Feasibility evaluation of x-ray imaging for measurement of fuel rod bowing in CFTL test bundles

Technical Report · Sun Jun 01 04:00:00 EDT 1980

DOI:https://doi.org/10.2172/5437589· OSTI ID:5437589

Baker, S. P.

The Core Flow Test Loop (CFTL) is a high temperature, high pressure, out-of-reactor helium-circulating system. It is designed for detailed study of the thermomechanical performance, at prototypic steady-state and transient operating conditions, of electrically heated rods that simulate segments of core assemblies in the Gas-Cooled Fast Breeder reactor demonstration plant. Results are presented of a feasibility evaluation of x-ray imaging for making measurements of the displacement (bowing) of fuel rods in CFTL test bundles containing electrically heated rods. A mock-up of a representative CFTL test section consisting of a test bundle and associated piping was fabricated to assist in this evaluation.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5437589
• Report Number(s): ORNL/TM-7208
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
DEFORMATION
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUEL RODS
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HELIUM COOLED REACTORS
INDUSTRIAL RADIOGRAPHY
MATERIALS TESTING
NONDESTRUCTIVE TESTING
PERFORMANCE
REACTOR COMPONENTS
REACTORS
TEST FACILITIES
TESTING
X-RAY RADIOGRAPHY