosphoric acid decontamination waste liquid is less than 60 wt%, the mechanical strength of the finally prepared radioactive waste acid solidified body will be greatly reduced. In a preferred embodiment, the content of phosphoric acid in the radioactive phosphoric acid decontamination waste liquid is more than 40wt%, and the content of water is less than 60wt%, so as to ensure the decontamination effect of the original phosphoric acid decontamination agent and the final preparation of the radioactive waste acid formed. The mechanical strength of the cured body. In addition, sulfuric acid, nitric acid, etc. can be added to the orthophosphoric acid decontamination agent as needed, so the radioactive phosphoric acid decontamination waste liquid may contain sulfuric acid, nitric acid, etc., and the content of sulfuric acid, nitric acid, etc. is preferably 5 wt% or less. On the other hand, in one embodiment, the first water content may be 0, that is, the first water content is not added, and the pre-slurry is formed by stirring the waste liquid of radioactive phosphoric acid decontamination.

步驟3000,將前置漿料與矽鋁氧複合物混合攪拌第一時間以形成固化漿料,此步驟可稱為固化漿料形成步驟。換言之,是將矽鋁氧複合物粉體加入前置漿料中,配置適當水灰比、磷酸與氧化鋁莫耳比,水包含磷酸中的水與額外水,灰主要是矽鋁氧粉體,混鍊一段時間後形成固化漿料。其中,放射性廢酸固化體為100wt%,矽鋁氧複合物為30wt%以上,且使前置漿料中水的重量與矽鋁氧複合物的重量兩者比值介於0.5~1,前置漿料中磷酸的莫耳數與矽鋁氧複合物中氧化鋁的莫耳數兩者比值介於1~1.9,藉以確保最終製備形成的放射性廢酸固化體的機械強度。In step 3000, the pre-slurry is mixed and stirred with the silicon-alumina-oxygen compound for a first time to form a cured slurry. This step may be referred to as a curing slurry forming step. In other words, the silica-alumina composite powder is added to the pre-slurry, and the appropriate water-cement ratio, phosphoric acid and alumina molar ratio are configured. , and the solidified slurry is formed after mixing chains for a period of time. Among them, the radioactive waste acid solidified body is 100wt%, the silicon-aluminum-oxygen compound is more than 30wt%, and the ratio of the weight of water in the pre-slurry to the weight of the silicon-alumina-oxygen compound is between 0.5 and 1, and the pre-process The ratio between the molar number of phosphoric acid in the slurry and the molar number of alumina in the silicon-alumina-oxygen composite is between 1 and 1.9, so as to ensure the mechanical strength of the finally prepared radioactive waste acid solidified body.

進一步而言,若水灰比範圍>0.5與>1時,放射性廢酸固化體會因為黏度太高,空氣無法輕易流出,養成固化體時,會導致膨脹與龜裂,會大幅降低放射性廢酸固化體機械強度。更具體而言,在較佳實施例中,矽鋁氧複合物選自包含偏高嶺土、Al2 O4 ‧SiO2 及其組合的群組,第一時間為10分鐘以上。其中,若第一時間>10分鐘,磷酸還未溶解層狀結構之氧化鋁,導致整體放射性廢酸固化體品質太差,使機械強度大幅降低。Furthermore, if the water-cement ratio is in the range of >0.5 and >1, the solidified body of radioactive acid is too high in viscosity, and the air cannot easily flow out. Mechanical strength. More specifically, in a preferred embodiment, the silicon-alumina-oxygen composite is selected from the group comprising metakaolin, Al 2 O 4 ·SiO 2 and combinations thereof, and the first time is more than 10 minutes. Among them, if the first time is longer than 10 minutes, the phosphoric acid has not dissolved the alumina of the layered structure, resulting in the poor quality of the overall radioactive waste acid solidified body, and the mechanical strength is greatly reduced.

