DIVISION OF REACTOR DEVELOPMENT PROGRAMS MONTHLY REPORT FOR MARCH 1959
Plutonium Recycle Program. The preparation PuC, PuO/sub 2/, and graphite in the correct stoichiometric proportions is reported. Physical mixtures of UO/sub 2/-PuO/sub 2/ were fired at 1600 C for eight hours to provide the final data on solubility in the system U0/sub 2/-PuO/sub 2/. Compacts of Al/sub 2/O/sub 3/, MgO, and ZrO/sub 2/ have been sintered to densities ranging from 80 to 90% of theoretical. Billets were cast in order to obtain fabrication and corrosion data on Al-Pu alloys of modified matrix composition. The extrusion of Al-Pu rods is continuing. Twelve full-length PRTR Al rods clad with Zircaloy tubing have been tested to investigate assembly, wrapping, autoclaving, and warpage problems. Vibratory compaction of high- density UO/sub 2/ grains into metal tubes is being studied as an alternate method of fabrication of fuel elements. Postirradiation examination of fuel elements is reported. The heat of reaction of Zircaloy-2 in HNO/sub 3/-HF etch solution is reported. Examination was begun on a four-rod Zircaloy-2 clad, Al -Pu alloy fuel element cluster which was irradiated to ~ 2000 MWD/T. Heat transfer characteristics of the PRTR fuel element is being investigated. Calculations of water loss rates following a piping failure in the PRTR were completed with consideration of ruptures of the top header, top jumper, and bottom jumpers. Chemical Research and Development Operation. Work has continued on both the direct reduction of PuO/sub 2/ and the in situ conversion of it to chloride followed by reduction with Zn-Mg. The effect of U concentration on the distribution in the KCl-AlCl/sub 3/-Al system was examined. Physics and Instruments Research and Development Operation. Using Mummery's method, the PCTRderived values of K and f for various PRR lattices have been analyzed. Fabrication of the warp measurement unit for the profilometer was completed. Programming Operation. A detailed study of a schedule for charging, discharging, and chemical processing of PRTR fuel was completed. Basic Swelling Studies Program. Capsules are being designed for irradiation of unrestrained U specimens in the MTR and ETR. Uranium swelling has been simulated in the laboratory by the introduction of Xe gas into U by cathodic glow discharge at high temperatures. The diffusion of rare fission gases througth the U lattices is being studied. Graphite Studies. Surface area and pore size measurements were completed on four TSGBF graphite samples prior to outgassing and reactor irradiation at 550 C in high-pressure C0/sub 2/. Preliminary screening tests were completed on a siliconized impregnated and a siliconized graphite. (For preceding period see HW- 59600.) (W.L.H.)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- W-31-109-ENG-52
- NSA Number:
- NSA-13-012662
- OSTI ID:
- 4257589
- Report Number(s):
- HW-60043
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
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ALUMINUM ALLOYS- CASTING- CORROSION- EXTRUSION- FABRICATION- FUEL CANS- FUEL ELEMENTS- HEAT TRANSFER- IRRADIATION- PACKAGING- PLUTONIUM- PLUTONIUM ALLOYS- PRESSURE VESSELS- PRTR- REACTORS- REPROCESSING- RODS- TUBES- ZIRCALOY
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