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PYRO, a system for modeling fuel reprocessing

Conference · · Transactions of the American Nuclear Society; (USA)
OSTI ID:6927900
Compact, on-site fuel reprocessing and waste management for the Integral Fast Reactor are based on the pyrochemical reprocessing of metal fuel. In that process, uranium and plutonium in spent fuel are separated from fission products in an electrorefiner using liquid cadmium and molten salt solvents. Quantitative estimates of the distribution of the chemical elements among the metal and salt phases are essential for development of both individual pyrochemical process steps and the complete process. This paper describes the PYRO system of programs used to generate reliable mass flows and compositions.
OSTI ID:
6927900
Report Number(s):
CONF-891103--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 60
Country of Publication:
United States
Language:
English

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Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
052001 -- Nuclear Fuels-- Waste Processing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
ACCOUNTING
ALGORITHMS
ANL
CADMIUM
CHEMICAL COMPOSITION
CHEMICAL REACTIONS
COMPUTER CODES
DEMONSTRATION PROGRAMS
ELEMENTS
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FISSION PRODUCTS
FUEL CYCLE
FUELS
HIGH-LEVEL RADIOACTIVE WASTES
IFR REACTOR
ISOTOPES
MANAGEMENT
MATERIALS
MATHEMATICAL LOGIC
METALS
NATIONAL ORGANIZATIONS
NUCLEAR FUELS
OPERATION
P CODES
PLANNING
PROCESSING
PYROCHEMICAL REPROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
REACTOR MATERIALS
REACTORS
REPROCESSING
RESEARCH AND TEST REACTORS
SEPARATION PROCESSES
SPENT FUELS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
ZERO POWER REACTORS