• Title/Summary/Keyword: 모의 핵연료

Search Result 161, Processing Time 0.023 seconds

Nondestructive Measurement of the Coating Thickness in the Simulated TRISO-Coated Fuel Particle Using Micro-Focus X-ray Radiography (마이크로포커스 X-선 투과 영상을 이용한 모의 TRISO 핵연료 입자 코팅 층 두께 비파괴 측정)

  • Kim, Woong-Ki;Lee, Young-Woo;Park, Ji-Yeon;Park, Jung-Byung;Ra, Sung-Woong
    • Journal of the Korean Society for Nondestructive Testing
    • /
    • v.26 no.2
    • /
    • pp.69-76
    • /
    • 2006

  • TRISO(tri-isotropic)-coated fuel particle technology is utilized owing to its higher stability at a high temperature and Its efficient retention capability for fission products In the HTGR(high temperature gas-reeled reactor). The typical spherical TRISO fuel panicle with a diameter of about 1mm is composed of a nuclear fuel kernel and outer coating layers. The outer coating layers consist of a buffer PyC(pyrolytic carbon) layer, Inner PyC(1-PyC) layer, SiC layer, and outer PyC(O-PyC) layer Most of the Inspection Items for the TRTSO-coated fuel particle depend on destructive methods. The coating thickness of the TRISO fuel particle can be nondestructively measured by the X-ray radiography without generating radioactive wastel. In this study, the coaling thickness for the simulated TRISO-coated fuel particle with $ZrO_2$ kernel Instead of $%UO_2$ kernel was measured by using micro-focus X-ray radiography with micro-focus X-ray generator and flat panel detector The radiographic image was also enhanced by image processing technique to acquire clear boundary lines between coating layers. The coaling thickness wat effectively measured by applying the micro-focus X-ray radiography The inspection process for the TRISO-coated fuel particles will be improved by the developed micro-focus X-ray radiography and digital image processing technology.

  • PDF KSCI

Determination of volatile and residual iodine during the dissolution of spent nuclear fuel (사용 후 핵연료 용해 중 휘발 및 잔류 요오드 분석)

  • Kim, Jung Suk;Park, Soon Dal;Jeon, Young Shin;Ha, Young Keong;Song, Kyuseok
    • Analytical Science and Technology
    • /
    • v.22 no.5
    • /
    • pp.395-406
    • /
    • 2009

  • The determination of iodine in the spent nuclear fuel and the volatile behavior during its acid dissolution have been studied by NAA(neutron activation analysis) and electron probe microanalysis (EPMA). Simulated spent fuels (SIMFUELs) were dissolved in $HNO_3$(1+1) at $90^{\circ}C$ for 8 hours. The iodine remained in a dissolver solution after dissolution, and that condensed in dissolution apparatus and trapped in the adsorbent by volatilization during the dissolution were determined, respectively. The condensed iodine was recovered by the redistillation with $HNO_3$(1+1) after transfer of the dissolver solution. The iodines in the dissolver and redistilled solution were separated by solvent extraction followed by ion exchange or precipitation method and determined by RNAA (radiochemical neutron activation analysis). The ion exchange column and filtration kit used for the isolation of iodine, which were prepared with a polyethylene tube, were used as an insert in the pneumatic tube for neutron irradiation. The iodine volatilized during the dissolution of SIMFUELs was collected in a trapping tube containing Ag-silica gel (Ag-impregnated silica gel) adsorbent, and the distribution of iodine trapped in the adsorbents were determined by EPMA. The adsorbing characteristics shown with the SIMFUELs were compared with those shown with a real spent fuel from the nuclear power plant.

  • https://doi.org/10.5806/AST.2009.22.5.395 인용 PDF KSCI