• Title/Summary/Keyword: Nuclear pump

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Dynamic Modeling of the Free Piston Stirling Pump for the Passive Safety Injection of the Next Generation Nuclear Power Plant (차세대 신형원자로의 피동형 안전 주입장치를 위한 프리피스톤 스터링 펌프의 동특성 모델)

  • Lee, Jae-Young
    • Proceedings of the Korea Society for Energy Engineering kosee Conference
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    • 1999.11a
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    • pp.149-154
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    • 1999
  • This paper describes a passive safety injection system with free piston Stirling pump working withabundant decay heat in the nuclear reactor during the hypothetical accident. The water column in the tube assembly connected from the hot chamber to the cold chamber in the pump oscillates periodically due to thermal volume changes of non-condensable gas in each chamber. The oscillating pressure in the water column is converted into the pumping power with a suction-and-bleed type valve assembly. In this paper a dynamic model describing the frequency of oscillation and pumping pressure is developed. It was found that the pumping pressure is a function of the temperature difference between the chambers. Also, the frequency oscillation depends on the length of the tube with water column.

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Hydrogen Pumping Characteristics of a Scroll Pump (스크롤 펌프의 수소 배기특성)

  • In S. R.
    • Journal of the Korean Vacuum Society
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    • v.15 no.1
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    • pp.14-23
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    • 2006
  • The scroll pump is widely used in ultra clean vacuum systems. However, there is no commonly available information on the hydrogen pumping characteristics of this pump, which creates a difficulty in determining whether the scroll pump can be used or not in a fusion experiment system where hydrogen ,is the main working gas. In this paper the experimental setup, measurement procedures, experimental results, and discussions on the pumping speed, the maximum compression ratio and the back-streaming properties of the scroll pump, especially for the hydrogen gas, are reported.

Evaluation on Safety of Stainless Steels in Chemical Decontamination Process with Immersion Type of Reactor Coolant Pump for Nuclear Reactor (침적식 화학적 제염 공정 시 원자로 냉각재 펌프용 스테인리스강의 안전성 평가)

  • Kim, Seong-Jong;Han, Min-Su;Kim, Ki-Joon;Jang, Seok-Ki
    • Corrosion Science and Technology
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    • v.10 no.5
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    • pp.167-174
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    • 2011
  • Due to commercialization of nuclear power, most countries have taken interest in decontamination process of nuclear power plant and tried to develop a optimum process. Because open literature of the decontamination process are rare, it is hard to obtain skills on decontamination of foreign country and it is necessarily to develop proper chemical decontamination process system in Korea. In this study, applicable possibility in chemical decontamination for reactor coolant pump (RCP) was investigated for the various stainless steels. The stainless steel (STS) 304 showed the best electrochemical properties for corrosion resistance and the lowest weight loss ratio in chemical decontamination process with immersion type than other materials. However, the pitting corrosion was generated in both STS 415 and STS 431 with the increasing numbers of cycle. The intergranular corrosion in STS 431 was sporadically observed. The sizes of their pitting corrosion also increased with increasing cycle numbers.

Development of a sdms (Self-diagnostic monitoring system) with prognostics for a reciprocating pump system

  • Kim, Wooshik;Lim, Chanwoo;Chai, Jangbom
    • Nuclear Engineering and Technology
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    • v.52 no.6
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    • pp.1188-1200
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    • 2020
  • In this paper, we consider a SDMS (Self-Diagnostic Monitoring System) for a reciprocating pump for the purpose of not only diagnosis but also prognosis. We have replaced a multi class estimator that selects only the most probable one with a multi label estimator such that we are able to see the state of each of the components. We have introduced a measure called certainty so that we are able to represent the symptom and its state. We have built a flow loop for a reciprocating pump system and presented some results. With these changes, we are not only able to detect both the dominant symptom as well as others but also to monitor how the degree of severity of each component changes. About the dominant ones, we found that the overall recognition rate of our algorithm is about 99.7% which is slightly better than that of the former SDMS. Also, we are able to see the trend and to make a base to find prognostics to estimate the remaining useful life. With this we hope that we have gone one step closer to the final goal of prognosis of SDMS.