• 제목/요약/키워드: Creep Damage

검색결과 174건 처리시간 0.025초

PGSFR 소듐냉각고속로 원자로용기 설계 및 구조건전성 평가 (Structural design and integrity evaluations for reactor vessel of PGSFR sodium-cooled fast reactor)

  • 구경회;김성균
    • 한국압력기기공학회 논문집
    • /
    • 제12권1호
    • /
    • pp.70-77
    • /
    • 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.

Development of a structural integrity evaluation program for elevated temperature service according to ASME code

  • Kim, Nak Hyun;Kim, Jong Bum;Kim, Sung Kyun
    • Nuclear Engineering and Technology
    • /
    • 제53권7호
    • /
    • pp.2407-2417
    • /
    • 2021
  • A structural integrity evaluation program (STEP) was developed for the high temperature reactor design evaluation according to the ASME Boiler and Pressure Vessel Code (ASME B&PV), Section III, Rules for Construction of Nuclear Facility Components, Division 5, High Temperature Reactors, Subsection HB. The program computerized HBB-3200 (the design by analysis procedures for primary stress intensities in high temperature services) and Appendix T (HBB-T) (the evaluation procedures for strain, creep and fatigue in high temperature services). For evaluation, the material properties and isochronous curves presented in Section II, Part D and HBB-T were computerized for the candidate materials for high temperature reactors. The program computerized the evaluation procedures and the constants for the weldment. The program can generate stress/temperature time histories of various loads and superimpose them for creep damage evaluation. The program increases the efficiency of high temperature reactor design and eliminates human errors due to hand calculations. Comparisons that verified the evaluation results that used the STEP and the direct calculations that used the Excel confirmed that the STEP can perform complex evaluations in an efficient and reliable way. In particular, fatigue and creep damage assessment results are provided to validate the operating conditions with multiple types of cycles.

발전설비 강 용접부의 크리프 특성 평가 기술 개발 (Development of Creep Properties Evaluation Technique for Steel Weldment of Power Plant)

  • 이동환;정영훈;백승세;하정수;송기욱;이송인;유효선
    • 대한기계학회:학술대회논문집
    • /
    • 대한기계학회 2001년도 추계학술대회논문집A
    • /
    • pp.180-185
    • /
    • 2001
  • In the life assessment for plant structural component, the research on deterioration of toughness and material properties occurred in weldments has been considered as very important problems. In general, the microstructures composed in weldments are hugely classified with weld metal(W.M), fusion line(F.L), heat affected zone(HAZ), and base metal(B.M). It has been reported that the creep characteristics on weldments having variable microstructures could be unpredictably changed. Furthermore, it is also known that HAZ adjacent to F.L exhibits the decreased creep strength compared to those in base or weld metals, and promotes the occurrence of Type III and Type IV cracking due to the growth of grains and the coarsening carbides precipitated in ferritic matrix by welding and PWHT processes. However, the lots of works reported up to date on creep damage in power plant components have been mostly conducted on B.M and the creep properties on a localized microstructures in weldments have not as yet been throughly investigated. In this paper, for various microstructures such as coarse grain HAZ(CGHAZ), W.M and B.M in X20CrMoV121 steel weldment, the small punch-creep(SP-Creep) test using miniaturized specimen(t=0.5mm, 0.25mm) is performed to investigate a possibility for creep characteristics evaluation.

  • PDF

보강용 지오신세틱스의 가속 인장 크리프 시험방법 (Accelerated Tensile Creep Test Method of Geosynthetics for Soil Reinforcement)

  • 구현진;조항원
    • 한국지반공학회:학술대회논문집
    • /
    • 한국지반공학회 2008년도 추계 학술발표회
    • /
    • pp.196-203
    • /
    • 2008
  • Durability of geosynthetics for soil reinforcement is accounted for creep and creep rupture, installation damage and weathering, chemical and biological degradation. Among these, the long-term creep properties have been considered as the most important factors which are directly related to the failure of geosynthetic-reinforced soil(GRS). However, the creep test methods and strain limits are too various to compare the test results with each other. The most widely used test methods are conventional creep test, time-temperature superposition and stepped isothermal method as accelerated creep tests. Recently developed design guidelines recommend that creep-rupture curve be used to determine the creep reduction factor($RF_{CR}$) which is a conservative approach. In this study, the different creep test methods were compared and the creep reduction factors were estimated at different creep strain limits of 10% of total creep strain and creep rupture. In order to minimize the impact of creep strain to the GRS structures, the various creep reduction factors using different creep test methods should be investigated and then the most appropriated one should be selected for incorporating into the design.

  • PDF

Atypical viscous fracture of human femurs

  • Yosibash, Zohar;Mayo, Romina Plitman;Milgrom, Charles
    • Advances in biomechanics and applications
    • /
    • 제1권2호
    • /
    • pp.77-83
    • /
    • 2014
  • Creep phenomenon at the scale of bone tissue (small specimens) is known to be present and demonstrated for low strains. Here creep is demonstrated on a pair of fresh-frozen human femurs at the organ level at high strains. Under a constant displacement applied on femur's head, surface strains at the upper neck location increase with time until fracture, that occurs within 7-13 seconds. The monotonic increase in strains provides evidence on damage accumulation in the interior (probably damage to the trabeculae) prior to final fracture, a fact that hints on probable damage of the trabecular bone that occurs prior to the catastrophic fracture of the cortical surface layer.

