• Title/Summary/Keyword: Rapid depressurization

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Variability of plant risk due to variable operator allowable time for aggressive cooldown initiation

  • Kim, Man Cheol;Han, Sang Hoon
    • Nuclear Engineering and Technology
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    • v.51 no.5
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    • pp.1307-1313
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    • 2019
  • Recent analysis results with realistic assumptions provide the variability of operator allowable time for the initiation of aggressive cooldown under small break loss of coolant accident or steam generator tube rupture with total failure of high pressure safety injection. We investigated how plant risk may vary depending on the variability of operators' failure probability of timely initiation of aggressive cooldown. Using a probabilistic safety assessment model of a nuclear power plant, we showed that plant risks had a linear relation with the failure probability of aggressive cooldown and could be reduced by up to 10% as aggressive cooldown is more reliably performed. For individual accident management, we found that core damage potential could be gradually reduced by up to 40.49% and 63.84% after a small break loss of coolant accident or a steam generator tube rupture, respectively. Based on the importance of timely initiation of aggressive cooldown by main control room operators within the success criteria, implications for improvement of emergency operating procedures are discussed. We recommend conducting further detailed analyses of aggressive cooldown, commensurate with its importance in reducing risks in nuclear power plants.

A Study on the Combustion Characteristics of Composite Solid Propellants at Low Pressure using Vacuum Strand Burner (Vacuum Strand Burner를 이용한 혼합형 고체 추진제의 저압 연소특성 연구)

  • 박영규;유지창;김인철;이태호
    • Journal of the Korean Society of Propulsion Engineers
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    • v.3 no.1
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    • pp.95-103
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    • 1999
  • Low pressure combustion characteristics of the composite solid propellants were studied in terms of the propellant burning rate, ignition processes, and the structure of the extinguished surfaces. Optical Vacuum Strand Burner(OVSB) system was designed and configured for this purpose. Burning rates of the propellants were measured at subatmospheric pressure by developed test method in OVSB. The ignition and combustion phenomena of the studied propellants in the combustion chamber of OVSB were recorded and analyzed with the camera and VCR(30 frames/s). Burning surfaces of the propellants were extinguished by rapid depressurization method and analyzed with Scanning Electron Microscope(SEM).

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Foaming of Poly(butylene succinate) with Supercritical Carbon Dioxide (초임계 이산화탄소를 이용한 Poly(butylene succinate) 발포)

  • Son, Jae-Myoung;Song, Kwon-Bin;Kang, Byong-Wook;Lee, Kwang-Hee
    • Polymer(Korea)
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    • v.36 no.1
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    • pp.34-40
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    • 2012
  • The foaming of poly(butylene succinate) (PBS) using supercritical $CO_2(scCO_2)$ was studied. In order to improve the melt strength, PBS was modified using the reactive compounding technique. Rapid decompression of $scCO_2$-saturated PBS at a temperature above the depressed $T_m$ yielded expanded microcellular foams. The resulting foam structure could be controlled by manipulating process conditions. Experiments varying the foaming temperature while holding other variables constant showed that higher temperatures produced larger cells and reduced cell densities. Higher saturated pressures led to higher nucleation densities and smaller cell sizes. Decreasing the rate of depressurization permitted a longer period of cell growth and therefore larger cells were obtained.

Numerical Analysis on the Transient Load Characteristics of Supersonic Steam Impinging Jet using LES Turbulence Model (LES 난류모델을 이용한 초음속 증기 충돌제트의 과도하중 특성에 대한 수치해석 연구)

  • Oh, Se-Hong;Choi, Dae Kyung;Park, Won Man;Kim, Won Tae;Chang, Yoon-Suk;Choi, Choengryul
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.14 no.2
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    • pp.77-87
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    • 2018
  • In the case of high-energy line breaks in nuclear power plants, supersonic steam jet is formed due to the rapid depressurization. The steam jet can cause impingement load on the adjacent structures, piping systems and components. In order to secure the design integrity of the nuclear power plant, it is necessary to evaluate the load characteristics of the steam jet generated by high-energy pipe rupture. In the design process of nuclear power plant, jet impingement load evaluation was usually performed based on ANSI/ANS 58.2. However, U.S. NRC recently pointed out that ANSI/ANS 58.2 oversimplifies the jet behavior and that some assumptions are non-conservative. In addition, it is recommended that dynamic analysis techniques should be applied to consider transient load characteristics. Therefore, it is necessary to establish an evaluation methodology that can analyze the dynamic load characteristics of steam jet ejected when high energy pipe breaks. This research group has developed and validated the CFD analysis methodology to evaluate the transient behavior of supersonic impinging jet in the previous study. In this study, numerical study on the transient load characteristics of supersonic steam jet impingement was carried out and amplitude and frequency analysis of transient jet load was performed.