• Title/Summary/Keyword: 폐수지

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Method for Determining Transportation Grade for HIC Containing Spent Resin Using Radioactivity Analysis (방사성페기물 핵종분석 결과를 사용한 폐수지의 운반물등급 분류 방법)

  • Kim, Tae-Wook;Choi, Ki-Seop;Kang, Ki-Doo;Ha, Jong-Hyun
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.6 no.1
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    • pp.11-15
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    • 2008
  • In order to transport spent resin in a high integrated container made of high density polyethylene, a method for determining transportation grade by radioactivity analysis was developed. Ratios of radioisotopes in spent resin were derived from radioactivity analysis on spent resin. Associated curie-to-dose factors were determined to estimate radioisotope inventory from surface dose rates of spent resin. From the results, Activity limit of type A package was derived to be 1.19 TBq for HIC, and the corresponding surface dose rate was found to be 124.2 mSv/h.

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역삼투막을 이용한 정유공장 폐수지활용 공정개발에 관한 연구

  • 김병식;황종식;상병인;이규현;유제강
    • Proceedings of the Membrane Society of Korea Conference
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    • 1993.10a
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    • pp.44-45
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    • 1993
  • 우리나라의 산업폐수 발생업체 중 0.4%를 차지하고 있는 석유정제 산업체에서 배출되는 1일 폐수 발생량은 '89년 기준으로 약 $32,400m^3$으로서 전 산업체의 1일 폐수 발생량의 0.5%를 차지하고 있으며, 또한 발생폐수 전량이 종래의 폐수처리시설을 거쳐 하천, 호소 및 연안해역 등의 공공수역으로 방류되고 있다. 대량의 공업용수가 필요한 지역에 위치하고 있는 정유공장의 원활한 공업용수의 공급 및 수자원 확보를 위한 일환으로서, 경제적인 폐수 재활용 공정을 개발하여 대량의 폐수로부터 양질의 공업용수를 확보하고 아울러 최종방류량을 최소화하는 것이 바람직할 것이다.

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Simultaneous Separation and Determination of $^{l4}C\;and\;^3H$ in Spent Resins from PWR Nuclear Power Plants (가압경수로형 원전에서 발생된 폐수지의 $^{14}C$$^3H$ 동시 분리 및 측정)

  • Park, Soon-Dal;Kim, Jung-Suck;Kim, Jong-Goo;Han, Sun-Ho;Jee, Kwang-Yong
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.5 no.3
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    • pp.179-188
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    • 2007
  • In this work $^{14}C\;and\;^3H$ distribution characteristics of spent resins from nuclear power plants(NPPs), pressurized water reactors(PWRs), was investigated. It was found that the recovery percent of $^{14}C$ by the wet oxidation-acid stripping was $81%{\sim}100%$ for the added activity range of $^{14}C,\;0.72\;Bq{\sim}460\;Bq$, and it was not affected by the kinds of stripping acids, 3N-HCl, $3\;N-HNO_3\;and\;3\;N-H_2SO_4$. And the recovery percent of $^3H$ by distillation using the same apparatus was $81%{\sim}101%$ for the added activity range of $^3H,\;0.60\;Bq{\sim}435\;Bq$. Among the tested stripping acids, 3\;N-HCl, $3\;N-HNO_3\;and\;3\;N-H_2SO_4$, only the trapped $^3H$ solution by distillation in $3\;N-H_2SO_4$ was compatible with the 3H scintillator, Ultimagold XR. Neither of the $^{14}C\;and\;^3H$ trapping solutions from the spent ion exchange resin samples by the wet oxidation-3 $N-H_2SO_4$ stripping contained gamma nuclides. However, some gamma nuclides, $^{60}Co,\;^{134}Cs,\;^{137}Cs\;and\;^{54}Mn$, were found in the trapped $^3H$ solutions of the spent resins by the wet oxidation-3 N-HCl stripping. It was the same for the $^3H$ trapping solutions of the spent resins by Sample Oxidizer(PACKARD MODEL 307). Meanwhile only two nuclides, $^{134}Cs,\;and\;^{134}Cs$, were found in the $^{14}C$ trapping solutions of the spent resins by Sample Oxidizer(PACKARD MODEL 307). It was found that most of the $^{14}C$ in the spent resins existed as inorganic carbon form, more than about 70% of the total $^{14}C$ content. Among the analyzed 30 spent ion exchange resin samples, the average concentration of $^{14}C$ and $^3C$ for the high radioactive samples, 8 samples, was $19000\;Bq/g{\pm}41000\;Bq/g,\;670\;Bq/g{\pm}460\;Bq/g$ and that for the low radioactive samples, 22 samples, was $4.2\;Bq/g{\pm}4.3\;Bq/g,\;6.0\;Bq/g{\pm}5.3\;Bq/g$, respectively. And the average $^{14}C/^3H$ ratio for the high radioactive samples, was higher, 28, than that of low radioactive samples, 0.70. Some linear relationship trend was found between the activity concentrations of $^{14}C\;and\;^3H$.

