JPS631560B2 - - Google Patents
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- Publication number
- JPS631560B2 JPS631560B2 JP11789379A JP11789379A JPS631560B2 JP S631560 B2 JPS631560 B2 JP S631560B2 JP 11789379 A JP11789379 A JP 11789379A JP 11789379 A JP11789379 A JP 11789379A JP S631560 B2 JPS631560 B2 JP S631560B2
- Authority
- JP
- Japan
- Prior art keywords
- weight
- radioactive waste
- moo
- compound
- nio
- 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
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- 239000002901 radioactive waste Substances 0.000 claims description 52
- 239000000919 ceramic Substances 0.000 claims description 18
- 238000002844 melting Methods 0.000 claims description 17
- 230000008018 melting Effects 0.000 claims description 17
- 150000002697 manganese compounds Chemical class 0.000 claims description 16
- JKQOBWVOAYFWKG-UHFFFAOYSA-N molybdenum trioxide Chemical compound O=[Mo](=O)=O JKQOBWVOAYFWKG-UHFFFAOYSA-N 0.000 claims description 14
- 238000004519 manufacturing process Methods 0.000 claims description 11
- 238000002156 mixing Methods 0.000 claims description 9
- 150000002816 nickel compounds Chemical class 0.000 claims description 8
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 claims description 7
- CETPSERCERDGAM-UHFFFAOYSA-N ceric oxide Chemical compound O=[Ce]=O CETPSERCERDGAM-UHFFFAOYSA-N 0.000 claims description 7
- 229910000422 cerium(IV) oxide Inorganic materials 0.000 claims description 7
- 150000001875 compounds Chemical class 0.000 claims description 7
- 239000000470 constituent Substances 0.000 claims description 7
- JEIPFZHSYJVQDO-UHFFFAOYSA-N iron(III) oxide Inorganic materials O=[Fe]O[Fe]=O JEIPFZHSYJVQDO-UHFFFAOYSA-N 0.000 claims description 7
- 229910052750 molybdenum Inorganic materials 0.000 claims description 7
- 239000011733 molybdenum Substances 0.000 claims description 7
- 229910001404 rare earth metal oxide Inorganic materials 0.000 claims description 7
- 229910052768 actinide Inorganic materials 0.000 claims description 5
- 150000001255 actinides Chemical class 0.000 claims description 5
- NUJOXMJBOLGQSY-UHFFFAOYSA-N manganese dioxide Chemical compound O=[Mn]=O NUJOXMJBOLGQSY-UHFFFAOYSA-N 0.000 claims description 4
- 229910052712 strontium Inorganic materials 0.000 claims description 4
- CIOAGBVUUVVLOB-UHFFFAOYSA-N strontium atom Chemical compound [Sr] CIOAGBVUUVVLOB-UHFFFAOYSA-N 0.000 claims description 2
- 238000001816 cooling Methods 0.000 claims 5
- 150000001553 barium compounds Chemical class 0.000 claims 4
- 229940043430 calcium compound Drugs 0.000 claims 4
- 150000001674 calcium compounds Chemical class 0.000 claims 4
- 150000003438 strontium compounds Chemical class 0.000 claims 3
- 229910002674 PdO Inorganic materials 0.000 claims 1
- 229910019603 Rh2O3 Inorganic materials 0.000 claims 1
- 229910018162 SeO2 Inorganic materials 0.000 claims 1
- CXKCTMHTOKXKQT-UHFFFAOYSA-N cadmium oxide Inorganic materials [Cd]=O CXKCTMHTOKXKQT-UHFFFAOYSA-N 0.000 claims 1
- JPJALAQPGMAKDF-UHFFFAOYSA-N selenium dioxide Chemical compound O=[Se]=O JPJALAQPGMAKDF-UHFFFAOYSA-N 0.000 claims 1
- 229910000108 silver(I,III) oxide Inorganic materials 0.000 claims 1
- 238000007711 solidification Methods 0.000 claims 1
- 230000008023 solidification Effects 0.000 claims 1
- QHGNHLZPVBIIPX-UHFFFAOYSA-N tin(II) oxide Inorganic materials [Sn]=O QHGNHLZPVBIIPX-UHFFFAOYSA-N 0.000 claims 1
- 238000002386 leaching Methods 0.000 description 11
- 238000000034 method Methods 0.000 description 10
- 239000000463 material Substances 0.000 description 9
- 239000002699 waste material Substances 0.000 description 9
- 150000002736 metal compounds Chemical class 0.000 description 8
- 239000000203 mixture Substances 0.000 description 8
- 239000000843 powder Substances 0.000 description 7
- 239000007788 liquid Substances 0.000 description 6
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 6
- 230000000052 comparative effect Effects 0.000 description 5
- 239000000654 additive Substances 0.000 description 4
- 229910052791 calcium Inorganic materials 0.000 description 4
