Kepco Nuclear Fuel Co., Ltd.

Tae Sik Jung

Yoon Ho Kim

Seung Jae Lee

Chung Yong Lee

Yeon Soo Na

Sung Yong Lee

Jong Sung Yoo

Hun Jang

Yong Kyoon Mok

Jae Ik Kim

Min Young Choi

Seung-jae Lee

Dae Gyun Ko

Kwang-young Lim

Min Jae Ju

Kwang Young Lim

Dae Gyun Go

Yeon-soo Na

Provided is a nuclear-fuel sintered pellet based on oxide in which a plate-type fine precipitate material in a base of a sintered pellet of uranium dioxide, used as nuclear fuel in nuclear power plants, is uniformly dispersed in a matrix of uranium dioxide fuel thereof so as to form a donut-shaped precipitate cluster, and to a method of manufacturing the same. The plate-type fine precipitate material is uniformly precipitated in a tissue thereof or forms a donut-shaped precipitate cluster having a two-dimensional structure through dispersion to improve thermal and physical performance of the nuclear-fuel sintered pellet of uranium dioxide, whereby the creep deformation rate and thermal conductivity of the sintered pellet are improved. The nuclear-fuel sintered pellet based on oxide can reduce the Pellet-Clad Interaction (PCI) failure and the core temperature of nuclear fuel when an accident occurs, thereby significantly improving the safety of a nuclear reactor.

Nuclear-fuel sintered pellets based on oxide in which fine precipitate material is dispersed in circumferential direction and method of manufacturing same

A method of manufacturing a zirconium alloy for a nuclear fuel cladding tube includes melting a mixture of 0.5 wt % of Nb, 0.4 wt % of Mo, 0.1 to 0.15 wt % of Cu, 0.15 to 0.2 wt % of Fe, and a balance of zirconium to prepare a melted ingot; heat treating the melted ingot at 1,000 to 1,050&#xb0; C. for 30 to 40 min. followed by quenching in water to prepare a heat-treated ingot; preheating the heat-treated ingot at 630 to 650&#xb0; C. for 20 to 30 min. to prepare a preheated ingot followed by hot rolling the preheated ingot at a reduction ratio of 60 to 65% to provide a hot-rolled material; thrice performing vacuum annealing followed by cold-rolling; and vacuum annealing a third cold-rolled material in a final vacuum annealing at 510 to 520&#xb0; C. for 7 to 9 hrs. to provide the zirconium alloy as a cold-rolled material.

Method of manufacturing a corrosion-resistant zirconium alloy for a nuclear fuel cladding tube

The present invention relates to a recrystallization rate measurement method of zirconium alloy cladding of a nuclear fuel rod, the method including: step 1 of irradiating SEM electron beams at a given scanning interval onto a first specimen to a third specimen which were electrolytically polished and obtaining electron backscattered signals therefrom by an EBSD camera; step 2 of converting electron backscattered signals obtained in step 1 into pattern quality values, respectively, and generating the pattern quality values as frequencies by a specified interval; step 3 of obtaining pattern quality frequencies (B+D) which are a portion of a whole frequency distribution of the second specimen, and pattern quality frequencies (D+E) which are a portion of a whole frequency distribution of the first specimen; and step 4 of obtaining the recrystallization rate of the second specimen with an equation of 

Recrystallization rate measurement method of zirconium alloy cladding of nuclear fuel rod using EBSD pattern quality

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Daejeon, South Korea

Tae Sik Jung