Deshingkar et al., 1993 - Google Patents
Counter current studies on actinide partitioning from sulphate bearing simulated high level waste using CMPODeshingkar et al., 1993
View PDF- Document ID
- 18338861396385965357
- Author
- Deshingkar D
- Chitnis R
- Wattal P
- Theyyunni T
- Ramanujam A
- Dhami P
- Gopalakrishnan V
- Rao M
- Mathur J
- Murali M
- Iyer R
- Badheka L
- Banerji A
- Publication year
External Links
Snippet
High level wastes< HLW> arising from fuel reprocessing plants contain small quantities of actinides like plutonium, uranium and americium in addition to fission products. Removal of these ace in idea prior to vitrification of HLW can effectively reduce the active surveillance …
- 239000002927 high level radioactive waste 0 title abstract description 57
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
- G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/16—Processing by fixation in stable solid media
- G21F9/167—Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tars
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/20—Disposal of liquid waste
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/001—Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
- G21F9/002—Decontamination of the surface of objects with chemical or electrochemical processes
- G21F9/004—Decontamination of the surface of objects with chemical or electrochemical processes of metallic surfaces
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/001—Recovery of specific isotopes from irradiated targets
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Zhu et al. | Chinese experience in the removal of actinides from highly active waste by trialkylphosphine-oxide extraction | |
Mathur et al. | Partitioning of actinides from high-level waste streams of PUREX process using mixtures of CMPO and TBP in dodecane | |
US8354085B1 (en) | Actinide and lanthanide separation process (ALSEP) | |
Ozawa et al. | Partitioning of Actinides and Fission Products in Highly-active Raffin Ate from Purex Process by Mixer-settlers | |
Musikas et al. | Solvent extraction in nuclear science and technology | |
Vandegrift et al. | Lab-scale demonstration of the UREX+ process | |
Pereira et al. | Lab-scale demonstration of the UREX+ 2 process using spent fuel | |
Liljenzin et al. | Reducing the long-term hazard of reactor waste through actinide removal and destruction in nuclear reactors | |
Van Hecke et al. | Research on advanced aqueous reprocessing of spent nuclear fuel: literature study | |
Deshingkar et al. | Counter current studies on actinide partitioning from sulphate bearing simulated high level waste using CMPO | |
Horwitz et al. | Combined TRU-Sr extraction/recovery process | |
Antonya et al. | Separation of trivalent actinides from high-active waste | |
Kubota et al. | Development of the four group partitioning process at JAERI | |
Deshingkar et al. | Partitioning of actinide from simulated high level wastes arising from reprocessing of PHWR fuels: counter current extraction studies using CMPO | |
Castano | Nuclear fuel reprocessing | |
Horwitz et al. | Combined TRUEX-SREX extraction/recovery process | |
Xu et al. | An overview of R&D activities on high level liquid waste partitioning at Tsinghua University, China | |
Yim | Spent fuel reprocessing and nuclear waste transmutation | |
Venkatesan et al. | Advanced flow-sheet for partitioning of trivalent actinides from fast reactor high active waste | |
Romanovsky | Management of accumulated high level waste at the Mayak Production Association in the Russian Federation | |
Sypuła | Innovative SANEX process for trivalent actinides separation from PUREX raffinate | |
Paviet et al. | Nuclear Fuel Recycling | |
Choppin | Overview of chemical separation methods and technologies | |
Brewer et al. | Actinide partitioning from actual ICPP dissolved zirconium calcine using the TRUEX solvent | |
Bhattacharyya et al. | Evaluation of Lanthanide/Actinide separation using an aqueous soluble BTP derivative |