Resin-Based Preparation of HTGR Fuels: Uranium Loading Development Studies
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:4111971
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Uranium leading flowsheet conditions for recycle 233U were investigated and demonstrated in engineering equipment. Calculations made to estimate the capacities of equipment which is geometrically safe with respect to control of nuclear criticality indicate 100 kg/day or more of uranium for a single nitrate extraction line with four batch loading contactors. The four batch contactors might be replaced by a single continuous resin loading contactor of a modified Higgins contactor design. The resin loading process using solvent extraction of nitrate appears practical for use in a commercial-scale HTGR fuel recycle plant.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Energy Research and Development Administration (ERDA)
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-33-014360
- OSTI ID:
- 4111971
- Report Number(s):
- CONF-751101--26
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Issue: 1 Journal Volume: 22
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
*FUEL PARTICLES-- CHEMICAL PREPARATION
*HTGR TYPE REACTORS-- FUEL CYCLE
*URANIUM 233-- ADSORPTION
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AMINES
CATIONS
FLOWSHEETS
Fuel Kernel
Fuel Recycle Plant
High Temperature Gas-Cooled Reactors (HTGRs)
ION EXCHANGE MATERIALS
Modified Higgins Contactor Design
NITRIC ACID
Nuclear Criticality Safety Program (NCSP)
REPROCESSING
RESINS
SOLVENT EXTRACTION
URANYL NITRATES
Uranium Leading Flowsheet Conditions
*HTGR TYPE REACTORS-- FUEL CYCLE
*URANIUM 233-- ADSORPTION
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AMINES
CATIONS
FLOWSHEETS
Fuel Kernel
Fuel Recycle Plant
High Temperature Gas-Cooled Reactors (HTGRs)
ION EXCHANGE MATERIALS
Modified Higgins Contactor Design
NITRIC ACID
Nuclear Criticality Safety Program (NCSP)
REPROCESSING
RESINS
SOLVENT EXTRACTION
URANYL NITRATES
Uranium Leading Flowsheet Conditions