Nineteenth Annual Actinide Separations Conference: Conference Program and Abstracts
Conference
·
OSTI ID:219302
- Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
This report contains the abstracts from the conference presentations. Sessions were divided into the following topics: Waste treatment; Spent fuel treatment; Issues and responses to Defense Nuclear Facility Safety Board 94-1; Pyrochemical technologies; Disposition technologies; and Aqueous separation technologies.
- Research Organization:
- Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 219302
- Report Number(s):
- CONF-9506176-Absts.; L-19639-1; ON: DE96008497; TRN: 96:010690
- Resource Relation:
- Conference: 19. Annual Actinide Separations Conference, Monterey, CA (United States), 12-15 Jun 1995; Other Information: PBD: [1995]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
96 KNOWLEDGE MANAGEMENT AND PRESERVATION
ACTINIDES
SEPARATION PROCESSES
MEETINGS
RADIOACTIVE WASTE PROCESSING
TRUEX PROCESS
MATHEMATICAL MODELS
SOLUBILITY
HIGH-LEVEL RADIOACTIVE WASTES
PLUTONIUM
ALPHA-BEARING WASTES
ALKALINE HYDROLYSIS
SPENT FUELS
DECLADDING
STORAGE FACILITIES
REMEDIAL ACTION
AMERICIUM
CURIUM
SCRAP METALS
RADIOACTIVE WASTE STORAGE
ELECTROLYSIS
URANIUM
DISTILLATION
PYROCHEMICAL REPROCESSING
EVAPORATION
VITRIFICATION
SYNTHETIC ROCKS
EXTRACTION CHROMATOGRAPHY
SORPTION
SOLVENT EXTRACTION
CRITICALITY
RADIOISOTOPE SCANNERS
RADIOACTIVE WASTE DISPOSAL
Nuclear Criticality Safety Program (NCSP)
Waste Treatment
Spent Fuel Treatment
Issues and Responses to Defense Nuclear Facility Safety Board 94-1
Pyrochemical Technologies
Disposition Technologies
Aqueous Separation Technologies
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
96 KNOWLEDGE MANAGEMENT AND PRESERVATION
ACTINIDES
SEPARATION PROCESSES
MEETINGS
RADIOACTIVE WASTE PROCESSING
TRUEX PROCESS
MATHEMATICAL MODELS
SOLUBILITY
HIGH-LEVEL RADIOACTIVE WASTES
PLUTONIUM
ALPHA-BEARING WASTES
ALKALINE HYDROLYSIS
SPENT FUELS
DECLADDING
STORAGE FACILITIES
REMEDIAL ACTION
AMERICIUM
CURIUM
SCRAP METALS
RADIOACTIVE WASTE STORAGE
ELECTROLYSIS
URANIUM
DISTILLATION
PYROCHEMICAL REPROCESSING
EVAPORATION
VITRIFICATION
SYNTHETIC ROCKS
EXTRACTION CHROMATOGRAPHY
SORPTION
SOLVENT EXTRACTION
CRITICALITY
RADIOISOTOPE SCANNERS
RADIOACTIVE WASTE DISPOSAL
Nuclear Criticality Safety Program (NCSP)
Waste Treatment
Spent Fuel Treatment
Issues and Responses to Defense Nuclear Facility Safety Board 94-1
Pyrochemical Technologies
Disposition Technologies
Aqueous Separation Technologies