USAEC - AECL Cooperative Program (Monthly Progress Report, December 1966)

Technical Report · Fri Jan 13 04:00:00 EST 1967

DOI:https://doi.org/10.2172/1909440· OSTI ID:1909440

Hilborn, H. S. ^[1]; Crandall, J. L. ^[1]; Byars, R. F. ^[1]

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1. Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Lab.

Experiments have been performed at the Savannah River Laboratory (SRL) to investigate the physics behavior of simulated burned-up fuel. The analysis is still in progress. New Savannah River experiments are being prepared for the measurement of the change of η with temperature in a natural uranium lattice in the PDP. An irradiation test of in-core flux monitors is being made in one of the Savannah River Plant reactors to determine the life characteristics of a selection of flux detectors and of the mineral insulation used in their construction. Self-powered flux detectors are relatively new; therefore, confidence in their use hinges to a great extent on proven performance at large integrated exposures. The chief points of interest are 1) integrity of the conductors and sheath during life, 2) life of insulation, and 3) sensitivity. The higher flux density available at SRP (vis-à-vis Chalk River) will shorten the irradiation time for a given exposure and should also show whether or not any new high Intensity effects appear. Fabrication and installation of the detector rod in the reactor has been completed and testing is in progress. There were no special tests in February. No significant changes in the detector or cable outputs from those reported in DPST-66-83-8 have occurred. The data being collected will be reported in a separate topical report at the conclusion of the tests.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States); Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Lab.
• Sponsoring Organization: USDOE Office of Environmental Management (EM); US Atomic Energy Commission (AEC)
• DOE Contract Number: 89303321CEM000080
• OSTI ID: 1909440
• Report Number(s): DPST-66-83-12
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS