Earticle

To evaluate the performance of nuclear fuel, it is necessary to measure the fission gas release, fuel temperature, fuel stack elongation, cladding elongation, fuel rod inner pressure, coolant temperature, and neutron flux during irradiation tests. Linear variable differential transformer (LVDT) is applied to the in-pile instruments for measuring the fuel rod inner pressure. In this study, design modification of LVDT was carried out to measure the fuel elongation and cladding elongation, without changing the structural soundness of the conventional nuclear fuel test rig used in HANARO. The magnetic core was directly connected to the fuel stack or cladding using a supporter, and it moved through the guide rail of LVDT sensor according to the deformation of fuel pellets or cladding. The performance verification and data calibration of the modified LVDT were verified by the deformation simulation system, where displacement was induced using a micrometer.

This paper is to investigate the wear behavior of submerged-arc claddings by the wear test with a ball-on-disk type wear testing machine in air. The specimens were clad with Stoody105 alloy wire on a medium carbon steel (SM45C) substrate by submerged-arc cladding process under different welding parameters. The wear behavior of the cladding through ball-on-disk test has been studied under the wear load from 5 to 16 N and the sliding speed from 8 to 35 cm/s. The weight loss of the specimen was measured. Scanning electron micrographs of the worn surface show a layer of oxide film formed on the worn surface. Oxidation wear mechanism controls the wear process. The spatting of the oxide is caused by the repeated rubbing fatigue mechanism.

The recent development of bio-ceramic material is being studied in various bio-material engineering field. There are lots of technical difficulties because manufacturing or bonding technique are required bio-friendliness, cleanliness and persistence. Zirconia ceramic powder is cladded on Ti-6AI-4V metallurgically by laser cladding processing. Laser cladding system with powder feeding delivery is designed and manufactured for optimum processing condition. Increasing of manufacturing speed and good quality of clad layer are achieved by application of preheating of substrate before laser cladding. The thin dilution and good clad layer on the substrate are obtained for applications of bio-materials such as the dental materials and the articulated joints of human body.

Laser cladding process accompanies phase transformations from melting (on heating) through solidifying (on cooling) at the same time within a small material volume and to final solid phase. The phase transformations are not reversible, but an irreversible thermodynamic process; they accompany either absorption or release of thermal energy (referred to latent heat) during transformation. Yet, most analyses on materials processed by laser as a heat source have been performed on models of neglecting the latent heat in the process and those did not Justify the simplification. With literatures on the laser material process, we have not place an answer to how little the assumption affects on analyses. This led us to our current study: the effects of latent heat on thermo-mechanical analysis. To this end, we developed a fairly accurate program accommodating an algorithm for enforcing the latent heat whenever necessary and ran it combining with ABAQUS$^{TM}$. The simulation techniques we used in this study were verified by directly comparing our prediction with experimental publications elsewhere; our numerical results agreed accurately with the experiments. On the effects of the latent heat, we performed two alternatives about considering the latent heat in analysis, and compared each other. As a result, we found that more accurate conclusions might come out when considering the latent heat in process analyses.s.

The nuclear fuel cladding temperatures of the HANARO fuel test loop have been calculated by MARS code for the large break loss-of-coolant accidents. Conservative method was used for the analysis of the loss-of-coolant accidents. Consequently, the maximum peak cladding temperature was predicted as 1235K, which was lower than the design limit temperature (1477K) of nuclear fuels for the HANARO fuel test loop. This means that the cooling capability of the emergency cooling water system for the HANARO fuel test loop is sufficient for the large break loss-of-coolant accidents.

This paper presents the results of application and numerical prediction of wind pressure distribution and coefficient over building cladding. The analysis of wind pressure assessment due to wind-resistant design and wind effect to surrounding buildings is important to building cladding. This paper simulates the wind pressure distribution to the building and wind flow pattern around the building cladding, and shows the usability of CFD analysis to design process of building. A Navier-Stokes-Solver with Quick spatial discretization scheme and RNG k- ε turbulence model has been applied to the computation of the three dimensional turbulent flow.

소듐냉각 고속로 (SFR) 핵연료 피복관 후보재료로 고려되고 있는 중형 규모의 HT9 단조품 소재에 대한 금속조직학적 영향을 고찰하였다. 시험 재료는 유도가열법을 이용하여 1.1톤 규모의 잉곳으로 성형한 후, 1170℃에서 고온 단조 및 공랭을 통하여 160mm 직경 및 7000mm 길이를 갖는 단조품으로 가공하여 반 경방향으로 미세조직의 변화를 관찰하였다. 시험 결과 시험 재료는 페라이트-마르텐사이트 조직을 보였 으며 합금 조성에 의하여 2~3%의 델타 페라이트 (delta ferrite)를 가짐과 동시에 반경방향의 냉각속도 차 이에 의하여 최대 15%의 변태 페라이트 (transformed ferrite)를 함유함이 관찰되었다. 냉각곡선의 모델 링과 시간-온도-변태 (TTT) 선도를 이용한 민감도 분석을 통하여 단조품의 직경을 120mm로 줄였을 경우 중심부의 변태 페라이트 형성을 억제할 수 있음을 제시하였다.

