JP2019178962A - Cartridge for processing radioactive waste liquid - Google Patents
Cartridge for processing radioactive waste liquid Download PDFInfo
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- JP2019178962A JP2019178962A JP2018068506A JP2018068506A JP2019178962A JP 2019178962 A JP2019178962 A JP 2019178962A JP 2018068506 A JP2018068506 A JP 2018068506A JP 2018068506 A JP2018068506 A JP 2018068506A JP 2019178962 A JP2019178962 A JP 2019178962A
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- cartridge
- waste liquid
- inorganic binder
- radioactive waste
- boric acid
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- 239000007788 liquid Substances 0.000 title claims abstract description 21
- 239000002901 radioactive waste Substances 0.000 title claims abstract description 20
- 239000011230 binding agent Substances 0.000 claims abstract description 22
- 239000003365 glass fiber Substances 0.000 claims abstract description 19
- 239000004327 boric acid Substances 0.000 claims abstract description 18
- BTBUEUYNUDRHOZ-UHFFFAOYSA-N Borate Chemical compound [O-]B([O-])[O-] BTBUEUYNUDRHOZ-UHFFFAOYSA-N 0.000 claims abstract description 4
- 125000005619 boric acid group Chemical group 0.000 claims abstract 2
- 239000010808 liquid waste Substances 0.000 claims description 6
- 230000002285 radioactive effect Effects 0.000 claims description 6
- 230000008595 infiltration Effects 0.000 abstract description 9
- 238000001764 infiltration Methods 0.000 abstract description 9
- 230000004927 fusion Effects 0.000 abstract description 4
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 16
- 235000010338 boric acid Nutrition 0.000 description 16
- 239000000835 fiber Substances 0.000 description 15
- 230000000052 comparative effect Effects 0.000 description 6
- 238000011156 evaluation Methods 0.000 description 6
- 230000035515 penetration Effects 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- CDBYLPFSWZWCQE-UHFFFAOYSA-L Sodium Carbonate Chemical compound [Na+].[Na+].[O-]C([O-])=O CDBYLPFSWZWCQE-UHFFFAOYSA-L 0.000 description 2
- 230000007423 decrease Effects 0.000 description 2
- 238000010828 elution Methods 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- BWHMMNNQKKPAPP-UHFFFAOYSA-L potassium carbonate Substances [K+].[K+].[O-]C([O-])=O BWHMMNNQKKPAPP-UHFFFAOYSA-L 0.000 description 2
- FGIUAXJPYTZDNR-UHFFFAOYSA-N potassium nitrate Chemical compound [K+].[O-][N+]([O-])=O FGIUAXJPYTZDNR-UHFFFAOYSA-N 0.000 description 2
- 238000002791 soaking Methods 0.000 description 2
- VWDWKYIASSYTQR-UHFFFAOYSA-N sodium nitrate Chemical compound [Na+].[O-][N+]([O-])=O VWDWKYIASSYTQR-UHFFFAOYSA-N 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- WHXSMMKQMYFTQS-UHFFFAOYSA-N Lithium Chemical compound [Li] WHXSMMKQMYFTQS-UHFFFAOYSA-N 0.000 description 1
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 1
- 239000004111 Potassium silicate Substances 0.000 description 1
- 239000004115 Sodium Silicate Substances 0.000 description 1
- PMZURENOXWZQFD-UHFFFAOYSA-L Sodium Sulfate Chemical compound [Na+].[Na+].[O-]S([O-])(=O)=O PMZURENOXWZQFD-UHFFFAOYSA-L 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 239000004110 Zinc silicate Substances 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 229910021538 borax Inorganic materials 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 150000001642 boronic acid derivatives Chemical class 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000018044 dehydration Effects 0.000 description 1
- 238000006297 dehydration reaction Methods 0.000 description 1
