• 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.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.

• 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.

• Computational Structural Engineering
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• v.11 no.1
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• pp.153-160
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• 1998

A small break loss of coolant accident is postulated as a pressurized thermal shock accident in this study. From the temperature and pressure histories of coolant, distributions of the temperature and stress in a vessel wall are analytically calculated. The stress intensity factor and fracture toughness of the vessel wall are determined at the crack tip using the ASME code method and they are compared to check if cracking is expected to occur during the transient postulated. The maximum allowable reference nil-ductility transition temperatures are determined for various crack sizes and the results are discussed.

• Proceedings of the Korean Institute of Building Construction Conference
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• 2013.11a
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• pp.13-14
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• 2013

Mechanical splices has been applied in nuclear power plant according to ASME(American Society of Mechanical Engineering) and ACI(American Concrete Institute) Code requirements. In particular sleeve with ferrous filler metal splices and cold roll formed parallel threaded splices have been used in domestic nuclear power plants. The objective of this study is to find out the constructability of the mechanical splices which had been used in Korea nuclear job site and to review the technical trends in the near future.

• Nuclear Engineering and Technology
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• v.54 no.1
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• pp.401-413
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• 2022

This paper provides a simple method by which to estimate the cross-section stress profiles for nozzles designed according to ASME Code Section III. Further, this method validates the effectiveness of earlier work performed by the authors on standard nozzles. The method requires only the geometric information of the pressure vessel and the attached nozzle. A PWR direct vessel injection nozzle, a PWR outlet nozzle, a PWR inlet nozzle and a BWR recirculation outlet nozzle are selected based on their corresponding specific designs, e.g., a varying nozzle radius, a varying nozzle thickness and an outlet nozzle boss. A cross-section stress profile comparison shows that the estimates are in good agreement with the finite element analysis results. Differences in stress intensity factors calculated in accordance with ASME BPVC Section XI Appendix G are discussed. In addition, a change in the dimensions of an alternate nozzle design relative to the standard values is discussed, focusing on the stress concentration factors of the nozzle inside corner.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.40 no.9
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• pp.775-782
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• 2016

In this study, elevated temperature design and integrity evaluation have been conducted using two different piping design codes for the high-temperature piping systems of sodium integral effect test loop for safety simulation and assessment(STELLA-2) being developed by KAERI(Korea Atomic Energy Research Institute). The design code of ASME B31.1 for power piping and French nuclear grade piping design guideline, RCC-MRx RD-3600 were applied, and conservatism of those codes was quantified based on the piping integrity evaluation results. The piping system of Model DHRS, Model IHTS and PSLS are to be installed in STELLA-2. The integrity evaluation results for the three piping systems according to the two design codes showed that integrity of the piping system was confirmed. As a code comparison result, ASME B31.1 was shown to be more conservative for sustained loads while RD-3600 was more conservative for thermal loads compared to B31.1.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.19 no.8
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• pp.44-54
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• 2018

Stress and fatigue of the distributor, an equipment of the high-pressure evaporator for the HRSG, were evaluated according to ASME Boiler & Pressure Vessel Code Section VIII Division 2. First, from the results of the piping system analysis model, reaction forces of the tubes connected to the distributor were derived and used as the nozzle load applied to the detailed analysis model of the distributor afterward. Next, the detailed model to analyze the distributor was constructed, the distributor being statically analyzed for the design condition with the steam pressure and the nozzle load. As a result, the maximum stress occurred at the bore of the horizontal nozzle, and the primary membrane stress at the shell and nozzle was found to be less than the allowable. Next, for the transient operating conditions given for the distributor, thermal analysis was performed and the structural analysis was carried out with the steam pressure, nozzle load, and thermal load. Under the transient conditions, the maximum stress occurred at the vertical downcomer nozzle, and of which fatigue life was evaluated. As a result, the cumulative usage factor was less than the allowable and hence the distributor was found to be safe from fatigue failure.

• Journal of the KSME
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• v.33 no.8
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• pp.717-727
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• 1993

주요국의 보일러 및 압력용기의 기술기준 개발방향이 금속재료기술의 발달, 비파괴검사 기술의 개발, 용접기술의 급진전, 품질요건의 국제적인 규정의 제정 및 준수 등의 현상으로 볼 때 이를 대체적으로 수용하는 ASME Sec. III의 방향으로 통합되어 가는 느낌을 받고 있다. 따라서 우 리나라도 전담기구의 설립 또는 지정을 서둘러 장기적인 안목에서 체계적으로 대처하여야 급격히 변화하는 세계적인 기술흐름에 맞추어 우리의 관련산업이 지속적으로 발전 될 수 있으며 이와 관련된 기술개발방향이 바르게 갈 수 있을 것이다.