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Survivability assessment of Viton in safety-related equipment under simulated severe accident environments 원문보기

Nuclear engineering and technology : an international journal of the Korean Nuclear Society, v.50 no.5, 2018년, pp.683 - 689  

Ryu, Kyungha (Research Division of Environmental and Energy Systems, Department of Nuclear Equipment Safety, Korea Institute of Machinery and Materials) ,  Song, Inyoung (Department of Nuclear Engineering, School of Mechanical, Aerospace, and Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST)) ,  Lee, Taehyun (Research Division of Environmental and Energy Systems, Department of Nuclear Equipment Safety, Korea Institute of Machinery and Materials) ,  Lee, Sanghyuk (Research Division of Environmental and Energy Systems, Department of Nuclear Equipment Safety, Korea Institute of Machinery and Materials) ,  Kim, Youngjoong (Research Division of Environmental and Energy Systems, Department of Nuclear Equipment Safety, Korea Institute of Machinery and Materials) ,  Kim, Ji Hyun (Department of Nuclear Engineering, School of Mechanical, Aerospace, and Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST))

Abstract AI-Helper 아이콘AI-Helper

To evaluate equipment survivability of the polymer Viton, used in sealing materials, the effects of its thermal degradation were investigated in severe accident (SA) environment in a nuclear power plant. Viton specimens were prepared and thermally degraded at different SA temperature profiles. Chang...

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제안 방법

  • A degradation test was performed to evaluate the degradation effect during each state of the SA temperature profile within air. The test was performed for four cases, and the mechanical properties of Viton exposed to each state were measured using the tensile test, as illustrated in Table 2 and Fig.
  • Moreover, thermal lag analysis was performed to predict the temperature of the polymer in an SA environment. A performance test was conducted via measurement of the temperature distribution in the equipment.
  • Because the hydrogen burn was assumed to occur only at the initial state, for a conservative assessment, convective heat transfer coefficients were calculated by taking into account the burning status of hydrogen used in the initial and transient states. Correspondingly, a convective heat transfer coefficient of 703 W/m2·K was used for the initial and transient states.
  • First, the assessment of the equipment was conducted. For the performance test, the temperature distribution of the furnace was evaluated by measuring the temperature at 5-cm intervals from the center of the equipment.
  • First, the assessment of the equipment was conducted. For the performance test, the temperature distribution of the furnace was evaluated by measuring the temperature at 5-cm intervals from the center of the equipment. The measured temperature distribution of the tube is shown in Fig.
  • The performance test was conducted by measuring the temperature distribution of the equipment. Furthermore, tests were performed to evaluate the degradation effect of the temperature profiles at each SA state. In addition, the exposure temperatures of the polymer components inside the equipment during the SA temperature profile were analyzed using thermal lag analysis.
  • To simulate the rapidly elevated temperature in the initial state, a specimen-shifting system was designed using the temperature gradient of the electric furnace. Furthermore, the mechanical properties of the polymer after each SA temperature profile state were obtained using tensile tests.
  • Furthermore, tests were performed to evaluate the degradation effect of the temperature profiles at each SA state. In addition, the exposure temperatures of the polymer components inside the equipment during the SA temperature profile were analyzed using thermal lag analysis.
  • In this study, a performance test was conducted to verify the simulation environment of the SA for the ES assessment. The performance test was conducted by measuring the temperature distribution of the equipment.
  • In this study, a thermal degradation test was performed to evaluate the degradation effect of the polymer Viton for the temperature profile of SA environments. An electric furnace was used to provide the temperature profile of the SA.
  • In this study, performance and degradation tests were conducted to evaluate degradation effects of a polymer. Moreover, thermal lag analysis was performed to predict the temperature of the polymer in an SA environment.
  • Tests were conducted to evaluate the degradation effect during each state of the temperature profile of the SA. As part of this test, the specimens were exposed to different SA temperature profiles.
  • The performance test of the equipment for the assessment of ES using the tube furnace was based on an SA temperature profile simulation. The temperature was measured at 5-cm intervals from the center of the furnace.
  • In this study, a performance test was conducted to verify the simulation environment of the SA for the ES assessment. The performance test was conducted by measuring the temperature distribution of the equipment. Furthermore, tests were performed to evaluate the degradation effect of the temperature profiles at each SA state.
  • A degradation test was performed to evaluate the degradation effect during each state of the SA temperature profile within air. The test was performed for four cases, and the mechanical properties of Viton exposed to each state were measured using the tensile test, as illustrated in Table 2 and Fig. 9.
  • Test conditions of the initial and transient states (~10 m) and of the postaccident state (10 m at ~ 24 h) were included in cases 3 and 4. The tests in cases 5 and 6 were associated with exposed relative humidity (RH) values of 0 % and 40 % at 360 K, respectively, and were performed to evaluate the effects of RH on the degradation of Viton. These tests revealed a negligible variation in the Young's modulus and yield stress between the specimens for cases 5, 6, and the reference.
  • (2) [18]. To predict the exposure temperature of the polymer inside the ERDV, 3-D modeling was performed, as illustrated in Fig. 10, and thermal lag analysis was performed by computational analysis.

