Operational transient test series OPTRAN 1-2: experiment specification document. [BWR]
Technical Report
·
OSTI ID:6240616
Several test series are being conducted in the Power Burst Facility (PBF) to determine the behavior of light water reactor fuel rods during transient reactor conditions. The PBF Operational Transient (OPTRAN) test series has the overall objective of evaluating fuel rod behavior during conditions simulating anticipated operational transients with and without scram in light water reactors. Test OPTRAN 1-2, the second in the series, will be comprised of four preirradiated GE BWR/6-type fuel rods (8 x 8 configuration) each shrouded for environmental isolation. Included are the specifications for the fuel rods, the test train assembly, and the instrumentation. Complete information on the design characteristics of the irradiated GE BWR/6 fuel rods is not available at the present time.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6240616
- Report Number(s):
- TFBP-TR-317
- Country of Publication:
- United States
- Language:
- English
Similar Records
Test OPTRAN 1-1 results. [BWR]
Experimental results of the operational transient (OPTRAN) tests 1-1 and 1-2 in the Power Burst Facility
Experiment requirements for the study of anticipated transients with and without scram. [BWR; PWR]
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6546002
Experimental results of the operational transient (OPTRAN) tests 1-1 and 1-2 in the Power Burst Facility
Technical Report
·
Sat Jun 01 00:00:00 EDT 1985
·
OSTI ID:5341414
Experiment requirements for the study of anticipated transients with and without scram. [BWR; PWR]
Technical Report
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:6494116
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
BWR TYPE REACTORS
FUEL ASSEMBLIES
PBF REACTOR
PULSED REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
SAFETY
SPECIFICATIONS
TANK TYPE REACTORS
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
BWR TYPE REACTORS
FUEL ASSEMBLIES
PBF REACTOR
PULSED REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
SAFETY
SPECIFICATIONS
TANK TYPE REACTORS
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS