• 제목/요약/키워드: Post Irradiation Examination

검색결과 40건 처리시간 0.023초

조사후시험시설에서의 방사성 오염배기체의 포집장치 및 여과효율 (Filtration System and its Efficiency of Exhaust System at Post Irradiation Examination Facility)

  • 황용화;이형권;전용범;민덕기;엄성호;홍권표
    • 한국방사성폐기물학회:학술대회논문집
    • /
    • 한국방사성폐기물학회 2003년도 가을 학술논문집
    • /
    • pp.96-100
    • /
    • 2003
  • 조사후시험시설에는 시설내의 부압기준을 다르게 설정하여 시설의 운전조건을 최적화로 유지하고 방사성물질을 처리하기 위한 오염배기를 포집하는 여과장치가 설치되어 있다. 필터 포집장치에 대해 관련된 효율시험과 검사를 주기적으로 수행하여 운전효율과 안전을 향상시키고 있다.

  • PDF

FAST irradiations and initial post irradiation examinations - Part I

  • G. Beausoleil;L. Capriotti;B. Curnutt;R. Fielding;S. Hayes;D. Wachs
    • Nuclear Engineering and Technology
    • /
    • 제54권11호
    • /
    • pp.4084-4094
    • /
    • 2022
  • The Advanced Fuels Campaign Fission Accelerated Steady-state Test (FAST) at Idaho National Laboratory (INL) completed its first irradiation cycle within the Advanced Test Reactor (ATR). The test focused on the irradiation of alloy fuel forms for use in sodium fast reactors. The first cycle of FAST testing was completed and four rodlets were removed for the initial post irradiation examination (PIE). The rodlet design and irradiation conditions were evaluated using Monte Carlo N-Particle (MCNP) for as-run power history and COMSOL for temperature analysis. These rodlets include a set of low burnups (~2.5 % fissions per initial metal atoms [%FIMA]), control rodlets, and a helium-bonded annular rodlet (4.7 %FIMA). Nondestructive PIE has been completed and includes visual inspection, neutron radiography and gamma scanning of the FAST capsules and rodlets. Radiography confirmed the integrity of the experiments, revealed that the annulus in the annular fuel was filled at a modest burnup (4.7 %FIMA), and indicated potential slumping of the cooler rodlets at lower burnup. Precision gamma scanning indicated mostly usual fission product behavior, except for cesium in the He-bonded annular fuel. Future destructive PIE will be necessary to fully interpret the effects of accelerated irradiation on U-Zr metallic fuel behavior.

IRRADIATION DEVICE FOR IRRADIATION TESTING OF COATED PARTICLE FUEL AT HANARO

  • Kim, Bong Goo;Park, Sung Jae;Hong, Sung Taek;Lee, Byung Chul;Jeong, Kyung-Chai;Kim, Yeon-Ku;Kim, Woong Ki;Lee, Young Woo;Cho, Moon Sung;Kim, Yong Wan
    • Nuclear Engineering and Technology
    • /
    • 제45권7호
    • /
    • pp.941-950
    • /
    • 2013
  • The Korean Nuclear-Hydrogen Technology Development (NHTD) Plan will be performing irradiation testing of coated particle fuel at HANARO to support the development of VHTR in Korea. This testing will be carried out to demonstrate and qualify TRISO-coated particle fuel for use in VHTR. The testing will be irradiated in an inert gas atmosphere without on-line temperature monitoring and control combined with on-line fission product monitoring of the sweep gas. The irradiation device contains two test rods, one has nine fuel compacts and the other five compacts and eight graphite specimens. Each compact contains about 260 TRISO-coated particles. The irradiation device is being loaded and irradiated into the OR5 hole of the in HANARO core from August 2013. The device will be operated for about 150 effective full-power days at a peak temperature of about $1030^{\circ}C$ in BOC (Beginning of Cycle) during irradiation testing. After a peak burn-up of about 4 atomic percentage and a peak fast neutron fluence of about $1.7{\times}10^{21}\;n/cm^2$, PIE (Post-Irradiation Examination) of the irradiated coated particle fuel will be performed at IMEF (Irradiated Material Examination Facility). This paper reviews the design of test rod and irradiation device for coated particle fuel, and discusses the technical results for irradiation testing at HANARO.

