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Lee Dong Uk,Lee Byoung Oon,Kim Young Gyun,Lee Ki Bog,Jang Jin Wook Korean Nuclear Society 2003 Nuclear Engineering and Technology Vol.35 No.4
Material properties such as coolant specific heat, film heat transfer coefficient, cladding thermal conductivity, surface diffusion coefficient of the multi-bubble are improved in MACSIS-Mod1. The axial power and flux profile module was also incorporated with irradiation history. The performance and feasibility of the updated driver fuel pin have been analyzed for nominal parameters based on the conceptual design for the KALIMER breakeven core by MACSIS-MOD1 code. The fuel slug centerline temperature takes the maximum at 700mm from the bottom of the slug in spite of the nearly symmetric axial power distribution. The cladding mid-wall and coolant temperatures take the maximum at the top of the pin. Temperature of the fuel slug surface over the entire irradiation life is much lower than the fuel-clad eutectic reaction temperature. The fission gas release of the driver fuel pin at the end of life is predicted to be $68.61\%$ and plenum pressure is too low to cause cladding yielding. The probability that the fuel pin would fail is estimated to be much less than that allowed in the design criteria. The maximum radial deformation of the fuel pin is $1.93\%$, satisfying the preliminary design criterion ($3\%$) for fuel pin deformation. Therefore the conceptual design parameters of the driver fuel pin for the KALIMER breakeven core are expected to satisfy the preliminary criteria on temperature, fluence limit, deformation limit etc.
Lee,Chul,Kuk,Myung-Ho,Lee,Byoung-Oon,Jae,Won-Mok 韓陽大學校 環境科學硏究所 1986 環境科學論文集 Vol.7 No.-
플라스틱 비적 검출기에 대한 이온화율의 함수로써의 침식율을 측정하는 방법을 설명하였다. 고체상태의 비적 검출기는 폴리아마이드를 사용했다. 비적을 형성하는 중하전 이온으로써 우라늄-238의 핵분열 생성물을 이용하였다. 직각으로 입사된 입자의 경우만 비적을 측정하였다. 침식율의 변화측정과 입자확인을 위해 비적의 반경을 측정하였다. 오랜 침식기간을 거친 뒤에 문턱영역에서의 반응곡선을 결정하였다. 반응곡선은 V=1+?? 라는 관계식으로 나타내며 β는 약 2.67이었다. 이 반응곡선에 의하여 중원소를 찾는데 도움이 될 것이다. This study describes a method for measuring the variation of the etching rate as a function of the ionization rate for polyamide nuclear detector. Polyamide sheets were used as solid state nuclear track detector. The U-238 fission fragments are used as energetic heavy ions for the track formation The evolution of etched tracks is considered only for the case of normally incident particles. The track radii are measured for the determination of the differential track etch rate and for particle identification. Response curve (etching rate ratio, V versus restricted energyloss, REL) of polyamide sheet was determined in the threshold region after a long etching period. It was found that the V(REL) curve can be well described by the relation V= 1+αREL?, where power index β is 2.67. With the response curve, it may be helpful to search heavy elements.
Thermo-Mechanical Analysis for Metallic Fuel Pin under Transient Condition
Lee, Dong-Uk,Lee, Byoung-Oon,Kim, Yeong-Il,Hahn, Dohee The Korean Society for Energy 2004 에너지공학 Vol.13 No.3
Computational models for analyzing the in-reactor behavior of metallic fuel pins under transient conditions in liquid-metal reactors are developed and implemented in the TRAMAC (TRAnsient thermo-Mechanical Analysis Code) for a metal fuel rod under transient operation conditions. Not only the basic models for a fuel rod performance but also some sub-models used for transient condition are installed in TRAMAC. Among the models, a fission gas release model, which takes the multi-bubble size distribution into account to characterize the lenticular bubble shape and the saturation condition on the grain boundary and the cladding deformation model have been developed based mainly on the existing models in the MAC-SIS code. Finally, cladding strains are calculated from the amount of thermal creep, irradiation creep, and irradiation swelling. The cladding strain model in TRAMAC predicts well the absolute magnitudes and gen-eral trends of their predictions compared with those of experimental data. TRAMAC results for the FH-1,2,6 pins are more conservative than experimental data and relatively reasonable than those of FPIN2 code. From the calculation results of TRAMAC, it is apparent that the code is capable of predicting fission gas release, and cladding deformation for LMR metal fuel finder transient operation conditions. The results show that in general, the predictions of TRAMAC agree well with the available irradiation data.
