Papers by Author: Kee Nam Song

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Authors: Kee Nam Song, S.D. Hong, H.Y. Park
Abstract: PHE (Process Heat Exchanger) is a key component for transferring the high-temperature heat generated from a VHTR (Very High Temperature Reactor) to a chemical reaction for massive production of hydrogen. Recently, Korea Atomic Energy Research Institute (KAERI) has manufactured a medium-scale PHE prototype made of Hastelloy-X of high-temperature alloy and a performance test on the PHE prototype is scheduled in a small-scale nitrogen gas loop established at KAERI. In this study, in order to evaluate the high-temperature structural integrity of the PHE prototype under the steady-state and trip conditions of the gas loop before the performance test on the PHE prototype, elastic and elastic-plastic structural analyses on the PHE prototype were carried out and the analyses results were compared each other.
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Authors: Kee Nam Song, Soo Sung Kim
Abstract: A spacer grid assembly, which is an interconnected array of slotted grid straps welded at the intersections to form an egg crate structure, is one of the core structural components of the nuclear fuel assemblies of a Pressurized light Water Reactor (PWR). The spacer grid assembly is structurally required to have enough buckling strength under lateral loads so that the nuclear fuel rods are maintained in a coolable geometry, and that control rods are able to be inserted. The ability of a spacer grid assembly to resist lateral loads is usually characterized in terms of its dynamic and static crush strengths. Since the crush strengths of a spacer grid assembly are known to depend on the weld qualities at the intersections of the slotted grid straps, high-tech welding methods, such as a TIG welding, LASER beam welding or Electron beam welding method, have been used recently in the nuclear fuel manufacturing fields. In this study, to meet the above requirements, two kinds of researches were carried out. First, by adjusting the LASER beam welding parameters, an optimum welding combination of the LASER beam welding parameters was obtained for welding a spacer grid assembly. Second, a new LASER beam welding technique was proposed to obtain a longer weld line and a smaller weld bead size by tilting the LASER beam. The buckling strength of the spacer grid welded by the new LASER beam welding technique was enhanced by up to 30 % when compared to that by the conventional LASER beam welding method.
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Authors: Kee Nam Song, Soo Sung Kim, Soo Bum Lee, Yong Wan Kim
Abstract: A spacer grid assembly, which is an interconnected array of slotted grid straps welded at the intersections to form an egg crate structure, is one of the core structural components for the nuclear fuel assemblies of a Pressurized light Water Reactor (PWR). The commercial spacer grid assembly is spot-welded at the crossing points of the intersections by a TIG welding, LASER beam welding or Electron beam welding method. In this study, a LASER beam welding apparatus and a method for an inner strap welding has been proposed to obtain a longer and finer weld line and a smaller weld bead size for a spacer grid assembly for a PWR fuel assembly. Also a rapid welding and excellent weld quality have been achieved by the proposed welding apparatus and method.
507
Authors: Kee Nam Song, S.D. Hong
Abstract: The IHX (Intermediate Heat Exchanger) of a VHTR (Very High Temperature Reactor) transfers 950°C heat generated from the VHTR to a hydrogen production plant. The Korea Atomic Energy Research Institute (KAERI) has manufactured a 70 kW class lab-scale PCHE (Printed Circuit Heat Exchanger) prototype made of SUS316L under consideration as a candidate. In this study, as a part of a structural integrity evaluation of the lab-scale PCHE prototype, an elastic structural analysis including structural analysis modeling and a thermal/elastic structural analysis was carried out under the test conditions of a helium experimental loop (HELP). In addition, a structural integrity evaluation considering the weld material properties was conducted.
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Authors: Kang Hee Lee, Heung Seok Kang, Kyung Ho Yoon, Kee Nam Song
Abstract: A 5x5 partial fuel assembly was used for a comparative design evaluation test of a newly developed spacer grid from a mechanical/hydraulic vibration aspect. Axial flow pattern along this rod bundle in the test was very complex due to the intermediate spacers and the mixing vane; Understanding of this flow field of a dynamic pressure is a preliminary step for a theoretical analysis of a vibratory behavior of a partial fuel assembly. Since a fluctuating pressure induced by the randomly-varying flow turbulence cannot be accurately predicted by an analysis alone, it has to be measured directly on the surface over the rod or in an accessible vicinity of the bundle. In this study, the fluctuating pressure acting on a partial fuel assembly with a spacer grid and a mixing vane was measured. The measured PSD showed different spectral features from the results of the literatures and had a series of periodic pulsations with sidebands over the specific frequency ranges; it is believed that the periodic components in the PSD have to do with the design of the spacer grid and the mixing vane. And, the exciting force function for the theoretical analysis of a partial fuel assembly with spacers and a mixing vane was estimated as a possible PSD form.