- 239000011575 calcium Substances 0.000 description 4
- 230000005855 radiation Effects 0.000 description 4
- 239000000941 radioactive substance Substances 0.000 description 4
- 238000005245 sintering Methods 0.000 description 4
- 229910052788 barium Inorganic materials 0.000 description 3
- 238000001354 calcination Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000010438 heat treatment Methods 0.000 description 3
- 238000012545 processing Methods 0.000 description 3
- 239000012857 radioactive material Substances 0.000 description 3
- 239000002915 spent fuel radioactive waste Substances 0.000 description 3
- OYPRJOBELJOOCE-UHFFFAOYSA-N Calcium Chemical compound [Ca] OYPRJOBELJOOCE-UHFFFAOYSA-N 0.000 description 2
- VTYYLEPIZMXCLO-UHFFFAOYSA-L Calcium carbonate Chemical compound [Ca+2].[O-]C([O-])=O VTYYLEPIZMXCLO-UHFFFAOYSA-L 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 2
- 241000238631 Hexapoda Species 0.000 description 2
- 229910002651 NO3 Inorganic materials 0.000 description 2
- NHNBFGGVMKEFGY-UHFFFAOYSA-N Nitrate Chemical compound [O-][N+]([O-])=O NHNBFGGVMKEFGY-UHFFFAOYSA-N 0.000 description 2
- NBIIXXVUZAFLBC-UHFFFAOYSA-N Phosphoric acid Chemical compound OP(O)(O)=O NBIIXXVUZAFLBC-UHFFFAOYSA-N 0.000 description 2
- 229910052778 Plutonium Inorganic materials 0.000 description 2
- 229910052770 Uranium Inorganic materials 0.000 description 2
- MCMNRKCIXSYSNV-UHFFFAOYSA-N Zirconium dioxide Chemical compound O=[Zr]=O MCMNRKCIXSYSNV-UHFFFAOYSA-N 0.000 description 2
- 229910052799 carbon Inorganic materials 0.000 description 2
- 230000035784 germination Effects 0.000 description 2
- 230000017525 heat dissipation Effects 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
- 239000011572 manganese Substances 0.000 description 2
- MIVBAHRSNUNMPP-UHFFFAOYSA-N manganese(2+);dinitrate Chemical compound [Mn+2].[O-][N+]([O-])=O.[O-][N+]([O-])=O MIVBAHRSNUNMPP-UHFFFAOYSA-N 0.000 description 2
- RGVLTEMOWXGQOS-UHFFFAOYSA-L manganese(2+);oxalate Chemical compound [Mn+2].[O-]C(=O)C([O-])=O RGVLTEMOWXGQOS-UHFFFAOYSA-L 0.000 description 2
- XMWCXZJXESXBBY-UHFFFAOYSA-L manganese(ii) carbonate Chemical compound [Mn+2].[O-]C([O-])=O XMWCXZJXESXBBY-UHFFFAOYSA-L 0.000 description 2
- 238000005259 measurement Methods 0.000 description 2
- 239000002245 particle Substances 0.000 description 2
- 239000010802 sludge Substances 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 description 1
- 238000006424 Flood reaction Methods 0.000 description 1
- 229910003514 Sr(OH) Inorganic materials 0.000 description 1
- 230000001133 acceleration Effects 0.000 description 1
- MQRWBMAEBQOWAF-UHFFFAOYSA-N acetic acid;nickel Chemical compound [Ni].CC(O)=O.CC(O)=O MQRWBMAEBQOWAF-UHFFFAOYSA-N 0.000 description 1
- 230000000996 additive effect Effects 0.000 description 1
- 229910000147 aluminium phosphate Inorganic materials 0.000 description 1
- -1 and as a result Substances 0.000 description 1
- ITHZDDVSAWDQPZ-UHFFFAOYSA-L barium acetate Chemical compound [Ba+2].CC([O-])=O.CC([O-])=O ITHZDDVSAWDQPZ-UHFFFAOYSA-L 0.000 description 1
- DSAJWYNOEDNPEQ-UHFFFAOYSA-N barium atom Chemical compound [Ba] DSAJWYNOEDNPEQ-UHFFFAOYSA-N 0.000 description 1
- AYJRCSIUFZENHW-UHFFFAOYSA-L barium carbonate Chemical compound [Ba+2].[O-]C([O-])=O AYJRCSIUFZENHW-UHFFFAOYSA-L 0.000 description 1
- RQPZNWPYLFFXCP-UHFFFAOYSA-L barium dihydroxide Chemical compound [OH-].[OH-].[Ba+2] RQPZNWPYLFFXCP-UHFFFAOYSA-L 0.000 description 1
- 229910001863 barium hydroxide Inorganic materials 0.000 description 1
- 239000005388 borosilicate glass Substances 0.000 description 1
- 229910000019 calcium carbonate Inorganic materials 0.000 description 1
- AXCZMVOFGPJBDE-UHFFFAOYSA-L calcium dihydroxide Chemical compound [OH-].[OH-].[Ca+2] AXCZMVOFGPJBDE-UHFFFAOYSA-L 0.000 description 1
- 229910010293 ceramic material Inorganic materials 0.000 description 1
- 230000015271 coagulation Effects 0.000 description 1
- 238000005345 coagulation Methods 0.000 description 1
- 238000010612 desalination reaction Methods 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000018109 developmental process Effects 0.000 description 1
