• Title/Summary/Keyword: atomic gas

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A vacuum tube based pulse generator for gas lasers (기체 레이저용 진공관식 펄스 전원)

  • Jin, Jeong-Tae;Cha, Byung-Heon;Nam, Sung-Mo;Lee, Heung-Ho
    • Proceedings of the KIEE Conference
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    • 2002.11d
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    • pp.221-223
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    • 2002

  • This paper describes a vacuum tube based high voltage pulse generator for pulsed gas lasers. The pulse generator delivers 20 kV, 300 A pulse outputs with more than 10 kHz pulse repetition rates It can be controlled its Pulse width from 30 ns to 80 ns continuously without any hardware change.

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FUEL PERFORMANCE CODE COSMOS FOR ANALYSIS OF LWR UO2 AND MOX FUEL

  • Lee, Byung-Ho;Koo, Yang-Hyun;Oh, Jae-Yong;Cheon, Jin-Sik;Tahk, Young-Wook;Sohn, Dong-Seong
    • Nuclear Engineering and Technology
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    • v.43 no.6
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    • pp.499-508
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    • 2011

  • The paper briefs a fuel performance code, COSMOS, which can be utilized for an analysis of the thermal behavior and fission gas release of fuel, up to a high burnup. Of particular concern are the models for the fuel thermal conductivity, the fission gas release, and the cladding corrosion and creep in $UO_2$ fuel. In addition, the code was developed so as to consider the inhomogeneity of MOX fuel, which requires restructuring the thermal conductivity and fission gas release models. These improvements enhanced COSMOS's precision for predicting the in-pile behavior of MOX fuel. The COSMOS code also extends its applicability to the instrumented fuel test in a research reactor. The various in-pile test results were analyzed and compared with the code's prediction. The database consists of the $UO_2$ irradiation test up to an ultra-high burnup, power ramp test of MOX fuel, and instrumented MOX fuel test in a research reactor after base irradiation in a commercial reactor. The comparisons demonstrated that the COSMOS code predicted the in-pile behaviors well, such as the fuel temperature, rod internal pressure, fission gas release, and cladding properties of MOX and $UO_2$ fuel. This sufficient accuracy reveals that the COSMOS can be utilized by both fuel vendors for fuel design, and license organizations for an understanding of fuel in-pile behaviors.

  • https://doi.org/10.5516/NET.2011.43.6.499 인용 PDF KSCI

Analysis of Gases in Nuclear Fuel Rod by Quadrupole Mass Spectrometry (Quadrupole Mass Spectrometry를 이용한 핵연료봉내 기체분석)

  • Kim, Seung-Soo;Kang, Moon-Ja;Park, Soon-Dal;Park, Yong-Joon;Joe, Kih-Soo
    • Analytical Science and Technology
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    • v.12 no.2
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    • pp.94-98
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    • 1999

  • An analysis method of components and isotopic compositions of low pressure gases from nuclear fuel rod using quadrupole mass spectrometer was studied. The calibration curves of each gas in pure and mixtures of He, $N_2$, $O_2$, Ar, Kr and Xe were obtained as a function of pressure and concentration, respectively. Effect of molecular leak, located between sample chamber and analyser chamber, on the sensitivites was also studied. The results suggested that samples could be analysed accurately at the same analytical condition as that of synthetic gas mixture. The difference of sensitivities among isotopes of Kr and Xe was not observed in the range of measured pressure.

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