• 대한기계학회논문집
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• 제19권6호
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• pp.1460-1468
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• 1995

The objective of this paper is to evaluate the material properties of SA106 Gr. C carbon steel and its associated weld manufactured for main steam system of Yonggwang 3,4 nuclear generating stations. A total of 43 tensile and 35 fracture toughness tests were performed and the effects of various parameters such as pipe size, crack plane orientation, test temperature, welding on material properties were discussed. Test results show that the effects of crack plane orientation, test temperature, and welding on fracture toughness were significant while the effects of pipe size, specimen orientation and test temperature on tensile properties were negligible. Especially the dependence of J-R curves on the crack plane orientation appears to be the characteristics of carbon steel.

• 대한기계학회논문집
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• 제19권6호
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• pp.1451-1459
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• 1995

The objective of this paper is to evaluate the material properties of SA312 TP316 and SA312 TP304 stainless steels and their associated welds manufactured for safety injection system of Yonggwang 3,4 nuclear generating stations. A total of 62 tensile tests and 46 fracture toughness tests were conducted and the effects of various parameters such as pipe size, crack plane orientation, tests were conducted and the effects of various parameters such as pipe size, crack plane orientation, test temperature, welding on material properties were discussed. Test results show that the effect of test temperature on fracture toughness was significant while the effects of pipe size and crack plane orientation on fracture toughness were negligible. Fracture toughness of the weld metal was in general higher than that of the base metal.

• 대한기계학회논문집A
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• 제25권9호
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• pp.1350-1358
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• 2001

During the last decade, a number of experiments and numerical analyses had been performed in conjunction with the development of simplified analytical methods to estimate the fracture behavior of cracked piping in nuclear power plant. However, the necessity of further investigation for the analytical methods was issued because of the discrepancies with the experimental data. The objective of this paper is to find out the optimum methods to evaluate the load-carrying capacities for cracked pipes. To do this, numerous analytical and finite element analyses were carried out for various pipe and crack geometries and materials. These results were synthesized for crack shapes and can be used as basic data for leak before analyses and risk informed inspections.

• 대한조선학회논문집
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• 제31권4호
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• pp.119-129
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• 1994

본 연구의 목적은 좌초시 선저 보강판 부재를 대상으로 강체 웨지가 종방향으로 보강된 판으로 진입할 때의 흡수에너지-찢김길이 관계를 나타내는 실험식을 도출하는 것이다. 본 연구는 제1보에서 수행한 시리즈 실험 결과 및 찢김응답에 관한 주요 인자들의 중요도 조사 결과를 바탕으로 하고 있다. 준정적 하중상태에서 수행된 실험 결과를 바탕으로 무차원 해석을 수행하여 찢김이 진행되는 동안의 판부재의 흡수에너지를 찢김길이, 항복응력, 등가판두께, 웨지각도의 함수로 정식화하였다. 또한, 이식을 충격하중 작용시에도 적용할 수 있도록 동적 효과를 고려하였다. 특히, 본 연구에서는 동적 마찰 효과를 고려하기 위하여 동적 마찰 감소 계수의 개념을 도입하였다. 본 제안식의 유용성을 확인하기 위하여 기존의 제안식 및 충격 실험에 의해 얻어진 결과와 본 제안식의 결과를 비교하였다.

• 대한기계학회논문집A
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• 제20권6호
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• pp.1843-1853
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• 1996

The objective of this paper is to evaluate the crack stability of the nuclear main stresm pipes, considering the load reduction effect due to the presence of circumferential throuth-wall crack. Also, the optimization techniques are adoped tosimulate the crack effect on the elbow component of the piuping system. By using a general beam elemetn which contains a discontinuous cross-section, the piping analysis is accomplished to acquire the reduced load. Considering this reduced load, it is feasible for the LBB application in nuclear main stresm pipe. Also, by combining an optimization program and a genaral finite element analysis program, the appropriate dimensions of the simplified beam elemtn which represents the effect of crack in elbow could be successfully determined.

• 대한기계학회논문집
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• 제14권3호
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• pp.646-655
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• 1990

본 연구에서는 EPIES 프로그램의 상세한 내용과 이를 이용한 5가지 파괴역학 시편에 대한 사례 연구에 대하여 보고하고자 한다.

• 대한기계학회논문집A
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• 제25권10호
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• pp.1567-1574
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• 2001

In order to operate an RPV safely it is necessary to keep the pressure-temperature (P-T) limit during the heatup and cooldown process. While the ASME Code provides the P-T limit curve for safe operation, this limit curve has been prepared under conservative assumptions In this paper the effects of conservative assumptions involved in the P-T limit curve specified in the ASME Code Sec. XI were investigated. Three different parameters the crack depth the cladding thickness and the cooling rate, were reviewed based on 3-D finite element analyses. Also the constraint effect on P-T limit curve generation was investigated based on J- T approach. It was shown that the crack depth and the constraint effect change the safe region in P-T limit curve significantly Therefore it is recommended to prepare a more precise P-T limit curve based on finite element analysis to obtain P-T limit for safe operation of an RPV.