- 238000010891 electric arc Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000003912 environmental pollution Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000011521 glass Substances 0.000 description 1
- BDAGIHXWWSANSR-NJFSPNSNSA-N hydroxyformaldehyde Chemical compound O[14CH]=O BDAGIHXWWSANSR-NJFSPNSNSA-N 0.000 description 1
- 239000003456 ion exchange resin Substances 0.000 description 1
- 229920003303 ion-exchange polymer Polymers 0.000 description 1
- 239000011656 manganese carbonate Substances 0.000 description 1
- 229940093474 manganese carbonate Drugs 0.000 description 1
- 235000006748 manganese carbonate Nutrition 0.000 description 1
- 229910000016 manganese(II) carbonate Inorganic materials 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 229910044991 metal oxide Inorganic materials 0.000 description 1
- 150000004706 metal oxides Chemical class 0.000 description 1
- 229940078494 nickel acetate Drugs 0.000 description 1
- BMGNSKKZFQMGDH-FDGPNNRMSA-L nickel(2+);(z)-4-oxopent-2-en-2-olate Chemical compound [Ni+2].C\C([O-])=C\C(C)=O.C\C([O-])=C\C(C)=O BMGNSKKZFQMGDH-FDGPNNRMSA-L 0.000 description 1
- 229910000008 nickel(II) carbonate Inorganic materials 0.000 description 1
- ZULUUIKRFGGGTL-UHFFFAOYSA-L nickel(ii) carbonate Chemical compound [Ni+2].[O-]C([O-])=O ZULUUIKRFGGGTL-UHFFFAOYSA-L 0.000 description 1
- 230000001590 oxidative effect Effects 0.000 description 1
- 238000013001 point bending Methods 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 238000000746 purification Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 238000004062 sedimentation Methods 0.000 description 1
- 239000002002 slurry Substances 0.000 description 1
- 239000002910 solid waste Substances 0.000 description 1
- 239000007921 spray Substances 0.000 description 1
- 230000003068 static effect Effects 0.000 description 1
- 229910000018 strontium carbonate Inorganic materials 0.000 description 1
- UUCCCPNEFXQJEL-UHFFFAOYSA-L strontium dihydroxide Chemical compound [OH-].[OH-].[Sr+2] UUCCCPNEFXQJEL-UHFFFAOYSA-L 0.000 description 1
- 229910001866 strontium hydroxide Inorganic materials 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
- 229910052726 zirconium Inorganic materials 0.000 description 1
Landscapes
- Compositions Of Oxide Ceramics (AREA)
Description
本発明は、放射性廃棄物の固化体およびその製
造方法に関し、詳しくはか焼した放射性廃棄物
（「か焼体」という）を含有するセラミツク固化体
およびか焼体粉末にマンガン化合物を混合後、溶
融により前記セラミツク固化体を製造する方法に
関する。
本発明の固化体は放射性廃棄物を効率的に貯蔵
することができ、化学的、機械的に安定で、放射
性廃棄物を半永久的に貯蔵することに適する。
又、この固化体はそのまま貯蔵容器に保存しても
良いが、例えば、適当なしやへい物を設け、放射
線量を制御することで食品に放射線を照射し、輸
送及び貯蔵中の腐敗、虫害及び発芽等の防止、保
存期間の延長等に役立つ。
電力供給に対する原子力発電の寄与が増大する
につれ、特に使用済核燃料の再処理工場から発生
する高濃度の放射性廃液は年々増大する傾向にあ
る。これらの貯蔵において、廃液のままでのタン
ク貯蔵は安全上、管理上のみならず数量および容
積的な点で貯蔵スペースが問題となるため、保管
しやすい固化体およびその製造方法の確立が切望
されている。
一般に、放射性廃棄物の固化体およびその製造
技術に於いては、放射性物質の周囲への漏洩が、
最小限となる形態に廃棄物を変換し、かつ、変換
した形態が化学的、機械的に安定していて長期の
貯蔵によつても、環境汚染の原因にならないこと
が必要である。また、放射性廃棄物の量は将来に
わたつて増大することが予想されることから、貯
蔵を効率的に行うために廃棄物と添加量の重量の
総和に対する廃棄物の重量の比（以下「含有率」
という）は可能な限り大きいことが望まれる。本
発明の放射性廃棄物の固化体およびその製造方法
はこのような要求に応えて開発された。
従来放射性廃棄物の貯蔵のためには、か焼体と
して貯蔵することが提唱されてきた。処理温度
400〜650℃でか焼体を製造し、硝酸塩成分を完全
に除去して、酸化物から成るか焼体は硝酸塩成分
の分解がないので静的にはそれなりに長期的に安
定性が保てるが、次のような欠点があつた。すな
わち、か焼体単独では、焼結性は不良であり、一
部の核種の飛散も生じ易いこと、水に溶け易いた
めに耐浸出性が極めて劣ること、熱伝導性が低い
ために放射性元素の崩壊により生ずる熱の放射性
が悪く、その結果貯蔵時に温度上昇を来し易いこ
と、更にこの温度上昇のために保存容器の破損が
生じやすく、強度的にはくずれ易いこと、等々で
ある。これらの欠点のために、長期の貯蔵上安定
性を欠き、特に地震・洪水等の天災など不慮の災
害を予想すると著しく安全性を欠くという難点が
あつた。
放射性物質の水への耐浸出性、熱的安定性及び
機械的強度を比較的大きいものに改善するため、
放射性廃棄物に何らかの添加物を配合し熱処理を
施した固化体が考えられる。この場合、添加剤の
分量が多くなれば、それだけ放射性廃棄物の含有
率が減少するので安全性は高まるが、それだけ貯
蔵の点では効率が低下することになる。従つて、
より効率的に放射性廃棄物を高密度充填すること
ができる添加剤の選択、およびかかる添加剤を用
いた固化体の開発が切望されていた。
従来、かかる固化体の例として、ガラス固化体
が知られている。ガラス固化体は、高濃度の放射
性廃棄物をリン酸もしくはホウケイ酸ガラス等と
ともに溶融後、一定形状のインゴツトに凝固させ
た固化体である。
この方法によれば、ガラスの組成を検討するこ
とにより、放射性物質の水への浸出性が小さく、
機械的強度も比較的大きいガラス固化体を得るこ
とができるが、安定した構造のガラス固化体を得
るためには、か焼体粉末の添加量は、25〜30重量
％が上限であるとされていた。そのため、熱伝導
率が大きいために放熱性がよく、しかして放射性
物質の崩壊熱に対して耐久力があり、しかも、よ
り高密度で放射性廃棄物を充填・固化し得る固化
体、およびその製造方法の開発が望まれていた。
また、固化体中に、モリブデン単体又は、
Na2O・MoO3，K2O・MoO3，Cs2O・MoO3等の
相が構成相として存在すると、これらの相は水に
対する耐浸出性が極めて小さいために、放射性物
質の溶出、更にこれを起点とする固化体の劣化を