- ZOIVSVWBENBHNT-UHFFFAOYSA-N dizinc;silicate Chemical compound [Zn+2].[Zn+2].[O-][Si]([O-])([O-])[O-] ZOIVSVWBENBHNT-UHFFFAOYSA-N 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 229910052744 lithium Inorganic materials 0.000 description 1
- PAZHGORSDKKUPI-UHFFFAOYSA-N lithium metasilicate Chemical compound [Li+].[Li+].[O-][Si]([O-])=O PAZHGORSDKKUPI-UHFFFAOYSA-N 0.000 description 1
- 229910052912 lithium silicate Inorganic materials 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 150000007522 mineralic acids Chemical class 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 229910017604 nitric acid Inorganic materials 0.000 description 1
- 238000011056 performance test Methods 0.000 description 1
- 229910000027 potassium carbonate Inorganic materials 0.000 description 1
- 235000011181 potassium carbonates Nutrition 0.000 description 1
- 235000010333 potassium nitrate Nutrition 0.000 description 1
- 239000004323 potassium nitrate Substances 0.000 description 1
- NNHHDJVEYQHLHG-UHFFFAOYSA-N potassium silicate Chemical compound [K+].[K+].[O-][Si]([O-])=O NNHHDJVEYQHLHG-UHFFFAOYSA-N 0.000 description 1
- 229910052913 potassium silicate Inorganic materials 0.000 description 1
- 235000019353 potassium silicate Nutrition 0.000 description 1
- OTYBMLCTZGSZBG-UHFFFAOYSA-L potassium sulfate Chemical compound [K+].[K+].[O-]S([O-])(=O)=O OTYBMLCTZGSZBG-UHFFFAOYSA-L 0.000 description 1
- 229910052939 potassium sulfate Inorganic materials 0.000 description 1
- 235000011151 potassium sulphates Nutrition 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 238000005204 segregation Methods 0.000 description 1
- 150000004760 silicates Chemical class 0.000 description 1
- RMAQACBXLXPBSY-UHFFFAOYSA-N silicic acid Chemical compound O[Si](O)(O)O RMAQACBXLXPBSY-UHFFFAOYSA-N 0.000 description 1
- 235000012239 silicon dioxide Nutrition 0.000 description 1
- 229910000029 sodium carbonate Inorganic materials 0.000 description 1
- 235000017550 sodium carbonate Nutrition 0.000 description 1
- 235000010344 sodium nitrate Nutrition 0.000 description 1
- 239000004317 sodium nitrate Substances 0.000 description 1
- NTHWMYGWWRZVTN-UHFFFAOYSA-N sodium silicate Chemical compound [Na+].[Na+].[O-][Si]([O-])=O NTHWMYGWWRZVTN-UHFFFAOYSA-N 0.000 description 1
- 229910052911 sodium silicate Inorganic materials 0.000 description 1
- 235000019794 sodium silicate Nutrition 0.000 description 1
- 229910052938 sodium sulfate Inorganic materials 0.000 description 1
- 235000011152 sodium sulphate Nutrition 0.000 description 1
- 235000010339 sodium tetraborate Nutrition 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- WUUHFRRPHJEEKV-UHFFFAOYSA-N tripotassium borate Chemical compound [K+].[K+].[K+].[O-]B([O-])[O-] WUUHFRRPHJEEKV-UHFFFAOYSA-N 0.000 description 1
- BSVBQGMMJUBVOD-UHFFFAOYSA-N trisodium borate Chemical compound [Na+].[Na+].[Na+].[O-]B([O-])[O-] BSVBQGMMJUBVOD-UHFFFAOYSA-N 0.000 description 1
- BIKXLKXABVUSMH-UHFFFAOYSA-N trizinc;diborate Chemical compound [Zn+2].[Zn+2].[Zn+2].[O-]B([O-])[O-].[O-]B([O-])[O-] BIKXLKXABVUSMH-UHFFFAOYSA-N 0.000 description 1
- 229910021642 ultra pure water Inorganic materials 0.000 description 1
- 239000012498 ultrapure water Substances 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
- 235000019352 zinc silicate Nutrition 0.000 description 1
Landscapes
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
Abstract
Description
本発明は、放射性廃液を廃棄処分するに際し、被処理物の放射性廃液を含浸させて加熱溶融し、ガラス固化させるのに使用される放射性廃液処理用カートリッジに関する。 The present invention relates to a radioactive waste liquid treatment cartridge that is used for impregnating a radioactive waste liquid of an object to be processed, heat-melting it, and vitrifying it when the radioactive waste liquid is disposed of.
