• Nuclear Engineering and Technology
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• 제38권3호
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• pp.293-300
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• 2006

A liquid metal reactor (LMR) operated at high temperatures is subjected to both cyclic mechanical loading and thermal loading; thus, creep-fatigue is a major concern to be addressed with regard to maintaining structural integrity. The Korea Advanced Liquid Metal Reactor (KALIMER), which has a normal operating temperature of $545^{\circ}C$ and a total service life time of 60 years, is composed of various cylindrical structures, such as the reactor vessel and the reactor baffle. This study focuses on the creepfatigue crack initiation for a cylindrical Y-junction structure made of 316 stainless steel (SS), which is subjected to cyclic axial tensile loading and thermal loading at a high-temperature hold time of $545^{\circ}C$. The evaluation of the considered creep-fatigue crack initiation was carried out utilizing the ${\sigma}_d$ approach of the RCC-MR A16 guide, which is the high-temperature defect assessment procedure. This procedure is based on the total accumulated strain during the service time. To confirm the evaluated result, a high-temperature creep-fatigue structural test was performed. The test model had a circumferential through wall defect at the center of the model. The defect front of the test model was investigated after the $100^{th}$ cycle of the testing by utilizing a metallurgical inspection technique with an optical microscope, after which the test result was compared with the evaluation result. This study shows how creep-fatigue crack initiation for a high-temperature structure can be predicted with conservatism per the RCC-MR A16 guide.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 요약집 춘계학술발표대회
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• pp.316.2-316.2
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• 2004

• Nuclear Engineering and Technology
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• 제43권3호
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• pp.301-308
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• 2011

The diametral creep of pressure tubes (PTs) in CANDU (CANada Deuterium Uranium) reactors is one of the principal aging mechanisms governing the heat transfer and hydraulic degradation of the heat transport system (HTS). PT diametral creep leads to diametral expansion, which affects the thermal hydraulic characteristics of the coolant channels and the critical heat flux (CHF). The CHF is a major parameter determining the critical channel power (CCP), which is used in the trip setpoint calculations of regional overpower protection (ROP) systems. Therefore, it is essential to predict PT diametral creep in CANDU reactors. PT diametral creep is caused mainly by fast neutron irradiation, temperature and applied stress. The objective of this study was to develop a bundle position-wise linear model (BPLM) to predict PT diametral creep employing previously measured PT diameters and HTS operating conditions. The linear model was optimized using a genetic algorithm and was devised based on a bundle position because it is expected that each bundle position in a PT channel has inherent characteristics. The proposed BPLM for predicting PT diametral creep was confirmed using the operating data of the Wolsung nuclear power plant in Korea. The linear model was able to predict PT diametral creep accurately.

• 콘크리트학회논문집
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• 제14권3호
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• pp.382-391
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• 2002

본 연구에서 초기재령 콘크리트의 크리프 특성을 고려한 단면 내 온도 및 수축응력을 구하는 3차원 유한요소 해석 프로그램을 개발하기 위한 수치해석 절차에 관하여 정립하였다. 최근 들어 구조물의 노후화에 따른 콘크리트의 내구성에 대한 관심이 고조되고 있고, 초기재령에서 발생하는 균열은 구조물의 내구성 및 사용성과 같은 장기적인 성능에 큰 영향을 미친다. 많은 토목 기술자들이 초기재령 콘크리트의 체적변화에 의한 응력 및 균열 문제를 심도 깊게 다루지 않는 데는 장기적인 내구성과 사용성에 대한 인식이 부족하고, 경화가 진행되는 콘크리트의 체적변화는 매우 복잡한 영향인자를 고려해야 되기 때문이다. 또한 초기재령 콘크리트의 체적변화로 인한 응력을 예측하는 기존 프로그램들은 주로 수화열에 의한 온도 및 열응력 해석에 국한되거나, 수화과정과 연계되지 않은 습도분포에 의한 수축 응력해석을 대상으로 한다. 따라서 본 연구에서는 초기재령 콘크리트의 체적 변화에 의한 모든 응력 요소를 하나의 통합적인 해석 시스템으로 구성하여, 초기재령 콘크리트의 균열 제어 수단으로 활용하고자 한다. 본 연구는 초기재령 콘크리트의 온도 및 수분에 관련된 재료 물성 뿐 만 아니라 역학적 특성 등 모든 재료 물성을 수화도에 기초하여 모델링하였다. 또한 콘크리트가 강성을 가지는 시점부터의 초기재령 크리프 실험을 수행하고, 그 결과로부터 수화도에 따른 크리프 거동을 모델링하여 해석 프로그램에 반영하였다. 개발된 해석프로그램을 이용하여 수치해석 결과와 실험결과를 비교하여 그 타당성을 검증하고, 해석 예제를 통하여 각 변형률 성분에 의한 잔류 응력의 변화 양상을 비교, 분석하였다.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2008년도 추계학술대회 논문집
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• pp.605-606
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• 2008

• 한국지반신소재학회논문집
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• 제3권2호
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• pp.31-38
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• 2004

2종류 지오그리드의 장기안정성의 검토되었다. 멤브레인 연신형 지오그리드는 지수함수형 인장거동을, 섬유형 지오그리드는 파단점에 가까울수록 빠른 인장특성 증가를 나타내었다. 섬유형 지오그리드의 경우 가속 크리프 시험을 실시하였지만 멤브레인 연신형 지오그리드의 경우에는 열적특성 때문에 가속 크리프 시험을 실시할 수 없었다. 멤브레인 연신형 지오그리드의 크리프 변형률은 인장시험에 의한 극한변형률보다 훨씬 큰 값을 나타내었으며, 섬유형 지오그리드의 크리프 변형에 의한 감소인자는 멤브레인 연신형 지오그리드에 비해 작은 값을 나타내었다.

