PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JUNE 1958

Developments for Zirconium-Clad Fuel Elements. The thermal conductivity of Zircaloy-2 clad specimezs of U, U-l.5 wt. % Zr, and Zircaloy-2 was measured from 20 to 800 C prior to irradiation. Corrosion data for a 1000 hr test at 3O0 C in pure water of nine Zr alloys are given: Zr -Sn-Mo, Zr-Sn-Mo-Nb, Zr - Sn-Mo-Nb (trace Fe and Ni), Zr-Sn-Mo (trace Fe and Ni) Zr-Sn, and Zr-Sn (trace Fe and Ni). Developments for Aluminum-Clad Fanel Elements. Studies continued in casting Al and cladding with Al. Corrosion results are given for 15 min tests in 300 C water of U-Zr alloys with traces of V, Nb, Ni, Ti, Mo, Pt, Cr, Si, Al, and Ru in various combinations. Studies of Uranium and Uranium Alloy Fuels. Corrosion danta are given for a U-Mo-Nb alloy and some U-Mo-Nb-Ru alloys in 680 F water after 672 hours. Oxidation data are given for U-Nb alloys versus time at 350 and 400 C. Corrosion Problems Associated with Separation Processes. Studies of corrosion of alloys in Darex, Sulfex-Thorex, and fluoride volatility processes are reported. Data are given for INOR-1 and INOR-8 in NaF-ZrF/sub 4/ at 650 C for 500 and 1010 hours. Developments for SRE, OMRE, and OMR. Casting techniques for preparation of UC were studied, and post-irradiation evaluation of SRE Th-U specimens is reported. Studies of Na-Ta Compatibility at High Temperatures. These studies continued, data being given for creep of partially-annealed arc-cast Ta at 1200 F. Other work preparatory to developmental studies for PWR, MGCR, and NMSR is described. (For preceding period see BMI-1267.) (T.R.H.