• Journal of the Computational Structural Engineering Institute of Korea
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• v.13 no.1
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• pp.147-158
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• 2000

For the large scale reinforced concrete cooling tower shells, the shape imperfection can be introduced due not only to mistakes in the process of construction but also to the long term behavior of concrete. The shape imperfection evokes the additional responses such as displacements and stresses in addition to the design values. In this study, the statistical behavior of the RC cooling tower shell due to the shape imperfection is investigated using the Monte Carlo simulation. The radius of cooling tower and the shell thickness are adopted as the parameters which cause the shape imperfection. The shape imperfection is modeled as a stochastic field rather than the local one of axisymmetric or bulge type of imperfection. The randomness in the radius is shown to be more affecting the structural responses than the randomness in the shell thickness. In addition to the geometrical randomness, the effect of randomness in the modulus of elasticity on the structural response is also investigated and compared with that of the geometrical ones.

• KSCE Journal of Civil and Environmental Engineering Research
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• v.12 no.4
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• pp.59-70
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• 1992

Inelastic nonlinear behavior of a hyperbolic cooling tower under wind loading is studied using a finite element program developed on a Cray Y-MP. Convergence studies for the elastic and inelastic analyses are performed using three mesh models. It is shown that the mesh convergence plays an important role in accurately predicting the inelastic behavior of a cooling tower. Even though the cooling tower resists the applied forces through membrane stresses, it is found that the bending stresses play an important role in the failure and behavior of the cooling tower. The present analysis gives a shape factor of 1.48, which indicates a significant redistribution of meridional stresses. It is further evidenced by the distribution of meridional reinforcement yielding which reaches up to $30^{\circ}$ from the windward meridian. The present practice of using elastic analysis for calculating the design stresses appears to be at least safe and conservative. A more comprehensive study should lead to conclusions that would allow use of a higher-than-one shape factor, thus requiring less meridional reinforcement than the present design method does.

• Nuclear Engineering and Technology
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• v.27 no.3
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• pp.393-402
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• 1995

The structural analysis of the reactor coolant system mainly consist of too fields. The one is the static analysis considering the impact of pressure and temperature built up during normal operation. The other is the dynamic analysis to estimate the impact of postulated events such as the seismic loads or postulated branch line pipe breaks event. Since the most important goal of the RCS structural analysis is to prove the safety of the RCS during normal operation or postulated events, a widely proven theory having enough conservatism is adopted. The load occurring on the RCS during normal operation is considered as the basic design loading condition throughout whole plant life time. The most typical characteristic of the RCS during normal operation is the thermal expansion of the RCS caused by reactor coolant with high temperature and pressure. Therefore, the exact estimation on the thermal movement of the RCS is needed to get more clear understanding on the thermal movement behavior of the RCS. In this study, the general structural analysis concept and modeling method to evaluate the thermal movement of the RCS under the normal plant operation condition are presented. To discuss the validation of the suggested analysis, analysis results are compared with the measured data which ore referred from the standardized 1000 MWe PWR plant under construction.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.34 no.1
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• pp.49-54
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• 2010

Fretting wear behavior under elastic deformable contacts was experimentally examined by using a simulated dual cooled fuel rod and its supporting structure. As this fuel rod has larger outer diameter than the typical solid rod to accommodate sufficient internal flow, new supporting structure geometries should be designed and their reliabilities (i.e. vibration characteristics, fretting wear resistance, etc.) are also examined with both analytical and experimental methods. In this study, the supporting structure characteristics and fretting wear behaviors are analyzed and examined by using one of the supporting structure candidates which has an embossing shape. The supporting structure characteristics were examined by using a specially designed test rig and their results were compared with that of analytical method. Based on the test results, the relationship between the supporting structure characteristics and their fretting wear behaviors was discussed in detail.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.669-674
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• 1997

LAVA(Lower-plenum Arrested Vessel Attack) 실험은 중대사고시 고온의 노심 용융물이 냉각수가 존재하는 원자로 용기 하부 반구내로 재배치되는 경우 노심 용융물과 하부반구의 열적 거동 모사와 노심용융물과 하부 반구 사이의 구조 분석 및 고화 후의 용융물형상에 대한 관측을 통하여 노심용융물의 자연 냉각 현상을 규명하고자 하는 실험 연구이다. 원자로 용기 하부 반구를 1/8로 선형 축소한 반구형 반응 용기 내부로 $Al_2$O$_3$/Fe Thermite 용융물을 주입하여 용융물과 하부 반구 사이의 구조 및 하부 반구의 열적 거동을 분석하는 실험을 2회 수행하였다. 각각 20, 40kg의 $Al_2$O$_3$/Fe Thermite 용융물을 주입시 킨 LAVA_PRE, LAVA-1 실험 결과 용융물 주입에 따른 하부 반구의 파손은 발생하지 않았으며, 유사한 실험조건에서 수행된 일본 ALPHA실험에 비해서는 하부 반구의 최대 온도가 500 K 이상 높게 측정되었고 냉각율 또한 현저히 낮게 나타났다. 이는 $Al_2$O$_3$/Fe Thermit 용융물중 과열상태의 Fe성분이 하부 반구와 용접되었기 때문으로 판단되며 보다 정확한 하부 반구의 열적거동을 모사하기 위하여 반구 시편에 대한 재료, 조직 검사를 수행하고 있다. 추후의 실험에서는 하부 반구 내외부의 압력 부하에 따른 반응 양상 및 Fe 용융물(금속용융물) 성분을 제거하고 순수한 $Al_2$O$_3$용융물(산화용융물) 만을 주입하여 용융물 성분에 따른 하부 반구의 열적거동을 분선 할 예정이다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.649-656
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• 1996

