The effect of swelling in Inconel 600 on the performance of FFTF (Fast Flux Test Facility) reflector assemblies
The Fast Flux Test Facility (FFTF) is designed with non-fueled outer row assemblies, each of which consists of a stack of Inconel 600 blocks penetrated by 316 stainless steel (SS) coolant tubes. These assemblies act as a radial neutron reflector and as a straight but flexible core boundary. During an FFTF refueling outage it was observed that the degree of difficulty in withdrawing an outer row driver fuel assembly was a function of the peak fast fluence of neighboring reflector assemblies. It was subsequently determined through various postirradiation examinations that the reflector assemblies were both bowed and stiff. Measurements of the individual Inconel 600 blocks indicated that the blocks had distorted into a trapezoidal cross section due to differential swelling of Inconel 600 in a steep radial flux gradient. Immersion density results indicate greater irradiation induced volumetric swelling than any previously reported data or correlation for Inconel 600 at equivalent fast fluence. The Inconel 600 swelled approximately the same amount as the SA 316 SS reflector components. Transmission electron microscopy studies on the Inconel blocks and swelling measurements on related materials have been performed and these data have been related to the performance of the reflector materials.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 6299173
- Report Number(s):
- HEDL-SA-3388-FP; CONF-860605-46; ON: DE87014366
- Resource Relation:
- Conference: 13. international symposium on the effects of radiation on materials, Seattle, WA, USA, 23 Jun 1986; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
Nonlinear, inelastic fast reactor subassembly interaction analyses
Performance of titanium stabilized D9 cladding and ducts
Related Subjects
36 MATERIALS SCIENCE
FFTF REACTOR
FUEL ASSEMBLIES
INCONEL 600
PERFORMANCE
PHYSICAL RADIATION EFFECTS
POST-IRRADIATION EXAMINATION
REACTOR MATERIALS
STAINLESS STEEL-316
SWELLING
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FAST REACTORS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INCONEL ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
RADIATION EFFECTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
STAINLESS STEELS
STEELS
TEST REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties