THERMAL STRESS ANALYSIS OF THE ART HEAT EXCHANGER CHANNELS AND HEADER PIPES
The stresses, deflections, and the forces and moments acting on the Aircraft Reactor Test heat exchanger channels and header pipes due to relative thermal expansion between the channels and pressure shell at full power operation are summarized. (auth) Investigations were conducted on replacing type 347 stailnless steel for 304B and 304L as matrix and cladding material in APPR-core 1. The Hayces-25 combs used as flux suppressors in the control rods of core 1 contributed to the high cobalt activity of the system, and therefore dispersions of Eu/sub 2/O/sub 3/ in stainless steel were developed for use as flux suppressors in core II. In an effort to provide for operation of core II with a bank of five control rods rather than seven as in core I, means were studied for increasing the boron concentration in the fuel plates. Irradiation tests of fuel plates in the MTR failed to indicate any radiation damage in the specimens even for U/sup 235/ burnup as high as 57%. Methods were developed for fabricating absorber sections for the control rods that consisted of a type 304 stainless steel clad dispersion of 2.86 wt.% B/sup 10/ in electrolytic iron. The absorber section developed for core II consists of a roll-clad stainiess steel composite plate containing a dispersion of 38 wt.% Eu/sub 2/0/sub 3/ in stainless steel. Experiments were performed in which irradiated fuel plates were melted under controlled conditions simulating the loss-of-coolant accident. A review was made of the critical experiments performed in connection with the APPR-1. Under the Gas Cooled Reactor Program a gascooled loop was designed form-pile testing of advanced fuel specimens in two adjacent lattice positions in the ORR. (W.D.M.)
- Research Organization:
- Oak Ridge National Lab., Tenn.
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-14-002220
- OSTI ID:
- 4238521
- Report Number(s):
- ORNL-2442
- Country of Publication:
- United States
- Language:
- English
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