RELAP5/MOD3.1.2을 이용하여 영광3/4호기의 부분충수운전중 정지냉각계통 기능상실사고를 모의하였다. 이 해석은 노심에서 발생되는 증기를 가압기 Manway로 배출시켜 노심을 냉각할 경우, 증기발생기 2차측 냉각재 유무에 따르는 계통거동을 분석한 것이다. 해석결과, 노심에서의 비등은 사고후 약 6분 경에 발생하였으며, 증기발생기 2차측에 냉각재가 없는 경우는, 냉각재가 채워져 있는 경우보다 0.16 bar 더 높은 1.8 bar의 계통 압력을 나타내어, 현재의 운전절차서에 제시한 RWST의 수위 (70%)로는 중력주입이 불가능한 것으로 밝혀졌다. 이런 해석결과를 토대로 할 때, 부분충수 운전중 증기발생기 2차측 냉각재는 최소한 한 대에는 충수하고, RWST 수위 제한치도 84 % 이상으로 증가시키는 운전 절차서의 개정이 필요한 것으로 판단된다.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.707-712
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• 1998

이종 코드에 의한 CE형 발전소의 대형 냉각재 상실 사고 해석이 수행되었다. 이 연구는 상대적으로 최근에 개발된 웨스팅하우스 대형 냉각재 상실 사고 해석 코드를 사용하여 영광 3&4호기의 대형 냉각재 상실 사고를 계산해 봄으로써 CE 대형 냉각재 상실 사고 해석 코드의 개선 방향을 고찰하는 것을 목적으로 하였다. 계산은 가장 제한적인 대형 냉각재 상실 사고의 Blowdown 및 Refill 기간 동안 수행하였다. 이 기간 동안의 RCS내 열수력적 거동 및 연료봉 온도 변화는 CE 대형 냉각재 상실 사고 해석 코드를 사용하여 계산한 경우와 크게 다르지 않음을 확인하였다. 따라서 향후 CE 대형 냉각재 상실 사고 해석 코드의 성능 개설은 Reflood 해석용 코드의 개선 및 개발을 중심으로 이루어져야 한다는 결론을 얻었다.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.37 no.1
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• pp.1-8
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• 2013

Coolant rubber hoses for automotive radiators can degrade under thermal and mechanical loadings and thus fail owing to the influences of locally formed electricity. In this study, an advanced test method was developed to simulate the failure of a rubber hose. The aging behavior of carbon-black-filled ethylene-propylene diene monomer (EPDM) rubber used as a radiator hose material under a combination of electrochemical stresses and tensile strain was analyzed. The changing behaviors of the current and the resistance as a function of the aging time were analyzed in consideration of the tensile strain, voltage, and aging temperature. Sectioned specimens clarified the failure mechanisms of the aged skin layer under the combined electrochemical stresses.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11a
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• pp.103-109
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• 1996

고리 원자력 1호기 14주기(‘95년도) 운전기간 중 증기발생기 세관 열전달 용량 저하로 전출력 운전 기간동안 정격출력보다 15% 감발 운전한 경험이 있었는데, 이 기간중 냉각재내 방사성 부식생성물(CRUD) 농도가 약 80% 감소됨을 발견하였다. 이때 출력감소 비율보다 많은 CRUD 감소현상 규명을 위해 냉각재 수질관리인자와 EPRI 피복재 부식모델인 PFCC코드를 사용한 피 복재 산화물 두께변화 등을 비교한 결과, 운전중 용출되는 방사성 부식생성물은 핵연료 표면의 피복재 산화물에 흡착된 Co핵종이 피복재 산화물 이탈시 함께 거동하는 것으로 확인되었으며, 피복재 산화물 이탈은 산화막 두께 및 열유속에 주로 의존함이 밝혀졌다. 따라서 냉각재내에서 방사성 부식 생성물의 생성률 저감을 위해서는 정상운전시 핵연료 표면의 산화막 증가를 억제할 수 있는 수질 조건을 도출하고 그에따른 운전을 통해 원전 작업자의 방사선 피폭량 저감 및 방사성폐기물의 발생을 줄일 수 있을 것으로 여겨진다.

• Journal of Korean Association for Spatial Structures
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• v.12 no.3
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• pp.97-104
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• 2012

In the design procedure of the cooling tower the form-finding of the shell is the most important process, because the shape of the shell determines the sensitivity of dynamic behaviour of the whole tower against wind excitation. In engineering practice, geometric parameters of the shell are generally determined based on natural frequency analysis. 32 cooling tower shell geometries were selected through variation of the geometric parameters of an existing cooling tower shell. They were evaluated based on the first natural frequency. From the result three representative cooling towers are selected for the analysis of the structural behaviour by means of linear FE-method. As a result, a hyperbolic rotational shell with the small radius overall will yield the shell geometry with a higher first natural frequency and thus a wind-insensitive structure.