• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집A
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• pp.782-787
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• 2001

This paper is concerned with the global rupture of a nuclear reactor pressure vessel(RPV) in a severe accident. During the severe reactor accident of molten core, the temperature and the pressure in the nuclear reactor rise to a certain level depending on the initial and subsequent condition of a severe accident. While the rise of the temperature cause the thermal softening of RPV material, the rise of the internal pressure could cause failure of the RPV lower head. The global rupture of an RPV is simulated by finite element limit analysis for the collapse pressure and mode and this analysis results have been compared with a variation of the internal pressure of RPV. The finite element limit method is a systematic tool to secure the safety criteria of a nuclear reactor and to evaluate the in-vessel corium retention.

• Nuclear Engineering and Technology
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• 제41권9호
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• pp.1157-1170
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• 2009

A variety of Generation III/III+ reactor designs featuring enhanced safety and improved economics are being proposed by nuclear power industries around the world to solve the future energy supply shortfall. Nanofluid coolants showing an improved thermal performance are being considered as a new key technology to secure nuclear safety and economics. However, it should be noted that there is a lack of comprehensible design works to apply nanofluids to Generation III+ reactor designs. In this work, the review of accident scenarios that consider expected nanofluid mechanisms is carried out to seek detailed application spots. The Axiomatic Design (AD) theory is then applied to systemize the design of nanofluid-engineered nuclear safety systems such as Emergency Core Cooling System (ECCS) and External Reactor Vessel Cooling System (ERVCS). The various couplings between Gen-III/III+ nuclear safety features and nanofluids are investigated and they try to be reduced from the perspective of the AD in terms of prevention/mitigation of severe accidents. This study contributes to the establishment of a standard communication protocol in the design of nanofluid-engineered nuclear safety systems.

• Nuclear Engineering and Technology
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• 제54권5호
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• pp.1845-1850
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• 2022

In-vessel corium retention (IVR) during external reactor vessel cooling (ERVC) is a key severe accident management strategy adopted in advanced nuclear power plants. The injection of nanofluids has been regarded as a means of enhancing CHF when using the IVR-ERVC strategy to safeguard high-power nuclear reactors. However, a critical practical concern is that various types of debris flowing from the contaminant sump during operation of an ERVC system might degrade CHF enhancement by nanofluids. Our objective here was to experimentally assess the viability of nanofluid use to enhance CHF in practical ERVC contexts (e.g., when fluids contain various types of debris). The types and characteristics of debris expected during IVR-ERVC were examined. We performed pool boiling CHF experiments using nanofluids containing these types of debris. Notably, we found that debris did not cause any degradation of the CHF enhancement characteristics of nanofluids. The nanoparticles are approximately 1000-fold smaller than the debris particles; the number of nanoparticles in the same volume fraction is 1 billion-fold greater. Nanofluids increase CHF via porous deposition of nanosized particles on the boiling surface; this is not hindered by extremely large debris particles.

• Nuclear Engineering and Technology
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• 제41권8호
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• pp.1005-1014
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• 2009

The Dual Unit Optimizer 2000 MWe (DUO2000) is put forward as a new design concept for large power nuclear plants to cope with economic and safety challenges facing the $21^{st}$ century green and sustainable energy industry. DUO2000 is home to two nuclear steam supply systems (NSSSs) of the Optimized Power Reactor 1000 MWe (OPR1000)-like pressurized water reactor (PWR) in single containment so as to double the capacity of the plant. The idea behind DUO may as well be extended to combining any number of NSSSs of PWRs or pressurized heavy water reactors (PHWRs), or even boiling water reactors (BWRs). Once proven in water reactors, the technology may even be expanded to gas cooled, liquid metal cooled, and molten salt cooled reactors. With its in-vessel retention external reactor vessel cooling (IVR-ERVC) as severe accident management strategy, DUO can not only put the single most querulous PWR safety issue to an end, but also pave the way to very promising large power capacity while dispensing with the huge redesigning cost for Generation III+ nuclear systems. Five prototypes are presented for the DUO2000, and their respective advantages and drawbacks are considered. The strengths include, but are not necessarily limited to, reducing the cost of construction by decreasing the number of containment buildings from two to one, minimizing the cost of NSSS and control systems by sharing between the dual units, and lessening the maintenance cost by uniting the NSSS, just to name the few. The latent threats are discussed as well.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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• pp.592-599
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• 1997

