SPERT PROJECT. Quarterly Technical Report, July--September 1967.
Technical Report
·
OSTI ID:4487257
- ed.
- Research Organization:
- Phillips Petroleum Co., Idaho Falls, Idaho. Atomic Energy Div.
- DOE Contract Number:
- AT(10-1)-205
- NSA Number:
- NSA-22-048648
- OSTI ID:
- 4487257
- Report Number(s):
- IDO--17271
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BEHAVIOR
BURNOUT
CANNING
DEFORMATION
DESIGN
EXCURSIONS
FUEL ELEMENTS
HEAT TRANSFER
HOT SPOTS
INSPECTION
MEASUREMENT
MOCKUP
N38180* --Power Reactor Development--Safety & Siting
NUMERICALS
OPERATION
OXIDES
PERFORMANCE
POWER
PRESSURE
REACTIVITY
REACTIVITY/effects on pressurized-water reactor peak power
analysis of reactor behavior during
REACTOR CORE
REACTOR FUEL ELEMENTS/temperatures of oxide
effects of initial system temperature and reactor period on hot-spot
REACTOR PERIOD
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS/excursions in SPERT pressurized-water oxide core mockup
effects of cold-startup and hot-standby conditions on short-period
REACTOR SAFETY EXPERIMENTS/fuel rods for SPERT
design characteristics of F-type
REACTORS
REACTORS
PRESSURIZED-WATER/excursions in
measurement and analysis of effects of cold-startup and hot-standby conditions short-period
REACTORS
PRESSURIZED-WATER/power transients in
effects of step-reactivity insertions on
RELIABILITY
RESEARCH REACTORS
RODS
SPERT-4
STARTUP
TEMPERATURE
TESTING
TRANSIENTS
WATER COOLANT
BURNOUT
CANNING
DEFORMATION
DESIGN
EXCURSIONS
FUEL ELEMENTS
HEAT TRANSFER
HOT SPOTS
INSPECTION
MEASUREMENT
MOCKUP
N38180* --Power Reactor Development--Safety & Siting
NUMERICALS
OPERATION
OXIDES
PERFORMANCE
POWER
PRESSURE
REACTIVITY
REACTIVITY/effects on pressurized-water reactor peak power
analysis of reactor behavior during
REACTOR CORE
REACTOR FUEL ELEMENTS/temperatures of oxide
effects of initial system temperature and reactor period on hot-spot
REACTOR PERIOD
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS/excursions in SPERT pressurized-water oxide core mockup
effects of cold-startup and hot-standby conditions on short-period
REACTOR SAFETY EXPERIMENTS/fuel rods for SPERT
design characteristics of F-type
REACTORS
REACTORS
PRESSURIZED-WATER/excursions in
measurement and analysis of effects of cold-startup and hot-standby conditions short-period
REACTORS
PRESSURIZED-WATER/power transients in
effects of step-reactivity insertions on
RELIABILITY
RESEARCH REACTORS
RODS
SPERT-4
STARTUP
TEMPERATURE
TESTING
TRANSIENTS
WATER COOLANT