• Title/Summary/Keyword: 방사성폐기물 유리화

Search Result 75, Processing Time 0.023 seconds

Characteristics of Vitrification Process for Mixture of Simulated Radioactive Waste Using Induction Cold Crucible Melter (유도가열식 저온용융로를 이용한 혼합모의 방사성폐기물의 유리화 공정 특성)

  • 김천우;양경화;박병철;박승철;황태원;박종길;신상운;하종현;송명재
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.2 no.3
    • /
    • pp.165-174
    • /
    • 2004
  • In order to simultaneously vitrify the ion exchange resin(IER) and combustible dry active waste(DAW) generated from Korean nuclear power plants, a vitrification pilot test was conducted using an induction cold crucible melter(CCM) . The energy necessary for startup of the glass using a Ti-ring was evaluated as about 290 kWh. The power supplied from a high frequency generator to melt the glass properly was ranged from 160 to 190 kW without any interruption. When the mixture of the IER and DAW was fed into the CCM, the concentration of CO was lowered up to 1/40 compared to feeding the IER solely. It may be caused by the DAW which can produce about 1.8 times higher heat compared to the IER. When the swelling phenomenon occurred in the glass melt, the concentration of $NO_2$, oxidizing gas, was higher than NO, reducing gas. Total feed amounts of the IER and DAW were 368 and 751 kg, respectively. And then, about 74 of volume reduction factor was achieved.

  • PDF

악티늄족 및 란탄족 원소 회수를 위한 기능성 고분자-탄소 나노 구조체

  • Jeong, Yong-Ju;Sim, Jun-Bo;Baek, Seung-U;Kim, Si-Hyeong;Gwon, Sang-Un;Kim, Gwang-Rak;Jeong, Heung-Seok;An, Do-Hui
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2009.11a
    • /
    • pp.198-199
    • /
    • 2009
  • 킬레이팅 고분자를 메조기공 탄소 표면 위에 흡착시킴으로써 금속이온과 착물을 형성할 수 있는 기능성 나노구조체를 제조하였다. 악티늄족 원소를 단일입자 내에 영구처분을 위한 예비연구로서 Eu을 대용물(surrogate)로 사용하여 기능성 나노 구조체에 주입한 후 메조기공 입구를 고분자반응을 통해 봉쇄함으로써 Eu의 단일입자 내 고정화를 시도하였다. 시간에 따라 침출현상을 분석한 결과, 고분자로 메조기공을 blocking 하였을 때 Eu의 침출현상이 크게 완화되는 것을 확인하였다. 이는 시멘트화나 유리화 등과 같은 고비용 공정을 거치지 않고도 단일입자 내 유해 금속의 영구처분이 가능하다는 것을 의미한다. 더 나아가, 이러한 접근방법은 지지체로 메조기공 탄소에 국한되지 않고 실리카와 같은 다른 메조기공 금속산화물에 적용될 수 있다는 점에서 큰 강점이 있다.

  • PDF

Characteristics of Vitrification Process and Vitrified Form for Radioactive Waste (방사성폐기물 유리화 공정 및 유리고화체 특성)

  • Kim, Cheon-Woo;Kim, Ji-Yean;ChoI, Jong-Rak;Ji, Pyung-Kook;Park, Jong-Kil;Shin, Sang-Woon;Ha, Jong-Hyun;Song, Myung-Jae
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.2 no.3
    • /
    • pp.175-180
    • /
    • 2004
  • In order to vitrify the combustible dry active waste (DAW) generated from Korean Nuclear Power Plants, a glass formulation development based on waste composition was performed. A borosilicate glass, DG-2, was formulated to vitrify the DAW in an induction cold crucible melter (CCM). The processability, product performance, and volume reduction effect of the candidate glass were evaluated using a computer code and were measured experimentally in the laboratory and CCM. The glass viscosity and electrical conductivity as the process parameters were in the desired ranges. Start-up and maintaining glass melt of the candidate glass were favorable in the CCM. The product of the glass product such as chemical durability, phase stability, and density was satisfactory. The vitrification process using the candidate glass was also evaluated assuming that it was operated as economically as possible.

  • PDF

Performance of High Temperature Filter System for Radioactive Waste Vitrification Plant (방사성폐기물 유리화 플랜트 고온여과시스템의 성능 특성)

  • Seung-Chul, Park;Tae-Won, Hwang;Sang-Woon, Shin;Jong-Hyun, Ha;Hey-Suk, Kim;So-Jin, Park
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.2 no.3
    • /
    • pp.201-209
    • /
    • 2004
  • Important operation parameters and performance of a high temperature ceramic candle filter system were evaluated through a series of demonstration tests at a pilot-scale vitrification plant. At the initial period of each test, due to the growth of dust cake on the surface of ceramic candles, the pressure drop across the filter media increased sharply. After that it became stable to a certain range and varied continuously proportion to the face velocity of off-gas. On the contrary, at the initial period of each test, the permeability of filter element decreased rapidly and then it became stable. Back flushing of the filter system was effective under the back flushing air pressure range of 3∼5 bar. Based on the dust concentrations measured by iso-kinetic dust sampling at the inlet and outlet point of HTF, the dust collection efficiency of HTF evaluated. The result met the designed performance value of 99.9%. During the demonstration tests including a hundred hour long test, no specific failure or problem affecting the performance of HTF system were observed.