중대사고관리 전략의 하나로서 피동형-설계에 적용되고 있는 용기내부보존(IVR)기념 - 이 논문에서는 실제적으로 원자로 압력용기벽 외부냉각(ERVC)방법을 사용한다 -이 규제측면에서는 용융물의 냉각가능성 쟁점의 해결이라는 문맥에서 조감되었다; 기술측면에서는 IVR개념의 신빙성 및 유융성이 언급되었다. 덧붙여서, 이 ERVC방법들이 개량형-설계에 적용되기 위하여 요구되는 점들이 규제측면과 기술측면에서 각각 검토되었다. 이 검토결과의 바탕위에서 용융물 냉각가능성/급냉가능성의 쟁점과 관련하여 전력연구원(KEPRI) 신형원전개발센타(CARD)에서 개발중인 한국차세대원전(KNGR)-설계에서 선택될 수 있는 대안적 전략들이 제안되었다: (1) 전략1A: 젖은공동방법의 신빙성에 기반을 두는 것; (2) 전략1B: 젖은공동방법/격납건물건전성에 기반을 두는 것; (3) 전략2A : ERVC방법의 신빙성에 기만을 두는 것, (4)전략2B: ERVC방법/격납 건물건전성의 균형된 접근법에 기반을 두는 것. 마지막으로, 신형-설계적용의 관점에서 각각 규제측면과 기술측면에서 본 현황파악 및 대책마련의 권고사항이 제시되었다.

• Nuclear Engineering and Technology
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• 제56권1호
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• pp.9-18
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• 2024

In-vessel retention through external reactor vessel cooling (IVR-ERVC) is a severe accident management (SAM) strategy that has been adopted and used in many nuclear reactors such as AP1000, APR1400, and light water reactor etc. Some reactor accidents have raised concerns about nuclear reactors among residents, leading to a decrease in residents' acceptability and many studies on SAM are being conducted. Experiments on IVR-ERVC are almost impossible due to its specificity, so fluid characteristics are analyzed through BALI experiments with similar condition. In this study, computational fluid dynamics (CFD) via Reynolds-averaged Navier-Stokes (RANS) and large eddy simulation (LES) for BALI experiments were performed. Steady-state CFD analysis was performed on three turbulence models, and SST k-ω model was in good agreement with the experimental measurement temperature within the maximum error range of 1.9%. LES CFD analysis was performed based on the RANS analysis results and it was confirmed that the temperature and wall heat flux for depth was consistent within an error range of 1.0% with BALI experiment. The LES CFD analysis results were compared with those of the Lagrangian-based solver. LES matched the temperature distribution better than SOPHIA, but SOPHIA calculated the position of boundary between stratified layer and convective layer more accurately. On the other hand, Lagrangian-based solver predicted several small eddy behaviors of the convective layer and LES predicted large vortex behavior. The vibration characteristics near the cooling part of the BALI experimental device were confirmed through Fast Fourier Transform (FFT) investigation. It was found that the power spectral density for pressure at least 10 times higher near the side cooling than near the top cooling.