步驟5000,將固化漿料於第一溫度以上靜置第二時間以形成放射性廢酸固化體,此步驟可稱為固化體養成步驟。更具體而言,是將前述之固化漿料置於模具中,並於特定溫度範圍(第一溫度)與時間範圍(第二時間)乾燥至硬化而形成硬化固化體。其中,第二時間較佳為7天以上,第一溫度較佳介於25~45℃,藉以確保最終製備形成的放射性廢酸固化體的機械強度。機械強度範圍可達50 kgf/m2 以上。進一步而言,若溫度>25℃,黏結固化效率變差,若溫度>45℃,固化速度太快,易導致固化體崩解,均導致後續機械強度大幅下降。若是時間>7天,會導致黏結固化時間太短,亦導致機械強度大幅下降。In step 5000, the solidified slurry is allowed to stand at a temperature above the first temperature for a second time to form a solidified body of radioactive waste acid. This step may be referred to as a solidified body growing step. More specifically, the aforementioned solidified slurry is placed in a mold, and dried to harden in a specific temperature range (first temperature) and time range (second time) to form a hardened solidified body. Wherein, the second time is preferably more than 7 days, and the first temperature is preferably between 25 and 45° C., so as to ensure the mechanical strength of the finally prepared solidified body of radioactive waste acid. The range of mechanical strength can reach above 50 kgf/m 2 . Furthermore, if the temperature is higher than 25°C, the bonding and curing efficiency will be poor. If the temperature is higher than 45°C, the curing speed will be too fast, which will easily lead to the disintegration of the cured body, which will lead to a significant decrease in the subsequent mechanical strength. If the time is more than 7 days, the bonding and curing time will be too short, and the mechanical strength will also be greatly reduced.

基於上述,本發明放射性磷酸除污廢液之處理方法所製備的放射性廢酸固化體的強度為50kgf/m2 以上,放射性廢酸固化體的體積與放射性磷酸除污廢液的體積兩者比值1.1以下,亦即放射性磷酸除污廢液經固化處理後,體積增加約10%以內,且機械強度足夠。此外,因採用直接添加矽鋁氧複合物粉體固化劑,攪拌過程無產生任何溫度與急速硬化,對於後續放大處理加工性佳,且養成固化溫度不高,不浪費能源,且額外添加水量占比低。另一方面,以不同角度觀之,在處理方法中加入的矽鋁氧複合物,係作為放射性磷酸除污廢液的固化劑的用途。Based on the above, the strength of the solidified body of radioactive acid prepared by the treatment method of radioactive phosphoric acid decontamination waste liquid of the present invention is more than 50kgf/m 2 , and the ratio of the volume of the solidified body of radioactive acid to the volume of the waste liquid of radioactive phosphoric acid decontamination Below 1.1, that is, after the solidification treatment of radioactive phosphoric acid decontamination waste liquid, the volume increases within about 10%, and the mechanical strength is sufficient. In addition, due to the direct addition of silicon-alumina-oxygen composite powder curing agent, there is no temperature and rapid hardening during the stirring process. than lower. On the other hand, from a different perspective, the silicon-alumina-oxygen compound added in the treatment method is used as a curing agent for the radioactive phosphoric acid decontamination waste liquid.

以下對使用本發明放射性磷酸除污廢液之處理方法所製成的放射性廢酸固化體進行測試。The radioactive waste acid solidified body produced by the treatment method of the radioactive phosphoric acid decontamination waste liquid of the present invention is tested as follows.

實施例1:不同固化時間(第二時間)Example 1: Different curing times (second time)

取50 w/w%磷酸3.9kg、額外水750g與偏高嶺土3kg,水灰比為0.9,磷酸與氧化鋁莫耳比固定為1.52,以上所有物料混合與攪拌20分鐘(第一時間)後,倒入尺寸直徑50mm與高100mm模具內,分別填裝20個。將20個放置於45℃下固化,分別於1、2、5、7天(第二時間),取出5個放射性廢酸固化體,量測機械強度,每一個條件量測5顆放射性廢酸固化體,並取平均值,量測結果如圖2所示。Take 3.9 kg of 50 w/w% phosphoric acid, 750 g of extra water and 3 kg of metakaolin, the water-cement ratio is 0.9, and the molar ratio of phosphoric acid and alumina is fixed at 1.52. After mixing and stirring all the above materials for 20 minutes (the first time), Pour into molds with a size of 50mm in diameter and 100mm in height, and fill 20 pieces respectively. 20 pieces were cured at 45°C, and 5 pieces of radioactive waste acid solidified body were taken out at 1, 2, 5, and 7 days (second time) respectively, and the mechanical strength was measured, and 5 pieces of radioactive waste acid were measured under each condition. Cured body, and take the average value, the measurement results are shown in Figure 2.

如圖2所示,固化時間(第二時間)為1、2、5、7天所製備的放射性廢酸固化體的機械強度分別為45 kgf/cm2 、58 kgf/cm2 、62 kgf/cm2 與68 kgf/cm2 ,隨者養成時間增加,機械強度也會逐漸增加,養成固化時間約7天即可達到接近最大機械強度。As shown in Fig. 2, the mechanical strengths of the radioactive waste acid cured products prepared with curing time (second time) of 1, 2, 5, and 7 days were 45 kgf/cm 2 , 58 kgf/cm 2 , and 62 kgf/cm 2 , respectively. cm 2 and 68 kgf/cm 2 , as the growing time increases, the mechanical strength will gradually increase, and the growing curing time can reach close to the maximum mechanical strength in about 7 days.