原子力発電において使用された使用済み燃料を再処理工場において再処理するに際して、ウラン、超ウラン元素及び核分裂生成物を含んだ硝酸を含む高レベル放射性廃液が副生する。 When the spent fuel used in nuclear power generation is reprocessed in a reprocessing plant, high-level radioactive liquid waste containing nitric acid containing uranium, transuranium elements and fission products is by-produced.
例えば、特許文献１には、充分な圧縮強度や衝撃強度を保有し、外観の毛羽立ちも少なく保管する際の形状安定性も高く、大量生産に向いた放射性廃液処理用ガラスファイバーカートリッジが開示されている。 For example, Patent Document 1 discloses a glass fiber cartridge for radioactive waste liquid treatment that possesses sufficient compressive strength and impact strength, has low fluffing appearance, has high shape stability when stored, and is suitable for mass production. Yes.
しかし、特許文献１のカートリッジは、カートリッジへの廃液の染込性が十分ではなく、さらなる改良が求められていた。 However, the cartridge of Patent Document 1 has not been sufficiently impregnated with waste liquid into the cartridge, and further improvement has been demanded.
本発明はこのような事情を考慮してなされたもので、染込性に優れた放射性廃液処理用カートリッジを提供することを目的とする。 The present invention has been made in view of such circumstances, and an object of the present invention is to provide a radioactive waste liquid treatment cartridge excellent in infiltration.
本発明に係る放射性廃液処理用カートリッジは、上述した課題を解決するために、ガラス繊維と、ガラス繊維を融着させる無機結合剤と、を備え、所定形状に成形された放射性廃液処理用カートリッジであり、前記無機結合剤を、０．０４０〜０．０５５ｇ/ｃｍ３含有することを特徴とする。 In order to solve the above-mentioned problem, the radioactive waste liquid treatment cartridge according to the present invention is a radioactive waste liquid treatment cartridge which is formed into a predetermined shape, and includes glass fibers and an inorganic binder for fusing the glass fibers. Yes, the inorganic binder is contained in an amount of 0.040 to 0.055 g / cm 3 .
本発明に係る放射性廃液処理用カートリッジにおいては、優れた染込性を有することができる。 The radioactive waste liquid treatment cartridge according to the present invention can have excellent infiltration properties.
本発明の放射性廃液処理用カートリッジ（以下、単に「カートリッジ」という。）は、ガラス繊維と、ガラス繊維を融着させる無機結合剤と、を備えている。カートリッジは、例えば直径７０ｍｍ、高さ７０ｍｍの円柱形状などの所定形状に成形されている。カートリッジは、無機結合剤を、０．０４０〜０．０５５ｇ/ｃｍ３含有している。無機結合剤の含有量は、例えばカートリッジから既定形状（例えば縦２０ｍｍ、横２０ｍｍ、高さ２０ｍｍの立方体）の試験体を抽出し、試験体について無機結合剤の含有量を確認することにより行われる。含有量が０．０４０ｇ/ｃｍ３以下の場合は圧縮強度、衝撃強度が低くなり、０．０５５ｇ/ｃｍ３以上の場合は染込性が低くなる。
また、無機結合剤は、カートリッジ全体にわたり圧縮強度、衝撃強度及び染込性を備えるために、カートリッジ全体にわたり均一にバラツキなく含有されていることが好ましい。バラツキは、例えば、上述した試験体を１０体切り出して、無機結合剤の含有量に関する標準偏差を算出することにより測定することができる。カートリッジから切り出された試験体間における無機結合剤の含有量の標準偏差は、０．４ｇ/ｃｍ３以下であることが好ましい。標準偏差が０．４ｇ/ｃｍ３を超える場合、無機結合剤の偏析が大きく、カートリッジの染込性が低くなるためである。
A cartridge for treating radioactive liquid waste according to the present invention (hereinafter simply referred to as “cartridge”) includes glass fibers and an inorganic binder for fusing the glass fibers. The cartridge is molded into a predetermined shape such as a cylindrical shape having a diameter of 70 mm and a height of 70 mm. The cartridge contains 0.040 to 0.055 g / cm 3 of an inorganic binder. The content of the inorganic binder is performed, for example, by extracting a test specimen having a predetermined shape (for example, a cube having a length of 20 mm, a width of 20 mm, and a height of 20 mm) from the cartridge and confirming the content of the inorganic binder for the test specimen. . When the content is 0.040 g / cm 3 or less, the compressive strength and impact strength are low, and when the content is 0.055 g / cm 3 or more, the infiltration property is low.
