• 한국주조공학회지
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• 제22권4호
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• pp.167-173
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• 2002

The hydrogen gas pick-up problem that can occur during Lost Foam Casting was investigated by reduced pressure test and practical Lost Foam Casting. The proper test pressure of reduced pressure test was determined by experiments not to use polystyrene and gas contents of the melt were calculated from density measurement results. The results showed that the hydrogen pick-up increased with the increased amount of polystyrene that was replaced by melt. The hydrogen pick-up was larger in the case of no degassed melt than that of degassed melt. So the hydrogen pick-up depended on the initial hydrogen content of the melt and the contact time of the melt with the decomposed gas phase. The mold evacuation decreased the hydrogen pick-up and increased the flow length of melt during Lost Foam Casting. And the error of calculated hydrogen pick-up was calculated by numerical method.

• Nuclear Engineering and Technology
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• 제30권5호
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• pp.396-402
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• 1998

Experiments on the steamside corrosion and hydrogen pick-up of Zircaloy-4 under high pressure up to 10.3MPa are carried out to estimate the pressure effects on the kinetics. Temperature and reaction time are determined to be 37$0^{\circ}C$ and 72hours for the pre-transition test and $700^{\circ}C$ and 210minutes for the post-transition test, respectively. Results show that under 10.3MPa pressure the oxidation reaction is 50% and 100% enhanced in the pre-and the post-transition regime, respectively. Total amount of hydrogen uptake in the reaction is proportionally increased as corrosion weight gain is elevated. However, pick-up fraction is not affected by the high pressure. The fraction is almost twice greater than that in the waterside corrosion. Edges in the specimens play a certain role in the enhancement, especially in the post-transition regime. To identify physical property changes of oxide film such as micro-cracks or micro-pores, careful and thorough examination must be needed with some special techniques.

• 한국주조공학회지
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• 제23권5호
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• pp.268-275
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• 2003

The mechanism of the hydrogen gas pore formation was investigated in Lost Foam Casting of Al-alloy by reduced pressure test and real casting. The hydrogen gas pick-up was affected by the formed gas during the decomposition of polystyrene in addition to the liquid product. It depended on pouring temperature and a proper temperature of metal front gave the minimum hydrogen pick-up. At a low pouring temperature, the hydrogen went into the melt mainly from entrapped liquid product of polystyrene but pores were formed from the gas as well as the liquid product at a high pouring temperature. The mold flask evacuation down to 710torr decreased the gas porosity down by around 0.4% vol%. The entrapped decomposition product of polystyrene in the melt was observed through the visualization of filling behavior of Al alloy-melt with the high speed camera.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.915-916
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• 2004

• 한국재료학회지
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• 제8권3호
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• pp.268-273
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• 1998

Zircaloy-4 합금판재에 230-250ppm의 수소를 장입시키고 $400^{\circ}C$에서 72시간동안 균질하게 수소화물을 형성시킨후 $350^{\circ}C$의 static autoclave를 이용하여 여러 가지 농도의 LiOH 부식용액조건에서 부식시험을 수행하였다. 부식평가는 시간에 따른 무게증가의 변화로서 측정하였고, 시편의 미세구조는 광학현미경과 주사전자현미경을 사용하여 관찰하였다. 부식시험 후 형성된 산화막에서의 H와 Li의 분포를 확인하기 위해 secondary ion mass spectrometry(SIMS)를 이용해 각 원소의 분포를 두께방향에서 측정하였다. 여러 가지 농도의 LiOH 수용액조건에서 Li+ 이온의 용액농도가 30ppm 이상으로 증가하면 합금의 부식은 급격히 가속화되었다. 이것은 $Li^{+}$가 산화막 내의 $Zr^{4+}$ 자리를 치환함에 따라 산소공공이 증가로 산화반응이 증가되고, 이로 인해 형성되는 수소화물의 양이 증가하기 때문이다. LiOH용액조건에서 부식시험 전에 시편 내에 수소를 장입시켜 수소화물을 형성시키면 수소를 장입하지 않은 시편보다 부식이 더 빨리 가속되지만, 시험기간이 길어지면 오히려 수소를 미리 장입시키지 않은 시편의 부식속도가 더 빨라진다. 이것은 부식시험 전에 수소를 시편에 미리 장입을 시키면 이때 형성된 수소화물에 의해 초기에 부식이 빨리 가속되지만 이미 고용도 이상의 수소가 금속 내부에 존재하므로 부식과정 중에 생기는 수소가 금속의 내부로 확산되어 들어오는 것이 억제되어 부식속도가 둔화되는 것으로 생각된다.