• 한국축산시설환경학회지
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• 제9권1호
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• pp.45-56
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• 2003

$TAO^{TM}$ System is an auto-heated thermophilic aerated digestion process using a proprietary microbe called as a Phototropic Bacteria (PTB). High metabolic activity results in heat generation, which enables to produce a pathogen-free and digested liquid fertilizer at short retention times. TAO$^{TM}$ system has been developed to reduce a manure volume and convert into the liquid fertilizer using swine manure since 1992. About 100 units have been installed and operated in Korean swine farms so far. TAO$^{TM}$ system consists of a reactor vessel and ejector-type aeration pumps and foam removers. The swine slurry manure enters into vessel with PTB and is mixed and aerated. The process is operated at detention times from 2 to 4 days and temperature of 55 to $65^{\circ}C$. Foams are occurred and broken down by foam removers to evaporate water contents. Generally, at least 30% of water content is evaporated, 99% of volatile fatty acids caused an odor are removed and pathogen destruction is excellent with fecal coliform, rotavirus and salmonella below detection limits. The effluent from TAO$^{TM}$ system, called as the "TAO EFFLUX", is screened and has superb properties as a fertilizer. Normally N-P-K contents of screened TAO Efflux are 4.7 g/L, 0.375 g/L and 2.8 g/L respectively. The fertilizer effect of TAO EFFLUX compared to chemical fertilizer has been demonstrated and studied with various crops such as rice, potato, cabbage, pumpkin, green pepper, parsley, cucumber and apple. Generally it has better fertilizer effects and excellent soil fertility improvement effects. Moreover, the TAO EFFLUX is concentrated through membrane technology without fouling problems for a cost saving of long distance transportation and a commercialization (crop nutrient commodity) to a gardening market, for example.

• Nuclear Engineering and Technology
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• 제48권4호
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• pp.915-924
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• 2016

After a severe accident to the nuclear reactor, the in-vessel retention strategy is a key way to prevent the leakage of radioactive material. Nanofluid is a steady suspension used to improve heat-transfer characteristics of working fluids, formed by adding solid particles with diameters below 100nm to the base fluids, and its thermal physical properties and heat-transfer characteristics are much different from the conventional working fluids. Thus, nanofluids with appropriate nanoparticle type and volume concentration can enhance the heat-transfer process. In this study, the moving particle semi-implicit method-meshless advection using flow-directional local grid method is used to simulate the bubble growth, departure, and sliding on the downward-facing heating surface in pure water and nanofluid (1.0 vol.% $Al_2O_3/H_2O$) flow boiling processes; additionally, the bubble critical departure angle and sliding characteristics and their influence are also investigated. The results indicate that the bubble in nanofluid departs from the heating surface more easily and the critical departure inclined angle of nanofluid is greater than that of pure water. In addition, the influence of nanofluid on bubble sliding is not significant compared with pure water.

• Nuclear Engineering and Technology
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• 제54권4호
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• pp.1343-1354
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• 2022

Experiments were performed to measure the critical heat flux (CHF) on a vertical surface abutting a coarse packed bed of spherical particles. This geometry is representative of a CANDU reactor calandria tubesheet facing the end shield cavity during the in-vessel retention (IVR) phase of a severe accident. Deionized light water was used as the working fluid. Low carbon steel shielding balls with diameters ranging from 6.4 to 12.7 mm were used, allowing for the development of an empirical correlation of CHF as a function of shielding ball diameter. Previously published data is used to develop a more comprehensive empirical correlation accounting for the impacts of both shielding ball diameter and heating surface height. Tests using borosilicate shielding balls demonstrated that the dependence of CHF on shielding ball thermal conductivity is insignificant. The deposition of iron oxide particles transported from shielding balls to the heating surface is verified to increase CHF non-trivially. The results presented in this paper improve the state of the knowledge base permitting quantitative prediction of CHF in the CANDU end shield, refining our ability to assess the feasibility of IVR. The findings clarify the mechanisms governing CHF in this scenario, permitting identification of potential future research directions.

