WASTE RESIN PROCESSING METHOD AND WASTE RESIN PROCESSING SYSTEM

• Main Authors: OYA YASUMASA, MUKAI YOSUKE, HAMAGUCHI RYOKICHI, TANIUCHI TOSHINORI, OGAWA NAOKI
• Format: Patent
• Language: English; Japanese
• Published: 02.08.2018
• Subjects: DECONTAMINATION ARRANGEMENTS THEREFOR; NUCLEAR ENGINEERING; NUCLEAR PHYSICS; PHYSICS; PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULARRADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL

PROBLEM TO BE SOLVED: To provide a processing method for waste ion exchange resin which reduces a high dose radioactive waste amount generated by cement solidification .SOLUTION: The waste resin processing method includes: a separation step S1 for separating a mixed ion exchange resin absorbing a radioactive nuclide into an anion exchange resin and a cation exchange resin by specific gravity separation; an elution step S2 for supplying a sulfuric acid solution to the cation exchange resin separated at the separation step S1 so as to elute the radioactive nuclide from the cation exchange resin; a recovery step S4 for recovering at least a part of sulfuric acid via a diffusion permeable membrane from the eluted solution which is the sulphuric acid solution including the radioactive nuclide eluted at the elution step S2; a sulfuric acid removal step S5 for causing an eluted waste solution which is the eluted solution from which the sulfuric acid is recovered at the recovery step S4 to pass through the anion exchange resin so as to remove the sulfuric acid remaining in the eluted waste solution; and an eluted waste solution solidification step S7 for concentrating a sulfuric acid removed waste solution which is the eluted waste solution from which the sulfuric acid is removed at the sulfuric acid removal step S5 to cement-solidifying it.SELECTED DRAWING: Figure 2 【課題】セメント固化によって生じる高線量の放射性廃棄物量を低減する廃イオン交換樹脂の処理方法を提供する。【解決手段】廃樹脂処理方法は、放射性核種を吸着した混合イオン交換樹脂を、比重分離によってアニオン交換樹脂とカチオン交換樹脂とに分離する分離工程Ｓ１と、分離工程Ｓ１で分離されたカチオン交換樹脂に硫酸溶液を供給し、カチオン交換樹脂から放射性核種を溶離する溶離工程Ｓ２と、溶離工程Ｓ２で溶離された放射性核種を含む硫酸溶液である溶離液から、拡散透析膜を介して硫酸の少なくとも一部を回収する回収工程Ｓ４と、回収工程Ｓ４で硫酸を回収された溶離液である溶離廃液をアニオン交換樹脂に通水し、溶離廃液に残存する硫酸を除去する硫酸除去工程Ｓ５と、硫酸除去工程Ｓ５で硫酸が除去された溶離廃液である硫酸除去廃液を濃縮させてセメント固化する溶離廃液固化工程Ｓ７と、を含む。【選択図】図２