In addition, the inorganic binder is preferably contained uniformly throughout the entire cartridge in order to have compressive strength, impact strength, and penetration through the entire cartridge. The variation can be measured, for example, by cutting out 10 test specimens described above and calculating a standard deviation regarding the content of the inorganic binder. The standard deviation of the content of the inorganic binder between the test specimens cut out from the cartridge is preferably 0.4 g / cm 3 or less. This is because when the standard deviation exceeds 0.4 g / cm 3 , the segregation of the inorganic binder is large and the infiltration property of the cartridge becomes low.
ガラス繊維としては、繊維径が０．５〜４０μｍ、繊維長が０．５〜２２ｍｍの範囲のものを使用できる。その中でも、残留応力、形状安定性及び染込速度等の特性全体を満足でき、生産性も満足できるという観点から、繊維径が７〜１５μｍ、繊維長が１〜１５ｍｍの範囲で、アスペクト比が１００〜１９００となるような組み合わせを選択するのが好ましい。ここで、前記アスペクト比は、次ぎのように定義される値である。
アスペクト比＝繊維長（ｍｍ）÷繊維径（ｍｍ）
As the glass fiber, one having a fiber diameter of 0.5 to 40 μm and a fiber length of 0.5 to 22 mm can be used. Among them, from the viewpoint of satisfying the entire characteristics such as residual stress, shape stability, and infiltration rate, and satisfying productivity, the fiber diameter is 7 to 15 μm, the fiber length is 1 to 15 mm, and the aspect ratio is It is preferable to select a combination that will be 100-1900. Here, the aspect ratio is a value defined as follows.
Aspect ratio = fiber length (mm) ÷ fiber diameter (mm)
例えば、繊維径が１１．５μｍの場合は、繊維長が１．２〜１５ｍｍの範囲においてアスペクト比が１００〜１９００の範囲内とすることができる。この繊維長の範囲で、残留応力、形状安定性及び染込性等の特性全体を満足できるものとなるが、その中でも、特に繊維長は３〜６ｍｍの範囲とすることが好ましい。 For example, when the fiber diameter is 11.5 μm, the aspect ratio can be in the range of 100 to 1900 in the range of the fiber length of 1.2 to 15 mm. Within this range of fiber length, the entire characteristics such as residual stress, shape stability, and dyeability can be satisfied. Among these, the fiber length is particularly preferably in the range of 3 to 6 mm.
アスペクト比が１００未満となる繊維長０．５ｍｍ未満では、加熱融着時に繊維同士の接着が少なくなり、落下した際の粉落ちが多くなる。また、アスペクト比が１９００を超える繊維長２２ｍｍ超えでは、ガラス繊維を型に入れ、加熱融着させた際に残留応力が残りやすく、落下させた際の割れが生じやすいものとなる。 When the fiber length is less than 0.5 mm at which the aspect ratio is less than 100, the adhesion between the fibers decreases at the time of heat-sealing, and the powder falling off when falling is increased. On the other hand, when the fiber length exceeds 22 mm and the aspect ratio exceeds 1900, residual stress tends to remain when glass fibers are put into a mold and heat-sealed, and cracks are likely to occur when dropped.
本発明カートリッジを構成するガラス繊維の密度は２４０〜２６０ｋｇ／ｍ３となるように調整するのが好ましい。密度が２４０ｋｇ／ｍ３未満の場合には、十分な圧縮強度が得られない。また、密度が２６０ｋｇ／ｍ３を超えると、放射性廃液の染込量が少なくなる。 The density of the glass fibers constituting the cartridge of the present invention is preferably adjusted so as to be 240 to 260 kg / m 3 . When the density is less than 240 kg / m 3 , sufficient compressive strength cannot be obtained. On the other hand, when the density exceeds 260 kg / m 3 , the infiltration amount of the radioactive liquid waste decreases.
