Kepco Nuclear Fuel Co., Ltd.

Min Young Choi

Yoon Ho Kim

Yong Kyoon Mok

Seung Jae Lee

Chung Yong Lee

Sung Yong Lee

Hun Jang

Yeon Soo Na

Jung Min Suh

Jung Ho Shin

Jong Sung Yoo

Tae Sik Jung

Seung-jae Lee

Jae Ik Kim

Dae Gyun Ko

Kwang-young Lim

Tae Sik Jeong

Dae Gyun Go

Yeon-soo Na

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

A device for maintaining the internal temperature of a pressure vessel. The device includes a pressure vessel equipped with a main heater for heating test water to a predetermined test temperature and for maintaining the predetermined test temperature, a preheater for primarily heating the test water to the predetermined test temperature before the main heater heats the test water, and a heat exchanger including an feed pipe for feeding the test water heated by the preheater to the pressure vessel and a discharge pipe for transporting the test water discharged from the pressure vessel, in which the feed pipe is disposed inside the discharge pipe.

Device for maintaining internal temperature of pressure vessel

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

Min Young Choi