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Authors: Kee Nam Song, Kyung Ho Yoon, Jae Jun Lee, Kyung Jin Park
Abstract: The spacer grid assembly, which is an interconnected array of slotted grid straps and welded at the intersections to form an egg crate structure, is one of the main structural components of the nuclear fuel assemblies of a Pressurized light Water Reactor (PWR). The spacer grid assembly is structurally required to have enough crush strength under lateral loads due to lateral seismic accelerations, lateral Loss Of Coolant Accident (LOCA) blowdown forces, and shipping and handling loads so that the fuel rods are maintained within a coolable geometry, and that the control rods are able to be inserted. The ability of the spacer grid assembly to resist the lateral loads is usually characterized in terms of its dynamic and static crush strengths, which are acquired from the relevant tests. In this study, dynamic buckling tests and finite element analyses on spacer grid assembly specimens are carried out. As a result of the comparisons, the analysis results are in good agreement with the test results to within an 8 % difference range. Therefore, we could predict the crush strength of a spacer grid assembly in advance before performing the dynamic buckling test.
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Authors: Kee Nam Song, Eung Seon Kim, S.Y. Jang
Abstract: The IHX (Intermediate Heat Exchanger) of a VHTR (Very High Temperature Reactor) transfers 950°C heat generated from the VHTR to a hydrogen production plant. The Korea Atomic Energy Research Institute has manufactured a lab-scale Alloy 800HT PCHE (Printed Circuit Heat Exchanger) prototype under consideration as a candidate of the IHX (Intermediate Heat Exchanger). In this study, as a part of a structural integrity evaluation of the PCHE prototype, an elasto-plastic structural analysis including a thermal analysis was carried out under the designed test conditions of the PCHE prototype in a helium experimental loop (HELP). The analysis results were reflected to re-design the pipeline layout of HELP and to determine the actual test conditions of the PCHE prototype in the re-designed HELP in view of experimental safety.
280
Authors: Kee Nam Song
Abstract: PHE (Process Heat Exchanger) is a key component for transferring the high-temperature heat generated from a VHTR (Very High Temperature Reactor) to a chemical reaction for massive production of hydrogen. Korea Atomic Energy Research Institute has established a small-scale nitrogen gas loop for the performance test on VHTR components and has manufactured a small-scale PHE prototype made of Hastelloy-X of high-temperature alloy. A performance test on the PHE prototype is underway in the gas loop. In this study, in order to evaluate the high-temperature structural integrity of the PHE prototype under the test condition of the gas loop, structural analysis on the PHE prototype was carried out to gauge the stiffness of pipelines connected to the PHE prototype in the gas loop.
465
Authors: Kee Nam Song, Kyung Ho Yoon, Jae Jun Lee, Kyung Jin Park
Abstract: The spacer grid assembly, which is an interconnected array of slotted grid straps and welded at the intersections to form an egg crate structure, is one of the main structural components of the nuclear fuel assembly of a Pressurized light Water Reactor (PWR). The spacer grid assembly supports and aligns the fuel rods, guides the fuel assemblies past each other during handling and, if needed, sustains lateral seismic loads. The ability of the spacer grid assembly to resist the lateral loads is usually characterized in terms of its dynamic and static crush strengths, which are acquired from tests. In this study, dynamic buckling tests and finite element analyses on spacer grid assembly specimens are carried out. Comparisons show that the analysis results are in good agreement with the test results to within an 8 % difference range. Therefore, we could predict the crush strength of a spacer grid assembly in advance before performing the dynamic buckling test.
1555
Authors: Kee Nam Song, Kyung Ho Yoon, Heung Seok Kang, Kang Hee Lee
Abstract: A spacer grid assembly is one of the main structural components of the fuel assemblies of Pressurized light Water Reactors. The spacer grid assembly is structurally required to have enough buckling strength under various kinds of lateral loads acting on the fuel assembly so as to keep the fuel assembly straight. The structural performance of the spacer grid assembly is characterized in terms of its dynamic crush strength, which is usually acquired from the test. In this study, a dynamic buckling test and a finite element analysis on the KAERI designed spacer grid assembly are carried out. The pendulum-type tester was used in the test. In the finite element analysis, we proposed an analysis methodology that could predict the dynamic failure behavior of the spacer grid assembly using a commercial finite element code ABAQUS/explicit with appropriate boundary conditions. As a result of the comparisons, the analysis result is in good agreement with the test result to within a 10% difference range. Therefore, we could predict the dynamic behaviors of a spacer grid assembly in advance before performing the dynamic buckling test.
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