Kepco Nuclear Fuel Co., Ltd.

Korea Advanced Institute of Science and Technology

Hun Jang

Yoon Ho Kim

Sung Yong Lee

Yong Kyoon Mok

Seung Jae Lee

Chung Yong Lee

Tae Sik Jung

Min Young Choi

Dae Gyun Ko

Jong Sung Yoo

Yeon Soo Na

Changheui Jang

Jae Ik Kim

Hyunmyung Kim

Chaewon Kim

Dae Gyun Go

Embodiments of the disclosure relate to a ferritic alloy having excellent ability to withstand nuclear power plant accidents and a method of manufacturing a nuclear fuel cladding tube using the same. The alloy includes iron (Fe), aluminum (Al), chromium (Cr), and nickel (Ni). The nickel (Ni) may be included 0.5 to 10 wt % based on a total amount of the alloy. The chromium may be included 13 to 18 wt % based on the total amount of the alloy. The aluminum may be included 5 to 7 wt % based on the total amount of the alloy.

Ferritic alloy and method of manufacturing nuclear fuel cladding tube using the 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

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

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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Sejong-si, South Korea

Hun Jang