지반 크리프 거동의 미시학적 모델링 (Microscopic Modeling of Creep Behavior for Soils)

  • 김대규
    • 한국산학기술학회논문지
    • /
    • 제7권3호
    • /
    • pp.409-413
    • /
    • 2006
  • 미시학적 비배수 크리프 현상의 누적 변형은 점성토 시공지역 지반의 전반 파괴를 야기 할 수 있다. 본 연구에서는 점성토의 비배수 크리프 거동을 예측하기 위하여 Perzyna의 일반 점성이론을 소성론의 개념에서 간략화하고 수정 Cam clay 모델 및 데미지 이론을 포함하는 하나의 시간의존적 구성방정식을 유도하였다. 유도된 구성방정식을 활용하여 예측한 크리프 거동은 비배수 크리프 파괴를 포함하는 크리프 실험결과와 잘 부합하였다.

  • PDF

CREEP-FATIGUE CRACK GROWTH AND CREEP RUPTURE BEHAVIOR IN TYPE 316 STAINLESS STEELS- EFFECT OF HOLD TIME AND AGING TREATMENT

  • Mi, J.W.;Won, S.J.;Kim, M.J.;Lim, B.S.
    • International Journal of Automotive Technology
    • /
    • 제1권2호
    • /
    • pp.71-77
    • /
    • 2000
  • High temperature materials in service are subjected to mechanical damage due to operating load and metallurgical damage due to operating temperature. Therefore, when designing or assessing life of high temperature components, both factors must be considered. In this paper, the effect of tensile hold time on high temperature fatigue crack growth and long term prior thermal aging heat treatment on creep rupture behavior were investigated using STS 316L and STS 316 austenitic stainless steels, which are widely used for high temperature components like in automotive exhaust and piping systems. In high temperature fatigue crack growth tests using STS 316L, as tensile hold time increased, crack growth rate decreased in relatively short tensile hold time region. In long term aged specimens, cavity type microcracks have been observed at the interface of grain boundary and coarsened carbide.

  • PDF

Thermal creep effects of aluminum alloy cladding on the irradiation-induced mechanical behavior in U-10Mo/Al monolithic fuel plates

  • Jian, Xiaobin;Ding, Shurong
    • Nuclear Engineering and Technology
    • /
    • 제52권4호
    • /
    • pp.802-810
    • /
    • 2020
  • Three-dimensional finite element simulations are implemented for the in-pile thermo-mechanical behavior in U-Mo/Al monolithic fuel plates with different thermal creep rates of cladding involved. The numerical results indicate that the thickness increment of fuel foil rises with the thermal creep coefficient of cladding. The maximum Mises stress of cladding is reduced by ~85% from 344 MPa on the 98.0th day when the creep coefficient of cladding increases from 0.01 to 10.0, due to its equivalent thermal creep strain enlarged by 3.5 times. When the thermal creep coefficient of Aluminum cladding increases from 0 to 1.0, the maximum mesoscale stress of fuel foil varies slightly. At the same time, the peak mesoscale normal stress of fuel foil can reach 51 MPa on the 98.0th day for the thermal creep coefficient of 10, which increases by 60.3% of that with the thermal creep un-occurred in the cladding. The maximum through-thickness creep strain components of fuel foil differ slightly for different thermal creep coefficients of cladding. The dangerous region of fuel foil becomes much closer to the heavily irradiated side when the creep coefficient of cladding becomes 10.0. The creep performance of Aluminum cladding should be optimized for the integrity of monolithic fuel plates.

Creep strain modeling for alloy 690 SG tube material based on modified theta projection method

  • Moon, Seongin;Kim, Jong-Min;Kwon, Joon-Yeop;Lee, Bong-Sang;Choi, Kwon-Jae;Kim, Min-Chul
    • Nuclear Engineering and Technology
    • /
    • 제54권5호
    • /
    • pp.1570-1578
    • /
    • 2022
  • During a severe accident, steam generator (SG) tubes undergo rapid changes in the pressure and temperature. Therefore, an appropriate creep model to predict a short term creep damage is essential. In this paper, a novel creep model for Alloy 690 SG tube material was proposed. It is based on the theta (θ) projection method that can represent all three stages of the creep process. The original θ projection method poses a limitation owing to its inability to represent experimental creep curves for SG tube materials for a large strain rate in the tertiary creep region. Therefore, a new modified θ projection method is proposed; subsequently, a master curve for Alloy 690 SG material is also proposed to optimize the creep model parameters, θi (i = 1-5). To adapt the implicit creep scheme to the finite element code, a partial derivative of incremental creep with respect to the stress is necessary. Accordingly, creep model parameters with a strictly linear relationship with the stress and temperature were proposed. The effectiveness of the model was validated using a commercial finite element analysis software. The creep model can be applied to evaluate the creep rupture behavior of SG tubes in nuclear power plants.

크리프-피로상호작용하의 파단수명에 관한 연구 (Study on Fracture Life Under Mutual Interaction of Creep and Fatigue)

  • 조용이;김희송
    • 한국정밀공학회지
    • /
    • 제10권3호
    • /
    • pp.97-106
    • /
    • 1993
  • This is the study on fracture life under the interaction of creep and fatigue. It is difficult to explain the interaction of the creep and fatigue with indication of frequency but the dependency of the time should be considered. The formulation of material varieties causing by interaction of creep and fatigue is required in the accumulative damage method. The strain range partition method requires some of modification corresponding to the changes in temperature and load. All of other method also comprehended with above mentioned problems. Generally, in this field, the variety of stress-strain and suitable parameter is required and connective study between the macro and micro results seems to be insufficient. The linear damage rule is acquiring the support generally but it requires modification in the hgigh temperature instruments. The variety of stress effecting on crack and variety of stress on the metallurgical side are considered to be problems in the future days.

  • PDF