本発明の無機質結合剤としては、特に限定されるものではないが、ホウ酸、ケイ酸や、ケイ酸ナトリウム、ケイ酸カリウム、ケイ酸リチウム、ケイ酸亜鉛、ホウ酸ナトリウム、ホウ酸カリウム、ホウ酸リチウム、ホウ酸亜鉛等のケイ酸塩やホウ酸塩の使用が好ましいが、硝酸ナトリウム、硫酸ナトリウム、炭酸ナトリウム、硝酸カリウム、硫酸カリウム、炭酸カリウム等の各種無機酸、無機塩が使用可能である。 The inorganic binder of the present invention is not particularly limited, but boric acid, silicic acid, sodium silicate, potassium silicate, lithium silicate, zinc silicate, sodium borate, potassium borate, boron It is preferable to use silicates and borates such as lithium acid and zinc borate, but various inorganic acids and salts such as sodium nitrate, sodium sulfate, sodium carbonate, potassium nitrate, potassium sulfate, and potassium carbonate can be used. .
特に、放射性廃液処理用カートリッジにおいて、組成のバランスが崩れないという理由でホウ酸またはホウ酸塩（ホウ酸系）であることが好ましい。 In particular, in the cartridge for radioactive liquid waste treatment, boric acid or borate (boric acid type) is preferable because the balance of the composition is not lost.
次ぎに、本発明に係る放射性廃液処理用カートリッジの実施例を、比較例と共に説明する。 Next, examples of the radioactive waste liquid treatment cartridge according to the present invention will be described together with comparative examples.
実施例１から３として、ホウ酸の含有量が０．０４０〜０．０５５ｇ/ｃｍ３の範囲に入るようにするために、脱水処理時にカートリッジ全体に均一に加熱されるように加熱処理を行った。シート状に形成せずに、繊維長がある程度均一になるように解繊し、表１に示すようにアスペクト比が１００〜１９００の範囲内となるように調整した各種ガラス繊維を型に入れ、ガラス繊維の密度が２５０ｋｇ／ｍ３となるように型内に充填した。次に、加熱融着温度７００℃、加熱融着時間３０分間の条件で、加熱融着してガラス繊維を融着し、直径７０ｍｍ、高さ７０ｍｍの円柱形状のガラスファイバー製のカートリッジを作成した。 In Examples 1 to 3, heat treatment was performed so that the entire cartridge was uniformly heated during the dehydration process so that the boric acid content was in the range of 0.040 to 0.055 g / cm 3. It was. Without forming into a sheet shape, the fiber length is defibrated so that the fiber length is uniform to some extent, and various glass fibers adjusted so that the aspect ratio is in the range of 100 to 1900 as shown in Table 1 are put into a mold, The mold was filled so that the density of the glass fiber was 250 kg / m 3 . Next, the glass fiber was fused by heat fusion under the conditions of a heat fusion temperature of 700 ° C. and a heat fusion time of 30 minutes, thereby producing a cylindrical glass fiber cartridge having a diameter of 70 mm and a height of 70 mm. .
比較例１から３として、ホウ酸の含有量が０．０４０〜０．０５５ｇ/ｃｍ３の範囲を外れるようにしたこと以外は実施例１から３と同様にしてガラスファイバー製のカートリッジを作成した。特に比較例３については、後述する方法で測定されるホウ酸の含有量の標準偏差が０．４ｇ/ｃｍ３以上となるカートリッジを作成した。 As Comparative Examples 1 to 3, glass fiber cartridges were prepared in the same manner as in Examples 1 to 3 except that the boric acid content was out of the range of 0.040 to 0.055 g / cm 3 . . In particular, for Comparative Example 3, a cartridge was prepared in which the standard deviation of the boric acid content measured by the method described later is 0.4 g / cm 3 or more.
