• 한국ITS학회:학술대회논문집
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• 2004.11a
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• pp.106-110
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• 2004

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.261-267
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• 2004

Inventories, projections, and characteristics of spent nuclear fuel(SNF) generated from domestic nuclear power plants were updated to support high-level waste disposal system design. The historical and projected inventory by the end 2055 is expected to be 20,500 and 14,800MTU for PWR and CANDU spent nuclear fuel, respectively The ratio of quantity for TEX>$17{\times}17$ SNF was shown to be 0.6 as of 2003. The amount of TEX>$17{\times}17$ SNF, however, will be less than that of TEX>$16{\times}16$ KSFA after 2012, while the quantity of TEX>$16{\times}16$ KSFA will reach to 70% of the total spent fuels in the 2055. Average turnup of SNF revealed ~36GWD/MTU and ~40GWD/MTU for the period of 1994-1999 and 2000-2003, respectively. It is expected that the average burnup of SNF will exceed 45GWD/MTU at the end of 2000's. Therefore, it seems reasonable to use the TEX>$17{\times}17$ 4.5w/o, 45GWD/MTU as the Reference SNF at present state. The TEX>$16{\times}16$ KSFA 4.5w/o, 55GWD/MTU, however, should be Reference SNF after ~2010.

• Nuclear Engineering and Technology
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• v.45 no.3
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• pp.377-384
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• 2013

During the last three decades, South Korean nuclear power plants have discharged about 5,950 tons of spent fuel and the maximum burn-up reached 55 GWd/MTU in 2002. This study was performed to support the development of Korean dry spent fuel storage alternatives. First, we chose V5H-$17{\times}17$ and KSFA-$16{\times}16$ as representative domestic spent fuels, considering current accumulation and the future generation of the spent fuels. Examination reveals that their average burn-ups have already increased from 33 to 51 GWd/MTU and from 34.8 to 48.5 GWd/MTU, respectively. Evaluation of the fuel characteristics shows that at the average burn-up of 42 GWd/MTU, the oxide thickness, hydrogen content, and hoop stress ranged from $30{\sim}60{\mu}m$, 250 ~ 500 ppm, and 50 ~ 75 MPa, respectively. But when burn-up exceeds 55 GWd/MTU, those characteristics can increase up to 100 ${\mu}m$, 800 ppm, and 120 MPa, respectively, depending on the power history. These results demonstrate that most Korean spent nuclear fuels are expected to remain within safe bounds during long-term dry storage, however, the excessive hoop stress and hydrogen concentration may trigger the degradation of the spent fuel integrity early during the long-term dry storage in the case of high burn-up spent fuels exceeding 45 GWd/MTU.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.1
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• pp.87-93
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• 2006

Inventories, and characteristics such as dimension, fuel rod array, weight, $^{235}U$ enrichment, and discharge burnup of spent nuclear fuel (SNF) generated from existing and planed nuclear power plants based on National 2nd Basic Plan for Electric Power Demand and Supply were investigated and projected to support geological disposal system design. The historical and projected inventory by the end 2057 is expected to be 20,500 and 14,800MTU for PWR and CANDU spent nuclear fuel, respectively. The quantity of SNF with initial $^{235}U$ enrichment of 4.5 wt.% and below was shown to be 96.5% in total. Average burnup of SNF revealed $\sim36$ GWD/MTU and $\sim40$ GWD/MTU for the period of 1994-1999 and 2000-2003, respectively. It is expected that the average burnup of SNF will be $\sim45$ GWD/MTU at the end of 2000's. From the comprehensive study, it was concluded that the imaginary SNF with $16\times16$ Korean Standard Fuel Assembly, cross section of $21.4cm\times21.4cm$, length of 453cm, mass of 672 kg, initial $^{235}U$ enrichment of 4.5 wt.%, discharge burnup of 55 GWD/MTU could cover almost all SNFs to be produced by 2057.

• Nuclear Engineering and Technology
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• v.35 no.5
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• pp.471-481
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• 2003

In order to evaluate the microstructural characteristics of irradiated fuel claddings (Zircaloy-4), two irradiated specimens having different burnups (18 GWD/MTU and 42 GWD/MTU) were prepared from the G23-M4 fuel rods, which were loaded in Kori Unit 1 for 4 fuel cycles. The oxide thickness, hydride morphology and hardness change were characterized by an optical microscope and a micro-hardness tester after preparing the irradiated specimens in the PIE (Post Irradiation Examination) facilities. The dislocation loops and the amorphous transformation of precipitates induced by the neutron irradiation in the nuclear plant were also examined by a TEM. As the burnup increased from 18 GWD/MTU to 42 GWD/MTU, the oxide thickness increased from $6.0{\mu}m\;to\;25.3{\mu}m$ and the contents of hydrogen pick-up in the Zr matrix also greatly increased. In the comparison of the hardness of the unirradiated fuel cladding, the amount of hardness increase was nearly $9.3\%\;and\;24.2\%$ for the irradiated samples of 18 and 42 GWD/MTU, respectively. Both -type dislocation loops and -type dislocation components were observed simultaneously in the irradiated specimens and the densities of the dislocation was increased by increasing the burnup. The precipitates in both the irradiated specimens were amorphously transformed by the neutron irradiation and the trend of the amorphous transformation of the precipitates was enhanced at a higher burnup.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.311-316
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• 1997

