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      • KCI등재

        Corrosion Fatigue Crack Initiation of Type 316N Weldment Under the Influence of Cyclic Stress Amplitude

        A. Poonguzhali,S. Ningshen,G. Amarendra 대한금속·재료학회 2020 METALS AND MATERIALS International Vol.26 No.10

        Corrosion fatigue behavior of type 316N stainless steel (SS) weldments on the damage characteristics is studied. The S–Ncurve of the fatigue life versus stress amplitude showed a specific two slope Basquin relationship. At low stress amplitude,the deformation microstructure consists mainly of planar slip dislocation structure and at high-stress amplitudes, planarmultiple slip dislocations govern the cyclic behavior. A correlation between microstructural changes and the correspondingsusceptibility of 316N SS weldment in as-welded condition towards environmental cracking in boiling acidified aqueoussolution has been presented. The objective of the present study is to investigate the environmental effects on the corrosionfatigue crack initiation of type 316N weldmetal under the influence of cyclic stress amplitude. The difference in deformationmicro mechanisms with stress amplitude in a corrosive environment is believed to be the major reason for the occurrence ofa specific bilinear Basquin relationship in the S–N curve.

      • KCI등재

        Design and development of enhanced criticality alarm system for nuclear applications

        Padi Srinivas Reddy,R. Amudhu Ramesh Kumar,M. Geo Mathews,G. Amarendra 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.5

        Criticality alarm systems (CASs) are mandatory in nuclear plants for prompt alarm in the event of anycriticality incident. False criticality alarms are not desirable as they create a panic environment for radiationworkers. The present article describes the design enhancement of the CAS at each stage andprovides maximum availability, preventing false criticality alarms. The failure mode and effect analysisare carried out on each element of a CAS. Based on the analysis, additional hardware circuits aredeveloped for early fault detection. Two different methods are developed, one method for channel loopfunctionality test and another method for dose alarm test using electronic transient pulse. The designenhancement made for the external systems that are integrated with a CAS includes the power supply,criticality evacuation hooter circuit, radiation data acquisition system along with selection of differentsoft alarm set points, and centralized electronic test facility. The CAS incorporating all improvements areassembled, installed, tested, and validated along with rigorous surveillance procedures in a nuclear plantfor a period of 18,000 h.

      • SCIESCOPUSKCI등재

        Design and development of enhanced criticality alarm system for nuclear applications

        Srinivas Reddy, Padi,Kumar, R. Amudhu Ramesh,Mathews, M. Geo,Amarendra, G. Korean Nuclear Society 2018 Nuclear Engineering and Technology Vol.50 No.5

        Criticality alarm systems (CASs) are mandatory in nuclear plants for prompt alarm in the event of any criticality incident. False criticality alarms are not desirable as they create a panic environment for radiation workers. The present article describes the design enhancement of the CAS at each stage and provides maximum availability, preventing false criticality alarms. The failure mode and effect analysis are carried out on each element of a CAS. Based on the analysis, additional hardware circuits are developed for early fault detection. Two different methods are developed, one method for channel loop functionality test and another method for dose alarm test using electronic transient pulse. The design enhancement made for the external systems that are integrated with a CAS includes the power supply, criticality evacuation hooter circuit, radiation data acquisition system along with selection of different soft alarm set points, and centralized electronic test facility. The CAS incorporating all improvements are assembled, installed, tested, and validated along with rigorous surveillance procedures in a nuclear plant for a period of 18,000 h.

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