得られた実施例１から３、比較例１から３の各カートリッジについて、性能試験を実施した。その結果を下表に示す。 A performance test was performed on each of the obtained cartridges of Examples 1 to 3 and Comparative Examples 1 to 3. The results are shown in the table below.
表１中のホウ酸含有量（溶出量）、硬さ（圧縮強度）、衝撃強度、染込性、総合評価については、次のようにして評価した。 The boric acid content (elution amount), hardness (compressive strength), impact strength, penetration, and comprehensive evaluation in Table 1 were evaluated as follows.
１．ホウ酸含有量（溶出量）
容器内に超純水を約１５０ｍｌ入れ、その中にカートリッジ（直径７０ｍｍ、高さ７０ｍｍ）から切り出した立方体の試験体（縦２０ｍｍ、横２０ｍｍ、高さ２０ｍｍ）を浸漬させ、溶出液をＩＣＰ−ＭＳ（Agilent社製7500S）にて分析した。
バラツキは、上述した試験体１０体のホウ酸含有量に関する標準偏差を算出することにより測定した。
1. Boric acid content (elution amount)
About 150 ml of ultrapure water is placed in a container, and a cubic specimen (length 20 mm, width 20 mm, height 20 mm) cut out from a cartridge (diameter 70 mm, height 70 mm) is immersed therein, and the eluate is ICP- The analysis was performed by MS (Agilent 7500S).
The variation was measured by calculating the standard deviation regarding the boric acid content of the 10 specimens described above.
２．硬さ（圧縮強度）
カートリッジの直径方向に１０ｋｇの荷重を掛け、その際のカートリッジの変化量を測定した。求められる強度は変形量５ｍｍ以下とし、評価基準は次のようにした。
○：変化量が３ｍｍ未満、△：変化量が３〜５ｍｍ、×：変化量が５ｍｍ超え
2. Hardness (compressive strength)
A load of 10 kg was applied in the diameter direction of the cartridge, and the amount of change of the cartridge at that time was measured. The required strength was a deformation amount of 5 mm or less, and the evaluation criteria were as follows.
○: Change amount is less than 3 mm, Δ: Change amount is 3 to 5 mm, ×: Change amount is more than 5 mm
３．衝撃強度
垂直に立てた直径８０ｍｍ、長さ３０００ｍｍのパイプの中に２０個のカートリッジを一度に落下させ、最下部のカートリッジの欠損状態を確認した。評価基準は次のようにした。
○：変化なし、△：やや膨らみ等が発生、×：明らかに欠け、変形、クラックが発生
3. Impact strength Twenty cartridges were dropped at once into a vertically standing pipe having a diameter of 80 mm and a length of 3000 mm, and the defect state of the bottom cartridge was confirmed. The evaluation criteria were as follows.
○: No change, △: Slight bulge, etc. x: Clearly chipped, deformed, cracked
４．染込性
カートリッジの初期重量を測定し、その後、カートリッジを水に浸漬させ、泡が出なくなる状態まで放置した。その後、垂直に持ち上げ水が落ちなくなるまで静かに待ち、重量を測定した。求められる染込性は、前後の重量差がカートリッジ１ｇ当り、水３．２ｇ以上とし、評価基準は次のようにした。
○：３．４ｇ／ｇ超え、△：３．２〜３．４ｇ／ｇ、×：３．２ｇ／ｇ未満
4). Stainability The initial weight of the cartridge was measured, and then the cartridge was immersed in water and allowed to stand until no bubbles were generated. Then, it was lifted vertically and gently waited until the water did not fall, and the weight was measured. The required soaking property was such that the weight difference between before and after was 3.2 g or more of water per 1 g of cartridge, and the evaluation criteria were as follows.
