• 제목/요약/키워드: $^{239-240}Pu$

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$^{244}Pu$ + $^{136}Xe$ 반응에서 생성된 Pu, Np 및 U에 관한 연군 (Studies on Plutonium, Neptunium, and Uranium Produced in the /$^{244}Pu$ + $^{136}Xe$ Reaction)

  • Won Mok Jae
    • Nuclear Engineering and Technology
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    • 제13권3호
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    • pp.139-144
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    • 1981
  • Pu-244와 Xe-136반응에서 생성된 Pu, Np 및 U을 분리하여 그 핵반응 단면적을 측정하였다. 핵반응단면적은 각각 $\sigma$($^{245}$ Pu)=66 mb, $\sigma$($^{243}$ Pu)=57 mb, $\sigma$($^{246}$ Pu)=6.0 mb, $\sigma$($^{239}$ Np)=15 mb, $\sigma$($^{240}$ U)=12 mb, $\sigma$($^{241}$ U)=6.4 mb이었다.

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ABSORBED INTERNAL DOSE CONVERSION COEFFICIENTS FOR DOMESTIC REFERENCE ANIMALS AND PLANT

  • Keum, Dong-Kwon;Jun, In;Lim, Kwang-Muk;Choi, Yong-Ho
    • Nuclear Engineering and Technology
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    • 제42권1호
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    • pp.89-96
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    • 2010
  • This paper describes the methodology of calculating the internal dose conversion coefficient in order to assess the radiological impact on non-human species. This paper also presents the internal dose conversion coefficients of 25 radionuclides ($^3H,\;^7Be,\;^{14}C,\;^{40}K,\;^{51}Cr,\;^{54}Mn,\;^{59}Fe,\;^{58}Co,\;^{60}Co,\;^{65}Zn,\;^{90}Sr,\;^{95}Nb,\;^{99}Tc,\;^{106}Ru,\;^{129}I,\;^{131}I,\;^{136}Cs,\;^{137}Cs,\;^{140}Ba,\;^{140}La,\;^{144}Ce,\;^{238}U,\;^{239}Pu,\;^{240}Pu$) for domestic seven reference animals (roe deer, rat, frog, snake, Chinese minnow, bee, and earthworm) and one reference plant (pine tree). The uniform isotropic model was applied in order to calculate the internal dose conversion coefficients. The calculated internal dose conversion coefficient (${\mu}Gyd^{-1}$ per $Bqkg^{-1}$) ranged from $10^{-6}$ to $10^{-2}$ according to the type of radionuclides and organisms studied. It turns out that the internal does conversion coefficient was higher for alpha radionuclides, such as $^{238}U,\;^{239}Pu$, and $^{240}Pu$, and for large organisms, such as roe deer and pine tree. The internal dose conversion coefficients of $^{239}U,\;^{240}Pu,\;^{238}U,\;^{14}C,\;^3H$, and $^{99}Tc$ were independent of the organism.

