• 제목/요약/키워드: KAERI

검색결과 1,544건 처리시간 0.032초

소듐냉각고속로 부수로 해석코드 검증을 위한 37봉다발 실험방법 개념 개발 (Experimental Methodology Development for SFR Subchannel Analysis Code Validation with 37-Rods Bundle)

  • 어동진;장석규;배황;김석;김형모;최해섭;최선락;이형연
    • 한국유체기계학회 논문집
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    • 제17권6호
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    • pp.89-94
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    • 2014
  • The 4th generation SFR is being designed with a milestone of construction by 2028. It is important to understand the subchannel flow characteristics in fuel assembly through the experimental investigations and to estimate the calculation uncertainties for insuring the confidence of the design code calculation results. The friction coefficient and the mixing coefficient are selected as primary parameters. The two parameters are related to the flow distribution and diffusion. To identify the flow distribution, an iso-kinetic method was developed based on the previous study. For the mixing parameters, a wire mesh system and a laser induced fluorescence methods were developed in parallel. The measuring systems were adopted on 37 rod bundle test geometry, which was developed based on the Euler number scaling. A scaling method for a design of experimental facility and the experimental identification techniques for the flow distribution and mixing parameters were developed based on the measurement requirement.

Inhibition of $N^{+}-K^{+}$ Adenosine Triphosphatase Activity in Fisher Rats by Uranyl Nitrate

  • Lee, Kee-Ho;Lee, Je-Ho;Lee, Soo-Yong;Park, Sang-Yoon;Lee, Seung-Hoon;Yun, Taik-Koo;Ryu, Young-Wun;Lim, In-Kyoung
    • Journal of Radiation Protection and Research
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    • 제15권2호
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    • pp.1-6
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    • 1990
  • An attempt was made to test the possibility of a major role for the $Na^{+}-K^{+}$ adenosine triphosphatase (ATPase)system in the diuresis induced by uranyl nitrate(UN). Fisher 344 rats were intravenously injected with UN(5 mg/kg, 15 mg/kg and 30 mg/kg). Urinary excretion of $Na^{+}\;and\;K^{+}$ significantly increased in 24 h exposure on the UN and then decreased below the normal level 3 days after the treatment. $Na^{+}-K^{+}$ ATPase activity of kidney was significantly inhibited in high dosages of UN 15mg/kg and UN 30 mg/kg 3-5 days after injection. And then the recovery of the enzyme activity was observed within 5-10 days after injection, at which the regeneration of the tubular cells occurred.

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Evaluation of a Sodium-Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor

  • Ahn, Sang June;Ha, Kwi-Seok;Chang, Won-Pyo;Kang, Seok Hun;Lee, Kwi Lim;Choi, Chi-Woong;Lee, Seung Won;Yoo, Jin;Jeong, Jae-Ho;Jeong, Taekyeong
    • Nuclear Engineering and Technology
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    • 제48권4호
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    • pp.952-964
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    • 2016
  • The prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Korea Atomic Energy Research Institute. This reactor uses sodium as a reactor coolant to transfer the core heat energy to the turbine. Sodium has chemical characteristics that allow it to violently react with materials such as a water or steam. When a sodium-water reaction (SWR) occurs due to leakage or breakage of steam generator tubes, high-pressure waves and corrosive reaction products are produced, which threaten the structural integrity of the components of the intermediate heat-transfer system (IHTS) and the safety of the primary heat-transfer system (PHTS). In the PGSFR, SWR events are included in the design-basis event. This event should be analyzed from the viewpoint of the integrities of the IHTS and fuel rods. To evaluate the integrity of the IHTS based on the consequences of the SWR, the behaviors of the generated high-pressure waves are analyzed at the major positions of a failed IHTS loop using a sodium-water advanced analysis method-II code. The integrity of the fuel rods must be consistently maintained below the safety acceptance criteria to avoid the consequences of the SWR. The integrity of the PHTS is evaluated using the multidimensional analysis of reactor safety-liquid metal reactor code to model the whole plant.