JPH0141238B2 - - Google Patents
Info
- Publication number
- JPH0141238B2 JPH0141238B2 JP7466383A JP7466383A JPH0141238B2 JP H0141238 B2 JPH0141238 B2 JP H0141238B2 JP 7466383 A JP7466383 A JP 7466383A JP 7466383 A JP7466383 A JP 7466383A JP H0141238 B2 JPH0141238 B2 JP H0141238B2
- Authority
- JP
- Japan
- Prior art keywords
- adsorption
- gas
- tuff
- silica gel
- adsorbent
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
- 238000001179 sorption measurement Methods 0.000 claims description 30
- 239000003463 adsorbent Substances 0.000 claims description 26
- 238000000034 method Methods 0.000 claims description 14
- 229910052680 mordenite Inorganic materials 0.000 claims description 6
- JYIBXUUINYLWLR-UHFFFAOYSA-N aluminum;calcium;potassium;silicon;sodium;trihydrate Chemical compound O.O.O.[Na].[Al].[Si].[K].[Ca] JYIBXUUINYLWLR-UHFFFAOYSA-N 0.000 claims description 5
- 229910001603 clinoptilolite Inorganic materials 0.000 claims description 5
- 239000003758 nuclear fuel Substances 0.000 claims description 2
- 238000012958 reprocessing Methods 0.000 claims description 2
- 239000007789 gas Substances 0.000 description 27
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 17
- 239000000741 silica gel Substances 0.000 description 17
- 229910002027 silica gel Inorganic materials 0.000 description 17
- 239000010457 zeolite Substances 0.000 description 9
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 8
- HNPSIPDUKPIQMN-UHFFFAOYSA-N dioxosilane;oxo(oxoalumanyloxy)alumane Chemical compound O=[Si]=O.O=[Al]O[Al]=O HNPSIPDUKPIQMN-UHFFFAOYSA-N 0.000 description 7
- 229910021536 Zeolite Inorganic materials 0.000 description 6
- 238000007791 dehumidification Methods 0.000 description 5
- 238000005984 hydrogenation reaction Methods 0.000 description 5
- 239000002253 acid Substances 0.000 description 4
- 238000001994 activation Methods 0.000 description 4
- 239000003595 mist Substances 0.000 description 4
- 238000012360 testing method Methods 0.000 description 4
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 3
- 230000004913 activation Effects 0.000 description 3
- 229910017604 nitric acid Inorganic materials 0.000 description 3
- 239000011148 porous material Substances 0.000 description 3
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 2
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 2
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 2
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 2
- 239000012159 carrier gas Substances 0.000 description 2
- 229910052802 copper Inorganic materials 0.000 description 2
- 239000010949 copper Substances 0.000 description 2
- 239000013078 crystal Substances 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 229910052739 hydrogen Inorganic materials 0.000 description 2
- 239000011630 iodine Substances 0.000 description 2