대상 데이터

  • 4. The dimensions of the metal housing were 25 mm diameter and 110 mm length. The dimensions of the Viton specimen were 5 mm diameter and 80 mm length.
  • The test equipment consisted of an electric furnace with a specimen-shifting system. Figs.

데이터처리

  • For the thermal lag analysis, the convective heat transfer coefficient was calculated during the burning of hydrogen. Moreover, using the calculated coefficient, thermal lag analysis using a 3-D model of the ERDV actuator was conducted through computational analyses. The analysis results revealed that Viton was exposed to temperatures up to 610 K.
  • where h, Re, and k are the convective heat transfer coefficient, Reynold's number, and thermal conductivity, respectively. Using the analyzed convective heat transfer coefficients, computational analysis was performed on a 3-D model of the ERDV actuator to predict the exposure temperature of the equipment.

이론/모형

  • The convective heat transfer coefficient was calculated using the equation proposed by Churchill and Bernstein, who introduced it in 1977; this equation is valid for RePr > 0.2 [18].
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참고문헌 (20)

  1. IAEA, Safety Assessment and Verification of Nuclear Power Plants, Safety Standard Series, 2002. No. NS-G-1.2. 

  2. Y.H. Seo, Won Sang Jeong, Young Tea Moon, Equipment survivability assessment in APR1400, Korea Nucl. Soc. (2012) 731. 

  3. S.I. Lee, H.K. Jung, Development of the NPP instrument requirements for highly survivability under severe accidents, in: Conference on Korea Society for Energy Engineering, 2013, 121-121. 

  4. R. Lin, Z. Wang, Y. Sun, Wireless sensor network solutions for real time monitoring of nuclear power plant, in: Proceedings of the 5th World Congress on Intelligent Control and Automation, June 2004. HangZhou, China. 

  5. IEEE, IEEE standard for qualifying class 1E equipment for nuclear power generating station, IEEE Std (1973), 323-1974. 

  6. IEEE, IEEE standard for qualifying class 1E equipment for nuclear power generating station, IEEE Std (2003), 323-2003. 

  7. IEEE, IEEE standard for seismic qualification of equipment for nuclear power generating stations, IEEE Std (2013), 344-2013. 

  8. IAEA, Assessment of nuclear power plant equipment reliability performance for severe accident condition, TECDOCDD 1135. 

  9. D.H. Kim, Y.S. Park, Severe Accident Mitigation Design in APR+ Nuclear Power Plant, Korea Society for Energy Engineering, 2013. 

  10. USNRC, 10CFR50.34(f), Additional TMI-related Requirements, 2009. 

  11. USNRC, SECY-90-016, Evolutionary Light-Water Reactor Certification Issues and Their Relationship to Current Regulatory Requirements, 1990. 

  12. USNRC, SECY 93-9087, Policy Technical and Licensing Issues Pertaining to Evolutionary and Advanced Light Water Reactor Design, 1993. 

  13. Pacific Northwest National Laboratory, PNNL-24198, Light Water Reactor Sustainability Program-Assessment of Cable Aging Equipment, Status of Acquired Materials, and Experimental Matrix at the Pacific Northwest National Laboratory, 2015. 

  14. EPRI, Plant Support Engineering: Elastomer Handbook for Nuclear Power Plants, 1014800, 2007. 

  15. KIMM, Development of Emerging Core Technique of Equipment Qualification on Design Based Events and Severe Accidents of NPPs, TR-2016-195, 2016. 

  16. R.K. Weese, A.K. Burnham, H.C. Tuner, T.D. Tran, Physical characterization of RX-55-AE-5 a formulation of 97.5% 2,6-diamino-3,5-dinitropyrazine-1-oxide (LLM-105) and 2.5% Viton A, in: North American Thermal Analysis Society 33rd Annual Conference, 2005. 

  17. F.P. Incropera, D.P. Dewitt, T.L. Bergman, A.S. Lavine, Fundamentals of Heat and Mass Transfer, Wiley, 1981. 

  18. S.W. Churchill, W. Bernstein, A correlating equation for forced convection from gases and liquid to a circular cylinder in crossflow, J. Heat Transfer ASME (1977). 

  19. C. Lee, K.Y Kim, B.H. Ryu, K.J. Lim, Evaluation of radiation degradation of crosslinked polyethylene using TGA, J. KIIS, (2003). 

  20. KAERI, Accelerated ageing test of cable materials used in nuclear power plants for the evaluation of lifetime, KAERI/TR-2424, (2003). 

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