• 제목/요약/키워드: TROI실험

검색결과 17건 처리시간 0.019초

원자로 물질의 증기폭발에서 고화 입자 크기 분석 (Analyses of Size of Solidified Particles in Steam Explosions of Molten Core Material)

  • 박익규;김종환;민병태;홍성완
    • 대한기계학회논문집B
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    • 제34권12호
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    • pp.1051-1060
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    • 2010
  • 고화 입자 크기의 관점에서 TROI 용융물-냉각수 반응 실험의 결과에 대한 물질 효과를 분석하였다. 고화 입자 크기를 분석하면 용융물-냉각수 반응에서 초기 조건, 혼합, 폭발을 기적으로 해석할 수 있다. 증기 폭발이 발생한 경우와 폭발이 발생하지 않는 경우의 고화 입자 크기를 분석한 결과 증기 폭발이 발생한 경우에는 미세 입자가 많고 비교적 큰 입자는 적은 것으로 나타났다. 또한, 혼합 과정에 대한 정보를 보존할 수 있는 증기 폭발이 발생하지 않은 용융물-냉각수 반응을 이용하여 용융물 입자 크기에 대한 물질 효과를 분석하였다. 증기 폭발이 잘 발생하는 용융물은 증기 폭발에 참여할 수 있는 큰 입자를 많이 포함하고 있었고, 증기 폭발이 잘 발생하지 않는 용융물은 증기 폭발보다는 냉각되기 쉬운 작은 입자 혹은 미세 입자를 많이 포함하고 있었다.

원자로에서 중대사고시 냉각수의 수심과 용융물 성분이 증기폭발에 미치는 영향 (The Influence of Water Depth and Melt Composition on a Steam Explosion in Severe Accidents in a Nuclear Reactor)

  • 김종환;박익규;홍성완;민병태;송진호;김희동
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2003년도 추계학술대회
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    • pp.414-419
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    • 2003
  • In the recent TROI experiments, melts of zirconia and two different compositions of corium were used to observe the occurrence of a steam explosion when it came into contact with water at two different depths. The compositions of the corium were 70 : 30 and 80 : 20 in weight percent of $UO_{2}$ and $ZrO_{2}$, and the mass of the corium was about 10kg. The depth of water in the interaction vessel was 67cm and 130cm. A steam explosion did not occur in the interaction between 80 : 20 corium melt and water at 130cm depth, while steam spikes were observed in the interactions between corium melts of two different compositions and water at 67cm depth. A strong steam explosion occurred in the interaction between 5.43kg of zirconia melt and water at 67cm depth. This fact shows that the explosivity of zirconia is much greater than that of corium.

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원자로 노심용융물의 성분비 변화가 증기폭발에 미치는 영향 (An Influence of Corium Composition Variations on a Spontaneous Steam Explosion in Severe Accidents in a Nuclear Reactor)

  • 김종환;박익규;홍성완;민병태;송진호;김희동
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2004년도 춘계학술대회
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    • pp.2041-2046
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    • 2004
  • Recently series of steam explosion experiments have been performed in the TROI facility to identify the influence of corium compositions on the occurrence of a spontaneous steam explosion varying corium melt composition. The compositions of the corium were 0 : 100, 50 : 50, 70 : 30, 80 : 20 and 87 : 13 at weight percent of $UO_2$ to $ZrO_2$, and the mass of the corium was about 10kg. Corium melt at 0 : 100 weight percent (pure zirconia) caused a strong spontaneous steam explosion, and melt at 70 : 30 weight percent(eutectic corium) led to a weak steam spike, while melts at other compositions did not result in spontaneous steam explosions, when they came into contact with 67cm deep water pool at room temperature. It seems that the explosivity of pure zirconia is stronger than that of corium at other compositions and a steam explosion is not likely to occur with corium melts at non-eutectic compositions which are included in mushy zone region.

