• Title/Summary/Keyword: 방사능붕괴

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Quartz Dissolution by Irradiated Bacillus Subtilis (방사선을 조사(照射)한 Bacillus Subtilis에 의한 석영 용해)

  • Lee, Jong-Un
    • Economic and Environmental Geology
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    • v.42 no.4
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    • pp.335-342
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    • 2009
  • The effects of bacterial lysis on the rate of quartz dissolution were investigated under pH 7 condition using Bacillus subtilis cells which were either irradiated or non-irradiated with gamma ray. The amount of dissolved organic carbon (DOC) which resulted from bacterial lysis increased in slurries of quartz and bacteria mixture over experimental period. Lysis of non-irradiated bacteria led to the elevated concentration of dissolved silicon when compared with abiotic control. Concomitant increase in the amounts of DOC and dissolved silicon over time indicated that lixiviation of silicon from quartz was due to bacterial lysis. Higher amounts of DOC and dissolved silicon were present in the irradiated bacterial slurries than those of non-irradiated bacteria. The enhancement of quartz dissolution in the irradiated bacterial slurries was likely attributed to disruption of organic molecules in the bacterial cells by gamma ray and formation of effective ligands for quartz dissolution. The results suggest that the effects of bacterial lysis on mineral weathering rate should be considered for prediction of time for released radionuclides to migrate to surface biosphere in high level radioactive waste disposal site.

Fly ash로부터 합성한 Swelling Mica의 양이온 교환 특성

  • 우영안;최충렬;이동훈;김장억;최정
    • Proceedings of the Korean Environmental Sciences Society Conference
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    • 2003.11b
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    • pp.315-318
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    • 2003
  • 본 연구에서는 NaCl 용응법에 의해 fly ash로부터 합성된 swelling mica의 다양한 이온의 교환특성과 이온교환이 결정구조에 미치는 영향을 규명함으로서 swelling mica에 의한 유해 방사능 물질 및 중금속의 효과적인 제거제로서의 활용 가능성을 조사하고자 하였다. 1가 양이온이 흡착된 FA-swelling mica의 $d_{001}$/ peak의 강도는 흡착된 이온의 직경이 클수록 감소하는 경향을 나타내었으나, $d_{001}$/ value는 흡착된 이온의 직경과 뚜렷한 상관관계가 없었다. 또한 FA-swelling mica의 NH4 이온의 흡착량은 133 $cmol^{+}$/kg, K 이온은 127 $cmol^{+}$/kg, Li 이온은 23 $cmol^{+}$/kg으로서 방사성 물질과 중금속 이온에 비해 낮은 경향을 나타내었다. 2가 양이온이 흡착된 FA-swelling mica의 $d_{001}$/ peak 강도와 $d_{001}$/ value는 이온의 직경에 관계없이 비슷한 값을 나타내었으며 1가 양이온의 흡착에 비해 구조적 안정성이 높았다. Sr 및 Ba 이온의 흡착반응은 느리고 지속적으로 일어났으며 Ca와 Mg 같은 2가 양이온에 비해 선택성이 훨씬 높은 것으로 나타났다. 또한 Sr 및 Ba 이온과 같이 직경이 큰 방사성 원소들은 swelling mica의 층간에 흡착되어 결정구조가 부분적으로 붕괴됨으로서 이온을 비가역적으로 고정하는 특성을 나타내었다. Zn, Cu, Cd 및 Pb 등의 중금속 이온이 흡착된 FA-swelling mica의 $d_{001}$/ value는 12.70~12.80$\AA$으로서 매우 일정하였으며, 이온 흡착에 의한 층간 팽창정도는 이온의 크기뿐만 아니라 수화정도에 따라 상이하였다. FA-swelling mica의 중금속 이온의 흡착은 층간 붕괴에 의해 일어나는 것으로 판단되며, 선택성과 흡착능력은 층간 붕괴속도와 비례하는 경향을 나타내었다. 또한 FA-swelling mica의 중금속 이온의 선택성은 Pb>Cu>Cd$\geq$Zn 순으로 나타났다.

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Thermal Release of LiCl Waste Salt from Pyroprocessing (파이로프로세싱 발생 LiCl염폐기물의 열발생)

  • Kim, Jeong-Guk;Kim, Kwang-Rag;Kim, In-Tae;Ahn, Do-Hee;Lee, Han-Soo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.7 no.2
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    • pp.73-78
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    • 2009
  • The decay heat of Cs and Sr contained in a LiCl waste salt, generated from an electrolytic reduction process in pyroprocessing of spent nuclear fuel, has been calculated. The calculation has been carried out under some assumptions that most of the LiCl waste is purified and recycled to main process, and the residual is fabricated to make a waste form. As a result, the decay heat from daughter nuclides such as Ba and Y seems to be maximum 4.6 times higher than that from their parent nuclides such as Cs and Sr. The thermal release from Cs and Sr in the LiCl waste is the maximum around the first one month, so an cooling system operation for some time at the beginning would be suggested to control a rapid increase in the temperature of the LiCl waste salt.