Microstructural and mechanical property were evaluated at the medium-sized HT9 (12Cr-1MoWV) forged steel which was considered as primary candidate for the fuel cladding in sodium-cooled fast reactor (SFR). Material was forged at 1170 C after the induction melting to make round bar as 160mm diameter, 7000mm length then the radial distribution of microstructure as well as microhardness was evaluated. The results showed that overall microstructure exhibited as ferrite-martensite structure, where small amount (2 3%) of delta ferrite was formed throughout the specimen and maximum 15% of transformed ferrite was formed at the center, where it gradually decreased toward the radial direction. Sensitivity analysis of the cooling curve and Time-Temperature- Transformation (TTT) diagram revealed that formation of transformed ferrite could be avoided when the diameter was decreased down to 120mm.

본 논문에서는 X선 광전자 분광법(X-ray photoelectron spectroscopy, XPS)을 이용하여 ZIRLO (ZIRconium Low Oxidation)피복관의 표면 산화 거동을 연구하였다. 산화 시간 (10-336 시간, 500℃) 및 산화 온도 (400-700℃, 10 시간)에 따른 산화 특성변화를 관찰하였다. XPS peak 분석 결과, 500℃에서 산화된 피복관의 산화 시간이 24 시간이 될 때 ZrO2 peak가 11.86% 관찰되었으며, 이후 산화 시간이 길어질수록 ZrO2의 비율이 17.93%까지 (336 시간) 증가하는 것이 확인되었다. 반면, 10 시간산화된 피복관에서 5.68% 존재하던 ZrO 상은 산화 시간이 24 시간으로 늘어남에 따라 사라지는 것이 관찰되었다. 산화 온도 증가에 의한 영향 분석 결과에서는 산화 온도가 400℃에서 500, 600, 700℃로 증가할 때 ZrO 상의 비율이 0% 부터 5.68,8.31, 9.16%로 증가하는 것이 확인되었다. 이 때, ZrO2 상은 700℃에서 산화된 시료에서만 관찰되었다. ZrO 상의 형성 메커니즘은 불명확하지만, 고온에서 공기 중의 수분과 Zr의 반응으로 인해 Zr(OH)4 상의 형성이 가속되는 것으로 예상된다. 본논문에는 500℃에서 산화된 ZIRLO 피복관과 이들의 염소화 반응 특성에 대한 논의도 포함되었으며, 염소화 반응 진행 가능성에 있어서 산화막의 두께가 중요한 역할을 하는 것으로 보여진다.

Surface oxidation behavior of ZIRLO (ZIRconium Low Oxidation) hulls was investigated using an X-ray photoelectronspectroscopy (XPS) technique. The effects of oxidation time (10-336 h at 500℃) and temperature (400-700℃ for 10 h)were studied. Deconvolution results of the hulls oxidized at 500℃ revealed that a ZrO2 phase appeared after 24 h (11.86%),and an increase in the ZrO2 ratio was observed when the hulls were oxidized for 336 h (17.93%). On the other hand, the ZrOphase which employed 5.68% in the 10 h oxidized sample disappeared when the oxidation time increased to 24 h. The XPSresults also showed that an increase in the oxidation temperature resulted in an increase in the ratio of ZrO, which increasedfrom 0 to 5.68, 8.31, and 9.16% when the oxidation temperature increased from 400 to 500, 600, and 700℃, respectively. ZrO2 phase was observed only in the sample that was oxidized at 700℃. The mechanism of ZrO formation was not conclusive,but it was suggested that a formation of hydroxide might have been accelerated at elevated temperatures leading to aformation of a Zr(OH)4 phase. The relationship between the surface oxidation status of the hulls oxidized at 500℃ and theirchlorination reaction feasibility was discussed, and it was suggested that the thickness of the oxide layer is an importantparameter that determines the chlorination reaction feasibility.

