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Brazed thermocouple pass-through for sodium service in a liquid-metal- cooled fast breeder reactor

Description: Sensors installed in special fuel elements for the EBR-II reactor had 30- ft-long leads that would pass from the sodium environment through a sealed bulkhead. A hydrogen-atmosphere, induction-heated brazing furnace was constructed to simultaneously braze 20-26 separate sensor leads at one time. The brazed seals were leak-tight, and the sheath wall has less than 10 percent interaction with the braze alloy. (auth)
Date: October 1, 1975
Creator: Walker, D.E.
Partner: UNT Libraries Government Documents Department


Description: Each Borax-lIl fuel subassembly consists of a group of aluminum-clad aluminum-uranium alloy fuel plates arranged in an MTR-type array. The fuel plates are electric-resistance spot-welded to two aluminum sideplates and an aluminum central-support plate. An anuminum-0.6 wt.% boron, burnable poison strip is attached to each fuel subassembly. The poison strips are made by hot extruding a mixture of aluminum and elemental boron powders in the desired proportions. (auth)
Date: January 1, 1958
Creator: Walker, D.E. & Noland, R.A.
Partner: UNT Libraries Government Documents Department

Mechanized welding in a glove box

Description: An orbital-tungsten-arc welding gun was installed in a helium glove box to automatically weld final end closures to capsules that were to contain an atmosphere of required composition and quality. A fixture, tooling, and procedures were developed to automatically position the tungsten electrode repetitively with respect to the end of the tube to be welded closed. (auth)
Date: October 1975
Creator: Pugacz, M. A. & Walker, D. E.
Partner: UNT Libraries Government Documents Department

Fusion welding of irradiated AISI 304L stainless steel tubings

Description: Fast reactor irradiated AISI 304L stainless steel tubing was fusion-welded using conventional inert gas-tungsten arc welding (GTAW) procedures which were adapted for remote operation. Metallographic examination of weld joints sometimes revealed porosity in the weld zone and cracks at the tube inner wall within the heat-affected zone. A stress analysis was performed to evaluate these defects as sites for weld failure and to establish procedures for the detection and rejection of weld joints likely to fail in service.
Date: 1978
Creator: Hall, M. M., Jr.; Hins, A. G.; Summers, J. R. & Walker, D. E.
Partner: UNT Libraries Government Documents Department

Experimental Breeder Reactor II (EBR-II) Fuel-Performance Test Facility (FPTF)

Description: The Fuel-Performance Test Facility (FPTF) is the latest in a series of special EBR-II instrumented in-core test facilities. A flow control valve in the facility is programmed to vary the coolant flow, and thus the temperature, in an experimental-irradiation subassembly beneath it and coupled to it. In this way, thermal transients can be simulated in that subassembly without changing the temperatures in surrounding subassemblies. The FPTF also monitors sodium flow and temperature, and detects delayed neutrons in the sodium effluent from the experimental-irradiation subassembly beneath it. This facility also has an acoustical detector (high-temperature microphone) for detecting sodium boiling.
Date: January 1, 1982
Creator: Pardini, J.A.; Brubaker, R.C.; Veith, D.J.; Giorgis, G.C.; Walker, D.E. & Seim, O.S.
Partner: UNT Libraries Government Documents Department

Nuclear Rocket Program, Metallurgy Division progress report for quarter ending December 31, 1964

Description: Activities reported include: metallurgical work; development and fabrication of high-temperature cermets; stabilization of urania; development of small-diameter, thin-walled tungsten tubing; cladding high-temperature cermet fuels; properties of high-temperature materials; evaluation of high-temperature cermets; nondestructive testing of ultrahigh-temperature reactor components; and irradiation of high-temperature cermet fuels.
Date: April 30, 1965
Creator: Burt, W.R.; Flinn, J.E.; Beals, R.J.; Pugacz, M.A.; Renken, C.J.; Yaggee, F.L. et al.
Partner: UNT Libraries Government Documents Department

