Kepco Nuclear Fuel Co., Ltd.

Yeon Soo Na

Seung Jae Lee

Yoon Ho Kim

Chung Yong Lee

Yong Kyoon Mok

Tae Sik Jung

Min Young Choi

Jung Min Suh

Jung Ho Shin

Sung Yong Lee

Hun Jang

Jae Ik Kim

Dae Gyun Ko

Dae Gyun Go

Tae Sik Jeong

Min Jae Ju

Kwang Young Lim

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

Disclosed herein are zirconium alloy compositions having a low hydrogen pick-up rate and high hydrogen embrittlement resistance. This zirconium alloy composition can be usefully used as a nuclear fuel components in a nuclear power plant because it has a very low hydrogen pick-up rate and high hydrogen embrittlement resistance under operation environments of nuclear power plant.

Zirconium alloy composition having low hydrogen pick-up rate and high hydrogen embrittlement resistance and method of preparing the same

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Daejeon, South Korea

Yeon Soo Na