The effect of swelling in Inconel 600 on the performance of FFTF reflector assemblies
- 1. Hanford Engineering Development Lab., P.O. Box 1970, Richland, WA (USA)
Description
The fast flux test facility (FFTF) is designed with nonfueled 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 because of 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 material have been performed, and these data have been related to the performance of the reflector materials
Additional details
Publishing Information
- Publisher
- ASTM.
- Imprint Place
- Philadelphia, PA (USA)
- ISBN
- 0-8031-0962-8
- Imprint Title
- Radiation-induced changes in microstructure: ASTM 13th international symposium (Part I)
- Journal Page Range
- p. 207-219.
Conference
- Title
- 13. international symposium on the effects of radiation on materials.
- Dates
- 23-25 Jun 1986.
- Place
- Seattle, WA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19098997
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOY-NI76CR15FE8; DAMAGING NEUTRON FLUENCE; FFTF REACTOR; FUEL ASSEMBLIES; HEAT EXCHANGERS; NEUTRON REFLECTORS; PHYSICAL RADIATION EFFECTS; REACTOR COOLING SYSTEMS; SWELLING; TENSILE PROPERTIES; TRANSMISSION ELECTRON MICROSCO; TUBES
- Descriptors DEC
- ALLOYS; ALUMINIUM ADDITIONS; CHROMIUM ALLOYS; COOLING SYSTEMS; CORROSION RESISTANT ALLOYS; DEFORMATION; ELECTRON MICROSCOPY; EPITHERMAL REACTORS; FAST REACTORS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; MICROSCOPY; NEUTRON FLUENCE; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS; TITANIUM ADDITIONS