Kang Suk-Ku,Moon Byoung-Ho,Lee Jeang-Oon,Goh Hyun-Gwan Korean Chemical Society 1985 Bulletin of the Korean Chemical Society Vol.6 No.4
(Z)-13-Octadecen-1-yl acetate, the pheromone mimic of the Rice Leaf Folder Moth, Cnaphalocrosis medinalis, was synthesized from 1,13-tridecanediol in three steps. Monoacetylation of 1,13-tridecanediol followed by PCC oxidation gave 13-acetoxytridecan-1-al. Wittig olefination of the 13-acetoxytridecan-1-al with pentylidenetriphenylphosphonium ylide afforded (Z)-13-octadecen-1-yl acetate, the pheromone mimic of the Rice Leaf Folder.
Reaction between a Rare Earth Element and 9Cr-2W Steel
Jun Hwan Kim,Jong Hyuk Baek,Byoung Oon Lee,Chan Bock Lee,윤영수 대한금속·재료학회 2011 METALS AND MATERIALS International Vol.17 No.4
We analyzed the reaction between a rare earth element and ferritic-martensitic stainless steel in order to evaluate the role of the rare earth element in the fuel cladding chemical interaction (FCCI). A diffusion couple test between Misch metal (70Ce-30La) and 9Cr-2W (Gr.92) steel at both 660 °C and 800 °C was conducted,and a microstructural analysis was carried out. The result showed that Fe in the Gr.92 material and Ce in the Misch metal mainly diffused and reacted to form intermetallic compounds, namely Fe2Ce and Fe17Ce phases, above 660 °C, whereas La hardly diffused or reacted in the Gr.92 material. In the specimen tested at 660 °C, the Fe diffused outside of the clad interface so that Cr-rich precipitated beneath the clad interface. In the specimen tested at 800 °C, a local reaction caused by the eutectic transformation of the (Fe,Cr)_17Ce phase resulted in a local penetration across the clad.
Interaction behavior between binary xCe-yNd alloy and HT9
Kim, Jun Hwan,Cheon, Jin Sik,Lee, Byoung Oon,Kim, June Hyung Elsevier 2016 Journal of nuclear materials Vol.479 No.-
<P><B>Abstract</B></P> <P>Studies were carried out to investigate the role of Ce and Nd, contained inside metal fuel during reactor operation, and their effect on the Fuel-Cladding Chemical Interaction (FCCI) phenomenon, which limits fuel performance in the Sodium-cooled Fast Reactor (SFR). Binary model alloys of xCe-yNd were manufactured, and then diffusion couple tests with HT9 (12Cr-1MoWV) ferritic-martensitic cladding material were carried out at a temperature of 660 °C for up to 25 h. The results showed that both Ce and Nd reacted with Fe in the cladding material to form an interaction layer. Analysis of the microstructure and reaction kinetics revealed that Fe in the cladding material rapidly migrates into Ce to form eutectic reaction, leaving a Fe depleted zone, in which Ce substitutes. In the case of Nd element, a typical solid-solid diffusion process governed to form a Fe<SUB>17</SUB>Nd<SUB>2</SUB> type intermetallic compound. Synergism between Ce and Nd occurred so that the reaction thickness was increased, reaching the maximum reaction thickness in the case of the xCe-yNd alloy, whose composition was nearly 1:1.</P>