  • PDF

Performance Evaluation of Sintered Metal Filter in LILW Vitrification Facility (중.저준위 방사성폐기물 유리화설비에서 금속필터 적용성평가)

  • Park, Seung-Chul;Kim, Byong-Ryol;Hwang, Tae-Won
    • Journal of Energy Engineering
    • /
    • v.15 no.3 s.47
    • /
    • pp.146-153
    • /
    • 2006
  • A performance test of the stainless steel based sintered metal filter was conducted on the low and intermediate level radioactive waste (LILW) vitrification process. The applicability of the metal filter was based on the test results as well. The baseline pressure drop of the metal filter was evaluated similar to the ceramic filter. During the test, when the flow rate of off-gas was $110Nm^{3}/h$, the total baseline pressure drop was shown as $92mmH_{2}O$. The total pressure drop was attributed to the filter media and the residual dust layer and the value of each was $25mmH_{2}O\;and\;67mmH_{2}O$ respectively. The SEM-EDS spectrum and micrograph of the metal filter specimen showed, no corrosion and no physical damage both at the skin membrane and at the support layer. And most of the baseline pressure drop was caused by the deposition of dust on the surface of the membrane. In conclusion, even though the filter exposure time was short at the test, the performance of the stainless steel based metal filter was acceptable for the treatment of LILW vitrification process.

Experiment on the Vitrification of Nonflammable Wastes Using AP-200L Plasma Torch (AP-200L 토치를 이용한 비가연성 방사성폐기물 고온용융처리)

  • 최종락;유병수;김천우;박종길;하종현
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2003.11a
    • /
    • pp.48-53
    • /
    • 2003
  • The high temperature melting test for nonflammable wastes using a plasma torch was conducted. The AP-200L hollow cathode type plasma torch was installed at the pilot plasma melting furnace in NETEC. The surrogates were prepared to simulate concrete, soil and their mixture with steel. The experimental conditions such as feeding rate, the distance between melts surface and torch nozzle, torch rotation speed, gas flow rate and pressure in the furnace were decided. Basic parameters such as temperatures of cooling waters, off-gas and torch power were measured. The vitrified samples were analyzed by SEM/EDS.

  • PDF

공기정화필터 프레임 재사용과 그에 따른 효과 고찰

  • 윤철종;송대원;장동철
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2005.06a
    • /
    • pp.194-195
    • /
    • 2005
  • 방사선관리구역 내에서 발생되는 많은 양(발전소별 연간 약$100{\sim}700$개 정도)의 사용 후 공기정화 필터는 고체 폐기물 드럼의 단면적 보다 넓어 별도로 필터를 압축하거나 분해 작업 없이는 폐기물로 직접 처리가 곤란하다. 처리 시 많은 양의 분진이 발생하여 작업자의 내부피폭 가능성 및 많은 양의 고체 폐기물이 발생할 수 있는 잠재성이 있어 시료분석 결과 오염된 필터 내지는 바로 드럼 처리하여 내부 피폭 가능성을 미연에 방지하고 필터 프레임은 재사용을 유도하여 폐기물 저감화, 작업환경 개선 및 경제적인 이익을 창출할 수 있다. 영광 3발전소와 울진 3발전소의 경우 타 발전소에 비해 방사선관리구역 내 공기정화 처리기의 설치수량이 많아(약 700개/년) 공기정화필터가 매년 다수 발생되고 있으며, 이를 전량 드럼 처리 시 고체폐기물 드럼이 더 발생하게 되어 영구처분비용의 증가를 초래하게 된다. 발전소 전체적으로는 약 3,500개/년의 폐필터가 발생되고 있다. 이렇게 발생되는 공기정화필터의 프레임을 재사용함으로써 그 효과는 1) 알루미늄을 포함한 유리섬유를 드럼처리 시 고체방사성 폐기물드럼 생성량 감소 2) 프레임 재사용으로 인한 예산절감 효과 3) 폐필터 분해작업 시 분진에 의한 작업자 체내${\cdot}$외 피폭방지와 작업장 오염 확산 방지 및 환경 개선 4) 작업시간 단축 및 소요인력 감소 효과를 볼 수 있다.

  • PDF