- 229910052740 iodine Inorganic materials 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 239000002808 molecular sieve Substances 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- URGAHOPLAPQHLN-UHFFFAOYSA-N sodium aluminosilicate Chemical compound [Na+].[Al+3].[O-][Si]([O-])=O.[O-][Si]([O-])=O URGAHOPLAPQHLN-UHFFFAOYSA-N 0.000 description 2
- 239000002915 spent fuel radioactive waste Substances 0.000 description 2
- JKFYKCYQEWQPTM-UHFFFAOYSA-N 2-azaniumyl-2-(4-fluorophenyl)acetate Chemical compound OC(=O)C(N)C1=CC=C(F)C=C1 JKFYKCYQEWQPTM-UHFFFAOYSA-N 0.000 description 1
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 description 1
- 229910021612 Silver iodide Inorganic materials 0.000 description 1
- XLYOFNOQVPJJNP-PWCQTSIFSA-N Tritiated water Chemical compound [3H]O[3H] XLYOFNOQVPJJNP-PWCQTSIFSA-N 0.000 description 1
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 description 1
- 230000003213 activating effect Effects 0.000 description 1
- 238000007605 air drying Methods 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 229910052804 chromium Inorganic materials 0.000 description 1
- 239000011651 chromium Substances 0.000 description 1
- 229910017052 cobalt Inorganic materials 0.000 description 1
- 239000010941 cobalt Substances 0.000 description 1
- GUTLYIVDDKVIGB-UHFFFAOYSA-N cobalt atom Chemical compound [Co] GUTLYIVDDKVIGB-UHFFFAOYSA-N 0.000 description 1
- 238000011437 continuous method Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000002425 crystallisation Methods 0.000 description 1
- 230000008025 crystallization Effects 0.000 description 1
- 238000004090 dissolution Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000010304 firing Methods 0.000 description 1
- 239000011491 glass wool Substances 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- -1 hydrogen ions Chemical class 0.000 description 1
- 238000005342 ion exchange Methods 0.000 description 1
- 229910052742 iron Inorganic materials 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 229910052759 nickel Inorganic materials 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 238000010992 reflux Methods 0.000 description 1
- 230000008929 regeneration Effects 0.000 description 1
- 238000011069 regeneration method Methods 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 229940045105 silver iodide Drugs 0.000 description 1
- 229910052722 tritium Inorganic materials 0.000 description 1
- 238000005406 washing Methods 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
Landscapes
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
Description
この発明は、原子力発電所の原子炉で使用済と
なつた核燃料を再処理する際に発生する放射性物
質を含んだ排ガスを安全に処理する方法に関する
ものである。
使用済の核燃料を再処理するために、燃料棒を
せん断してこれを硝酸に溶解させる湿式法が採ら
れているが、この溶解工程で、硝酸の蒸気ととも
に、放射性ヨウ素をふくむヨウ素、トリチウム水
をふくむ水、NOX、Kr、Xeなどを含む排ガスが
発生する。このうち硝酸ミスト、水分(トリチウ
ム水を含む)大部分はミストキヤツチヤおよびシ
リカゲル脱湿塔によつて捕促されるが、その排ガ
ス中にはなお、NOX約1vol.%(NO2はその90%
程度)、I220〜200ppm、CO2300ppm程度、H2O
トレース(シリカゲル脱湿塔の運転条件にもよる
が、露点−10〜−15℃程度)、微量のXr、Xeなど
の放射性ガス(残部は空気)が含まれている。
I2を除去する一つの方法として、Agを担持さ
せたゼオライトを使用し、I2をヨウ化銀として回
収する方法が知られているが、効率が悪く、理論
量の5〜10倍ものAgが必要であるという欠点が
ある。また「モレキユラシーブ13X」、ゼオラム
