• KSCE Journal of Civil and Environmental Engineering Research
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• v.29 no.6A
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• pp.577-585
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• 2009

A 9-node degenerated shell finite element(FE), which has been developed for assessment of ultimate pressure capacity and nonlinear analysis for nuclear containment building is described in this paper. Reissner-Midnlin(RM) assumptions are adopted to develop the shell FE so that transverse shear deformation effects is considered. Material model for concrete prior to cracking is constructed based on the equivalent stress-equivalent strain relationship. Tension stiffening model, shear transfer mechanism and compressive strength reduction model are used to model the material behavior of concrete after cracking. Niwa and Aoyagi-Yamada failure criteria have been adapted to find initial cracking point in compression-tension and tension-tension region, respectively. Finally, the performance of the developed program is tested and demonstrated with several examples. From the numerical tests, the present results show a good agreement with experimental data or other numerical results.

• Journal of Radiation Protection and Research
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• v.40 no.4
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• pp.244-251
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• 2015

The containment filtered venting system reduces the range of the contamination area around the nuclear power plant by strengthening the integrity of the containment building. In this study, the probabilistic assessment code MACCS2 was used to assess the effect of the CFVS to off-site. The accident source term was selected from a Probabilistic Safety Analysis report of SHINKORI 1&2 Nuclear Power Plant. The three source term categories from 19 STC were chosen to evaluate the effective dose and thyroid dose of residents around the power plant and the dose with CFVS and without CFVS were compared. The dose was calculated according to the distance from the nuclear power plant, so the damage scale based on the distance that exceeds the IAEA criteria for effective dose (100 mSv per 7 days) and thyroid dose (50 mSv per 7 days) were compared. The effective dose reduction rates of the STC-3, STC-4, STC-6 were about 95-99% in the whole range (0~35 km), 96-98% for the thyroid dose. There are similar results between effective dose and thyroid dose. After applying the CFVS, the damage scale that exceeds the effective dose criteria was about 1 km (mean). Especially, the STC-4 damage scale was decreased from 26 km (mean) to 1.2 km (mean) significantly. The damage scale that exceed the thyroid dose criteria was decreased to 2~3 km (mean). The STC-4 damage scale was also decreased significantly as compared to STC-3, STC-6 in terms of effective dose.

• Journal of the Korea Concrete Institute
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• v.22 no.6
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• pp.817-824
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• 2010

The concrete containment structures have been widely used in nuclear power plants, LNG storage tanks, etc., due to their high safety and economic efficiency. The containment structure consists of a bottom slab, wall, ring beam and dome. The shape of the roof dome has a very significant effect on structural safety, the quantity of materials, and constructability; the thickness and curvature of the dome should therefore be determined to give the optimum design. The ring beam plays the role as supports for the dome, resulting in a minimized deformation of the wall. The main issues in designing the ring beam are the correct dimensions of the section and the prestress level. In this study, an efficient design procedure is proposed that can be used to determine an optimal shape and prestress level of the dome and ring beam. In the preliminary design stage of the procedure, the membrane theory of shells of revolution is adopted to determine several plausible alternatives which can be obtained even by hand calculation. Based on the proposed procedures, domes and ring beams of the existing domestic containment structures are analyzed and some improvements are discussed.

• Computational Structural Engineering
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• v.2 no.2
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• pp.17-19
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• 1989

건축구조물의 이차원 해석을 위한 SWAN88은 한국과학기술원의 이동근 교수에 의하여 개발되었으며 소프트웨어센터를 통해서 보급되고 있다. SWAN88은 보와 기둥으로 구성된 프레임이나 여기에 전단벽이 추가적으로 사용된 구조물의 해석이 사용될 수 있으며 개인용 컴퓨터를 사용하여 짧은 시간내에 상당히 큰 구조물의 해석이 가능하도록 개발되었다. 사무소건물, 아파트, 호텔, 병원 및 학교건물 등과 같이 규칙적인 형태의 구조물에 대한 해석에 매우 효율적인 SWAN88은 주택, 공장, 창고, 격납고 또는 체육관 등과 같이 보, 기둥 및 전단벽 이외에 트러스나 아취 등이 사용되는 구조물의 해석에는 적합하지 않다.

• Proceedings of the Korean Nuclear Society Conference
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• 2003.05a
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• pp.177-177
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• 2003

• Proceedings of the Korean Nuclear Society Conference
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• 2004.05a
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• pp.163.2-163.2
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• 2004

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.689-694
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• 1997

본 논문에서는 초음속연소 발생 기준에 대해 ABB-CE에서 System80+에 적용한 방법론과 W. Breitung 등이 최근 실험자료를 이용하여 제시한 방법론에 대한 모델의 특징을 비교ㆍ분석하였다. W. Breitung 등이 제시한 방법론을 이용한 격납건물내에서 존재할 수 있는 여러 격실크기에서 수소농도를 가정하여 초음속연소 가능성 평가 수행 및 초음속연소 발생 평가절차를 제시하였다.

• Proceedings of the SAREK Conference
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• 2003.07a
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• pp.215-215
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• 2003

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.16 no.1
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• pp.37-41
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• 2020

The Nuclear containment building is a main safety-related structure that performs shielding and conservation functions to prevent highly radioactive materials from leakage to the outside environment in the case of various environmental conditions and postulated accidents. The containment building contains a reactor, steam generator, pressurizer, tank, reactor coolant system, auxiliary system and engineering safety system, and is designed so that highly radioactive materials above the limits specified in 10 CFR 100 do not escape to the outside environment in the case of LOCA(Loss of Coolant Accident) for instance. The containment metal liner plate(CLP) is a carbon steel plate with a nominal plate thickness of 6 mm, which functions as a mold for the wall and dome of the containment building when concrete is filled, fulfills airtightness to prevent leakage of seriously radioactive materials. In recent years, backside corrosion was found on the liner plate in some domestic nuclear power plants. The main cause of backside corrosion was unfilled concrete. In this paper, an inspection technique of assessing filling suitability for CLP backside concrete is developed. Results show that the validity of inspection technique for CLP backside concrete using vibration sensor is successfully verified.

• Computational Structural Engineering
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• v.7 no.4
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• pp.145-150
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• 1994

Seismic isolation in ordinary buildings has been successively adapted to provide flexibility for the reduction of base shear forces and its concept is accepting wide agreement in lengthening the natural, period to lessen the spectral acceleration transmitted into the structure. However, one of difficulties in implementing the innovative concept to nuclear structures is due to more severe requirements in both understanding and predicting the characteristics of isolators and the behavior of cushioned structures, Stochastic analysis has been carried out to investigate the response of base isolated nuclear containers to the random earthquake ground motion.