もたらすので、特にこれらの相が存在しない固化
体およびその製造方法の確立が望まれていた。
本発明の目的は、放射性廃棄物に金属塩を用
い、セラミツク固化体とすることにより、含有率
が大きくて放射性廃棄物を効率的に貯蔵すること
ができる固化体で、モリブデン相又はNa2O・
MoO3，K2O・MoO3もしくはCs2O・MoO3等の
相を含まないために放射性物質の水への浸出性が
小さく、放熱性・耐熱性に優れ、さらに機械的強
度において優れた固化体を提供することにある。
かかる固化体は放射性廃棄物の安全かつ半永久的
な貯蔵に適するものである。
本発明の固化体は、酸化物に換算してNa2O5
〜40重量％、Fe2O35〜20重量％、MoO35〜15重
量％、ZrO25〜15重量％、CeO22〜10重量％、
Cs2O2〜10重量％、BaO1〜５重量％、SrO1〜５
重量％、Rb2O0.2〜２重量％、Y2O30.2〜２重量
％、NiO0.2〜２重量％、希土類酸化物５〜20重
量％、Cr2O30.2〜２重量％、及びその他の元素酸
化物の組成を含有する放射性廃棄物のか焼体に、
マンガン化合物を30重量％以上（MnO2として）
配合し、溶融を施し固化させて成り、モリブデン
単体、Na2O・MoO3，K2O・MoO3および
Cs2O・MoO3を構成相として含まないセラミツク
固化体であることを特徴とする。（か焼体中に含
まれるその他の酸化物としては、Tc2O7，RuO2，
Rh2O3，PdO，Ag2O，CdO，SnO，SeO2，
TeO2およびアクチニド元素酸化物等があげられ
る。）
本発明における放射性廃棄物のか焼体は、例え
ば使用済核燃料を処理した後、Ｕ，Puを回収し
た残りの放射性廃棄物の他、混床式脱塩器の再生
廃液の濃縮液、建屋から発生する床ドレン・機器
ドレンの濃縮廃液等の放射性物質を含む各種の廃
液又は、原子炉浄化系・燃料プール系・復水系・
ドレン系の各系統から生ずる使用済イオン交換樹
脂やフイルタースラツジ、廃液の凝集沈澱処理に
よつて生じる沈澱スラツジ等の各種の固体廃棄物
をか焼することによつて得られる高濃度または中
低濃度の放射性物質であり、本発明は広い範囲の
放射性廃棄物の処理に利用することができる。
又、本発明で使用するマンガン化合物は、
MnO2又は溶融もしくは焼結処理によりMnO2に
変化する化合物であればよい。溶融、焼結により
MnO2に変化するマンガン化合物としては、例え
ば炭酸マンガン（MnCO3），しゆう酸マンガン
（Mn（COO）22H2O），硝酸マンガン（MnNO3）2
等があげられる。
マンガン化合物をか焼体中に30重量％以上
（MnO2に換算して）配合し、溶融により製造し
たセラミツク固化体は、1000℃以上の高温におい
ても、極めて安定で、か焼体単独で焼結させたも
のに較べ、耐浸出性、熱伝導性、および機械的強
度の点で極めて優れている。しかも、これらの優
れた特性を損うことなく、含有率を最高70重量％
まで高めることができる。
本発明の固化体は、放射性廃棄物のか焼体にマ
ンガン化合物を30重量％以上（MnO2として）配
合、固化させたものであるが、他の物質を更に配
合、固化させることを妨げない。すなわち、ニツ
ケル化合物を１〜10重量％（NiOとして）配合さ
せると、固化体の機械的強度を更に向上させるこ
とができる。配合比を１〜10重量％に制限したの
は10重量％を越えた場合、固化体の耐浸出性の劣
化をもたらし、１重量％未満を配合させてもその
効果があらわれないからである。ニツケル化合物
としては、NiO又は溶融もしくは焼結処理により
NiOとなる化合物、ニツケルアセテート
（C10H14NiO4・4H2O），ニツケルアセチルアセト
ネート（C10H14NiO4），炭酸ニツケル（NiCO3・
2Ni（OH）2・4H2O）等を使用することができる。
また、カルシウム、ストロンチウム、およびバリ
ウムのうち少なくとも一種の金属化合物を１〜15
重量％（CaO，SrO，BaOとして）配合させる
と、固化体の耐浸出性を更に高めることができ
る。配合比を１〜15重量％に制限したのは15重量
％を越えた場合、固化体の耐浸出性の劣化をもた
らし、１重量％未満を配合させてもその効果があ
らわれないからである。これらカルシウム等の化
合物としても最終的に酸化物となるものであれば
使用できる。例えば、炭酸ストロンチウム
（SrCO3），ストロンチウム・ハイドロオキサイド
（Sr（OH）2・8H2O），炭酸バリウム（BaCO3）バ
リウムアセテート（C4H6O4Ba）バリウムハイド
ロオキサイド（Ba（OH）2・8H2O）炭酸カルシウ
ム（CaCO3）又は水酸化カルシウム（Ca（OH）2）
等があげられる。Zr，Ni，Ca等の２種以上を含
む化合物も勿論使用することができる。
本発明の固化体は、次のようにして容易に製造
することができる。
放射性廃棄物のか焼体に、前述のマンガン化合
物を所定量配合し、必要に応じてニツケル化合物
および／またはCa，Sr，Baのうち少なくとも一
種の金属化合物を所定量配合し、十分に混合す
る。放射性廃棄物と金属化合物の混合方法は通常
の粉体混合の他、配合すべき金属化合物の粉末の
表面に被膜を形成する方法。例えば、この粉末に
水を加えて混練してスラリー状にした後、篩を通
して造粒したものを流動床として例えば600℃程
度の温度で放射性廃棄物を粒子の表面に吹きつけ
てもよい。この配合物を容器に装入し、約1600〜
2500℃で溶融し、次に一定形状のインゴツトに凝
固させることにより、セラミツク固化体とするこ
とができる。配合する金属化合物が、炭酸マンガ
ン，しゆう酸マンガン（Mn（COO）22H2O），硝
酸マンガンMnNO3等である場合には、焼結又は
溶融処理により、セラミツク固化体中で最終的に
酸化物（例えばZrO2，NiO，CaO等）に変化す
るように、空気中等の酸化性雰囲気で溶融を行う
必要がある。
本発明の固化体は外部加熱または内部加熱を問
わず既存の溶融方法により製造することができ
る。
本発明の放射性廃棄物の固化体、および固化体
の製造方法により、次のような効果を得ることが
できる。
(1) 放射性廃棄物のか焼体は、例えば第１〜３表
に模擬的に組成を示したように、一般に金属酸
化物から成り、それ自体では焼結固化は比較的
不良であるが、本発明によれば、MnO2のため
に、緻密で強固なセラミツク固化体を得ること
ができる。特に、ニツケル化合物を配合した場
合には、一層機械的強度に優れた固化体を得る
ことができる。
(2) 本発明の固化体中においては、か焼体は、
ZrO2，NiO，CaO等とともに熱的に安定な相
を有している。その結果、長期にわたり放射性
廃棄物を安全に貯蔵することができる。
(3) 本発明の固化体は、耐浸出性においても優れ
ており、特にCa，Sr，Ba等の金属化合物を配
合、固化させた場合には、一層耐浸出性の優れ
たものとなる。
(4) 本発明の固化体には、放射性廃棄物のか焼体
を最高70重量％まで充填することができる。す
なわち、従来のガラス固化体に比し、含有率が
大幅に向上し、その結果、放射性廃棄物を、貯
蔵容器（キヤニスタ）中に高密度充填すること
ができ、キヤニスタの数量を低減することがで
きる。
(5) 固化体をそのまま貯蔵容器に保存してもよい
が、例えば適当なしやへい物を設け、放射線量
を制禦することで食品に放射線を照射し、輸送
及び貯蔵中の腐敗、虫害及び発芽等の防止、保
存期間の延長等の用途に適する。
次に、本発明の実施例および比較例について説
明する。
なお、実施例および比較例で使用する放射性廃
棄物のか焼体として、使用済核燃料を処理した
後、Ｕ，Puを回収した残りの放射性廃棄物のか
焼体の組成を模擬して第１〜３表の組成を有する
３種の粉末を調整した（以下「模擬か焼体」とい
う）。
The present invention relates to a solidified body of radioactive waste and a method for producing the same, and more specifically, the present invention relates to a solidified body of radioactive waste and a method for manufacturing the same, and more specifically, after mixing a manganese compound into a solidified ceramic body containing calcined radioactive waste (referred to as "calcined body") and powder of the calcined body, The present invention relates to a method of producing the solidified ceramic body by melting. The solidified material of the present invention can efficiently store radioactive waste, is chemically and mechanically stable, and is suitable for semi-permanently storing radioactive waste.