• Nuclear Engineering and Technology
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• 제35권5호
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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.

• Nuclear Engineering and Technology
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• 제50권2호
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• pp.313-317
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• 2018

Licenses for the storage of spent nuclear fuel (SNF) and vitrified highly active waste in casks under dry conditions are limited to 40 years and have to be renewed for prolonged storage periods. If such a license renewal has to be expected since as in accordance with the new site selection procedure a final repository for spent fuel in Germany will not be available before the year 2050. For transport and possible unloading and loading in new casks for final storage, the integrity and the maintenance of the geometry of the cask's inventory is essential because the SNF rod cladding and the cladding of the vitrified highly active waste are stipulated as a barrier in the storage concept. For SNF, the cladding integrity is ensured currently by limiting the hoop stress and hoop strain as well as the maximum temperature to certain values for a 40-year storage period. For a prolonged storage period, other cladding degradation mechanisms such as inner and outer oxide layer formation, hydrogen pick up, irradiation damages in cladding material crystal structure, helium production from alpha decay, and long-term fission gas release may become leading effects driving degradation mechanisms that have to be discussed.

• 한국수소및신에너지학회논문집
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• 제22권1호
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• pp.118-127
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• 2011

An IGCC was evaluated as one of the next generation technologies that would be able to substitute for coal-fired power plants. According to "The 4th Basic Plan of Long-term Electricity Supply & Demand" which is developed by the Electricity Business Acts, the first IGCC will be operated at 2015. Like other new and renewable energy such as solar PV, Fuel cell, The IGCC is considered as non-competitive generation technology because it is not maturity technology. Before the commercial operation of an IGCC in our electricity market, its economic feasibility under the Korean electricity market, which is cost-based trading system, is studied to find out institutional support system. The results of feasibility summarized that under the current electricity trading system, if the IGCC is considered like a conventional plant such as nuclear or coal-fired power plants, it will not be expected that its investment will be recouped within life-time. The reason is that the availability of an IGCC will plummet since 2016 when several nuclear and coal-fired power plants will be constructed additionally. To ensure the reasonable return on investment (NPV>0 IRR>Discount rate), the availability of IGCC should be higher than 77%. To do so, the current electricity trading system is amended that the IGCC generator must be considered as renewable generators to set up Price Setting Schedule and it should be considered as pick load generators, not Genco's coal fired-generators, in the Settlement Payment.

• 한국재료학회지
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• 제9권4호
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• pp.378-385
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• 1999

핵 연료 피복관 재료로 샤용되고 었는 Zr 합금의 부식특성을 개선하기 위하여 Zn-xSn 2원계 합금과 Zr-0.4Nb-xSn 3원계 합금을 제조하여 부식특성을 평가하였다. 부식 실험은 $360^{\circ}C$ 물 분위기의 mini-autoclave에서 수행하였다. 2원계 합금의 경우 Sn이 0.5, 0.8, 1.5wt.% 첨가된 합금에서는 15일에서 속도천이가 발생한 후 급격한 부식 가속 현상이 나타녔으나, 2.0wt.% 가 첨가된 합금의 경우 80일까지의 부식 실험에서도 천이 현상을 보이지 않는 매우 높은 부식 저항성을 보였다. 3원계 합금에서는 Sn 함량이 증가할수록 부식이 증가하는 경향을 보였다. 이러한 경향은 2원계 합금과 3원계 합금에서 Sn의 고용도 차, 미량 첨가된 Nb의 영향 및 석출물의 특성과 관련이 잇는 것으로 생각된다. 또한 Zr-xSn, Zr-O.4Nb-xSn 합금의 부식은 tetragonal-$ZrO_2$의 분율과 수소 흡수율에 의해서 제어될 수도 있다.