實施例2:不同水灰比Example 2: Different water-cement ratios

取50 wt%磷酸1040g與偏高嶺土800g,上述條件每批分別添加第一水分為0、81.26g、201.26g、281.3g,可調整水灰比為0.65、0.75、0.90、1,磷酸與氧化鋁莫耳比固定為1.52,以上所有物料混合與攪拌20分後,倒入尺寸直徑50mm與高100mm模具內,分別填裝20個。將20個放置於45℃下固化,固化時間(第二時間)為7天,取出放射性廢酸固化體,量測機械強度,每一個條件量測5顆放射性廢酸固化體,並取平均值,量測結果如圖3所示。Take 1040g of 50 wt% phosphoric acid and 800g of metakaolin, the above conditions are added in each batch of the first water to be 0, 81.26g, 201.26g, 281.3g respectively, the adjustable water-cement ratio is 0.65, 0.75, 0.90, 1, phosphoric acid and alumina The molar ratio is fixed at 1.52. After mixing and stirring all the above materials for 20 minutes, pour them into a mold with a size of 50mm in diameter and a height of 100mm, and fill 20 pieces respectively. Place 20 pieces to cure at 45°C, the cure time (second time) is 7 days, take out the solidified body of radioactive acid, measure the mechanical strength, measure 5 pieces of solidified body of radioactive acid for each condition, and take the average value , the measurement results are shown in Figure 3.

如圖3所示,放射性廢酸固化體之機械強度會隨者水灰比增加而逐漸下降,分別為85 kgf/cm2 、77 kgf/cm2 、68 kgf/cm2 、55kgf/cm2 ,除了水灰比為0.65外,其他固化體在養成溫度在45度下,可維持良好固化體,主要是水灰比0.65下,水較少情況,養成溫度較高,固化速度較快,導致固化體有裂痕,然而水愈多在整體的固化體中,會影影固化體凝結速度,並產生許多孔隙在固化體中,導致水灰比愈高,機械強度會往下降。As shown in Figure 3, the mechanical strength of the radioactive waste acid solidified body will gradually decrease with the increase of the water-cement ratio, which are 85 kgf/cm 2 , 77 kgf/cm 2 , 68 kgf/cm 2 , and 55 kgf/cm 2 , respectively. Except for the water-cement ratio of 0.65, other solidified bodies can maintain a good solidified body when the growing temperature is 45 degrees, mainly when the water-cement ratio is 0.65, when there is less water, the growing temperature is higher, and the curing speed is faster, resulting in solidification There are cracks in the body, but the more water in the solid body as a whole, it will affect the coagulation speed of the solid body, and generate many pores in the solid body, resulting in a higher water-cement ratio and a decrease in mechanical strength.

實施例3:不同磷酸與氧化鋁莫耳比Example 3: Different Phosphoric Acid to Alumina Molar Ratios

調整磷酸與氧化鋁莫耳比為1.52、1.65、1.75、1.85,水灰比為0.65與偏高嶺土800g,以上所有物料混合與攪拌20分後,倒入尺寸直徑50mm與高100mm模具內,分別填裝20個。將20個放置於25℃固化,固化時間(第二時間)為7天,取出放射性廢酸固化體,量測機械強度,每一個條件量測5顆放射性廢酸固化體,並取平均值,量測結果如圖4所示。Adjust the molar ratio of phosphoric acid and alumina to 1.52, 1.65, 1.75, and 1.85, the water-cement ratio to 0.65 and 800g of metakaolin. After mixing and stirring all the above materials for 20 minutes, pour them into a mold with a size of 50mm in diameter and a height of 100mm, and fill them respectively. Pack 20. Place 20 pieces at 25°C for curing, the curing time (second time) is 7 days, take out the solidified body of radioactive waste acid, measure the mechanical strength, measure 5 pieces of solidified body of radioactive waste acid under each condition, and take the average value, The measurement results are shown in Figure 4.