Transport Parameters of 99Tc, 137Cs, 90Sr, and 239+240Pu for Soils in Korea

  • Keum, D.K.;Kim, B.H.;Jun, I.;Lim, K.M.;Choi, Y.H.
    • Journal of Nuclear Fuel Cycle and Waste Technology
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    • 제1권1호
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    • pp.49-55
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    • 2013
  • To characterize quantitatively the transport of $^{99}Tc$ and the global fallout ($^{137}Cs$, $^{90}Sr$, and $^{239+240}Pu$) for soils in Korea, the transport parameters of a convective-dispersion model, apparent migration velocity, and apparent dispersion coefficient were estimated from the vertical depth profiles of the radionuclides in soils. The vertical profiles of $^{99}Tc$ were measured from a pot experiment for paddy soil that had been sampled from a rice-field around the Gyeongju radioactive waste repository in Korea, and the vertical depth distributions of the global fallout $^{137}Cs$, $^{90}Sr$, and $^{239+240}Pu$ were measured from the soil samples that were taken from local areas in Korea. The front edge of the $^{99}Tc$ profiles reached a depth of about 12 cm in 138 days, indicating a faster movement than the fallout radionuclides. A weak adsorption of $^{99}Tc$ on the soil particles by the formation of Tc(VII) and a high water infiltration velocity seemed to have controlled the migration of $^{99}Tc$. The apparent migration velocity and dispersion coefficient of $^{99}Tc$ for the disturbed paddy soil were 2.88 cm/y and 6.3 $cm^2/y$, respectively. The majority of the global fallout $^{137}Cs$, $^{90}Sr$, and $^{239+240}Pu$ were found in the top 20 cm of the soils even after a transport of about 30 years. The transport parameters for the global fallout radionuclides were 0.01-0.1cm/y ($^{137}Cs$), 0.09-0.13cm/y ($^{90}Sr$), and 0.09-0.18cm/y ($^{239+240}Pu$) for the apparent migration velocity: 0.21-1.09 $cm^2/y$ ($^{137}Cs$), 0.12-0.7$cm^2/y$ ($^{90}Sr$), and 0.09-0.36$cm^2/y$ ($^{239+240}Pu$) for the apparent dispersion coefficient.

Sequential determination of $^{239,240}Pu,\;^{238}Pu,\;^{90}Sr$ and $^{241}Am$ Isotopes in Environmental Samples

  • Lee, Myung-Ho;Jo, Mi-Hyun;Park, Jong-Ho;Ahn, Hong-Joo;Lee, Chang-Heon;Song, Kyu-Seok
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2009년도 학술논문요약집
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    • pp.407-408
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    • 2009
  • In this work, a quantitative method of the sequential separation of $^{90}Pu,\;^{90}Sr$ and $^{241}Am$ nuclides was developed in environmental soil samples using by an anion exchange resin connected with a Sr Spec resin. The sequential methods of Pu, $^{90}Sr$ and $^{241}Am$ nuclides can reduce analysis cost and time. With the sequential methodupdated in this study, the activity concentrations of $^{239,240}Pu,\;^{90}Sr$ and $^{241}Am$ in the IAEA reference materials were close to the reference values reported by the IAEA.

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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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DETERMINATION OF THE TRANSURANIC ELEMENTS INVENTORY IN HIGH BURNUP PWR SPENT FUEL SAMPLES BY ALPHA SPECTROMETRY

  • Joe, Kih-Soo;Song, Byung-Chul;Kim, Young-Bok;Han, Sun-Ho;Jeon, Young-Shin;Jung, Euo-Chang;Jee, Kwang-Yong
    • Nuclear Engineering and Technology
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    • 제39권5호
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    • pp.673-682
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    • 2007
  • The contents of transuranic elements in high-burnup spent fuel samples were determined. The activity amounts of $^{238}Pu,\;^{239}Pu,\;^{240}Pu,\;^{241}Am,\;^{244}Cm\;and\;^{242}Cm$ were measured by alpha spectrometry using $^{242}Pu\;and\;^{243}Am$ as tracers, respectively. A spike addition method for $^{237}Np$ was established by an alpha and gamma spectrometry using $^{239}Np$ as a spike after the optimum conditions for the measurements of $^{237}Np\;and\;^{239}Np$, respectively, were obtained. A separation system using anion exchange chromatography and diethylhexylphosphoric acid extraction chromatography was applied for the separation of these elements. This method was applied to high-burnup spent nuclear fuel samples $(40{\sim}60GWD/MTU)$. The contents of the transuranic elements were compared with those by ORIGEN-2 code. Measurements and the calculations of the contents of the plutonium isotopes $^{238}Pu,\;^{239}Pu\;and\;^{240}Pu$ agreed to within 10% on average. The contents of $^{237}Np$ agreed to within approximately 5% except for one instance of a calculation, while those of $^{241}Am,\;^{244}Cm\;and\;^{242}Cm$ showed higher values by approximately 19%, 35% and 14% on average, respectively, compared to the calculations according to the burnup.