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Measurement of Radon Daughters in Airborne Dust (공기부유진내(空氣浮游塵內)의 Radon 붕괴생성물(崩壞生成物)의 농도측정(濃度測定))

  • Kim, Pill-Soo;Min, Duck-Kee;Ro, Seung-Gy
    • Journal of Radiation Protection and Research
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    • v.2 no.1
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    • pp.9-16
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    • 1977
  • A simple method has been established for determining RaA, RaB and RaC concentrations in airborne dust. This is to evaluate the concentration from measurement of total alpha activities in three selected-time intervals after an air sample is taken from the membrane filter paper (mean pore size: $0.8{\mu}m$). As a preliminary trial, a time-variation of the concentrations has been determined using the single-filter method at the KAERI site (N. Lat. $37^{\circ}38'$ and E. Long $127^{\circ}15'$), Seoul, Korea. It appears that there is a large variation of the concentrations depending on the sampling time. Generally the highest value was observed in the morning that may coincide with the highest density of atmosphere in a day while the lowest value was obtained around fourteen o'clock.

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액체폐기물 처리계통 고선량 폐필터 장기저장설비

  • Lee, Sang-Tae;An, Won-Seok;Mun, Cheol-Ung;Lee, Eun-Hak;Im, Wan-Seok
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2007.05a
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    • pp.65-66
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    • 2007
  • 원자력 발전소 방사선 관리구역 1차 계통수의 수질 정화 후 발생된 고선량 폐필터를 방사능 붕괴 후 잡고체 폐기물로 처리하기 위한 장기저장시설 내 설치 될 설비 임. 동 설비는 자동화공정을 기본으로 한정된 공간에 다량의 폐필터를 가장 효율적으로 저장 할 수 있는 최적의 설비이며, 폐필터 장입, 인출 시 작업시간단축, 작업자 피폭저감, 오염확산 방지는 물론 폐기물을 감용시켜 폐기물처리, 처분 비용 절감에 기여하고자 한다.

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Slab Thickness Calculations on Hot Cell

  • Ha, Yung-Joon;Kim, Seong-Yun;Kim, Dong-Hoon
    • Nuclear Engineering and Technology
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    • v.10 no.1
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    • pp.26-36
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    • 1978
  • Numerical computations of radioactivities and decay energies in a spent fuel have been carried out for designing of a hot cell. Optimum wall and window thicknesses that can preserve spent fuel rods for experimental purposes are estimated with burnup rate of 33,000 MWD/T(U) which is nearly maximum from a pressurized water reactor such as the Go-Ri Unit 1. Before putting the spent fuels into a hot cell, it is assumed for thickness estimates of shield materials that they are cooled in a storage tay for several lime intervals. Considered are various types of shield materials through which changing the distances from a source to an observation point is also made.

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Special Theme_재난통신 및 방송 - IT Expert Interview 김응배 TTA 재난통신 PG 의장

  • 한국정보통신기술협회
    • TTA Journal
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    • s.131
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    • pp.30-39
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    • 2010
  • 급격한 기후변화에 의한 집중호우 및 소리 없이 쌓이는 폭설과 잦은 매머드급 태풍 그리고 지진과 해일, 화산활동 등의 자연재해가 언제 어떻게 일어날지 모르는 상황에서 국가는 국민의 생명과 재산을 보호해야 할 막중한 과제를 안고 있습니다. 또한 자연재해뿐 아니라 공공기관에 대한 테러와 자원쟁탈을 위한 국지적인 전쟁과 같은 참사가 지구상에서 수시로 발생하고 있으며, 원자로의 방사능 누출과 지하철이나 철도의 충돌사고 및 가스폭발사고와 초고층 대형 빌딩이나 지하터널, 해저터널 같은 대형구조물의 붕괴 등 인공재난이 수시로 발생하고 있습니다. 이와 같이 재난발생은 대형화 및 다양화되고 있으며, 복합화된 형태로 발생하여 단일 기관으로는 대응하는 데 어려움이 있어서 범 국가적인 통합지휘체계에 의한 재난 관리 및 재난 대응이 필요합니다. 이러한 대형 참사를 사전에 예방하고, 재난 발생시 신속히 대응하여 인명과 재산피해를 최소화하는 방안으로 어떠한 재난 통신 방안이 있으며, 관련 기술 표준과 선진국 등의 구축사례를 통하여 우리나라는 제대로 재난 통신 및 방송이 구축되어 있는 지 살펴보고 이를 통하여 유비무환(有備無患) 및 거안사위(居安思危)의 정신으로 언제 닥칠지 모르는 국가재난에 미리미리 대비하는 계기가 되었으면 합니다.

