Experiment Description for PNL Mixed Oxides (UO2-PuO2) Irradiations in the General Electric Test Reactor
- Battelle Pacific Northwest Labs., Richland, WA (United States)
A fuel irradiation test program and capsule design is described for the evaluation of the steady state and transient performance characteristics of prototypic FTR length fuel pins. The fuel pins to be tested comprise 31 in. of mixed oxide (75% UO2-25%PuO2) fuel pellets clad in 0.250 in. diameter type 304 stainless steel. The fuel pellets are 93% of theoretical density (TD) and with a 0.006 in. diametrical gap the fuel has an 88% TD smeared density. The capsule is a NaK bonded instrumented assembly designed to produce a fuel pin cladding surface temperature of 800 °F and fuel central temperature of 4000 °F when the fuel pin is producing 14.5 kW/ft (axial peak). The safety analysis, heat transfer calculations and operating instructions are also described.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- DOE Contract Number:
- AT(45-1)-1830
- NSA Number:
- NSA-24-046080
- OSTI ID:
- 4086233
- Report Number(s):
- BNWL-1382
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CAPSULES
Criticality
DESIGN
FTR
FUEL CANS
FUEL ELEMENTS
FUEL PINS
FUELS
Fuel
Fuel Pellets
Fuel Pins
GETR
HEAT TRANSFER
IRRADIATION
Irradiation
N38550* --Research & Test Reactors & Critical Assemblies-- Fuels
Nuclear Criticality Safety Program (NCSP)
OPERATION
PERFORMANCE
PLUTONIUM OXIDES
RESEARCH REACTORS
SAFETY
STAINLESS STEELS
Safety Analysis
TD
TESTING
Test Program
Theoretical Density
URANIUM DIOXIDE
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CAPSULES
Criticality
DESIGN
FTR
FUEL CANS
FUEL ELEMENTS
FUEL PINS
FUELS
Fuel
Fuel Pellets
Fuel Pins
GETR
HEAT TRANSFER
IRRADIATION
Irradiation
N38550* --Research & Test Reactors & Critical Assemblies-- Fuels
Nuclear Criticality Safety Program (NCSP)
OPERATION
PERFORMANCE
PLUTONIUM OXIDES
RESEARCH REACTORS
SAFETY
STAINLESS STEELS
Safety Analysis
TD
TESTING
Test Program
Theoretical Density
URANIUM DIOXIDE