In addition, this solidified product may be stored as is in a storage container, but for example, the food can be irradiated with radiation by providing an appropriate container or container to control the radiation dose to prevent spoilage, insect damage, and damage during transportation and storage. It is useful for preventing germination, etc., and extending storage period. As the contribution of nuclear power generation to the electricity supply increases, the amount of highly concentrated radioactive waste fluid generated, especially from spent nuclear fuel reprocessing plants, tends to increase year by year. When storing these waste liquids in tanks, storage space is a problem not only in terms of safety and management, but also in terms of quantity and volume, so there is a strong need for the establishment of a solidified substance that is easy to store and a method for producing it. ing. In general, in solidified radioactive waste and its manufacturing technology, leakage of radioactive materials into the surrounding area is
It is necessary to convert waste into a minimum form, and the converted form must be chemically and mechanically stable and not cause environmental pollution even after long-term storage. In addition, since the amount of radioactive waste is expected to increase in the future, in order to store it efficiently, the ratio of the weight of waste to the sum of the weight of waste and added amount (hereinafter referred to as ``contained amount'') rate"
) is desired to be as large as possible. The radioactive waste solidified body and its manufacturing method of the present invention were developed in response to such demands. Conventionally, it has been proposed to store radioactive waste as a calcined body. Processing temperature
The calcined body is manufactured at 400 to 650℃, and the nitrate component is completely removed.The calcined body made of oxides does not decompose the nitrate component, so it can maintain static stability for a long time. , it had the following drawbacks: In other words, the calcined body alone has poor sintering properties and is prone to scattering of some nuclides, has extremely poor leaching resistance because it is easily soluble in water, and has low thermal conductivity, so it is difficult to sinter radioactive elements. The heat generated by the decay of the container has poor radioactivity, and as a result, the temperature tends to rise during storage.Furthermore, this temperature rise tends to cause damage to the storage container, making it easy to collapse in terms of strength. Because of these shortcomings, it lacks stability in long-term storage, and is particularly unsafe in the face of unexpected natural disasters such as earthquakes and floods. In order to improve the resistance to leaching of radioactive substances into water, thermal stability and mechanical strength to a relatively large degree,
A possible solidified material is radioactive waste mixed with some additives and subjected to heat treatment. In this case, the greater the amount of additive, the lower the content of radioactive waste and the higher the safety, but the lower the efficiency in terms of storage. Therefore,
There has been a strong desire to select additives that can more efficiently pack radioactive waste at high density, and to develop solidified materials using such additives. Conventionally, a vitrified body is known as an example of such a solidified body. The vitrified material is a solidified material obtained by melting highly concentrated radioactive waste together with phosphoric acid or borosilicate glass, and then solidifying it into an ingot of a certain shape. According to this method, by considering the composition of the glass, the leachability of radioactive substances into water is small.
Although it is possible to obtain a vitrified body with relatively high mechanical strength, in order to obtain a vitrified body with a stable structure, the upper limit of the amount of calcined body powder added is 25 to 30% by weight. was. Therefore, we need a solidified material that has good heat dissipation due to its high thermal conductivity, is resistant to the decay heat of radioactive materials, and can be filled and solidified with radioactive waste at a higher density, and its production. Development of a method was desired. In addition, in the solidified body, molybdenum alone or
When phases such as Na 2 O・MoO 3 , K 2 O・MoO 3 , Cs 2 O・MoO 3 are present as constituent phases, these phases have extremely low leaching resistance to water, so they are less likely to elute radioactive substances. Furthermore, since these phases cause deterioration of the solidified product, it has been particularly desired to establish a solidified product in which these phases are not present and a method for producing the same. The object of the present invention is to use metal salts for radioactive waste to form a solidified ceramic material, which has a high content and can efficiently store radioactive waste, and which has a molybdenum phase or Na 2 O.・
Because it does not contain phases such as MoO 3 , K 2 O・MoO 3 or Cs 2 O・MoO 3 , it has low leachability of radioactive substances into water, excellent heat dissipation and heat resistance, and excellent mechanical strength. The objective is to provide a solidified product.
Such solidified bodies are suitable for safe and semi-permanent storage of radioactive waste. The solidified material of the present invention has Na 2 O 5 in terms of oxide.
~40 wt%, Fe2O3 5-20 wt%, MoO3 5-15 wt%, ZrO2 5-15 wt%, CeO2 2-10 wt%,
Cs 2 O2 ~ 10% by weight, BaO 1 ~ 5% by weight, SrO 1 ~ 5
% by weight, Rb 2 O 0.2-2% by weight, Y 2 O 3 0.2-2% by weight, NiO 0.2-2% by weight, rare earth oxides 5-20% by weight, Cr 2 O 3 0.2-2% by weight, and other elemental oxides in the calcined body of radioactive waste,
Manganese compound at least 30% by weight (as MnO2 )
It is made by blending, melting and solidifying, and consists of elemental molybdenum, Na 2 O・MoO 3 , K 2 O・MoO 3 and
It is characterized by being a solidified ceramic that does not contain Cs 2 O/MoO 3 as a constituent phase. (Other oxides contained in the calcined body include Tc 2 O 7 , RuO 2 ,
Rh 2 O 3 , PdO, Ag 2 O, CdO, SnO, SeO 2 ,
Examples include TeO 2 and actinide element oxides. ) The calcined bodies of radioactive waste in the present invention include, for example, radioactive waste remaining after processing spent nuclear fuel and recovering U and Pu, as well as concentrated liquid of recycled waste liquid from a mixed bed desalination machine, and waste from a building. Various waste liquids containing radioactive materials such as concentrated waste liquid from floor drains and equipment drains, reactor purification systems, fuel pool systems, condensate systems, etc.
High concentration or medium-low concentration obtained by calcining various solid wastes such as used ion exchange resin and filter sludge generated from each drain system, and precipitated sludge generated by coagulation and sedimentation treatment of waste liquid. This invention can be used to treat a wide range of radioactive wastes. In addition, the manganese compound used in the present invention is
Any compound may be used as long as it is MnO 2 or a compound that changes to MnO 2 by melting or sintering treatment. By melting and sintering
Examples of manganese compounds that change to MnO 2 include manganese carbonate (MnCO 3 ), manganese oxalate (Mn(COO) 2 2H 2 O), and manganese nitrate (MnNO 3 ) 2
etc. can be mentioned. A solidified ceramic body produced by blending 30% by weight or more of a manganese compound (in terms of MnO 2 ) into a calcined body and melting it is extremely stable even at high temperatures of 1000°C or higher, and the calcined body alone cannot be fired. It is extremely superior in terms of leaching resistance, thermal conductivity, and mechanical strength compared to those made by bonding. Moreover, the content can be reduced to up to 70% by weight without compromising these excellent properties.
It can be increased up to. The solidified body of the present invention is a calcined body of radioactive waste mixed with 30% by weight or more of a manganese compound (as MnO 2 ) and solidified, but this does not prevent other substances from being further blended and solidified. That is, when 1 to 10% by weight (as NiO) of a nickel compound is blended, the mechanical strength of the solidified body can be further improved. The reason why the blending ratio is limited to 1 to 10% by weight is because if it exceeds 10% by weight, the leaching resistance of the solidified product deteriorates, and if it is blended at less than 1% by weight, no effect will be obtained. As a nickel compound, NiO or melted or sintered
Compounds that become NiO, nickel acetate (C 10 H 14 NiO 4 4H 2 O), nickel acetylacetonate (C 10 H 14 NiO 4 ), nickel carbonate (NiCO 3 .
2Ni(OH) 2・4H 2 O) etc. can be used.
