• Title/Summary/Keyword: 조밀화

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The Criticality Analysis of Spent Fuel Pool with Consolidated Fuel in KNU 9 & 10 (조밀화 집합체로 중간저장하는 경우 원자력 발전소 9, 10호기의 사용 후 핵연료 저장조의 임계분석)

  • Jae, Moo-Sung;Park, Goon-Cherl;Chung, Chang-Hyun;Jang, Jong-Hwa
    • Nuclear Engineering and Technology
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    • v.20 no.1
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    • pp.27-34
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    • 1988

  • Since the lack of the spent fuel storage capcity has been expected for all Korean nuclear power plants in the mid-1990s, the maximum density rack (MDR) with consolidated fuels can be proposed to overcome the shortage of the storage capacity in KNU 9 & 10 which have most limited capacities. To ensure the safety when the alternatives are applied in the KNU 9 & 10, the multiplication factor are calculated with varying the rack pitch and the thickness of consolidated storage box by the AMPX-KENO IV codes. The computing system is verified by the benchmark calculation with criticality experiments for arrays of consolidated fuel modules, which was reported by B & W in 1981. Also an abnormal condition, i.e. malposition accident, is simulated. The results indicate that the KNU 9 & 10 storage pools with consolidated fuel are safe in the view of the criticality. Thus the storage capacity can be expanded from 9/3 cores into 27/3 cores even with considering equipments and cooling spaces.

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A Study on the Local Boiling of the Consolidated Spent Fuel Storage Pool (조밀화된 사용후 핵연료 저장조에서의 국부 비등에 관한 연구)

  • Lee, Chang-Ju;Lee, Kun-Jai
    • Nuclear Engineering and Technology
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    • v.25 no.1
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    • pp.8-19
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    • 1993

  • The natural convection model of the consolidated system has been developed to make sure the removal of decay heat generated in the spent fuel for the loss of forced cooling accident. The numerical technique employed was based on the ADI scheme. The calculation of heat generation rate in the spent fuel was peformed by the ANS-79 decay heat model, and the nonuniform surface heat flux is assumed with a chopped sine curve for the conservative decay heat generation input. The sensitivity study was performed to examine the possibility of the pool bulk boiling by varying the various parameters, i.e. inter-fuel spacing ratio, heat generation power, and radius of the fuel rod. The application results of this model show that the natural circulation flow through compacted spent fuel bundles enables the pool temperature to control in a safe and effective manner, after the required cooling time. The corresponding acceptance criteria of the cooling time for rearranging the spent fuel rods were also found.

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Sintering behavior of $\textrm{La}_{0.68}\textrm{Ca}_{0.32}\textrm{Cr}_{0.97}\textrm{O}_{3}$ Interconnector Material for SOFC (SOFC용 $\textrm{La}_{0.68}\textrm{Ca}_{0.32}\textrm{Cr}_{0.97}\textrm{O}_{3}$연결재료의 소결거동)

  • Lee, Yu-Gi;Park, Jong-Wan
    • Korean Journal of Materials Research
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    • v.7 no.4
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    • pp.276-286
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    • 1997

  • SOFC용 L $a_{0.68}$Ca/ sub 0.32/C $r_{0.97}$ $O_{3}$분말은 수산염법에 의해 제조되었고, 이 합성된 분말을 이용한 슬러리의 최적제조조건과 그린 필름의 최적 소성조건을 얻었으며,이 제조 조건에서 소결 시간과 온도에 따라 제조된 연결재료의 결정구조, 미세구조 및 소결거동을 각각X-선 회절, 주사전자현미경 그리고 에너지 분산 분광계를 이용하여 조사하였다. L $a_{0.68}$C $a_{0.32}$C $r_{0.97}$ $O_{3}$의 저온소결은 $Ca_{m}$ (Cr $O_{4}$)$_{n}$에 의해 이루어졌음이 관찰되었고, 이때 $Ca_{m}$ (Cr $O_{4}$)$_{n}$은 불규칙하게 녹아서 L $a_{1-x}$C $a_{x}$Cr $O_{3-}$$\delta$/와 반응하고 이 현상이 질량 이동을 증가시켜 시편의 급격한 결정립 성장과 조밀화를 야기시켰다. 이러한 결정립 성장과 조밀화는 소결온도 140$0^{\circ}C$부터 일어났다.X>부터 일어났다.

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