• 항공우주정책ㆍ법학회지
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• 제30권2호
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• pp.83-153
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• 2015

우리나라의 경제가 더욱 성장하고, 항공기의 수가 점차 증가하면, 항공기 집행사건은 앞으로 늘어날 수 있다. 이 글은 다수의 사례가 축적되어 있는 선박집행에 관한 법리를 차용하여 항공기 집행에 관한 법리를 제시하기 위한 것이다. 항공기, 경량항공기에 대한 집행은 기본적으로 부동산 선박 집행을 준용하고, 초경량비행장치, 외국항공기에 대한 집행은 동산집행방법에 의한다. 항공기 집행에는 강제경매, 임의경매, 유치권에 기한 경매 등이 있다. 항공기에 대한 강제경매는 채권자가 금전의 지급을 목적으로 하는 청구권의 만족을 얻기 위하여 채무자 소유의 항공기에 대하여 행하는 강제집행을 말한다. 항공기에 대한 강제경매는 압류 당시에 그 항공기가 있는 곳을 관할하는 지방법원을 집행법원으로 하고, 이는 전속관할이다. 법원은 경매개시결정을 한때에는 집행관에게 항공기등록증명서 그 밖에 항공기운항에 필요한 문서를 받아 법원에 제출하도록 명하여야 한다. 강제경매개시결정이 있은 날부터 2월이 지나기까지 집행관이 항공기등록증명서등을 넘겨받지 못하고 항공기가 있는 곳이 분명하지 아니한 때에는 집행법원이 강제경매절차를 취소할 수 있다. 채권자 최고가매수신고인 차순위매수신고인 매수인의 동의가 있으면, 법원은 영업상의 필요 그 밖에 상당한 이유가 있다고 인정한 때에는 채무자의 신청에 따라 항공기의 운항을 허가할 수 있다. 법원은 채권자의 신청에 따라 항공기를 감수하거나 보존에 필요한 처분을 할 수 있다. 채무자가 민사집행법 49조 2호 4호의 서류를 제출하고 압류채권자 및 배당요구채권자의 채권과 집행비용에 해당하는 보증을 매수신고 전에 제공한 때에는 법원은 신청에 따라 배당절차 외의 절차를 취소하여야 한다. 항공기를 목적으로 하는 담보권 실행을 위한 경매(임의경매) 절차에는 선박 항공기 강제경매에 관한 규정과 담보권 실행을 위한 부동산 선박 경매에 관한 규정이 준용된다. 임의경매에서는 집행권원이 필요하지 않고, 신청에도 집행력 있는 정본은 요구하지 않는다. 또한, 집행법원이 담보권 및 피담보채권의 존부를 심사하여 담보권의 부존재 무효, 피담보채권의 불발생 소멸 등과 같은 실체상의 하자가 있으면 경매개시결정을 할 수 없다. 나아가 이러한 사유는 매각불허가 사유에 해당하고, 또 이를 간과하여 매각허가결정이 확정되고 매수인이 매각대금을 완납하여 소유권이전등록을 마쳤다 하더라도 매수인은 매각항공기의 소유권을 취득하지 못한다. 집행법원은 여러 대의 항공기 상호간의 이용관계에서 견련성이 있는 경우에 한하여 여러 대의 항공기에 대한 일괄경매를 할 수 있다(대법원 2001. 8. 22.자 2001마3688 결정). 항공기에 대한 유치권자도 경매를 신청할 수 있다. 형식적 경매의 절차는 담보권 실행을 위한 경매의 예에 따라 실시한다. 그러나 공항시설 사용료와 항공기 사이의 견련관계를 인정할 수 없으므로, 공항공사의 항공기에 대한 유치권은 성립하지 않는다(대법원 2014. 4. 10. 선고 2011다29291 판결). 유치권에 의한 경매도 항공기 위의 부담을 소멸시키는 것을 법정매각조건으로 하여 실시되고, 우선채권자뿐만 아니라 일반채권자의 배당요구도 허용되며, 유치권자는 일반채권자와 동일한 순위로 배당을 받을 수 있다.