• 열병합발전
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• s.35
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• pp.4-11
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• 2003

• Journal of the Korea Academia-Industrial cooperation Society
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• v.11 no.12
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• pp.5177-5183
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• 2010

The effects of the ovalization of the tangential pipes to the elbows are analyzed. The geometric nonlinear behaviors of the elbows are shown with the element capable of ovalization. The relationships between the length of the tangential pipes in the models and the bend angles of the elbows are analyzed to supplement the ASME code. And the proper length of the tangential pipes for the elbow models are suggested.

• Proceedings of the KSME Conference
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• 2003.04a
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• pp.637-642
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• 2003

The Modified 9Cr-1Mo steel identified as T91, P91 and F91 in the ASME specification has been widely used for the construction of modern power plants. The available data on the influence of process parameters during manufacturing and fabrication on its properties are not sufficient. In this study, the influence of various thermal cycles on the hardness and the creep rupture strength was analyzed in the base metal and the weldments made in tube and pipe of a Mod.9Cr-1Mo steel. The low hardness, 155Hv, showed low creep rupture strength below the allowable stresses of T91 base metal in the ASME specification. This low value was attributed to the fully recovered dislocation structure and the weakening of precipitation hardening associated with the abnormal thermal cycles.

• Proceedings of the KSME Conference
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• 2003.04a
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• pp.648-653
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• 2003

In order to predict stress intensity limit of high-temperature creep structures, creep work-time equation, defined as $W_ct^P=B$, was used, and the results of the equation were compared with isochronous stress-strain curve (ISSC) ones of ASME BPV NH Code. For this purpose, the creep strain tests with. time variations for commercial type 316 stainless steel were conducted with different stresses; 160 MPa, 150 MPa, 145 MPa, 140 MPa and 135 MPa at $593^{\circ}C$. The results of log $W_c$ and log t plots showed a good linear relation up to $10^5$ hr. The constants p, B and stress intensity limit values showed comparatively good agreement to those of ASME NH ISSC. It is believed that the relation can be simply obtained with only several short-term 1% strain data without ISSC which can be obtained by long-term creep data.

• Nuclear Engineering and Technology
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• v.33 no.5
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• pp.498-513
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• 2001

Performed here is a comparative assessment study for the generation of the pressure- temperature (P/T) limit curve of the reactor vessel. Using the cooling or heating rate and vessel material properties, the stress distribution is obtained to calculate stress intensity factors, which are compared with the material fracture toughness to determine the relations between operating pressure and temperature during cool-down and heat-up. P/T limit curves are generated with respect to crack direction, clad thickness, toughness curve, cooling or heating rate and neutron fluence, and their results are compared.

• Nuclear Engineering and Technology
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• v.29 no.4
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• pp.310-319
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• 1997

A finite element analysis of a trunnion pipe anchor is presented. The structure is analyzed for the case of internal pressure and moment loadings. The stress results are categorized into the average (membrane) stress, the linearly varying (bending) stress and the peak stress through the thickness. The resulting stresses are interpreted per Section III of the ASME Boiler and Pressure Vessel Code from which the Primary(B$_1$), Secondary(C$_1$) and Peak(K$_1$) stress indices for pressure, the Primary (B$_2$), Secondary(C$_2$) and Peak(K$_2$) stress indices for moment are developed. Based on the comparison between stress value by stress indices derived in this paper and stress value represented by the ASME Code Case N-391-1, the empirical equations for stress indices are effectively used in the piping stress analysis. Therefore, the use of empirical equations can simplify the procedure of evaluating the local stress in the piping design stage.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.915-920
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• 1998

본 논문에서는 반구형 헤드(hemi-spherical head)를 가진 압력용기에 비방사형(non-radial) 노즐을 가공할 경우, 개구(opening) 간격이 반구형 헤드의 설계에 미치는 영향을 검토하기 위하여 개구 간격의 변화에 따른 응력분포변화를 분석하였다. ASME 코드는 NB-3222.4(d)의 설계 조건을 만족하는 압력 용기의 혜드에 노즐을 가공할 경우, NB-3338.2(d)에서 개구사이의 최소거리를 제시하고 있다. 본 논문에 서는 ASME 코드가 제시하고 있는 개구사이의 최소거리의 타당성과 설계상 이 요건을 만족하지 못하는 경우에 대하여 분석하고 검토하였다. 해석모델은 한국 표준형원자로의 가압기를 기본모델로하여 개구사이의 간격변화에 따른 응력변화를 검토하고, 설계시 고려하여야할 인자를 분석하였다.

• Journal of the Korean Society for Nondestructive Testing
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• v.13 no.4
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• pp.42-46
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• 1994

원자력발전소(原子力發電所)의 방진기의 역할은 운전중(運轉中) 지진(地震)이나 혹은 수격작용(水擊作用)등 순간적인 동적 하중의 발생으로부터 관련 배관(配管)과 기기(機器)를 보호하는 것이다. 1989년 이후 ASME Sec. XI에서 50kips 이상의 대형 방진기도 ASME/ANSI OM Part 4에 따라 육안검사(肉眼檢査) 및 성능시험(性能試驗)을 할 것을 추가 요구하고 있다. 따라서 본 보고서는 방진기(防震機) 기능, 미국 원전 방진기의 손상 사례, 검사(檢査) 기술기준(技術基準) 및 요구사항(要求事項)을 검토(檢討)하여 검사 및 성능시험을 적절한 제반 기술기준에 의거 수행토록 하며, 수행 결과 수반되는 손상 방진기에 대한 원인규명(原因糾明)과 까다로운 후속조치(後續措置)의 실시로 원전 40여년 수명기간동안 배관계통(配管系統) 및 기기(機器)의 건전성을 확보하는데 기여코자 한다.

• 한국전산유체공학회:학술대회논문집
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• 2011.05a
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• pp.596-600
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• 2011

In this numerical analysis, the distortion of flow measurement by inlet velocity profile of orifice flowmeter was investigated. To validate the numerical method, the convergence was monitored and the grid dependency was also checked. realizable k-e model was selected and y+ was about 50 in this calculation. the results shows that the pressure at the pressure tab near pipe wall was changed by inclined inlet velocity profile and it leads to distorted a measurement values of flow through the orifice plate from -3.8% to 9%. Therefore, the fully developed inlet flow was required for accurate flow measurement by orifice flowmeter. If not, the orifice plate installed at wrong location should be re-installed or additional actions should be taken.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.9 no.2
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• pp.480-486
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• 2008

The pipe elbows subjected to in-plane bending moments are analyzed with the finite element method. The results from the finite element analysis are compared with ASME code equations that are theoretical closed form solutions. The geometric nonlinear effects due to the ovalization are explained with the magnitude and the types of the stresses and the flexibilities of the elbows with the emphasis on the bend angles and elbow factors.