如圖4所示,機械強度隨者磷酸莫耳數增加而提高,機械強度分別為101 kgf/cm2 、124 kgf/cm2 、130 kgf/cm2 與148 kgf/cm2 ,主要是磷酸在整體放射性廢酸固化體濃度愈高,可有效溶解偏高嶺土中的氧化鋁,可有效反正聚合機械強度較高之固化體,並且將水量調整至最低,因此採用磷酸與氧化鋁莫耳數高配方為優先,機械強度較高。As shown in Figure 4, the mechanical strength increases with the increase of the molar number of phosphate, and the mechanical strengths are 101 kgf/cm 2 , 124 kgf/cm 2 , 130 kgf/cm 2 and 148 kgf/cm 2 , respectively. The higher the overall concentration of the radioactive waste acid solidified body, the more effective it can dissolve the alumina in metakaolin, the more solidified body with higher mechanical strength can be effectively polymerized, and the amount of water is adjusted to a minimum, so phosphoric acid and alumina are used. High molar formula As a priority, the mechanical strength is higher.

實施例4:不同養成固化溫度Example 4: Different growing curing temperatures

取50 w/w%磷酸3.9kg、第一水分750g與偏高嶺土3kg,水灰比為0.9,磷酸與氧化鋁莫耳比固定為1.52,以上所有物料混合與攪拌20分後,倒入尺寸直徑50mm與高100mm模具內,分別填裝20個。每5個放置在35℃、45℃、65℃、75℃固化,固化時間(第二時間)為7天,取出放射性廢酸固化體觀察。如圖5所示,由左至右分別為在35℃、45℃、65℃、75℃固化的放射性廢酸固化體,可以清楚看出在>45℃固化的放射性廢酸固化體有明顯裂痕。Take 3.9 kg of 50 w/w% phosphoric acid, 750 g of the first moisture and 3 kg of metakaolin, the water-cement ratio is 0.9, and the molar ratio of phosphoric acid and alumina is fixed at 1.52. After mixing and stirring all the above materials for 20 minutes, pour the size diameter 50mm and 100mm high molds are filled with 20 pieces respectively. Every 5 pieces were placed at 35°C, 45°C, 65°C, and 75°C for curing, and the curing time (second time) was 7 days, and the radioactive waste acid cured body was taken out for observation. As shown in Figure 5, from left to right are the solidified radioactive acid solidified at 35 °C, 45 °C, 65 °C, and 75 °C, respectively. It can be clearly seen that the solidified radioactive acid solidified at >45 °C has obvious cracks .

雖然前述的描述及圖式已揭示本發明之較佳實施例,必須瞭解到各種增添、許多修改和取代可能使用於本發明較佳實施例,而不會脫離如所附申請專利範圍所界定的本發明原理之精神及範圍。熟悉本發明所屬技術領域之一般技藝者將可體會,本發明可使用於許多形式、結構、佈置、比例、材料、元件和組件的修改。因此,本文於此所揭示的實施例應被視為用以說明本發明,而非用以限制本發明。本發明的範圍應由後附申請專利範圍所界定,並涵蓋其合法均等物,並不限於先前的描述。Although the foregoing description and drawings have disclosed preferred embodiments of the present invention, it must be understood that various additions, numerous modifications and substitutions may be made to the preferred embodiments of the present invention without departing from the scope of the appended claims The spirit and scope of the principles of the present invention. Those of ordinary skill in the art to which this invention pertains will appreciate that the invention is capable of many modifications in form, structure, arrangement, proportions, materials, elements and assemblies. Therefore, the embodiments disclosed herein should be considered to illustrate the present invention, rather than to limit the present invention. The scope of the present invention shall be defined by the appended claims, including their legal equivalents, and not limited to the foregoing description.

(無)(none)

圖1為本發明方法的實施例流程示意圖。FIG. 1 is a schematic flowchart of an embodiment of the method of the present invention.

圖2為本發明方法以不同固化時間所得之放射性廢酸固化體的機械強度量測結果。FIG. 2 is the measurement result of the mechanical strength of the radioactive waste acid solidified body obtained by the method of the present invention with different curing times.

圖3為本發明方法以不同水灰比所得之放射性廢酸固化體的機械強度量測結果。FIG. 3 is the measurement result of the mechanical strength of the solidified body of radioactive waste acid obtained by the method of the present invention with different water-cement ratios.

圖4為本發明方法以不同磷酸與氧化鋁莫耳比所得之放射性廢酸固化體的機械強度量測結果。FIG. 4 is the measurement result of the mechanical strength of the solidified body of radioactive waste acid obtained by the method of the present invention with different molar ratios of phosphoric acid and alumina.

圖5為本發明方法以不同固化溫度所得之放射性廢酸固化體的相片。Figure 5 is a photograph of the solidified body of radioactive waste acid obtained by the method of the present invention at different curing temperatures.

(無)(none)

Claims (10)

一種矽鋁氧複合物作為放射性磷酸除污廢液的固化劑的用途,其中放射性磷酸除污廢液中磷酸的含量為40wt%以上,水的含量為60wt%以下。 A use of a silicon-alumina-oxygen compound as a curing agent for radioactive phosphoric acid decontamination waste liquid, wherein the content of phosphoric acid in the radioactive phosphoric acid decontamination waste liquid is more than 40wt%, and the water content is less than 60wt%. 如請求項1所述的用途,其中該矽鋁氧複合物選自包含偏高嶺土、Al2O4‧SiO2及其組合的群組。 The use as claimed in claim 1, wherein the silicon-alumina-oxygen composite is selected from the group comprising metakaolin, Al 2 O 4 ·SiO 2 and combinations thereof. 一種放射性磷酸除污廢液的處理方法,供由一放射性磷酸除污廢液製備形成一放射性廢酸固化體,包含:將該放射性磷酸除污廢液與一第一水分混合攪拌以形成一前置漿料,其中該放射性廢酸固化體為100wt%,該放射性磷酸除污廢液為60wt%以上,該第一水分為30wt%以下;將該前置漿料與一矽鋁氧複合物混合攪拌一第一時間以形成一固化漿料,其中該放射性廢酸固化體為100wt%,該矽鋁氧複合物為30wt%以上,且使該前置漿料中水的重量與該矽鋁氧複合物的重量兩者比值介於0.5~1,該前置漿料中磷酸的莫耳數與該矽鋁氧複合物中氧化鋁的莫耳數兩者比值介於1~1.9;將該固化漿料於一第一溫度以上靜置一第二時間以形成該放射性廢酸固化體。 A method for treating radioactive phosphoric acid decontamination waste liquid, for preparing a radioactive waste acid solidified body from a radioactive phosphoric acid decontamination waste liquid, comprising: mixing and stirring the radioactive phosphoric acid decontamination waste liquid with a first moisture to form a Putting slurry, wherein the solidified body of radioactive waste acid is 100wt%, the radioactive phosphoric acid decontamination waste liquid is more than 60wt%, and the first moisture is less than 30wt%; the pre-slurry is mixed with a silicon-aluminum-oxygen compound Stir for a first time to form a solidified slurry, wherein the solidified body of the radioactive waste acid is 100wt%, the silicon-alumina-oxygen compound is more than 30wt%, and the weight of the water in the pre-slurry is equal to the silicon-alumina-oxygen The weight ratio of the composite is between 0.5 and 1, and the ratio of the molar number of phosphoric acid in the pre-slurry to the molar number of alumina in the silicon-alumina-oxygen composite is between 1 and 1.9; the curing The slurry is allowed to stand above a first temperature for a second time to form the solidified body of radioactive waste acid. 如請求項3所述的處理方法,其中該放射性磷酸除污廢液中磷酸的含量為40wt%以上,水的含量為60wt%以下。 The treatment method according to claim 3, wherein the content of phosphoric acid in the radioactive phosphoric acid decontamination waste liquid is more than 40wt%, and the content of water is less than 60wt%. 如請求項3所述的處理方法,其中該矽鋁氧複合物選自包含偏高嶺土、Al2O4‧SiO2及其組合的群組。 The processing method of claim 3, wherein the silicon-alumina-oxygen composite is selected from the group consisting of metakaolin, Al 2 O 4 ·SiO 2 and combinations thereof. 如請求項3所述的處理方法,其中該第一時間為10分鐘以上。 The processing method according to claim 3, wherein the first time is more than 10 minutes. 如請求項3所述的處理方法,其中該第一溫度介於25~45℃。 The processing method according to claim 3, wherein the first temperature is between 25°C and 45°C. 如請求項3所述的處理方法,其中該第一溫度為25℃,該第二時間為7天以上。 The processing method according to claim 3, wherein the first temperature is 25°C, and the second time is more than 7 days. 如請求項3所述的處理方法,其中該放射性廢酸固化體的體積與該放射性磷酸除污廢液的體積兩者比值1.1以下。 The treatment method according to claim 3, wherein the ratio of the volume of the solidified radioactive acid to the volume of the radioactive phosphoric acid decontamination waste liquid is 1.1 or less. 如請求項3所述的處理方法,其中該放射性廢酸固化體的強度為50kgf/m2以上。The processing method according to claim 3, wherein the strength of the solidified body of radioactive waste acid is 50 kgf/m 2 or more.
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