In addition, at least one metal compound of calcium, strontium, and barium is added at 1 to 15
When incorporated in weight percent (as CaO, SrO, BaO), the leaching resistance of the solidified material can be further improved. The reason why the blending ratio is limited to 1 to 15% by weight is because if it exceeds 15% by weight, the leaching resistance of the solidified product deteriorates, and if it is blended at less than 1% by weight, no effect will be obtained. Compounds such as calcium can be used as long as they eventually become oxides. For example, strontium carbonate (SrCO 3 ), strontium hydroxide (Sr(OH) 2.8H 2 O), barium carbonate (BaCO 3 ), barium acetate (C 4 H 6 O 4 Ba), barium hydroxide (Ba(OH) 2・8H 2 O) Calcium carbonate (CaCO 3 ) or calcium hydroxide (Ca(OH) 2 )
etc. can be mentioned. Of course, compounds containing two or more of Zr, Ni, Ca, etc. can also be used. The solidified product of the present invention can be easily produced as follows. A predetermined amount of the above-mentioned manganese compound is blended into the calcined body of radioactive waste, and if necessary, a predetermined amount of a nickel compound and/or a metal compound of at least one of Ca, Sr, and Ba is blended and thoroughly mixed. The method of mixing radioactive waste and metal compounds is not only the usual powder mixing, but also the method of forming a film on the surface of the metal compound powder to be mixed. For example, the powder may be kneaded with water to form a slurry, passed through a sieve, granulated, and used as a fluidized bed to spray radioactive waste onto the surface of the particles at a temperature of, for example, about 600°C. This mixture is charged into a container, and approximately 1600 ~
A solidified ceramic can be obtained by melting at 2500°C and then solidifying into an ingot of a certain shape. When the metal compound to be mixed is manganese carbonate, manganese oxalate (Mn(COO) 2 2H 2 O), manganese nitrate MnNO 3 , etc., it is finally dissolved in a solidified ceramic body by sintering or melting treatment. It is necessary to perform melting in an oxidizing atmosphere such as air so that it changes to an oxide (for example, ZrO 2 , NiO, CaO, etc.). The solidified product of the present invention can be produced by any existing melting method, regardless of whether external heating or internal heating is used. By the solidified body of radioactive waste and the method for producing the solidified body of the present invention, the following effects can be obtained. (1) Calcined bodies of radioactive waste are generally made of metal oxides, for example, as shown in the simulated compositions in Tables 1 to 3, and are relatively poorly sintered and solidified by themselves. According to the invention, a dense and strong ceramic solidified body can be obtained because of MnO 2 . In particular, when a nickel compound is blended, a solidified product with even better mechanical strength can be obtained. (2) In the solidified body of the present invention, the calcined body is
It has a thermally stable phase along with ZrO 2 , NiO, CaO, etc. As a result, radioactive waste can be safely stored for a long period of time. (3) The solidified product of the present invention is also excellent in leaching resistance, and in particular, when a metal compound such as Ca, Sr, Ba, etc. is blended and solidified, the leaching resistance becomes even more excellent. (4) The solidified body of the present invention can be filled with up to 70% by weight of calcined radioactive waste. In other words, the content rate is significantly improved compared to conventional vitrified materials, and as a result, radioactive waste can be packed in high density into storage containers (canisters), and the number of canisters can be reduced. can. (5) The solidified product may be stored as is in a storage container, but by controlling the radiation dose by, for example, providing an appropriate container or shield, food can be irradiated with radiation to prevent spoilage, insect damage, and damage during transportation and storage. Suitable for purposes such as preventing germination, extending storage period, etc. Next, examples and comparative examples of the present invention will be described. In addition, as the radioactive waste calcination bodies used in the examples and comparative examples, Nos. 1 to 3 were used to simulate the composition of the radioactive waste calcination bodies from which U and Pu were recovered after processing the spent nuclear fuel. Three types of powders having the compositions shown in the table were prepared (hereinafter referred to as "simulated calcined bodies").
【表】
その他アクチニド元素酸化物
[Table] Other actinide element oxides
【表】
その他アクチニド元素酸化物
[Table] Other actinide element oxides
【表】
その他アクチニド元素酸化物
実施例および比較例で得られた固化体につい
て、機械的強度、浸出率、熱伝導率を測定し、更
にＸ線回析により固化体中にモリブデン単体、
Na2O，MoO3，Cs2O・MoO3，K2O・MoO3の相
が生成しているか否かを調べ第４表(1)，第４表(2)
に示した。なお、機械的強度の測定は固化体より
測定用試験片（３×３×30mmの角柱）を作製し、
三点曲げ法によつて機械的強度（ただし、スパン
長さ20mm印加速度0.5cm／分）を測定した。
浸出率の測定法は（JIS−R3502）の方法に従
つて測定した。また、熱伝導率は室温でレーザフ
ラツシユ法に従つて測定した。
実施例１〜11，比較例１〜10
各実施例および各比較例に係る模擬か焼体と金
属化合物の配合物を、第４表(1)，(2)に示す配合比
で調整した。金属化合物の粉末は、平均粒径2μm
以下のものを用いた。調整した配合物100ｇをカ
ーボン容器の中に充填し、この配合物の中へカー
ボン電極を挿入した。アーク放電により2000℃で
配合物を溶融させた後、冷却して固化体とした。
溶融条件、得られた固化体についての測定結果
を、第４表(1)，(2)に併せ示した。[Table] Other actinide element oxides The mechanical strength, leaching rate, and thermal conductivity of the solidified bodies obtained in Examples and Comparative Examples were measured.
Examine whether phases of Na 2 O, MoO 3 , Cs 2 O・MoO 3 , K 2 O・MoO 3 are generated or not. Table 4 (1), Table 4 (2)
It was shown to. In addition, to measure the mechanical strength, a measurement test piece (3 x 3 x 30 mm square column) was prepared from the solidified body.
Mechanical strength was measured by the three-point bending method (span length 20 mm, applied acceleration 0.5 cm/min). The leaching rate was measured according to the method of (JIS-R3502). Further, the thermal conductivity was measured at room temperature according to the laser flash method. Examples 1 to 11, Comparative Examples 1 to 10 Blends of the simulated calcined body and metal compound according to each of the Examples and Comparative Examples were adjusted at the blending ratios shown in Table 4 (1) and (2). Metal compound powder has an average particle size of 2μm
The following were used. 100 g of the prepared blend was filled into a carbon container, and a carbon electrode was inserted into the blend. After melting the compound at 2000°C by arc discharge, it was cooled to form a solidified body.
The melting conditions and measurement results for the obtained solidified product are also shown in Table 4 (1) and (2).
