PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING APRIL 1958
Results are given from studies on: mechanical properties of Zircaloy-2; preparation of Al--U alloys; effects of N, Ca, Zr, and Mo on electrical properties of UO/sub 2/; effect of chloride, fluoride, and sulfate contamination on corrosion of type 304ELC stainless steel in boiling HNO/sub 3/; density of Mallinckrodt slag and MgF/sub 2/-base materials; development of gamma-phase U alloys; preparation of U--Nb alloys; oxidation of Nb and Nb alloys in dry air at 1000 and 1200 deg C; thermal expansion of UBe/sub 13/ and UC; phases and compositions in C --N--U system; creep of arc-cast Ta during exposure to high- temperature Nas pressure bonding of PWR fuel platess evaluation of UC as reactor fuels and fabrication of UO/sub 2/ fuel pellets for NMSR loop tests. (For preceding period see BMI-1259.) (T.R.H.)
- Research Organization:
- Battelle Memorial Inst., Columbus, Ohio
- DOE Contract Number:
- W-7405-ENG-92
- NSA Number:
- NSA-12-010060
- OSTI ID:
- 4344251
- Report Number(s):
- BMI-1262
- Country of Publication:
- United States
- Language:
- English
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ALLOTROPY-- CARBON-- NITROGEN-- REACTORS- - URANIUM
ALUMINUM ALLOYS-- PREPARATION-- REACTORS-- URANIUM ALLOYS
BERYLLIUM-- EXPANSION-- REACTORS-- THERMAL STRESSES-- URANIUM
BOILING-- CHLORIDES-- CONTAMINATION-- CORROSION-- FLUORIDES-- NITRIC ACID-- REACTORS-- STAINLESS STEELS-- SULFATES
BONDING-- FUEL ELEMENTS-- PLATES-- PRESSURE-- PWR-- REACTORS
CALCIUM-- ELECTRICITY-- MOLYBDENUM-- NITROGEN-- REACTORS-- URANIUM DIOXIDE-- ZIRCONIUM
CARBON-- EXPANSION- - REACTORS-- THERMAL STRESSES-- URANIUM
CASTING-- CREEP-- ELECTRIC ARCS-- HIGH TEMPERATURE-- REACTORS-- SODIUM- -
PHYSICS