F9」、「モレキユラシーブ5A」、「ゼオラムA−5」
などの商品名で市販されているX型又はA型ゼオ
ライトは、AgなしでもI2を吸着する能力がある
という報告もなされている。しかしながら、これ
らの主結晶格子中のSi:Alの比がほぼ等しいゼ
オライトのほとんどは耐久性がなく、酸が存在す
ると容易に結晶構造自体が崩解して吸着作用がな
くなり吸着剤として使用できなくなるという共通
の欠点を有している。前記のシリカゲル脱湿塔か
ら出た排ガスはNOXやI2を含有しているととも
に、シリカゲル脱湿塔で脱湿したといつても、前
述のように露点−10〜−15℃程度の水分を含有し
ているので、この排ガスがゼオライトを充填した
吸着塔に入ると、ゼオライト中で酸を生成し、吸
着剤としてのゼオライトの崩解を招き、実際の吸
着操作に重大な支障をきたす。
この発明は、上記のような従来法の欠点を除去
するためになされたもので、シリカゲルが水分と
ともにNO2を吸着する能力を有すること(NO2
は大部分HNO3として存在する)、および天然凝
灰岩を通常の方法で水素化することによつて得ら
れた改質天然凝灰岩が良好なI2吸着性と耐酸性を
有していることを見出し、シリカゲルで排ガス中
の水分およびNO2を除去する工程と、上記改質
天然凝灰岩でI2を除去する工程と、残存するNOX
を天然凝灰岩で除去する工程とを組合せることに
より、被処理排ガスが多量の水分を含有していて
も効果的にI2およびNOXを吸着除去できるように
した処理方法を提供することを目的としている。
シリカゲルは一般に水に対してのみ吸着性を示
すものと考えられているが、本発明者は、水分の
存在下でガス中のとくにNO2に対して強い吸着
性を示すことを見出した。すなわち再処理排ガス
からミストを除去し、ついでシリカゲルに接触さ
せた場合には、このガス中に含まれている水分と
ともに、NO2の相当部分を吸着除去することが
可能であり、これは従来は知られていなかつたこ
とである。
たとえば、NO20.84容量%、I280ppm、
H2O0.78%、空気1l/minの混合ガスを、27gのシ
リカゲルに約30時間通した。通ガス量は約1800l
であり、シリカゲル層の重量増加は15.83gであつ
た。このシリカゲルを、N2気流中で550℃に加熱
して脱着させたところ、HNO33.309g、I20.036g、
NO20.2008g、H2O11.71g、計15.26gの脱着物が得
られた。この結果によりI2はほとんど吸着されて
いないが、H2O、HNO3、NO2がよく吸着されて
いることがわかる。
この発明で使用される改質天然凝灰岩は、東北
地方、中国地方、九州地方などで天然に産出する
モルデナイト系またはクリノプチロライト系天然
凝灰岩を適当な方法で水素化および活性化するこ
とによつて得られたものである。この水素化は、
原石を破砕した適当な粒度の粒子を水洗したのち
風乾し、この粒子をたとえば1N−HClで100℃で
30時間還流し、ついで水洗および風乾することに
よつて行うことができる。この明細書において用
語「水素化」は、下記の式に示すように、対象と
する天然凝灰岩のNa成分を水素イオンで置換す
ることを意味する。
Ze−Na++H+→Ze−H++Na+
この水素化反応は、対象とする天然凝灰岩に直
接HClを作用させることによつて行なわせてもよ
く、またNH4Clなどでイオン交換したのち、加
熱してNH3をとばして水素化するもできる。こ
れら反応は次のとおりである。
[HClによる直接法]
Ze−Na++HCl→ZeH++Na+Cl
[NH4Clによる間接法]
Ze−Na++NH4 +Cl→Ze−NH4 ++Na+Cl
Ze−NH4 +加熱
――→
ZeH++NH3↑
このようにして水素化された天然凝灰岩は、使
用に先立つて、吸着している水分ばかりでなく、
化学的に結合している結晶水を除去することから
なる活性化を施しておくことが望ましい。この活
性化は、適当な粒度に破砕した天然凝灰岩を約
550℃約1時間保持することによつて行なうこと
ができる。このようにして改質された天然凝灰岩
は、NOXよりもI2に対して良好な吸着性を有する
ことが見出された。
図のグラフは、改質によるI2吸着性の変化をし
らべるテストの結果を示している。このテスト
は、適当なカラム内に各天然凝灰岩吸着剤を充填
して層高12.7cmの吸着層を形成し、このカラムの
頂部から底部に向けてテストガス242gを線速2.3
cm/secで流すことによつて行われた。テストガ
スは、空気(露点−55〜−60℃)をキヤリアガス
とし、その中に0.004重量%のI2を添加したもの
である。この結果から、改質天然凝灰岩吸着剤
が、活性化だけを受けた非改質天然凝灰岩吸着剤
には見られないすぐれたI2吸着性を有しているこ
とが明らかである(図中、〇印が改質、・印が非
改質)。天然凝灰岩が水素化によつてI2吸着性を
示すようになる理由は明確ではないが、水素化さ
れていないモルデナイト系天然凝灰岩のポアサイ
ズが4〜6Å、クリノプチロライト系のものでは
3〜5Åであるのに対して、水素化されたもので
はポアサイズが約10Åに増大していることから、
このポアサイズの増大によつてI2を吸着する性質
が格段に向上したことが一つの理由であると考え
られる。
なおゼオライト系吸着剤においては水素化は公
知であり、その技術も一般化しているが、この場
合の水素化は耐酸性の向上を目的とするものであ
り、また通常のゼオライトを水素化してもI2に対
する吸着性はほとんど向上しない。
上記の改質天然凝灰岩吸着剤からなる吸着層を
通過したガスは、この吸着剤の良好なI2吸着性に
よつてI2をほとんど含まないものになつている
が、核燃料再処理排ガスに含まれているNOXが
かなり残存しているので、I2を除去するための第
2吸着工程に引続いて、NOXを除去するための
第3吸着工程が必要である。この第3吸着工程
は、NOXに対して吸着性を有する通常の吸着剤
を用いて行うことができるが、最も良好な結果
は、モルデナイト系またはクリノプチロライト系
天然凝灰岩に活性化処理だけを施した吸着剤を用
いた場合に得られる。この非改質天然凝灰岩吸着
剤では、NO2はそのまま吸着されるが、NOは吸
着されたのちにNO2に酸化された形態で保持さ
れる。この酸化性態は、上記の天然凝灰岩に銅、
クロム、鉄、コバルト、ニツケル等の金属を活性
センターとして担持させておくことによつてさら
に向上する。
シリカゲルからなる第1の吸着剤層に供給され
る被処理ガスは、せん断燃料棒を溶解槽内で溶解
させる際に発生した排ガスであり、この排ガスに
とくに脱湿などの前処理を施しておく必要はな
く、ミストを除去する程度でよい。この排ガスは
シリカゲルからなる第1の吸着剤層に送られる。
この第1の吸着剤層では、流入ガスの水分の除去