무붕산 노심의 부하추종운전을 위하여 출력제어기법을 개발하였다. 무붕산 노심의 출력제어 논리는 출력 준위와 제어봉의 위치에 따라 제어군의 역할을 반응도 제어에 사용되는 제어군과 출력분포 제어에 사용되는 제어군으로 구분하여 8가지의 제어군 구동 형태를 가지며, ASI 편차를 입력으로 구동할 제어군이 결정된다. 무붕산 노심의 출력제어 논리를 적용하여 ONED94 코드로 일일 부하추종운전을 모사하였다. 모사 결과 주기초(0 MWD/MTU)와 주기중(7000 MWD/MTU)에는 ASI 편차 $\pm$10% 내에서 부하추종운전이 가능하며, 85% 주기말(11000 MWD/MTU)에서는 $\pm$12% 내에서 부하추종운전이 가능한 것으로 나타났다.

• Journal of KIISE:Computer Systems and Theory
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• v.29 no.12
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• pp.648-654
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• 2002

The Virtual Interface Architecture(VIA) is an industry standard for communication over system area networks(SANs). M-VIA is a software implementation of VIA technology on Linux. In this paper, we implemented the M-VIA on an AceNIC Gigabit Ethernet by developing a new AceNIC driver for the M-VIA. We analyzed the M-VIA data segmentation processes. When a Gigabit Ethernet MTU is larger than 1514 bytes, M-VIA data segmentation size leaves much room for improvement. So we experimented with various MTU and M-VIA data segmentation size and compared the performances.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.201-206
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• 1996

건식가공(Dry Process)이 사용전,후 DUPIC 핵연료의 붕괴열(Decay Heat), Hazard Index, 조사선량률(Dose Rate) 등에 미치는 영향을 계산하고, 그 원인을 분석하였다. DUPIC 사용방안으로 표준 연소도(35,000 MWD/MTU)의 경우와 장주기 연소도(50,000 MWD/MTU)의 경우를 고려하여 계산하였으며, DUPIC핵연료는 20년 냉각후 가공하는 것을 기준으로 하였다. 또한 DUPIC핵연료 장전시 고려할 수 있도록 사용전 DUPIC 핵연료에 대한 계산을 핵연료 집합체(Bundle) 단위로 하였다. 조사선량과 붕괴열은 건식가공에 상당히 민감한 반응을 보였고 이는 주로 Cs의 제기에 의한 것이다.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.799-804
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• 1995

DUPIC 핵연료의 사용전 그리고 사용후 조건에서 방사선량을 분석하였다. 사용후 핵연료로 35,000 MWD/MTU의 표준 연소도와 50,000 MWD/MTU의 고 연소도을 사용하였고 선량률을 계산하기 위해 CANDU의 핵연료 집합체을 균등 혼합체로 가정 하였다. 조사선량율은 건식가공을 거치지 않았을 때 매우 높은 수치를 나타내었지만 건식가공을 한 후에는 많이 감소하개 됨 을 볼 수 있었다. 특히 Cs에 민감한 반응을 보였고 Cs을 100% 제거하였을 경우 전체 선량율이 약 90%가 줄어드는 결과를 얻었다. 아울러 사용후 DUPIC핵연료의 선량율도 건식가공 방법에 많은 영향을 받고 있다.

• The KIPS Transactions:PartC
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• v.16C no.1
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• pp.37-50
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• 2009

The SCADA(Supervisory Control And Data Acquisition) system is a control system for infrastructure of nation. In the past, the SCADA system was designed without security function because of its closed operating environment. However, the security of the SCADA system has become an issue with connection to the open network caused by improved technology. In this paper we review the constraints and security requirements for SCADA system and propose advanced key management architecture for secure SCADA communications. The contributions of the present work are that our scheme support both message broadcasting and secure communications, while the existing key management schemes for SCADA system don't support message broadcasting. Moreover, by evenly spreading much of the total amount of computation across high power nodes (MTU or SUB-MTU), our protocol avoids any potential performance bottleneck of the system while keeping the burden on low power (RTU) nodes at minimal.