본 연구에서는 산화된 피복관으로부터 염소화 공정을 통해 Zr을 선택적으로 회수하기 위한 연구의 일환으로, 단면이 개방 된 ZIRLO 피복관의 염소화 반응 속도식을 열중량분석기를 이용하여 분석하였다. 실험을 통해 산화된 ZIRLO 피복관은 400 도 염소화 조건에서 염소 기체와 반응하지 않는 것으로 확인되었다. 하지만 피복관 한쪽 혹은 양쪽 끝의 새로운 단면이 개방 될 경우 ZIRLO의 염소화 반응이 가능함을 확인하였고 반응을 완료하기까지 8 시간이 소요되었다. 이는 반응 완료까지 7 시 간이 소요된 산화되지 않은 피복관에 비하여 반응시간이 14% 증가한 것이다. Sharp-Hancock 식을 이용하여 단면이 개방된 ZIRLO 피복관과 염소 기체의 반응을 모사하기 위한 구조함수를 도출하였으며, 부피축소 모델이 본 연구 조건에서 가장 적 합한 구조 함수로 확인되었다. 또한, 본 연구를 통해 ZIRLO 피복관의 표면이 산화되어 있는 조건에서도 단면노출을 통해 염 소화 공정에 적용이 가능함을 확인하였다.

The reaction rates of ZIRLO cladding hulls with cross-section openings were investigated using a thermo-gravimetric analysis system in order to identify whether selective recovery of Zr from oxidized cladding hulls is possible. The experimental results showed that an oxidized ZIRLO cladding hull was not reactive with chlorine gas at 400℃. However, providing fresh cross-sections on one or both ends of the ZIRLO hulls enabled a chlorination reaction. This reaction was completed after 8 hours; a 14% increase on the 7 hours seen with a bare ZIRLO cladding hull. The Sharp-Hancock plot analysis results revealed that the contracting volume model is the best for describing the reaction between the cross-section opened ZIRLO hulls and chlorine gas under the condition of this work. It was concluded that the chlorination process can be employed for oxidized ZIRLO cladding hulls by providing cross-section openings.

전해정련을 이용한 폐 피복관 처리의 타당성을 살펴보기 위하여, 500℃의 LiCl-KCl 용융염 내에서 표면이 산화된 10 g 규모의Zircaloy-4 피복관 및 순수한 Zircaloy-4 피복관의 전기화학적 거동을 살펴보았다. 산화된 Zircaloy-4 피복관이 담긴 basket을 작업전극으로하여 전압-전류 관계를 측정한 결과, 산화되지 않은 Zircaloy-4 피복관과 비교해 Zr의 산화 peak는 Ag/AgCl 기준전극 대비, 약 -0.7 V ~ -0.8 V로 유사한 반면, 산화 전류의 크기는 확연하게 감소하는 것으로 나타난다. 이러한 결과는 -0.78V의 일정전위를 가한 전기화학적 용해 실험에서 살펴본 전류-시간 곡선에서도 유사하게 나타나며, 피복관 조각들의 평균 두께 및 무게 변화로부터 확인할 수 있다. Zircaloy-4 피복관이 산화되었을 경우, 표면의 산화막이 피복관의 전도성에 영향을 주어 basket 내 위치에 따라 전기화학적 용해의 균일성 및 속도를 떨어뜨리는 것으로 나타나지만, 표면의 미세한 결함과 Zr 산화물의 상 특성으로 인해 전기화학적 용해가 진행되는 것으로 판단된다.

The electrochemical behaviors of 10 g-scale fresh and oxidized Zircaloy-4 cladding hulls were examined in 500oC LiCl-KCl molten salts to confirm the feasibility of the electrorefining process for the treatment of hull wastes. In the results of measuring the potential-current response using a stainless steel basket filled with oxidized Zircaloy-4 hull specimens, the oxidation peak of Zr appears to be at -0.7 to -0.8 V vs. Ag/AgCl, which is similar to that of fresh Zircaloy-4 hulls, while the oxidation current is found to be much smaller than that of fresh Zircaloy-4 hulls. These results are congruent with the outcome of current-time curves at -0.78 V and of measuring the change in the average weight and thickness after the electrochemical dissolution process. Although the oxide layer on the surface affects the uniformity and rate of dissolution by decreasing the conductivity of Zircaloy-4 hulls, electrochemical dissolution is considered to occur owing to the defect of the surface and phase properties of the Zr oxide layer.