• 한국압력기기공학회 논문집
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• 제12권1호
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• pp.70-77
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• 2016

In this paper, the structural design and integrity evaluations for a reactor vessel of PGSFR sodium-cooled fast reactor(150MWe) are carried out in compliance with ASME BPV III, Division 5 Subsection HB. The reactor vessel is designed with a direct contact of primary sodium coolant to its inner surface and has a double vessel concept enclosing by containment vessel. To assure the structural integrity for 60 years design lifetime and elevated operating temperature of $545^{\circ}C$, which can invoke creep and creep-fatigue damage, the structural integrity evaluations are carried out in compliance with the ASME code rules. The design loads considered in this evaluations are primary loads and operation thermal cycling loads of normal heat-up and cool-down. From the evaluations, the PGSFR reactor vessel satisfies the ASME code limits but it was found that there is a little design margin of creep damage for inner surface at the region of cold pool free surface.

• Structural Engineering and Mechanics
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• 제16권6호
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• pp.695-712
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• 2003

The non-linear structural analysis of reinforced concrete beams in fire consists of three separate steps: (i) The estimation of the rise of surrounding air temperature due to fire; (ii) the determination of the distribution of the temperature within the beam during fire; (iii) the evaluation of the mechanical response due to simultaneous time-dependent thermal and mechanical loads. Steps (ii) and (iii) are dealt with in the present paper. We present a two-step computational procedure where a 2D transient thermal analysis over the cross-sections of beams are made first, followed by mechanical analysis of the structure. Fundamental to the accuracy of the mechanical analysis is a new planar beam finite element. The effects of plasticity in concrete, and plasticity and viscous creep in steel are taken into consideration. The properties of concrete and steel along with the values of their thermal and mechanical parameters are taken according to the European standard ENV 1992-1-2 (1995). The comparison of our numerical and full-scale experimental results shows that the proposed mechanical and 2D thermal computational procedure is capable to describe the actual response of reinforced concrete beam structures to fire.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 1997년도 춘계학술대회 논문집
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• pp.905-909
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• 1997

A geometric error of machine parts is one of the most important factors that affect the accuracy of positioning, generating and measuring for precision machinery. It is known that the thermal deformation of a workpiece during surface grinding is the most important in the geometric error of ground surface. This paper experimentally describes the grinding characteristics of creep-feed grinding. The wheels have 6 slotted pieces in order to compare the grinding temperature with the geometric.

• 수산해양기술연구
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• 제28권1호
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• pp.71-78
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• 1992

Zr-4 used for a cladding and an end plug of reactor component has creep deformation under operation at high temperature. Creep is regarded as the time dependent deformation of a material under constant applied stress. Although the major source of the deformation of zirconium component in water-cooled reactors is irradiation creep, the thermal creep may give a rise to significant deformation in reactor component especially at relatively high temperatures and at various constant stresses, and therefore it must be predicted accurately. Stress relaxation is the time dependent change of stress at constant strain and it is a process related intimately to creep. In this paper, the creep behavior and stress relaxation of Zr-4 is examined at the temperature of 50$0^{\circ}C$ that is 40% of the absolute melting temperature of Zr-4 under the stress below yield stress and under the various constant strains. The results obtained are summarized as follows: 1) With an increase of stress, the steady state creep rate increases and the creep rupture time decreases. 2) The steady state creep rate $\varepsilon$(%/s) for the stress $\sigma$sub(c) (kgf/mm super(2)) of Zr-4 increases outstandingly. All the empirical equations computed for Zr-4 increases outstandingly. All the empirical equations computed for Zr-4 are in accord with Norton's model equation($\varepsilon$=K$\sigma$ sub(c) super (n)). The constants of materials computed are as follows: K=3.9881$\times$10 super(-5), n=1.9608 3) The rupture time T sub(r) (hr) decreases linearly with the increase of stress on the log-log scaled graph. The empirical equations computed for Zr-4 are in accord with Bailey's model equation (T sub(r)=K sub(1)$\sigma$sub(c) super(m)). The constants of materials computed are as follows: K sub(1)=1.2875$\times$10 super(16), m=-3.467 4) It seems clear that the strain could be quantitatively dependent on the high temperature creep properties such as creep stress, rupture time, steady state creep rate and total creep rate. It is found that these relationships are linear on the log-log graph. 5) In stress relaxation test, as the critical constant strain that can be allowed to the specimen is larger, stress relaxation becomes more rapid, and as the constant strain is smaller, the stress relaxation becomes slower.