• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.123-124
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• 2018

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.125-126
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• 2018

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2011년도 추계학술논문요약집
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• pp.261-262
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• 2011

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2012년도 춘계학술논문요약집
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• pp.185-186
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• 2012

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2012년도 춘계학술논문요약집
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• pp.187-188
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• 2012

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2012년도 춘계학술논문요약집
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• pp.217-218
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• 2012

• Nuclear Engineering and Technology
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• 제35권5호
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• pp.471-481
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• 2003

In order to evaluate the microstructural characteristics of irradiated fuel claddings (Zircaloy-4), two irradiated specimens having different burnups (18 GWD/MTU and 42 GWD/MTU) were prepared from the G23-M4 fuel rods, which were loaded in Kori Unit 1 for 4 fuel cycles. The oxide thickness, hydride morphology and hardness change were characterized by an optical microscope and a micro-hardness tester after preparing the irradiated specimens in the PIE (Post Irradiation Examination) facilities. The dislocation loops and the amorphous transformation of precipitates induced by the neutron irradiation in the nuclear plant were also examined by a TEM. As the burnup increased from 18 GWD/MTU to 42 GWD/MTU, the oxide thickness increased from $6.0{\mu}m\;to\;25.3{\mu}m$ and the contents of hydrogen pick-up in the Zr matrix also greatly increased. In the comparison of the hardness of the unirradiated fuel cladding, the amount of hardness increase was nearly $9.3\%\;and\;24.2\%$ for the irradiated samples of 18 and 42 GWD/MTU, respectively. Both -type dislocation loops and -type dislocation components were observed simultaneously in the irradiated specimens and the densities of the dislocation was increased by increasing the burnup. The precipitates in both the irradiated specimens were amorphously transformed by the neutron irradiation and the trend of the amorphous transformation of the precipitates was enhanced at a higher burnup.

• Nuclear Engineering and Technology
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• 제20권1호
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• pp.54-64
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• 1988

FLHT-2 실험 결과를 사용하여 원자력발전소의 중대사고발생시 노심의 거동을 해석하기 위한 전산코드인 SCDAP코드를 평가하였다. 계산결과에 의하면 코드는 실험시 측정된 노심의 온도경향, 총수소발생량 및 순간최대수소발생율, 그리고 연료봉내압과 피복재파열시간을 잘 예측하는 것으로 평가되었다. 그러나 이상유체높이와 복사열전달 및 zircaloy의 급격한 산화 시작 온도에 대한 모델은 수정되어야 할 것으로 평가되었다. 또한 핵 연료봉에서의 gap을 고려하여주는 것은 노심손상현상의 정확한 예측에 커다란 도움을 줄 수 있다는 것이 밝혀졌다.

• 열처리공학회지
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• 제18권3호
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• pp.164-171
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• 2005

Iodine-Induced Stress Corrosion Cracking (ISCC) properties of Zircaloy-4 and HANA4 developed in KAERI for the high burn-up nuclear fuel cladding were evaluated. To confirm the effect of final heat treatment on ISCC resistance of Zr-alloy, stress relieved and recrystallized specimens were prepared and tested. With the pre-cracked specimen at internal surface, ISCC crack propagation rates and threshold stress intensity factor ($K_{ISCC}$) based on the fracture mechanics were measured by internal pressurization test at $350^{\circ}C$ in iodine environment. $K_{ISCC}$ of Zircaloy-4 and HANA4 cladding were $3.3MPa{\cdot}m^{1/2}$ and $4.4MPa{\cdot}m^{1/2}$, respectively. Pitting corrosion at the crack surface was observed and it seemed that TG crack propagation was derived from the pitting.

• 대한용접접합학회:학술대회논문집
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• 대한용접접합학회 2005년도 추계학술발표대회 개요집
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• pp.70-72
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• 2005

Nuclear fuel assemblies for pressurized water reactors(PWR) are loaded in the reactor core throughout the residence time of three to five years. A spacer grid assembly, which is an interconnected array of slotted grid straps and is welded at the intersections to form an egg crate structure, is one of the main structural components of the nuclear fuel assembly. The spacer grid assembly is structurally required to have enough buckling strength under various kinds of lateral loads acting on the nuclear fuel assembly so as to keep the nuclear fuel assembly straight. To meet this requirement, it is necessary to weld the welding parts carefully and precisely. In this study, laser welding qualities of the Zircaloy spacer grid assembly welded by two welding companies, such as weld strength, weld penetration depth, and weld bead size, are examined and compared.