とともに、主としてNO2の吸着除去が行われる
(NO2のほとんどはHNO3の形で存在する)。第1
の吸着剤層を出たガスは、水分がほぼ完全に除か
れており、つぎに上記の改質天然凝灰岩からなる
第2の吸着剤層を通過し、ここでガス中の主とし
てI2が吸着され、さらに天然凝灰岩からなる第3
の吸着剤層を通過することによつて残りのNOX
が吸着除去される。
なお、H2OとNO2を吸着除去する第1吸着工
程のシリカゲル塔は、2塔ないしそれ以上の塔を
用いて、いわゆる追込み方式で行うと水分をより
完全に除去することができ、別個の1塔を脱着、
再生とする連続方式にするのが望ましい。第2吸
着工程、第3吸着工程も同様に連続方式にするこ
とができる。
実施例
直径17.5mm、長さ250mmのカラム内に、その上
端から下端にかけて順次に第1〜第3の吸着剤層
をグラスウールを介して形成した吸着塔を用意し
た。第1の吸着剤層は27.05gのシリカゲル(ユニ
オンカーバイド社製、商品名「Purasiv−N301」
からなり、第2の吸着剤層は、水素化されたモル
デナイト系天然凝灰岩(板戸産)9.50gからなる。
また第3の吸着剤層は、モルデナイト系天然凝灰
岩(板戸産)を破砕したのち550℃で焼成するこ
とによつて活性化したものからなる。この吸着塔
内に、頂部から底部に向けて被処理ガス1.785lを
線速約7cm/secで29.75時間かけて流した。被処
理ガスは、キヤリアガスとしての空気(水分0.78
%)にI280ppm、NO20.84容量%、NO0.10容量%
を添加して調整されたものである。各吸着剤層か
ら流出した処理ガスの組成(容量比)を第1表に
示す。
The present invention relates to a method for safely processing exhaust gas containing radioactive materials generated when spent nuclear fuel is reprocessed in a reactor of a nuclear power plant. In order to reprocess spent nuclear fuel, a wet method is used in which fuel rods are sheared and dissolved in nitric acid.In this dissolution process, along with nitric acid vapor, iodine containing radioactive iodine and tritium water are released. Exhaust gas containing water, NO x , Kr, X e , etc. is generated. Of this, most of the nitric acid mist and moisture (including tritiated water) are captured by the mist catcher and silica gel dehumidification tower, but the exhaust gas still contains approximately 1 vol.% of NO %
degree), I2 20-200ppm, CO2 approximately 300ppm, H2O
Trace (depending on the operating conditions of the silica gel dehumidification tower, dew point is about -10 to -15°C), trace amounts of radioactive gases such as X r and X e (the remainder is air) are included. One known method for removing I 2 is to use Ag-supported zeolite and recover I 2 as silver iodide, but it is inefficient and produces 5 to 10 times the theoretical amount of Ag. The disadvantage is that it requires Also "Molecular Sieve 13X", Zeorum
F9”, “Molecular Sieve 5A”, “Zeolum A-5”
It has also been reported that type X or type A zeolites, which are commercially available under trade names such as zeolites, have the ability to adsorb I 2 even without Ag. However, most of these zeolites with a nearly equal ratio of Si:Al in the main crystal lattice are not durable, and in the presence of acid, the crystal structure itself easily collapses and the adsorption effect disappears, making it impossible to use it as an adsorbent. They have a common drawback. The exhaust gas emitted from the silica gel dehumidification tower mentioned above contains NOx and I2 , and even if it is dehumidified in the silica gel dehumidification tower, it will contain moisture with a dew point of about -10 to -15℃ as mentioned above. When this exhaust gas enters an adsorption tower filled with zeolite, it generates acid in the zeolite, leading to the disintegration of the zeolite as an adsorbent, which seriously impedes the actual adsorption operation. This invention was made in order to eliminate the drawbacks of the conventional method as described above. Silica gel has the ability to adsorb NO 2 as well as water (NO 2