Electroplating fission-recoil barriers onto LEU-metal foils for {sup 99}Mo-production targets

Description: Electroplating experiments on uranium foil have been conducted in order to develop low-enriched uranium composite targets suitable for the production of {sup 99}Mo. Preparation of the foil surface prior to plating was found to play a key role in the quality of the resultant coating. A surface preparation procedure was developed that produces both zinc and nickel coatings with the desired level of coating adherence and coverage. Modifications of the existing plating processes now need investigation to improve to uniformity of the plating thickness, especially at the foil perimeter.
Date: October 1, 1997
Creator: Smaga, J.A.; Sedlet, J.; Conner, C.; Liberatore, M.W.; Walker, D.E.; Wygmans, D.G. et al.
Partner: UNT Libraries Government Documents Department

Development of annular targets for {sup 99}MO production.

Description: The new annular target performed well during irradiation. The target is inexpensive and provides good heat transfer during irradiation. Based on these and previous tests, we conclude that targets with zirconium tubes and either nickel-plated or zinc-plated foils work well. We proved that we could use aluminum target tubes, which are much cheaper and easier to work with than the zirconium tubes. In aluminum target tubes nickel-plated fission-recoil barriers work well and prevent bonding of the foil to the new target tubes during irradiation. Also, zinc-plated and aluminum-foil barriers appear promising in anodized aluminum tubes. Additional tests are anticipated to address such issues as fission-recoil barrier thickness and uranium foil composition. Overall, however, the target was successful and will provide an inexpensive, efficient way to irradiate LEU metal foil for the production of {sup 99}Mo.
Date: September 30, 1999
Creator: Conner, C.; Lewandowski, E. F.; Snelgrove, J. L.; Liberatore, M. W.; Walker, D. E.; Wiencek, T. C. et al.
Partner: UNT Libraries Government Documents Department

Design and Fabrication of the EBR-II Environmental Instrumented Subassembly : Test XX07

Description: The EBR-II environmental instrumented subassembly (EISA), or Test XX07, was designed, fabricated, and irradiated to provide in-core measurements of irradiation conditions. This subassembly contained 57 elements with uranium metal-5 wt.% fissium fuel and four non-fueled elements. It was instrumented with two permanent-magnet flowmeters, 13 coolant thermocouples at various axial and radial locations, 10fuel-centerline thermocouples, and two self-powered detectors. The subassembly was irradiated in EBR-II for about 11,600 MWd (-186 days), reaching a peak burnup of about 2.9 at.% During its residence in the reactor, XX07 provided in-core measurements of flow, temperature and flux levels under both steady-state and dynamic conditions.
Date: 1977
Creator: Gillette, J. L.; Ploncsik, J.; Smaardyk, A.; Walker, D. E.; Filewicz, E. C.; Longnecker, A. A. et al.
Partner: UNT Libraries Government Documents Department

EBR-II Environmental Instrumented Subassembly XX08 : Engineering and Assembly

Description: Subassembly XX08 is a fueled and instrumented subassembly designed primarily for an ongoing program to investigate the thermal-hydraulic core environment within EBR-II under normal and off-normal plant operating conditions. XX08 contains 58-xenon-tagged, EBR-II Mark-II driver-fuel elements. The Mark-II fuel is expected to provide XX08 with an irradiation lifetime three times as great as that attained with its predecessor, XX07, i.e., a 9 versus 2.9% burnup. A burnup of 9 at.% is equivalent to about 29,000 MWt dyays of EBR-II reactor operation, which corresponds to 11 reactor runs at 2700 MWd per run.
Date: May 1978
Creator: Smaardyk, A.; Filewicz, E. C.; Longnecker, A. A.; Poloncsik, J.; Tokar, J. V.; Walker, D. E. et al.
Partner: UNT Libraries Government Documents Department