REACTOR TECHNOLOGY QUARTERLY REPORT NO. 4. METALLURGY AND MATERIALS
Fuel Materials. An investigation was conducted to obtain more information on the strain-cycling behavior of U with specific emphasis being placed on those conditions where cyclic straining causes failure in 10 to 1000 cycles. Observations were made of UO/sub 2/-containing fuel specimens irradiuted at widely varying times, temperatures, and burnups,and the effects of each were determined. The preparation of a 6 wt. % U-Zr alloy containing Pt a tracer material is presented. Results of bend tests of irradiated fuel element sections are presented. The effect of structure and composition on the irradiation stability of Zr-base dispersion alloy fuel is being studied. Water corrosion testiing of a 3.8 wt. % U-- Zr alloy was completed for times up to 1400 hr. Corrosion experiments were carried out on ceramic fuels in 680 deg F waters and burnable poisons under 2000 psi in LiOH at a pH 10 and in NH/sub 3/ at a pH of 9. The theoretical and experimental aspects of ultrasonic immersion testing of oval fuel specimens are discussed. Poison Materials. Forming of burnable poison dispersion in ceramic matrices is described. The irradiation stability of several boron compounds and glasses and dispersion systems in which boron compound particles are dispersed in a metallic or cerimic matrix is being studied. The development of dispersiontype reactor poison components composed of neutronabsorbing glass particles as the dispersed phase is discussed. The fabrication of stainless steel-- boron alloy irradiation specimens with unbonded and bonded cladding is presented. A summary of the physical, mechanical, and high-temperature water-- corrosion properties of a wrought Ag--In--Cd control rod alloy was prepared. Structural Materials. Strain fatigue behavior of Zircaloy-2 and -3 at room temperature and 550 deg F is presented. The effect of stress pattern on the hydride formation in Zircaloy-2 is presented. The mechanical properties of stainless steel nitrided in sodium are presented. Welding and Brazing. The effects of welding atmosphere and pickling on the corrosion resistance of welded Zircaloy-2 and -3 is presented. Methods of joining Zircaloy- 2 to austenitic stainless steel are presented. The diffusion bonding of instrumented fuel element transition joints is described. The mechanical properties of diffusion-bonded joints between Zircaloy and type 304 stainless steel tubing was investigated. A method is presented for welding Ti to Hf. An investigation was made to obtain information on the welding of Ti and Ti alloys containing B. Welded transition joints between type 304 stainless steel and Croloy 2 1/4 after the thermal shock treatments of the joints were evaluated. The inert-gas-shielded consumable electrode or sigma welding process is discussed. The brazing of type 304 to type 304 stainless steel with high-temperature brazing alloys is presented. The corrosion resistance of type 304 stainless steel brazed joints in 6604DEF water is given. An investigation of the feasibility of diffusion bonding Zircaloy sheets using a stainless steel diffusion layer is presented. (W.L.H.)
- Research Organization:
- Knolls Atomic Power Lab., Schenectady, N.Y.
- DOE Contract Number:
- W-31-109-ENG-52
- NSA Number:
- NSA-12-016390
- OSTI ID:
- 4310167
- Report Number(s):
- KAPL-2000-1
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-58
- Country of Publication:
- United States
- Language:
- English
Similar Records
PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING DECEMBER, 1958
MARITIME REACTOR PROJECT ANNUAL PROGRESS REPORT FOR PERIOD ENDING NOVEMBER 30, 1958
Related Subjects
ABSORPTION- BONDING- BORIDES- BORON COMPOUNDS- CERAMICS- COATING- COMBUSTION- CORROSION- DISPERSIONS- FABRICATION- GLASS- IRRADIATION- MECHANICAL PROPERTIES- NEUTRONS- PARTICLES- POISONING- STABILITY- STAINLESS STEELS- TENSILE PROPERTIES- WATER
ACIDITY- CERAMICS- COMBUSTION- CORROSION- LITHIUM HYDROXIDES- NITRIC ACID- POISONING- ULTRASONICS
AUSTENITE- BONDING- BRAZING- CHROMIUM ALLOYS- CORROSION- CROLOY- DIFFUSION- FUEL ELEMENTS- HAFNIUM- INERT GASES- JOINTS- MECHANICAL PROPERTIES- STABILITY- STAINLESS STEELS- STEELS- THERMAL STRESSES- TITANIUM- TITANIUM BORIDES- TUBES- WELDING- ZIRCALOY
BURNUP