액체섬광계수기를 이용한 환경시료중 $^{241}Pu$분석 (Determination of $^{241}Pu$ in Environmental Samples Using Liquid Scintillation Counting System)

  • 이명호;홍광희;최용호;김상복;최근식;이창우
    • Journal of Radiation Protection and Research
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    • 제21권2호
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    • pp.91-98
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    • 1996
  • 알파방출핵종 존재하에 베타방출핵종인 $^{241}Pu$ 최적 분석조건을 검토하였다. 펄스파고 분석기법을 이용하여 PSA 준위를 설정하였다. $^{241}Pu$ 표준선원을 이용하여 figure of merit가 최대가 되도록 $^{241}Pu$ counting channel를 조정하였고 계측효율이 최대가 되도록 형광체 부피를 설정하였다. 최적화된 $^{241}Pu$ 분석법을 토양과 이끼등의 환경시료에 적용하여 $^{241}Pu$ 방사능농도를 측정하였고. $^{241}Pu/^{239,\;240}Pu$ 방사능 비율로부터 우리나라의 일부 토양 및 이끼에 침적된 Pu의 근원을 규명하였다.

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$^{90}Sr,\;^{241}Am,\;^{239,240}Pu$$^{238}Pu$ 동위원소들을 분리하기위한 축차분리법에 대한 고찰 (Investigation of sequential separation method for $^{90}Sr,\;^{241}Am,\;^{239,240}Pu$ and $^{238}Pu$ isotopes)

  • 이명호;송병철;박영재;지광용;김원호
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2005년도 춘계 학술대회
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    • pp.248-254
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    • 2005
  • 본 연구에서는 음이온 교환수지와 Sr-Spec 수지를 사용하여 $^{90}Sr,\;^{241}Am$ 및 Pu 동위원소들에 대하여 축차적으로 분리하는 정량법을 제시하였다. Pu 동위원소는 음이온 교환수지를 이용하여 분리하였다. 아메리슘 및 스트론튬은 옥살산 공침법을 사용하여 토양 메트릭스 성분으로부터 분리하였다. 아메리슘은 철공침법을 사용하여 스트론튬으로부터 분리한후 음이온 교환수지를 사용하여 란탄나이드 성분으로부터 순수분리하였다. 스트론튬은 Sr-Spec 수지를 사용하여 순수분리하였다. Pu 및 Am 동위원소는 알파스펙트로메타로 정량하였고 Sr-90은 액체섬광계수기를 사용하여 베타선을 측정하였다. 본 연구에서 고찰된 $^{90}Sr,\;^{241}Am$ 및 Pu 동위원소 분석법을 IAEA 기준시료에 적용하여 분석법의 타당성을 검증하였다.

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방사능 분석기술을 이용한 90Sr, 239,240Pu, 238Pu, 241Am 축차분리 (Sequential separation of 90Sr, 241Am, 239,240Pu and 238Pu by radioanalytical techniques)

  • 이명호;박경균;김종윤;박영재;김원호
    • 분석과학
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    • 제18권6호
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    • pp.469-474
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    • 2005
  • 본 연구에서는 음이온 교환수지와 Sr-Spec 수지를 사용하여 토양중 $^{90}Sr$, $^{241}Am$ 및 Pu 동위원소들에 대하여 축차적으로 분리하는 정량법을 제시하였다. 플루토늄은 음이온 교환수지를 이용하여 분리하였고, 아메리슘 및 스트론튬은 옥살산 공침법 및 Sr-Spec 수지를 사용하여 순수 분리하였다. Pu 및 Am 동위원소는 알파 스펙트로메트리법으로 정량하였고, Sr-90은 액체섬광계수기를 사용하여 정량하였다. 본 연구에서 고찰된 $^{90}Sr$, $^{241}Am$ 및 Pu 동위원소 분석법을 IAEA 기준시료에 적용하여 분석법의 타당성을 검증하였다.