• Nuclear Engineering and Technology
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• 제53권7호
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• pp.2312-2322
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• 2021

In recent studies, the creep rate of Zircaloy-4, one of the basic property parameters of the nuclear fuel code, has been commonly used with the axial creep model proposed by Rosinger et al. However, in order to calculate the circumferential deformation of the fuel cladding, there is a limitation that a difference occurs depending on the anisotropic coefficients used in deriving the circumferential creep equation by using the axial creep equation. Therefore, in this study, the existing axial creep law and the derived circumferential creep results were analyzed through a circumferential creep test by the internal pressurization method in the isothermal conditions. The circumferential creep deformation was measured through the optical image analysis method, and the results of the experiment were investigated through constructed IDECA (In-situ DEformation Calculation Algorithm based on creep) code. First, preliminary tests were performed in the isotropic β-phase. Subsequently in the anisotropic α-phase, the correlations obtained from a series of circumferential creep tests were compared with the axial creep equation, and optimized anisotropic coefficients were proposed based on the performed circumferential creep results. Finally, the IDECA prediction results using optimized anisotropic coefficients based on creep tests were validated through tube burst tests in transient conditions.

• 대한용접접합학회:학술대회논문집
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• 대한용접접합학회 2004년도 춘계 학술발표대회 개요집
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• pp.115-117
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• 2004

Nd:YAG laser welding system was used to manufacture instrumented irradiation fuel. The optimal condition of zircaloy-4 seal tube is charge voltage 180V and pulse per energy 51. We got good welding result in charge voltage 400V, pulse width 7ms, pulse frequency 5 in zircaloy-4 endcap welding.

• Tribology and Lubricants
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• 제17권6호
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• pp.453-458
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• 2001

The fretting wear of a nuclear fuel rod it a dangerous phenomenon. In this study, TiN coating was used to reduce the fretting wear of Zircaloy-4 tube, a nuclear fuel rod cladding material. TiN coating is probably one of the molt frequently and successfully used PVD coatings for the mitigation of fretting wear. The fretting tester was designed and manufactured for this experiment. The number of cycles, slip amplitude and normal load were selected as main factors of fretting wear. The results of this research showed that wear volume was improved 1.3∼3.2 times with TiN coating. The worn surfaces were observed by SEM. Wear mechanism at lower slip amplitude was the brittle cracks and rupture of TiN coating. However, adhesive and abrasive wear were mainly observed on most surfaces at higher slip amplitude.

• Nuclear Engineering and Technology
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• 제20권3호
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• pp.170-178
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• 1988

중수로형 핵연료의 피복재로 사용되는 Zircaloy-4관의 결함검사를 위한 자동초음파 탐상 장치가 개발되었다. 이 장치에는 중심진동수가 14 MHz이고 대역폭이 11MHz인 집속 초음파 펄스를 사용한 수침 펄스-에코우 탐상기술과 특별히 고안된 시험수조 이송식 초음파주사 기술이 적용되었다 같은 크기와 방향을 갖는 관내외면 결함들을 같은 높이의 초음파 신호로 검출하기 위한 초음파 빔의 최적입사각은 26도이었다. Zircaloy-4피복관의 최대 허용 결함인, 깊이가 관두께의 10%인 0.04 mm이고, 길이가 0.76 mm인 축방향 및 길이가 0.38 mm인 원주방향 V형 인공결함들이 관내외면에 개재된 표준시험관을 사용하여 이 장치의 성능시험을 수행하였다. 그 결과 인공 표준시험관내의 모든 결함들을 매우 우수한 재현성을 갖고 분당 약 1m의 속도로 검출할 수 있었으며 이때의 신호 대 잡음 비는 축방향 결함에 대해서는 20 dB, 원주방향 결함에 대해서는 12 dB 이상이었다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2019년도 춘계학술논문요약집
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• pp.65-66
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• 2019

• Journal of Welding and Joining
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• 제17권4호
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• pp.26-31
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• 1999

An attempt was made in this study to investigate the brazing characteristics of Zr-Be binary amorphous alloys for the development of a new brazing filler metal for joining Zircaloy-4 nuclear fuel cladding tubes. This study was also aimed at the feasibility study of rapidly solidified amorphous alloys to substitute the conventional physical vapor-deposited(PVD) metallic beryllium. The $Zr_{1-x}Be_{x}$($0.3\leq$x$\leq0.5$) binary amorphous alloys were produced in the ribbon form by the melt-spinning method. It was confirmed by x-ray diffraction that the ribbons were amorphous. The amorphous. the amorphous alloys were used to join bearing pads on Zircaloy-4 nuclear fuel cladding tubes. Using Zr-Be amorphous alloys as filler metals, it was found that the reduction in the tube wall thickness caused by erosion was prevented. Especially, in the case of using $Zr_{0.65}Be_{0.35}$ and $Zr_{0.7}Be_{0.3}$ amorphousalloys, the smooth and spherical primary $\alpha$-Zr particles appeared in the brazed layer, which was the most desirable microstructure from the corrosion-resistance standpoint.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2008년도 춘계학술대회 논문집
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• pp.501-502
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• 2008

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.931-932
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• 2004

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2019년도 춘계학술논문요약집
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• pp.84-85
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• 2019

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.121-122
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• 2018