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Minimum Detectable Radioactivity Concentration of Atmospheric Particulate Measurement System for Nuclear Test Monitoring (핵활동 감시를 위한 대기 입자 측정시스템의 최소검출 방사능 농도 결정)

  • Kim, Jong-Soo;Yoon, Suk-Chul;Shin, Jang-Soo;Kwack, Eun-Ho;Choi, Jong-Seo
    • Journal of Radiation Protection and Research
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    • v.22 no.2
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    • pp.111-117
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    • 1997
  • Recently, the conclusion of Comprehensive Test Ban Treaty(CTBT) is globally constructing a network system for nuclear test monitoring. The radionuclide experts of the Conference on Disarmament recommended that the detection of nuclear debris in the atmosphere was an essential factor of nuclear test monitoring and proposed the technical requirements. Based on those requirements, atmospheric radionuclide monitoring system to detect nuclear debris generated from the nuclear explosion test was composed. The system is comprised of high volume air sampler(HVAS), filter paper presser and high purity germanium detector(HPGe). Minimum detectable concentrations(MDCs) of the key nuclides requiring in CTBT monitoring strategies are determined by considering of decay time, counting time and flow rate of the high volume air sampler for the rapid explosion and the optimum measurement condition. The results were selected $10{\pm}$2h, $20{\pm}$2h and $850{\pm}50m^3$/h as parameters, respectively. The relation between the natural air-borne radionuclide concentration of $^{212}Pb$ and MDC were calculated which gave effect in the Compton continuum baseline due to those nuclides in the gamma-ray spectroscopy. These results can be used as an actually tool in the CTBT monitoring strategies.

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Measurement of Radon Daughters' Radioactivities by Using Single Filtering Method (단일집진법(單一集塵法)에 의(依)한 라돈 붕괴생성물(崩壞生成物)의 농도측정(濃度測定))

  • Chang, Si-Young;Ro, Seung-Gy;Hong, Jong-Sook
    • Journal of Radiation Protection and Research
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    • v.6 no.1
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    • pp.25-30
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    • 1981
  • A measurement has been made for the radioactivities (or concentrations) of radon daughters, i.e., RaA, RaB and RaC in airborne dust by means of single filtering method. This is to evaluate the radioactivities in terms of Ci or WL (working level) from gross alpha counts measured in the selected-time intervals after an air sample is taken from a membrane filter paper with a mean pore size of $0.8{\mu}m$. This work involves determinations of standard deviation in radioactivities, radioactive equilibrium factor and ratio. It appears that a concentration of total radon daughters is $0.30{\sim}2.36pCi/l\;or\;0.89{\times}10^{-3}{\sim}6.57{\times}10^{-3}WL$, depending on the sampling time. Generally the highest concentration was observed around nine o'clock in a day while the lowest value was obtained around seventeen o'clock. Standard deviations based on counting statistics of RaA's, RaB's and RaC's concentrations are ${\pm}57.75%,\;{\pm}22.32%\;and\;{\pm}31.29%$, respectively. It is revealed that the radioactive equilibrium factor is 0.322 while the radioactive equilibrium ratio is of pattern $C_1>C_2>C_3$ in general. Here $C_1,\;C_2\;and\;C_3$ stand for concentrations of RaA,RaB and RaC, respectively.

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Study on Decay Characteristics Change of Spent Fuel Materials by DUPIC Fuel Cycle (DUPIC핵연료주기에 의한 사용 후 경수로핵연료의 방사선적 특성변화 분석)

  • Choi, Jong-Won;Ko, Won-Il;Lee, Jae-Sol;Park, Hyun-Soo
    • Journal of Radiation Protection and Research
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    • v.21 no.1
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    • pp.27-39
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    • 1996
  • The change in spent fuel characteristics by DUPIC fuel cycle(burnup of spent PWR fuel again in CANDU) is examined with time elapse since discharge. Major characteristics examined include isotopic concentration, radioactivity, decay heat radiotoxicity and radiation source-term of spent fuel material, which is existing in a type of spent PWR and DUPIC fuel. Behaviors of major nuclides contributing to such changes are also analyzed in terms of radionuclide concentration. From the analysis, the change in radionuclide concentration by DUPIC shows approximately 2% decrease in actinides concentration and 20% increase in fission products concentration. Radioactivity and decay heat of spent DUPIC fuel does not depend upon radionuclides concentrations, which is a unique in sence of general characteristics of spent fuel. In terms of gamma spectrum, spent DUPIC fuel shows lower values than that of spent PWR fuel by 40 to 50% in the range of $0.01{\sim}0.575$ MeV but much higher over 3.5MeV. Neutron Intensities of both spent fuels are mainly determined by $({\alpha},\;n)$ reaction and spontaneous fission reaction of actinides. Of them, especially, the spontaneous fission reaction Is a major neutron source-term, which causes that neutron intensities of spent DUPIC fuel $having{\sim}3.3$ times higher Cm-244 concentration are ${\sim}4$ times higher than that of spent PWR fuel.

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