found that the modified natural tuff obtained by hydrogenating natural tuff in a conventional manner has good I 2 adsorption and acid resistance. , a step of removing moisture and NO 2 in the exhaust gas with silica gel, a step of removing I 2 with the above modified natural tuff, and a step of removing the remaining NO
The purpose of the present invention is to provide a treatment method that can effectively adsorb and remove I 2 and NO It is said that Although silica gel is generally thought to exhibit adsorption properties only to water, the present inventors have discovered that in the presence of moisture, silica gel exhibits strong adsorption properties, particularly to NO 2 in gases. In other words, when the mist is removed from reprocessed exhaust gas and then brought into contact with silica gel, it is possible to adsorb and remove a considerable portion of NO 2 along with the moisture contained in this gas, which was previously impossible. This was something that was not known. For example, NO 2 0.84% by volume, I 2 80ppm,
A gas mixture of 0.78% H 2 O and 1 l/min of air was passed through 27 g of silica gel for about 30 hours. Gas flow rate is approximately 1800l
The weight increase of the silica gel layer was 15.83g. When this silica gel was heated to 550°C in a N 2 stream to desorb it, 3.309 g of HNO 3 , 0.036 g of I 2 ,
A total of 15.26 g of desorbed material was obtained, including 0.2008 g of NO 2 and 11.71 g of H 2 O. This result shows that I 2 is hardly adsorbed, but H 2 O, HNO 3 and NO 2 are well adsorbed. The modified natural tuff used in this invention is obtained by hydrogenating and activating mordenite-based or clinoptilolite-based natural tuff, which is naturally occurring in the Tohoku region, Chugoku region, Kyushu region, etc., using an appropriate method. This is what was obtained. This hydrogenation is
Particles of a suitable size obtained by crushing raw stones are washed with water, air-dried, and then treated with, for example, 1N-HCl at 100℃.
This can be done by refluxing for 30 hours, followed by washing with water and air drying. In this specification, the term "hydrogenation" means replacing the Na component of the target natural tuff with hydrogen ions, as shown in the formula below. Ze−Na + +H + →Ze−H + +Na + This hydrogenation reaction may be performed by directly applying HCl to the target natural tuff, or after ion exchange with NH 4 Cl etc. It can also be hydrogenated by heating to drive off NH3 . These reactions are as follows. [Direct method using HCl] Ze−Na + +HCl→ZeH + +Na + Cl [Indirect method using NH 4 Cl] Ze−Na + +NH 4 + Cl→Ze−NH 4 + +Na + Cl Ze−NH 4 + heating―― → ZeH + +NH 3 ↑ The natural tuff hydrogenated in this way is not only free from adsorbed water but also before use.
