• 제목/요약/키워드: Cesium and strontium radionuclides

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Organic Association of the Fallout radionuclides in the Soil

  • Lee, Myung-Ho;Park, Hoi-Guk;Lee, Chang-Woo;Park, Yong-Ho;Kim, Sang-Bog;Hong, Kwang-Hee;Park, Gun-Sik;Lee, Jeong-Ho
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1997년도 춘계학술발표회논문집(2)
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    • pp.439-444
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    • 1997
  • In order to investigate organic association of fallout cesium, strontium and plutonium in the soil, soil samples influenced by fallout from nuclear weapon testings were treated with alkali (0.1 M-sodium hydroxide solution) to extract organic acids. After extraction, the resultant three fractions (sedimentary residue, humic and fulvic acid fractions) were subjected to the r-ray spectrometric analysis for $^{137}$ Cs, and radiochemical analysis for gosr and $^{239,240}$Pu. Alkali extraction experiments showed that a lot of $^{ 239,240}$Pu was extracted to organic acids from the soil samples, whereas most of $^{137}$ Cs and $^{90}$ Sr remained in residual fraction. Less than 10% of the total $^{137}$ Cs and $^{90}$ Sr was found in the organic fraction. The concentrations of $^{137}$ Cs and $^{90}$ Sr associated with humic fractions were higher than those with the corresponding fulvic fractions. It was found that more than 40% of the total $^{239,240}$Pu was associated with the organic fraction of soils. In contrast with $^{137}$ Cs and $^{90}$ Sr, $^{239,240}$Pu associated with vulvic fractions was much higher than in humic fractions.

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Effect of the Slag Former on the Metal Melting and Radionuclides Distribution in an Electric Arc Furnace

  • Song Song-Pyung;Min Byung-Youn;Choi Wang-Kyu;Chung Chong-Hun;Oh Won-zin
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2005년도 추계 학술대회 논문집
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    • pp.32-37
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    • 2005
  • The characteristics of the metal melting and radionuclide distribution of the radioactive has been investigated in a lab-scale arc furnace. The slag former based on the constituents of silica, calcium oxide, aluminum oxide, borate and calcium fluoride additions was used for melting of the stainless and carbon steel. In the melting of the stainless steel, the amount of slag formation increased with an increase of the concentration of the slag former. But the effects of the slag basicity on the amount of stag formation showed a local maximum value of the slag formation with an increase of the basicity index in the melting of the stainless steel as well as in the melting of the carbon steel. With an increase of the amount of slag former addition, the trends of the cobalt distribution into the ingot and the stag depended on the kind of slag former used in the melting of the stainless steel while the effect of the slag basicity on the distribution of the cobalt was not clarified in the melting of carbon steel. Tn the melting of the carbon steel, the strontium was captured at up to $50\%$ into the slag phase. Cesium was completely eliminated from the melt of the stainless steel as well as the carbon steel and distributed to the dust phase.

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국내 PWR 사용후핵연료에서 세슘, 스트론튬과 요오드의 갭 및 입계 재고량 측정 (Measurement of the Gap and Grain Boundary Inventories of Cs, Sr in and I in Domestic Used PWR Fuels)

  • 김승수;강광철;최종원;서항석;권수한;조원진
    • 방사성폐기물학회지
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    • 제5권1호
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    • pp.79-84
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    • 2007
  • 처분장에서 지하수로 쉽게 유출될 수 있는 방사성 핵종들의 양을 예측하기 위하여 국내 PWR 사용후핵연료 팰렛들의 갭(gap) 및 입계에 있는 용해성 원소들의 재고량을 측정하였다. 연소도가 $45{\sim}66$ GWD/MTU를 갖는 연료봉에서 얻은 펠렛들에서 세슘의 갭 재고량이 $0.85{\sim}1.7%$M로 나타났으며, 이는 핵분열 생성기체 유출률의 $1/6{\sim}1/3$에 해당하였다. 그러나 핵분열 생성기체 유출 률이 1%이하인 연료봉에서 취한 40 GWD/MTU이하의 연소도를 갖는 펠렛들의 경우, 세슘의 갭 재고량들을 핵분열 생성기체 유출률과 연관시키기는 곤란하였다. 갭 및 입계내 스트론튬의 재고량은 동일 연료봉내 펠렛에서는 크게 다르지 않았으며, 요오드의 갭 재고량은 핵분열 생성기체 유출률보다 작거나 유사한 값을 갖는 것으로 평가되었다.

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화학 및 천연 응집제를 이용한 수중 Cs, Sr 제거 (Removal of Cs and Sr in Water Using Chemical and Natural Coagulants)

  • 김성범;김영석;강성원;오대민;이원태
    • 대한환경공학회지
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    • 제38권12호
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    • pp.662-666
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    • 2016
  • 응집/침전 기술로 지표수 내 방사성 핵종(Cs, Sr)의 제거 가능성을 평가하였다. 화학응집제는 Alum (aluminum sulfate), PAC (poly aluminum chloride), PACS (poly aluminum hydroxide chloride silicate)를 사용하였고, 광물계 천연응집제는 일라이트(illite)와 제올라이트(zeolite)를 사용하였다. 화학 및 천연 응집제는 각각 주입하거나 혼합 주입한 후 jar-test를 통하여 안정화된 방사성 핵종($^{133}Cs$, $^{88}Sr$)의 제거율을 평가하였다. 응집/침전 공정에서 화학응집제(Alum, PAC, PACS) 주입만으로는 Cs과 Sr이 10% 미만으로 제거되었고, 고분자응집제(polyDADMAC)를 혼합하여 주입할 경우 Cs은 최대 23.1%, Sr은 최대 17.8%까지 제거가 가능하였다. 광물계 천연응집제(zeolite, illite)는 화학응집제(Alum, PAC, PACS)에 비하여 Cs과 Sr의 제거율이 높았는데, 화학응집제(PACS)와 고분자응집제에 zeolite를 추가로 주입(10~200 mg/L)한 경우 Cs 제거율은 최대 36.9%, Sr 제거율은 최대 17.1%로 증가하였다.