【表】【table】
【表】【table】
Claims (1)
Fe2O35〜20重量％、MoO35〜15重量％、ZrO25
〜15重量％、CeO22〜10重量％、Cs2O2〜10重量
％、BaO1〜５重量％、SrO1〜５重量％、
Rb2O0.2〜２重量％、Y2O30.2〜２重量％、
NiO0.2〜２重量％、希土類酸化物５〜20重量％、
Cr2O30.2〜２重量％を含有する放射性廃棄物のか
焼体に、マンガン化合物を30重量％以上（MnO2
として）配合し、溶融後冷却を施し固化して成
り、モリブデン単体、Na2O・MoO3、K2O・
MoO3及びCs2O・MoO3を構成層として含まない
ことを特徴とする放射性廃棄物のセラミツク固化
体。 ２ 酸化物に換算してNa2O5〜40重量％、
Fe2O35〜20重量％、MoO35〜15重量％、ZrO25
〜15重量％、CeO22〜10重量％、Cs2O2〜10重量
％、BaO1〜５重量％、SrO1〜５重量％、
Rb2O0.2〜２重量％、Y2O30.2〜２重量％、
NiO0.2〜２重量％、希土類酸化物５〜20重量％、
Cr2O30.2〜２重量％を含有する放射性廃棄物のか
焼体に、マンガン化合物30重量％以上（MnO2と
して）と、ニツケル化合物１〜10重量％（NiOと
して）を配合し、溶融後冷却を施し固化して成
り、モリブデン単体、Na2O・MoO3、K2O・
MoO3及びCs2O・MoO3を構成層として含まない
ことを特徴とする放射性廃棄物のセラミツク固化
体。 ３ 酸化物に換算してNa2O5〜40重量％、
Fe2O35〜20重量％、MoO35〜15重量％、ZrO25
〜15重量％、CeO22〜10重量％、Cs2O2〜10重量
％、BaO1〜５重量％、SrO1〜５重量％、
Rb2O0.2〜２重量％、Y2O30.2〜２重量％、
NiO0.2〜２重量％、希土類酸化物５〜20重量％、
Cr2O30.2〜２重量％を含有する放射性廃棄物のか
焼体に、マンガン化合物30重量％以上（MnO2と
して）と、カルシウム化合物、ストロンチウム化
合物、及びバリウム化合物の少なくとも１種１〜
15重量％（CaO、SrO、BaOとして）を配合し、
溶融後冷却を施し固化して成り、モリブデン単
体、Na2O・MoO3、K2O・MoO3及びCs2O・
MoO3を構成層として含まないことを特徴とする
放射性廃棄物のセラミツク固化体。 ４ 酸化物に換算してNa2O5〜40重量％、
Fe2O35〜20重量％、MoO35〜15重量％、ZrO25
〜15重量％、CeO22〜10重量％、Cs2O2〜10重量
％、BaO1〜５重量％、SrO1〜５重量％、
Rb2O0.2〜２重量％、Y2O30.2〜２重量％、
NiO0.2〜２重量％、希土類酸化物５〜20重量％、
Cr2O30.2〜２重量％を含有する放射性廃棄物のか
焼体に、マンガン化合物30重量％以上（MnO2と
して）と、ニツケル化合物１〜10重量％（NiOと
して）と、カルシウム化合物、ストロンチウム化
合物、及びバリウム化合物の少なくとも１種１〜
15重量％（CaO、SrO、BaOとして）を配合し、
溶融後冷却を施し固化して成り、モリブデン単
体、Na2O・MoO3、K2O・MoO3及びCs2O・
MoO3を構成層として含まないことを特徴とする
放射性廃棄物のセラミツク固化体。 ５ 酸化物に換算してNa2O5〜40重量％、
Fe2O35〜20重量％、MoO35〜15重量％、ZrO25
〜15重量％、CeO22〜10重量％、Cs2O2〜10重量
％、BaO1〜５重量％、SrO1〜５重量％、
Rb2O0.2〜２重量％、Y2O30.2〜２重量％、
NiO0.2〜２重量％、希土類酸化物５〜20重量％、
Cr2O30.2〜２重量％を含有する放射性廃棄物のか
焼体に、マンガン化合物30重量％以上（MnO2と
して）を配合し、溶融後冷却することを特徴とす
る放射性廃棄物のセラミツク固化体の製造法。 ６ 放射性廃棄物のか焼体に、マンガン化合物30
重量％以上（MnO2として）と、ニツケル化合物
１〜10重量％（NiOとして）を配合し、溶融後冷
却する特許請求の範囲第５項記載の放射性廃棄物
のセラミツク固化体の製造法。 ７ 放射性廃棄物のか焼体に、マンガン化合物30
重量％以上（MnO2として）と、カルシウム化合
物、ストロンチウム化合物、及びバリウム化合物
の少なくとも１種１〜15重量％（CaO、SrO、
BaOとして）を配合し、溶融後冷却する特許請
求の範囲第５項記載の放射性廃棄物のセラミツク
固化体の製造法。 ８ 放射性廃棄物のか焼体に、マンガン化合物30
重量％以上（MnO2として）と、ニツケル化合物
１〜10重量％（NiOとして）と、カルシウム化合
物、ストロンチウム化合物、及びバリウム化合物
の少なくとも１種１〜15重量％（CaO、SrO、
CaOとして）を配合し、溶融後冷却する、特許請
求の範囲第５項記載の放射性廃棄物のセラミツク
固化体の製造法。 ９ 酸化物に換算してNa2O5〜40重量％、
Fe2O35〜20重量％、MoO35〜15重量％、ZrO25
〜15重量％、CeO22〜10重量％、Cs2O2〜10重量
％、BaO1〜５重量％、SrO1〜５重量％、
Rb2O0.2〜２重量％、Y2O30.2〜２重量％、
NiO0.2〜２重量％、希土類酸化物５〜20重量％、
Cr2O30.2〜２重量％並びにTc2O7、RuO2、
Rh2O3、PdO、Ag2O、CdO、SnO、SeO2、
TeO2及びアクチニド元素酸化物の少なくとも１
種を含有する放射性廃棄物のか焼体に、マンガン
化合物を30重量％以上（MnO2として）配合し、
溶融後冷却を施し固化して成り、モリブデン単
体、Na2O・MoO3、K2O・MoO3及びCs2O・
MoO3を構成層として含まないことを特徴とする
放射性廃棄物のセラミツク固化体。[Claims] 1. 5 to 40% by weight of Na 2 O in terms of oxide,
Fe2O3 5 ~20wt%, MoO3 5~15wt%, ZrO25
~15% by weight, CeO2 2 ~10% by weight, Cs2O2 ~10% by weight, BaO1~5% by weight, SrO1~5% by weight,
Rb 2 O 0.2-2% by weight, Y 2 O 3 0.2-2% by weight,
NiO 0.2-2% by weight, rare earth oxides 5-20% by weight,
A manganese compound (MnO 2
) , melted and then cooled to solidify.