It is desirable to carry out activation which consists of removing chemically bound water of crystallization. This activation process consists of natural tuff crushed to an appropriate grain size.
This can be done by holding the temperature at 550°C for about 1 hour. Natural tuff modified in this way was found to have better adsorption properties for I2 than for NOX . The graph in the figure shows the results of a test to examine changes in I 2 adsorption due to modification. In this test, each natural tuff adsorbent was packed into an appropriate column to form an adsorption layer with a bed height of 12.7 cm, and 242 g of test gas was applied from the top to the bottom of the column at a linear velocity of 2.3.
This was done by flowing at cm/sec. The test gas was air (dew point -55 to -60°C) used as a carrier gas, to which 0.004% by weight of I2 was added. From this result, it is clear that the modified natural tuff adsorbent has excellent I 2 adsorption properties that are not observed in the unmodified natural tuff adsorbent that has undergone only activation (in the figure, 〇 indicates modified, ・mark indicates non-modified). It is not clear why natural tuff exhibits I 2 adsorption properties when hydrogenated, but the pore size of unhydrogenated mordenitic natural tuff is 4-6 Å, and that of clinoptilolite-based tuff is 3-3 Å. 5 Å, whereas in the hydrogenated version the pore size increases to approximately 10 Å,
One reason is thought to be that the property of adsorbing I 2 was significantly improved due to this increase in pore size. Hydrogenation of zeolite-based adsorbents is well known and the technology is common, but the purpose of hydrogenation in this case is to improve acid resistance, and even if ordinary zeolite is hydrogenated, Adsorption to I 2 hardly improves. The gas that has passed through the adsorption layer made of the above-mentioned modified natural tuff adsorbent contains almost no I 2 due to the good I 2 adsorption properties of this adsorbent, but it is contained in the nuclear fuel reprocessing exhaust gas. Since there remains a significant amount of NO x remaining, a third adsorption step to remove NO x is required following the second adsorption step to remove I 2 . This third adsorption step can be carried out using conventional adsorbents that have adsorption properties for NO x , but the best results are obtained by applying activation treatment to natural mordenite or clinoptilolite tuffs. Obtained when using an adsorbent treated with In this unmodified natural tuff adsorbent, NO 2 is adsorbed as is, but after being adsorbed, NO is retained in the form of oxidized NO 2 . This oxidation state is caused by copper and copper in the above natural tuff.
Further improvement can be achieved by supporting metals such as chromium, iron, cobalt, and nickel as active centers. The gas to be treated that is supplied to the first adsorbent layer made of silica gel is the exhaust gas generated when the sheared fuel rods are melted in the melting tank, and this exhaust gas has been subjected to pretreatment such as dehumidification. It is not necessary, and it is enough to remove the mist. This exhaust gas is sent to a first adsorbent layer made of silica gel.
In this first adsorbent layer, in addition to removing moisture from the inflow gas, NO 2 is mainly adsorbed and removed (most of the NO 2 is present in the form of HNO 3 ). 1st
The gas leaving the adsorbent layer has almost completely removed moisture, and then passes through the second adsorbent layer made of the above-mentioned modified natural tuff, where mainly I 2 in the gas is adsorbed. and a third layer made of natural tuff.
The remaining NO x by passing through the adsorbent layer of
is removed by adsorption. In addition, the silica gel column in the first adsorption step, which adsorbs and removes H 2 O and NO 2 , can be used in a so-called push-up method using two or more columns to remove moisture more completely. Detach one tower of
It is desirable to use a continuous method for regeneration. The second adsorption step and the third adsorption step can also be performed in a continuous manner. Example An adsorption tower was prepared in which first to third adsorbent layers were sequentially formed through glass wool from the upper end to the lower end in a column having a diameter of 17.5 mm and a length of 250 mm. The first adsorbent layer was made of 27.05 g of silica gel (manufactured by Union Carbide, trade name "Purasiv-N301").
