4 Matching Results

Search Results

Advanced search parameters have been applied.

Examination of irradiated 304L stainless steel to 6061-T6 aluminum inertia welded transition joints after irradiation in a spallation neutron

Description: The Savannah River Technology Center (SRTC) designed and fabricated tritium target/blanket assemblies which were irradiated for six months at the Los Alamos Neutron Science Center (LANSCE). Cooling water was supplied to the assemblies through 1 inch diameter 304L Stainless Steel (SS) tubing. To attach the 304L SS tubing to the modules a 304L SS to 6061-T6 Aluminum (Al) inertia welded transition joint was used. These SS/Al inertia weld transition joints simulate expected transition joints in the Accelerator Production of Tritium (APT) Target/Blanket where as many as a thousand SS/Al weld transition joints will be used. Materials compatibility between the 304L SS and the 6061-T6 Al in the spallation neutron environment is a major concern as well as the corrosion associated with the cooling water flowing through the piping. The irradiated inertia weld examination will be discussed.
Date: April 28, 2000
Creator: Dunn, K.A.
Partner: UNT Libraries Government Documents Department

Stainless steel recycle FY94 progress report

Description: The Materials Technology Section (MTS) of the Savannah River Technology Center (SRTC) was asked to demonstrate the practicality of recycling previously contaminated stainless steel components such as reactor heat exchanger heads, process water piping and slug buckets into 208 liters (55 gallon) drums and 2.8 cubic meter (100 ft{sup 3}) storage boxes. Radioactively contaminated stainless steel scrap will be sent to several industrial partners where it will be melted, decontaminated/cast into ingots, and rolled into plate and sheet and fabricated into the drums and boxes. As part of this recycle initiative, MTS was requested to demonstrate that radioactively contaminated Type 304L stainless steel could be remelted and cast to meet the applicable ASTM specification for fabrication of drums and boxes. In addition, MTS was requested to develop the technical basis of melt decontamination and establish practicality of using this approach for value added products. The findings presented in this investigation lead to the following conclusions: recycle of 18 wt% Cr-8 wt% Ni alloy can be achieved by melting Type 304 stainless steel in a air vacuum induction furnace; limited melt decontamination of the contaminated stainless steel was achieved, surface contamination was removed by standard decontamination techniques; carbon uptake in the as-cast ingots resulted from the graphite susceptor used in this experiment and is unavoidable with this furnace configuration. A new furnace optimized for melting stainless steel has been installed and is currently being tested for use in this program.
Date: October 28, 1994
Creator: Imrich, K. J.
Partner: UNT Libraries Government Documents Department

Corrosion tests of DWPF recycle solution

Description: Coupon immersion tests were performed on ASTM A537, Class 1 carbon steel in simulated Defense Waste Processing Facility recycle solutions at 93 {plus_minus} 2{degree}C, in an effort to reproduce the results of earlier tests in which hard, shock-sensitive deposits were found. There was no evidence of pitting corrosion on the coupons exposed to solutions containing 0.5 M hydroxide and 2000 ppm (0.043 M) nitrite. Liquid mercury and small solid deposits were found on the specimens` immersed surfaces. However, the deposits were soft and not shock-sensitive. The absence of shock-sensitive deposits may have been due to a lower mercuric ion concentration in the test solutions or to different post-immersion handling. Coupons of 304L stainless steel and alloy C276 were also immersed in the simulated recycle solution. These coupons were not subject to localized corrosion, nor were shock-sensitive deposits found. Additional immersion tests on A537 coupons will be started in July 1992.
Date: July 28, 1992
Creator: Zapp, P. E.
Partner: UNT Libraries Government Documents Department

Corrosion tests of DWPF recycle solution

Description: Coupon immersion tests were performed on ASTM A537, Class 1 carbon steel in simulated Defense Waste Processing Facility recycle solutions at 93 [plus minus] 2[degree]C, in an effort to reproduce the results of earlier tests in which hard, shock-sensitive deposits were found. There was no evidence of pitting corrosion on the coupons exposed to solutions containing 0.5 M hydroxide and 2000 ppm (0.043 M) nitrite. Liquid mercury and small solid deposits were found on the specimens' immersed surfaces. However, the deposits were soft and not shock-sensitive. The absence of shock-sensitive deposits may have been due to a lower mercuric ion concentration in the test solutions or to different post-immersion handling. Coupons of 304L stainless steel and alloy C276 were also immersed in the simulated recycle solution. These coupons were not subject to localized corrosion, nor were shock-sensitive deposits found. Additional immersion tests on A537 coupons will be started in July 1992.
Date: July 28, 1992
Creator: Zapp, P.E.
Partner: UNT Libraries Government Documents Department