○: More than 3.4 g / g, Δ: 3.2 to 3.4 g / g, ×: less than 3.2 g / g
５．総合評価
◎：全ての項目で○、○：ひとつでも△の項目がある、×：ひとつでも×の項目がある
5. Overall evaluation ◎: For all items, ○, ○: There is one item for △, ×: There is one item for ×
上記の表１から明らかなように、本発明の放射性廃液処理用カートリッジの実施例１から３では、充分な圧縮強度（硬さ）及び衝撃強度を保有し、染込性も良好な放射性廃液処理用カートリッジが得られることが確認できた。特に、実施例１及び２のようにホウ酸含有量が０．０４０〜０．０５５ｇ/ｃｍ３の範囲においては、染込性にも極めて優れた放射性廃液処理用カートリッジが得られることが確認できた。一方、ホウ酸含有量が０．０４０〜０．０５５ｇ/ｃｍ３の範囲を外れる比較例１から３のカートリッジでは、圧縮強度または染込性が不十分ではなく、カートリッジに求められる性能を備えていないことがわかる。
また、ホウ酸含有量の標準偏差が０．４ｇ/ｃｍ３以上である比較例３においては、硬さ、衝撃強度及び染込性の全ての評価項目において不十分となり、ホウ酸含有量が既定内であってもカートリッジ全体においてホウ酸含有量のバラツキがあると、カートリッジに求められる性能を備えていないことがわかる。
As is apparent from Table 1 above, in Examples 1 to 3 of the cartridge for radioactive waste liquid treatment of the present invention, the radioactive waste liquid treatment having sufficient compressive strength (hardness) and impact strength and good infiltration characteristics is provided. It was confirmed that a cartridge for use was obtained. In particular, as in Examples 1 and 2, in the range where the boric acid content is 0.040 to 0.055 g / cm 3 , it can be confirmed that a radioactive waste liquid treatment cartridge having extremely excellent infiltration properties can be obtained. It was. On the other hand, in the cartridges of Comparative Examples 1 to 3 in which the boric acid content is outside the range of 0.040 to 0.055 g / cm 3 , the compressive strength or the penetration property is not insufficient, and the performance required for the cartridge is provided. I understand that there is no.
Further, in Comparative Example 3 in which the standard deviation of boric acid content is 0.4 g / cm 3 or more, all evaluation items of hardness, impact strength, and penetration are insufficient, and the boric acid content is predetermined. Even in the case, if the boric acid content varies in the whole cartridge, it is understood that the performance required for the cartridge is not provided.
以上説明したように、本発明によればホウ酸含有量が０．０４０〜０．０５５ｇ/ｃｍ３のカートリッジ、特にバラツキが小さいカートリッジにおいて、充分な圧縮強度及び衝撃強度を保有し、染込性も良好な放射性廃液処理用カートリッジが得られる。 As described above, according to the present invention, a cartridge having a boric acid content of 0.040 to 0.055 g / cm 3 , particularly a cartridge with small variation, has sufficient compressive strength and impact strength, and has a soaking property. In this way, a cartridge for treating radioactive liquid waste can be obtained.
本発明に係る放射性廃液処理用カートリッジは、上述した課題を解決するために、ガラス繊維と、ガラス繊維を融着させる無機結合剤と、を備え、所定形状に成形された放射性廃液処理用カートリッジであり、前記無機結合剤を、０．０４０〜０．０５５ｇ/ｃｍ３含有し、前記無機結合剤はホウ酸またはホウ酸塩であることを特徴とする。 In order to solve the above-mentioned problem, the radioactive waste liquid treatment cartridge according to the present invention is a radioactive waste liquid treatment cartridge which is formed into a predetermined shape, and includes glass fibers and an inorganic binder for fusing the glass fibers. There, the inorganic binder, 0.040~0.055g / cm 3 containing the inorganic binder characterized by boric acid or borate der Rukoto.
Claims (3)
前記無機結合剤を、０．０４０〜０．０５５ｇ/ｃｍ３含有することを特徴とする放射性廃液処理用カートリッジ。 A cartridge for radioactive liquid waste treatment comprising glass fibers and an inorganic binder for fusing the glass fibers and molded into a predetermined shape,
A radioactive waste liquid treatment cartridge comprising 0.040 to 0.055 g / cm 3 of the inorganic binder.
