Graphical and tabular summaries of decay characteristics for once-through PWR, LMFBR, and FFTF fuel cycle materials. [Spent fuel, high-level waste fuel can scrap]
Based on the results of ORIGEN2 and a newly developed code called ORMANG, graphical and summary tabular characteristics of spent fuel, high-level waste, and fuel assembly structural material (cladding) waste are presented for a generic pressurized-water reactor (PWR), a liquid-metal fast breeder reactor (LMFBR), and the Fast Flux Test Facility (FFTF). The characteristics include radioactivity, thermal power, and toxicity (water dilution volume). Given are graphs and summary tables containing characteristic totals and the principal nuclide contributors as well as graphs comparing the three reactors for a single material and the three materials for a single reactor.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6858000
- Report Number(s):
- ORNL/TM-8061; ON: DE82007128
- Resource Relation:
- Other Information: Portions of document are illegible
- Country of Publication:
- United States
- Language:
- English
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Graphical and tabular summaries of decay characteristics for once-through PWR, LMFBR, and FFTF fuel cycle materials. [Spent fuel, high-level waste fuel can scrap]
Decay characteristics of once-through LWR and LMFBR spent fuels, high-level wastes, and fuel-assembly structural material wastes
ORIGEN2 model and results for the Clinch River Breeder Reactor
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Fri Jan 01 00:00:00 EST 1982
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OSTI ID:6858000
Decay characteristics of once-through LWR and LMFBR spent fuels, high-level wastes, and fuel-assembly structural material wastes
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Sat Nov 01 00:00:00 EST 1980
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OSTI ID:6858000
ORIGEN2 model and results for the Clinch River Breeder Reactor
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Tue Jun 01 00:00:00 EDT 1982
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12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
FFTF REACTOR
RADIOACTIVE WASTES
LMFBR TYPE REACTORS
PWR TYPE REACTORS
RADIOACTIVITY
RESIDUAL POWER
TOXICITY
SPENT FUELS
AFTER-HEAT
COMPUTER CODES
FUEL CANS
HIGH-LEVEL RADIOACTIVE WASTES
O CODES
SCRAP
THEORETICAL DATA
BREEDER REACTORS
DATA
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
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LIQUID METAL COOLED REACTORS
MATERIALS
NUCLEAR FUELS
NUCLEAR POWER
NUMERICAL DATA
POWER
RADIOACTIVE MATERIALS
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RESEARCH AND TEST REACTORS
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WATER MODERATED REACTORS
210802* - Nuclear Power Plants- Economics- Fuel Cycle
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