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Development of Chemical and Biological Decontamination Technology for Radioactive Liquid Wastes and Feasibility Study for Application to Liquid Waste Management System in APR1400 (액체방사성폐기물에 대한 화학적, 생물학적 제염기술 개발 및 APR1400 액체폐기물관리계통 적용을 위한 타당성 연구)

  • Son, YoungJu;Lee, Seung Yeop;Jung, JaeYeon;Kim, Chang-Lak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.17 no.1
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    • pp.59-73
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    • 2019
  • A decontamination technology for radioactive liquid wastes was newly developed and hypothetically applied to the liquid waste management system (LWMS) of the nuclear power plant (NPP) to evaluate its decontamination efficacy for the purpose of the fundamental reduction of spent resins. The basic principle of the developed technology is to convert major radionuclide ions in the liquid wastes into inorganic crystal minerals via chemical or biological techniques. In a laboratory batch experiment, the biological method selectively removed more than 80% of cesium within 24 hours, and the chemical method removed more than 95% of cesium. Other major nuclides (Co, Ni, Fe, Cr, Mn, Eu), which are commonly present in nuclear radioactive liquid wastes, were effectively scavenged by more than 99%. We have designed a module including the new technology that could be hypothetically installed between the reverse osmosis (R/O) package and the organic ion-exchange resin in the LWMS of the APR1400 reactor. From a technical evaluation for the virtual installation, we found that more than 90% of major radionuclides in the radioactive liquid wastes were selectively removed, resulting in a large volume reduction of spent resins. This means that if the new technology is commercialized in the future, it could possibly provide drastic cost reduction and significant extension of the life of resins in the management of spent resins, consequently leading to delay the saturation time of the Wolsong repository.

Pollutant Source Database and Water Quality Managemen Ecosystem Model for Juam Reservoir Watershed Using GIS (GIS를 응용한 주암 상수원수계의 오염원 DB 구축과 수질관리 생태계모형)

  • 양홍모;권유리
    • Korean Journal of Environment and Ecology
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    • v.13 no.3
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    • pp.209-219
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    • 1999
  • 주암호는 전라남도와 광주광역시에 약 1,180,000톤/일의 생활용수와 공업용수를 공급하는 상수원이다. 상수원수계의 생활하수, 축산폐수, 숙박업소, 식당 등 점오염원과 주거지, 농경지, 산림지역에서 우수와 함께 유출되는 비점오염원으로부터 발생하는 오염부하량으로 이들 상수원의 수질은 점점 악화되어 3급수로 전락할 우려가 높아지고 있다. 이들 상수원의 수질관리에 있어 중요한 인자의 파악과 인자들간 상호작용의 이해를 용이하게 해주는 수계수질관리 부분생태계모형을 제시하였으며 지리정보체계를 응용하여 수계의 점오염원과 비점오염원을 데이터베이스화하는 방법, 오염부하량 산출방법, 점원 및 비점오염원의 공간분석, 상수원 보호구역으로부터 완충구역분석, 위성자료 분석을통한 상수원 수계 토지이용분석과 비점오염원 부하량산출 응용 방법등을 연구하였다 분석결과 주암호수계의 BOD 부하량은 주거지. 생활하수, 축산폐수, 경작지, 식당이 차지하는 비율이 높으며 총질소 부하량은 경작지, 산림, 생활하수, 추간폐수가 높으며 그리고 총인 부하량은 생활하수, 축산폐수, 경작지가 높은 것으로 나타났다. 점오염원인 생활하수, 축산폐수, 식당 뿐만 아니라 비점오염원인 경작지도 수질오염에 상당한 영향을 미치고 있다.

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미생물에 의한 산업폐수처리

  • 시천방개
    • Proceedings of the Korean Society for Applied Microbiology Conference
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    • 1979.10a
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    • pp.240.1-240
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    • 1979
  • 하천, 호소등의 자정작용(Stream self purification), 즉 미생물에 의한 수중의 유기물의 안정화는, 유기물의 산화분해와 미생물세포의 합성이라는 두가지 대사과정의 조합에 의해 달성된다. 미생물에 의한 폐수처리는, 상술한 자연계의 자정작용을 인공적으로 관리, 운영하는 것이다. 즉, 미생물은 폐수중의 유기영양물을 산화분해하므로써 세포의 합성과 유지에 필요한 energy를 획득하며, 한편 폐수중의 유기물은 산화되어 안정화된다. 이산화반응을 생물학적산화라고 하며, 호기적산화와 혐기적산화의 두가지 형식으로 구별된다. 여기서는 폐수처리에 관여하는 미생물의 분류, 또 폐수처리의 형식으로 호기적산화(산화지, 활성 오이법, 산포처상법 및 회전원판법)와 혐기적산화(Methane발효법)에 대해서 설명한다. 활성오이법 에서 bulking 현상에 대해서도 언급하며, 미생물에 의한 폐수처리의 원리와함께 동력학식의 활성오이법에의 응용에 대해서도 설명한다.

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The solid waste production status in HANARO (하나로의 고체 폐기물 발생 현황)

  • Kang, Tae-Jin;Hwang, Seung-Ryeol;Choi, Ho-Yeong;Lee, Mun
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.130-134
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    • 2003
  • The quantity of solid waste produced during HANARO operation for the years from 1996 to 2002 has been investigated and the interrelation with the reactor power output has been analysed. The waste amount produced during this period was $69, 598{\ell}$ and the processing expense was 1, 878, 000 won. The waste amount and processing expense per reactor power output are $3.01{\ell}/MWD$ and 811 won/MWD, respectively. A dry equipment for the spent resin was developed and the spent resin volume has been reduced by about 40% by using it.

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