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Title: ARMY PACKAGE POWER REACTOR PROJECT PROGRESS REPORT FOR 1958

Technical Report ·
DOI:https://doi.org/10.2172/4796804· OSTI ID:4796804

Investigations were conducted on replacing type 347 stainless steel for 304B and 304L as matrix and cladding material in APPR-core 1. The Haynes-25 combs used as flux suppressors in the control rods of core 1 also 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. ln 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 studies for increasing the boron concentration in the fuel plates. Irradiation tests of fuel plates in the MTR failed to indicate any radiation damage to 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 stainless steel composite plate containing a dispersion of 38 wt% Eu/ sub 2/O/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-l. Under the Gas Cooled Reactor Program a gascooled loop was designed for in-pile testing of advanced fuel specimens in two adjacent lattice positions in the ORR. (W.D.M.)

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
DOE Contract Number:
W-7405-ENG-26
NSA Number:
NSA-16-028541
OSTI ID:
4796804
Report Number(s):
ORNL-2703
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English