A ceramic solidified body of radioactive waste characterized by not containing MoO 3 or Cs 2 O/MoO 3 as a constituent layer. 2 Na 2 O 5 to 40% by weight in terms of oxides,
Fe2O3 5 ~20wt%, MoO3 5~15wt%, ZrO25
~15% by weight, CeO2 2 ~10% by weight, Cs2O2 ~10% by weight, BaO1~5% by weight, SrO1~5% by weight,
Rb 2 O 0.2-2% by weight, Y 2 O 3 0.2-2% by weight,
NiO 0.2-2% by weight, rare earth oxides 5-20% by weight,
A calcined body of radioactive waste containing 0.2 to 2% by weight of Cr 2 O 3 is blended with 30% by weight or more of a manganese compound (as MnO 2 ) and 1 to 10% by weight of a nickel compound (as NiO), and after melting. It is made by cooling and solidifying, and consists of simple molybdenum, Na 2 O・MoO 3 , K 2 O・
A ceramic solidified body of radioactive waste characterized by not containing MoO 3 or Cs 2 O/MoO 3 as a constituent layer. 3 Na 2 O 5 to 40% by weight in terms of oxides,
Fe2O3 5 ~20wt%, MoO3 5~15wt%, ZrO25
~15% by weight, CeO2 2 ~10% by weight, Cs2O2 ~10% by weight, BaO1~5% by weight, SrO1~5% by weight,
Rb 2 O 0.2-2% by weight, Y 2 O 3 0.2-2% by weight,
NiO 0.2-2% by weight, rare earth oxides 5-20% by weight,
A calcined body of radioactive waste containing 0.2 to 2% by weight of Cr 2 O 3 is added with 30% by weight or more of a manganese compound (as MnO 2 ) and at least one of a calcium compound, a strontium compound, and a barium compound.
Contains 15% by weight (as CaO, SrO, BaO),
It is made by cooling and solidifying after melting, and contains elemental molybdenum, Na 2 O・MoO 3 , K 2 O・MoO 3 and Cs 2 O・
A ceramic solidified body of radioactive waste characterized by not containing MoO 3 as a constituent layer. 4 5 to 40% by weight of Na 2 O in terms of oxides,
Fe2O3 5 ~20wt%, MoO3 5~15wt%, ZrO25
~15% by weight, CeO2 2 ~10% by weight, Cs2O2 ~10% by weight, BaO1~5% by weight, SrO1~5% by weight,
Rb 2 O 0.2-2% by weight, Y 2 O 3 0.2-2% by weight,
NiO 0.2-2% by weight, rare earth oxides 5-20% by weight,
The calcined body of radioactive waste containing 0.2-2% by weight of Cr 2 O 3 is combined with at least 30% by weight of manganese compounds (as MnO 2 ), 1-10% by weight of nickel compounds (as NiO), calcium compounds, and strontium. compound, and at least one barium compound 1-
Contains 15% by weight (as CaO, SrO, BaO),
It is made by cooling and solidifying after melting, and contains elemental molybdenum, Na 2 O・MoO 3 , K 2 O・MoO 3 and Cs 2 O・
A ceramic solidified body of radioactive waste characterized by not containing MoO 3 as a constituent layer. 5 Na 2 O 5-40% by weight in terms of oxides,
Fe2O3 5 ~20wt%, MoO3 5~15wt%, ZrO25
~15% by weight, CeO2 2 ~10% by weight, Cs2O2 ~10% by weight, BaO1~5% by weight, SrO1~5% by weight,
Rb 2 O 0.2-2% by weight, Y 2 O 3 0.2-2% by weight,
NiO 0.2-2% by weight, rare earth oxides 5-20% by weight,
Ceramic solidification of radioactive waste characterized by blending 30% by weight or more of a manganese compound (as MnO 2 ) into a calcined body of radioactive waste containing 0.2 to 2% by weight of Cr 2 O 3 and cooling it after melting. How the body is manufactured. 6 Manganese compound 30 in the calcined body of radioactive waste
A method for producing a ceramic solidified body of radioactive waste according to claim 5, wherein at least 1% by weight (as MnO 2 ) and 1 to 10% by weight (as NiO) of a nickel compound are blended, melted, and then cooled. 7 Manganese compounds 30% in calcined bodies of radioactive waste
% by weight or more (as MnO 2 ) and 1 to 15% by weight of at least one of calcium compounds, strontium compounds, and barium compounds (CaO, SrO,
6. A method for producing a ceramic solidified body of radioactive waste according to claim 5, wherein the solidified ceramic body of radioactive waste is blended with BaO), melted, and then cooled. 8 Manganese compound 30% in the calcined body of radioactive waste
% by weight or more (as MnO2 ), 1-10% by weight of a nickel compound (as NiO), and 1-15% by weight of at least one of a calcium compound, a strontium compound, and a barium compound (CaO, SrO,
6. A method for producing a ceramic solidified body of radioactive waste according to claim 5, wherein the solidified ceramic body of radioactive waste is blended with CaO (as CaO), melted, and then cooled. 9 5 to 40% by weight of Na 2 O in terms of oxides,
Fe2O3 5 ~20wt%, MoO3 5~15wt%, ZrO25
~15% by weight, CeO2 2 ~10% by weight, Cs2O2 ~10% by weight, BaO1~5% by weight, SrO1~5% by weight,
Rb 2 O 0.2-2% by weight, Y 2 O 3 0.2-2% by weight,
NiO 0.2-2% by weight, rare earth oxides 5-20% by weight,
Cr 2 O 3 0.2-2% by weight and Tc 2 O 7 , RuO 2 ,
Rh2O3 , PdO, Ag2O , CdO, SnO , SeO2 ,
TeO 2 and at least one of actinide element oxides
Adding 30% by weight or more of a manganese compound (as MnO 2 ) to the calcined body of radioactive waste containing seeds,
It is made by cooling and solidifying after melting, and contains elemental molybdenum, Na 2 O・MoO 3 , K 2 O・MoO 3 and Cs 2 O・
A ceramic solidified body of radioactive waste characterized by not containing MoO 3 as a constituent layer.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP11789379A JPS5642198A (en) | 1979-09-17 | 1979-09-17 | Ceramiccsolidified radioactive waste products and preparing same |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP11789379A JPS5642198A (en) | 1979-09-17 | 1979-09-17 | Ceramiccsolidified radioactive waste products and preparing same |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5642198A JPS5642198A (en) | 1981-04-20 |
| JPS631560B2 true JPS631560B2 (en) | 1988-01-13 |
Family
ID=14722817
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP11789379A Granted JPS5642198A (en) | 1979-09-17 | 1979-09-17 | Ceramiccsolidified radioactive waste products and preparing same |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5642198A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| AU3183797A (en) * | 1996-07-04 | 1998-02-02 | British Nuclear Fuels Plc | Encapsulation of waste |
-
1979
- 1979-09-17 JP JP11789379A patent/JPS5642198A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5642198A (en) | 1981-04-20 |
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