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Citations (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60186797A (en) * | 1984-03-06 | 1985-09-24 | 動力炉・核燃料開発事業団 | Cartridge for solidifying radioactive waste liquor glass |
| JPS6194576U (en) * | 1984-11-26 | 1986-06-18 | ||
| JPS62222198A (en) * | 1986-03-25 | 1987-09-30 | 動力炉・核燃料開発事業団 | Manufacture of cartridge for processing radioactive waste liquor |
| JPH0249198A (en) * | 1988-08-11 | 1990-02-19 | Power Reactor & Nuclear Fuel Dev Corp | Production of cartridge for treating radioactive waste liquid |
| US4943395A (en) * | 1988-03-28 | 1990-07-24 | Doryokuro Kakunenryo Kaihatsu Jigyodan | Process of vitrifying radioactive liquid waste with suppressed formation of gaseous ruthenium |
| JPH03199999A (en) * | 1989-12-27 | 1991-08-30 | Power Reactor & Nuclear Fuel Dev Corp | Cartridge for treating radioactive waste fluid |
| JPH0915389A (en) * | 1995-06-27 | 1997-01-17 | Japan Atom Energy Res Inst | Radioactive nuclide adsorbent and its production method and volume reduction processing method for radioactive waste |
| JPH10291841A (en) * | 1997-04-18 | 1998-11-04 | Nippon Electric Glass Co Ltd | Glass fiber and glass fiber reinforced thermoplastic resin using the same |
| JPH11151707A (en) * | 1997-11-21 | 1999-06-08 | Kanegafuchi Chem Ind Co Ltd | Fiber mat, fiber board, and production of them |
| JP2001330696A (en) * | 2000-05-24 | 2001-11-30 | Nippon Muki Co Ltd | Glass fiber cartridge for treating radioactive liquid waste |
| JP2003338271A (en) * | 2002-05-21 | 2003-11-28 | Matsushita Electric Ind Co Ltd | Separator for lead battery and valve-control led lead battery using the same |
| JP2003344584A (en) * | 2002-05-29 | 2003-12-03 | Nippon Muki Co Ltd | Glass fiber cartridge |
-
2018
- 2018-03-30 JP JP2018068506A patent/JP6430676B1/en active Active
Patent Citations (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60186797A (en) * | 1984-03-06 | 1985-09-24 | 動力炉・核燃料開発事業団 | Cartridge for solidifying radioactive waste liquor glass |
| JPS6194576U (en) * | 1984-11-26 | 1986-06-18 | ||
| JPS62222198A (en) * | 1986-03-25 | 1987-09-30 | 動力炉・核燃料開発事業団 | Manufacture of cartridge for processing radioactive waste liquor |
| US4943395A (en) * | 1988-03-28 | 1990-07-24 | Doryokuro Kakunenryo Kaihatsu Jigyodan | Process of vitrifying radioactive liquid waste with suppressed formation of gaseous ruthenium |
| JPH0249198A (en) * | 1988-08-11 | 1990-02-19 | Power Reactor & Nuclear Fuel Dev Corp | Production of cartridge for treating radioactive waste liquid |
| JPH03199999A (en) * | 1989-12-27 | 1991-08-30 | Power Reactor & Nuclear Fuel Dev Corp | Cartridge for treating radioactive waste fluid |
| JPH0915389A (en) * | 1995-06-27 | 1997-01-17 | Japan Atom Energy Res Inst | Radioactive nuclide adsorbent and its production method and volume reduction processing method for radioactive waste |
| JPH10291841A (en) * | 1997-04-18 | 1998-11-04 | Nippon Electric Glass Co Ltd | Glass fiber and glass fiber reinforced thermoplastic resin using the same |
| JPH11151707A (en) * | 1997-11-21 | 1999-06-08 | Kanegafuchi Chem Ind Co Ltd | Fiber mat, fiber board, and production of them |
| JP2001330696A (en) * | 2000-05-24 | 2001-11-30 | Nippon Muki Co Ltd | Glass fiber cartridge for treating radioactive liquid waste |
| JP2003338271A (en) * | 2002-05-21 | 2003-11-28 | Matsushita Electric Ind Co Ltd | Separator for lead battery and valve-control led lead battery using the same |
| JP2003344584A (en) * | 2002-05-29 | 2003-12-03 | Nippon Muki Co Ltd | Glass fiber cartridge |
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