The second adsorbent layer consists of 9.50 g of hydrogenated mordenite-based natural tuff (from Itado).
The third adsorbent layer is made of crushed mordenite-based natural tuff (from Itado) and activated by firing at 550°C. Into this adsorption tower, 1.785 liters of the gas to be treated was flowed from the top to the bottom at a linear velocity of about 7 cm/sec over a period of 29.75 hours. The gas to be treated is air as a carrier gas (moisture 0.78
%) to I2 80ppm, NO2 0.84% by volume, NO0.10% by volume
It was prepared by adding. Table 1 shows the composition (volume ratio) of the processing gas flowing out from each adsorbent layer.
【表】
以上のようにこの発明方法によれば、シリカゲ
ル、水素化処理されたモルデナイト系またはクリ
ノプチロライト系改質天然凝灰岩、および天然凝
灰岩の3種の吸着剤よる3つの基本的な吸着工程
を組合せたので、被処理排ガスがどれほどの水分
を含んでいたとしても、水分の影響を受けること
なく、I2およびNOXを効果的に吸着除去すること
が可能となる。このため前処理工程が簡素化で
き、吸着工程の管理も容易になるなどの効果が得
られる。[Table] As described above, according to the method of this invention, three basic types of adsorption are possible using three types of adsorbents: silica gel, hydrogenated mordenite-based or clinoptilolite-based modified natural tuff, and natural tuff. By combining the steps, it is possible to effectively adsorb and remove I 2 and NO X without being affected by the moisture, no matter how much moisture the exhaust gas to be treated contains. Therefore, the pretreatment process can be simplified, and the adsorption process can be easily managed.
図は改質天然凝灰岩と非改質天然凝灰岩のI2吸
着特性を示すグラフである。
The figure is a graph showing the I 2 adsorption characteristics of modified natural tuff and unmodified natural tuff.
Claims (1)
せる際に発生するI2およびNOXを含む排ガスを処
理する方法において、シリカゲルからなる第1の
吸着剤層で上記排ガス中の主として水分とNO2
を吸着除去する第1吸着工程と、モルデナイト系
またはクリノプチロライト系天然凝灰岩を水素化
した吸着剤からなる第2の吸着剤層で、上記第1
の吸着剤層を通過したガス中の主としてI2を吸着
除去する第2吸着工程と、モルデナイト系または
(および)クリノプチロライト系天然凝灰岩から
なる第3の吸着剤層で、上記第2の吸着剤層を通
過したガス中に残存するNOXを吸着除去する第
3吸着工程とを備えたことを特徴とする核燃料再
処理排ガスの処理方法。1 In a method for treating exhaust gas containing I 2 and NO 2
a first adsorption step for adsorbing and removing the above-mentioned first
The second adsorption step mainly adsorbs and removes I 2 in the gas that has passed through the adsorbent layer, and the third adsorbent layer is made of mordenite-based or (and) clinoptilolite-based natural tuff. A method for treating nuclear fuel reprocessing exhaust gas, comprising: a third adsorption step for adsorbing and removing NOx remaining in the gas that has passed through the adsorbent layer.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58074663A JPS59198395A (en) | 1983-04-27 | 1983-04-27 | Method of processing nuclear fuel reprocessing gaseous waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58074663A JPS59198395A (en) | 1983-04-27 | 1983-04-27 | Method of processing nuclear fuel reprocessing gaseous waste |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS59198395A JPS59198395A (en) | 1984-11-10 |
| JPH0141238B2 true JPH0141238B2 (en) | 1989-09-04 |
Family
ID=13553694
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58074663A Granted JPS59198395A (en) | 1983-04-27 | 1983-04-27 | Method of processing nuclear fuel reprocessing gaseous waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59198395A (en) |
-
1983
- 1983-04-27 JP JP58074663A patent/JPS59198395A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS59198395A (en) | 1984-11-10 |
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