POST-IRRADIATION ANALYSES OF U-MO DISPERSION FUEL RODS OF KOMO TESTS AT HANARO

  • Ryu, H.J.;Park, J.M.;Jeong, Y.J.;Lee, K.H.;Lee, Y.S.;Kim, C.K.;Kim, Y.S.
    • Nuclear Engineering and Technology
    • /
    • 제45권7호
    • /
    • pp.847-858
    • /
    • 2013
  • Since 2001, a series of five irradiation test campaigns for atomized U-Mo dispersion fuel rods, KOMO-1, -2, -3, -4, and -5, has been conducted at HANARO (Korea) in order to develop high performance low enriched uranium dispersion fuel for research reactors. The KOMO irradiation tests provided valuable information on the irradiation behavior of U-Mo fuel that results from the distinct fuel design and irradiation conditions of the rod fuel for HANARO. Full size U-Mo dispersion fuel rods of 4-5 $g-U/cm^3$ were irradiated at a maximum linear power of approximately 105 kW/m up to 85% of the initial U-235 depletion burnup without breakaway swelling or fuel cladding failure. Electron probe microanalyses of the irradiated samples showed localized distribution of the silicon that was added in the matrix during fuel fabrication and confirmed its beneficial effect on interaction layer growth during irradiation. The modifications of U-Mo fuel particles by the addition of a ternary alloying element (Ti or Zr), additional protective coatings (silicide or nitride), and the use of larger fuel particles resulted in significantly reduced interaction layers between fuel particles and Al.

X-Ray Diffraction line profile analysis of defects and precipitates in high displacement damage neutron-irradiated austenitic stainless steels

  • Shreevalli M.;Ran Vijay Kumar;Divakar R.;Ashish K.;Padmaprabu C.;Karthik V.;Archna Sagdeo
    • Nuclear Engineering and Technology
    • /
    • 제56권1호
    • /
    • pp.114-122
    • /
    • 2024
  • Irradiation-induced defects and the precipitates in the wrapper material of the Indian Fast Breeder Test Reactor (FBTR), SS 316 are analyzed using the synchrotron source-based Angle Dispersive X-Ray Diffraction (ADXRD) technique with X-rays of energy 17.185 keV (wavelength ~0.72146 Å). The differences and similarities in the high displacement damage samples as a function of dpa (displacement per atom) and dpa rate in the range of 2.9 × 10-7- 9 × 10-7 dpa/s are studied. Ferrite and M23C6 are commonly observed in the present set of high displacement damage 40-74 dpa SS 316 samples irradiated at temperatures in the range of 400-483 ℃. Also, the dislocation density has increased as a function of the irradiation dose. The X-ray diffraction peak profile parameters quantified such as peak shift and asymmetry show that the irradiation-induced defects are sensitive to the dpa rate-irradiation temperature combinations. The increase in yield strength as a function of displacement damage is also correlated to the dislocation density.

HIGH BURNUP CHANGES IN UO2 FUELS IRRADIATED UP TO 83 GWD/T IN M5(R) CLADDINGS

  • Noirot, J.;Aubrun, I.;Desgranges, L.;Hanifi, K.;Lamontagne, J.;Pasquet, B.;Valot, C.;Blanpain, P.;Cognon, H.
    • Nuclear Engineering and Technology
    • /
    • 제41권2호
    • /
    • pp.155-162
    • /
    • 2009
  • Since the 90's, EDF and AREVA-NP have irradiated, up to very high burnups, lead assemblies housing $M5^{(R)}$ cladded fuels. Post-irradiation examination of high burnup $UO_2$ pellets show an increase in the fission-gas release rate, an increase in fuel swelling, and formation of fission-gas bubbles throughout the pellets. Xenon abundances were quantified, and phenomena leading to this bubble formation were identified. All examinations provided valuable data on the complex state of the fuel during irradiation. They show the good behavior of these fuels, exhibiting various microstructures at very high burnups, none of which is likely to lead to problems during irradiation.