• Journal of the Korean Society for Nondestructive Testing
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• v.26 no.5
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• pp.297-305
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• 2006

The thermal ratcheting deformation at the reactor baffle and upper internal structure of the liquid metal reactor (LMR) can occur due to movement of the hot sodium free surface. In in-service inspection of reactor internals of LMR, a new inspection technique should be developed for the detection of the thermal ratcheting damage. In this study, an inspection technique using ultrasonic guided wave is proposed for the detection of the thermal ratcheting damage of cylindrical vessels. A 316L stainless steel cylindrical shell specimen has been prepared. The thermal ratchet structural tests were cyclically performed by heat-up up to $550^{\circ}C$ with steep temperature gradients along the axial direction after cool-down by cooling water. Ultrasonic guided wave propagation has been characterized by analysis of dispersion curve of the stainless steel plate. The zero-order antisymmetric $A_0$ guided wave has been selected as the optimal mode for detection of the ratcheting deformation. It is confirmed that the thermal ratcheting deformation can be detected by the measurement of transit time difference of circumferentially propagated $A_0$ guided waves.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.235-240
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• 1996

본 연구에서는 고온의 천이 열하중을 받는 304 SS 재질의 액체금속로 원통용기에 대하여 진행성 변형기구인 열적 라체팅(thermal ratcheting) 변형거동을 해석하였다. 재료의 반복 소성을 나타내는 구성식으로서 Chaboche모델을 이용하였으며 이 모델의 적용을 위하여 ABAQUS의 사용자 프로그램을 개발하였다. 열천이 과정이 반복되는 동안에 축방향의 온도분포 이동에 따른 탄소성 해석을 수행한 결과 소성변형이 각 싸이클마다 누적되어 점진적 변형이 일어났으며 이 해석결과를 시험치와 비교함으로써 해석의 타당성을 검토하였다. 반복 소성거동에 대한 Chaboche 모델을 이용하면 천이 열하중을 받는 304 SS. 재질의 고온구조물에 대하여 라체팅 거동을 정량적으로 평가 할 수 있는 것으로 나타났다.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.342.2-342
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.659-665
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• 1995

액체금속로는 기존의 가압경수로와는 달리 55$0^{\circ}C$ 정도의 고온에서 운전이 되므로 고온 열응력이 중요한 문제로 대두되며 따라서 고은에서의 크립(Creep) 변형, 반복되는 기동과 정지 등으로 인한 되풀이 소성변형, 라체팅(Ratchetting), 크립과 소성의 상호작용 및 크립과 피로의 상호작용 등의 평가에 대한 기술 확립과 고온구조물에 대한 우리의 독자적인 설계방법을 개발하는 것이 필요하다 본 연구에서는 범용 유한요소해석코드인 ABAQUS의 축대칭 요소를 이용해서 액체 금속로 원자로용기와 이에 부착된 열소매(Thermal sleeve)를 Y-형태의 구조물로 모델링하여 반복되는 열천이하중에 대한 비탄성 구조해석을 수행하고 크립효과에 대한 영향을 분석하였다. 해석결과 액체금속로와 같은 고온구조물에 대하여 반복 열천이 하중과 고온 지속시간이 유발하는 크립효과가 크게 나타남을 알 수 있었다.

• Proceedings of the KSR Conference
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• 2007.05a
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• pp.767-774
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• 2007

Even though a constant repeated load is applied, plastic deformation may cumulate. This kind of behavior is called ratcheting. Ratcheting may lead to cracks and finally to failure of the rail. Usually ratcheting occurs on high rails in curves. Ratcheting is influenced by residual stresses, wheel-rail contact stresses, thermal stresses due to wheel/rail rolling contact, shear strength of the rail, strain hardening behavior, etc. In this study, contact stresses and thermal stresses are examined. It is found their value is considerable compared to the maximum contact pressure.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.26 no.3
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• pp.479-486
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• 2002

In this study, the progressive inelastic deformation, so called, thermal ratchet phenomenon which can occur in high temperature structures of liquid metal reactor was simulated with thermal ratchet structural test facility and 316L stainless steel test cylinder. The thermal ratchet deformation at the reactor baffle cylinder of the liquid metal reactor can occur due to the moving temperature distribution along the axial direction as the sodium free surface moves up and down under the cyclic heat-up and cool-down transients. The ratchet deformation was measured with the laser displacement sensor and LVDTs after cooling the structural specimen which is heated up to 55$0^{\circ}C$ with steep temperature gradients along the axial direction. The temperature distribution of the test cylinder along the axial direction was measured with 28 channels of thermocouples and was used for the ratchet analysis. The thermal ratchet deformation was analyzed with the constitutive equation of nonlinear combined hardening model which was implemented as ABAQUS user subroutine and the analysis results were compared with those of the test. Thermal ratchet load was applied 9 times and the residual displacement after 9 cycles of thermal load was measured to be 1.79mm. The ratcheting deformation shapes obtained by the analysis with the combined hardening model were in reasonable agreement with those of the structural tests.

• Proceedings of the KSME Conference
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• 2001.06a
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• pp.243-249
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• 2001

In this study, the progressive inelastic deformation, so called, thermal ratchet phenomenon which can occur in high temperature liquid metal reactor was simulated with thermal ratchet structural test facility and 316L stainless steel test cylinder. The inelastic deformation of the reactor baffle cylinder can occur due to the moving temperature distribution along the axial direction as the hot free surface moves up and down under the cyclic heat-up and cool-down of reactor operations. The ratchet deformations were measured with the laser displacement sensor and LVDTs after cooling the structural specimen which experiences thermal load up to $550^{\circ}$ and the temperature differences of about $500^{\circ}C$. During structural thermal ratchet test, the temperature distribution of the test cylinder along the axial direction was measured from 28 channels of thermocouples and the temperatures were used for the ratchet analysis. The thermal ratchet deformation analysis was performed with the NONSTA code whose constitutive model is nonlinear combined kinematic and isotropic hardening model and the test results were compared with those of the analysis. Thermal ratchet test was carried out with respect to 9 cycles of thermal loading and the maximum residual displacements were measured to be 1.8mm. It was shown that thermal ratchet load can cause a progressive deformation to the reactor structure. The analysis results with the combined hardening model were in reasonable agreement with those of the tests.