본 논문에서는 염소화 반응을 통해 Zircaloy-4 (Zry-4) 피복관으로부터 Zr의 회수 연구를 수행하였다. 피복관의 Zr을 전부 ZrCl4로 전환시키기 위해, Zry-4 피복관을 380도에서 70 cc/min Cl2 + 70 cc/min Ar 기체를 이용하여 8시간 동안 반응시켰다. 피복관의 초기 무게는 51.7 g이었으나, 8 시간 반응 후에는 0.49 g만이 잔류물로 남아있는 것을 확인하였는데 이는 초기 무게의 0.95wt%에 해당하는 값이다. 반응 생성물의 무게는 121.7 g 이었으며, Zr의 순도는 99.80wt%였다. 주요 불순물로는 Fe (0.18wt%)와 Sn (0.02wt%)를 확인할 수 있었다. 실험 결과를 통해 확인한 Zr의 회수율은 96.95wt%였으며, 실험상손실은 2.34wt%로 확인되었다. 반응 잔류물의 관찰을 통해 염소화 반응이 길이 방향으로 주로 일어나며, 표면의 산화층이 반응 잔류물로 남는다는 것을 확인할 수 있었다. 본 연구를 통해 확인된 Zr의 높은 순도와 회수율은 염소화 공정이 폐 피복관 처리 방법으로 매우 유망한 기술임을 의미한다고 볼 수 있다.

The recovery of Zr from Zircaloy-4 (Zry-4) cladding hulls using a chlorination method was demonstrated for complete conversion of Zr into ZrCl4. A chlorination reaction was performed by reacting Zry-4 hulls for 8 h under a 70 cc/min Cl2 + 70 cc/min Ar flow at 380oC. The initial weight of the reactant (51.7 g) decreased to 0.49 g after 8 h of operation, which is only 0.95wt% of the initial weight. The weight of the total reaction products was 121.7 g with a high Zr purity of 99.80wt%. Fe and Sn were identified as major (0.18wt%) and minor (0.02wt%) impurities of the reaction products, respectively. It was also shown that Zr exhibited a high recovery ratio of 96.95wt% with a relatively small experimental loss of 2.34wt%. Observation of the reaction residues revealed that the chlorination reaction was dominant along the longitudinal direction, and surface oxide layers remained as reaction residues. The high purity and recovery ratio of Zr proposed the feasibility of the chlorination technique as an effective hull waste treatment method.

A T-800 (Co-Mo-Cr) coating material is fabricated using Co-Mo-Cr powder feedstock and laser cladding. The microstructure and melted Al erosion properties of the laser-cladded T-800 coating material are investigated. The Al erosion properties of the HVOF-sprayed MoB-CoCr and bulk T-800 material are also examined and compared with the laser-cladded T-800 coating material. Co and lave phases (Co2MoCr and Co3Mo2Si) are detected in both the lasercladded T-800 coating and the bulk T-800 materials. However, the sizes of the lave phases are measured as 7.9 μm and 60.6 μm for the laser-cladded and bulk T-800 materials, respectively. After the Al erosion tests, the erosion layer thicknesses of the three materials are measured as 91.50 μm (HVOF MoB-CoCr coating), 204.83 μm (laser cladded T- 800), and 226.33 μm (bulk T-800). In the HVOF MoB-CoCr coating material, coarse cracks and delamination of the coating layer are observed. On the other hand, no cracks or local delamination of the coating layer are detected in the laser T-800 material even after the Al erosion test. Based on the above results, the authors discuss the appropriate material and process that could replace conventional bulk T-800 materials used as molten Al pots.

Strain states of clad sheets consisted of AL3003 and SUS430 were studied by FEM simulation. Main simulation parameters include roll size, reduction, material properties, material temperature, and friction between roll and material (or friction between materials). To investigate the effect of friction on the evolution of strain states, the friction coefficient between roll and material (or fraction coefficients between materials) was varied. Components of strain rate, strain were compared according to the variation of friction coefficients. And strain states during cladding were compared with those induced by simple rolling process.

To evaluate transport-induced cladding embrittlement after interim-dry storage, ring compression tests were carried out at room temperature(RT) and 135 ℃. The ring compression test specimens were prepared by simulating the interim-dry storage conditions that include four peak cladding temperatures of 250, 300, 350 and 400 ℃, two tensile hoop stresses of 80 and 100 MPa, two hydrogen contents of 250 and 500 wt.ppm-H and a cooling rate of 0.3 ℃/min. Radial hydride fractions of the ring specimens vary depending on those interim-dry storage conditions. The RT compression tests generated lower offset strains than the 135 ℃ ones. In addition, the RT and 135 ℃ compression tests indicate that a higher peak cladding temperature, a higher tensile hoop stress and the lower hydrogen content generated a lower offset strain. Based on the embrittlement criterion of 2.0% offset strain, an allowable peak temperature during the interim-dry storage may be proposed to be less than 350 ℃ under the tensile hoop stress of 80 MPa at the terminal cool-down temperature of 135 ℃.