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원자로 물질의 $ZrO_2$를 이용한 증기폭발 실험에서 용융물 거동 및 데브리의 분포 (An Investigation of Debris Configuration and Melt-Water Interaction in Steam Explosion Experiments using $ZrO_2$)

  • 송진호;김희동;홍성완;박익규;신용승;민병태;장영조
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 춘계학술대회논문집E
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    • pp.57-62
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    • 2001
  • Korea Atomic Energy Research Institute (KAERI) launched an intermediate scale steam explosion experiment named Test for Real cOrium Interaction with water (TROI) using reactor material to investigate whether the corium would lead to energetic steam explosion when interacted with cold water at low pressure. The melt-water interaction is confined in a pressure vessel with the multi-dimensional fuel and water pool geometry. The cold crucible technology, where the mixture of powder in a water-cooled cage is heated by high frequency induction, is employed. In this paper, results of the first series of tests ($TROI-1{\sim}5$) were discussed. The ZrO2 jets with 5kg mass and 5cm diameter were poured into the 67cm deep water pool at $30{\sim}95^{\circ}C$. Either spontaneous steam explosions or quenching was observed. The morphology of debris and pressure wave profiles clearly indicates the each case.

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주석-물 시스템의 증기폭발시 발생하는 압력거동에 대한 실험적 연구 (An Experimental Investigation on the Pressure Behavior Accompanying the Explosion of Tin in Water)

  • 신용승;송진호;김종환;박익규;홍성완;김희동
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 춘계학술대회논문집E
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    • pp.51-56
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    • 2001
  • Vapor explosion is one of the most important problems encountered in severe accident management of nuclear power plants. In spite of many efforts, a lot of questions still remain for the fundamental understanding of vapor explosion phenomena. Therefore, KAERI launched a real material experiment called TROI using 20 kg of UO2 and ZrO2 to investigate the vapor explosion phenomena. In addition, a small-scale experiment with molten-tin/water system was performed to quantify the characteristics of vapor explosion and to understand the phenomenology of vapor explosion. A number of instruments were used to measure the physical change occurring during the vapor explosion. In this experiment, the vapor explosion generated by molten fuel water interaction is visualized using high speed camera and the pressure behavior accompanying the explosion is investigated.

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원자로 물질을 이용한 증기폭발 실험 (Experiments on Steam Explosion Using Reactor Materials)

  • 김종환;박익규;홍성완;민병태;신용승;송진호;김희동
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2002년도 학술대회지
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    • pp.407-410
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    • 2002
  • A series of steam explosion experiments using real core materials of $ZrO_2$ and corium(a mixture of $ZrO_{2}\;and\;UO_{2}$) has been performed to evaluate the risk of steam explosion load in nuclear power plants. Surprisingly, spontaneous steam explosions are observed far both materials, which have been thought to be inexplosive so far. The dynamic pressure and morphology of the debris clearly indicate the evidence of an explosion. The experimental results also indicate that $ZrO_2$ is more explosive than corium.

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ZrO$_2$를 이용한 증기폭발 실험 (Steam Explosion Experiments using ZrO$_2$)

  • 송진호;김희동;홍성완;박익규;신용승;민병태;김종환;장영조
    • 대한기계학회논문집B
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    • 제25권12호
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    • pp.1887-1897
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    • 2001
  • Korea Atomic Energy Research Institute (KAERI) launched an intermediate scale steam explosion experiment named "Test for Real Corium Interaction with water (TROI)" using reactor material to investigate whether the molten reactor material would lead to energetic steam explosion when interacted wish cold water at low pressure. The melt-water interaction experiment is performed in a pressure vessel with the multi-dimensional fuel and water pool geometry. The novel concept of cold crucible technology, where powder of the reactor material in a water-cooled cafe is heated by high frequency induction, is firstly implemented for the generation of molten fuel. In this paper, the lest facility and cold crucible technology are introduced and the results or the first series of tests were discussed. The 5 kg of molten ZrO$_2$jet was poured into the 67cm deep water pool at 30 ∼ 95 $\^{C}$. Either spontaneous steam explosions or quenching was observed. The morphology of debris and pressure wave profiles clearly indicate the differences between the two cases.