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Korea Atomic Energy Research Institute

Korea Electric Power Corporation

Kyeong Ho Kim

Yong Hwan Jeong

Jong Hyuk Baek

Youn Ho Jung

Il Hiun Kuk

Byong Kwon Choi

Sang Yoon Park

Myung Ho Lee

Byoung Kwon Choi

Cheol Nam

Sun-Jae Kim

Sun Jae Kim

Younho Jung

Soon Dong Park

Myong Ho Lee

Disclosed is a method for manufacturing a tube and a sheet of niobium-containing zirconium alloys for the high burn-up nuclear fuel. The method comprises melting Nb-added zirconium alloy to ingot; forging the ingot at &bgr; phase range; &bgr;-quenching the forged ingot after solution heat-treatment at 1015-1075&deg; C.; hot-working the quenched ingot at 600-650&deg; C.; cold-working the hot-worked ingot in three to five passes, with intermediate vacuum annealing; and final vacuum annealing the cold-worked ingot at 440-600&deg; C., wherein temperatures of intermediate vacuum annealing and final vacuum annealing after &bgr;-quenching are changed so as to attain the condition under which precipitates in the alloy matrix are limited to an average diameter of 80 nm or smaller and the accumulated annealing parameter (&Sgr; A) is limited to 1.0&times;10 hr or lower.

Method for manufacturing a tube and a sheet of niobium-containing zirconium alloy for a high burn-up nuclear fuel

Zirconium alloy having high corrosion resistance and high strength

Niobium-containing zirconium alloy for nuclear fuel claddings

A method for production of mono-dispersed and crystalline titanium dioxide ultra fine powders comprises preparing an aqueous titanyl chloride solution, diluting the aqueous titanyl chloride solution to a concentration of between about 0.2 to 1.2 mole and heating the diluted aqueous titanyl chloride solution and maintaining the solution in a temperature range of between 15 to 155.degree. C. to precipitate titanium dioxide. The aqueous titanyl chloride solution is prepared by adding ice pieces of distilled water or icing distilled water to undiluted titanium tetrachloride.

Method for production of mono-dispersed and crystalline TiO.sub.2

The present invention is directed to an advanced zirconium alloy having superior corrosion resistance and high strength suitable for fuel rod cladding, spacer grids and other structural components in a reactor core of nuclear power plants.

Composition of zirconium alloy having low corrosion rate and high

The invention presented herein relates to a zirconium alloy with superior corrosion resistance and high strength for use in fuel rod claddings, spacer grids and structural components as used in reactor core of light water and heavy water nuclear power plant. The zirconium alloy of this invention with superior corrosion resistance and high strength comprises an alloy composition as follows:

Composition of zirconium alloy having high corrosion resistance and high

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Taejon-si, South Korea

Kyeong Ho Kim