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Chung, Heung June; Chun, Se Young; Kim, Bok Deuk; Chung, Moon Ki; No, Hee Cheon
Proceedings of the KNS autumn meeting1994
Proceedings of the KNS autumn meeting1994
AbstractAbstract
[en] Several interfacial wave patterns were identified for countercurrent stratified air-water two-phase flow in a horizontal pipe. The instantaneous water heights were measured by using parallel-wire conductance probes. And the fundamental wave characteristics, mean wave velocities, wave number, wave amplitude were characterized by statistical method
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Korean Nuclear Society, Taejon (Korea, Republic of); 958 p; 1994; p. 291-296; 1994 autumn meeting of the KNS; Seoul (Korea, Republic of); 29 Oct 1994; Available from KNS, Taejon (KR); 3 refs, 6 figs
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[en] An analytical work on the void wave propagations is performed from the linear stability analysis of the two-fluid model. Several wave propagation properties are derived from the dispersion relation. Based upon the concept of 'most unstable waves', the wave propagation properties, which is independent of the wave number, are derived
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Korean Nuclear Society, Taejon (Korea, Republic of); 958 p; 1994; p. 265-270; 1994 autumn meeting of the KNS; Seoul (Korea, Republic of); 29 Oct 1994; Available from KNS, Taejon (KR); 8 refs, 4 figs
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[en] The effects of the major parameters such as pipe length, pipe diameter, water subcooling, and system pressure on the critical flow rates of both the upper and the lower boundaries have been examined. The critical flow rates are sensitive to pipe diameter, pipe length and system pressure, but not to the subcooling of water over the practical operating ranges. The condensation-induced waterhammer region boundary maps have been presented to be used in the system design and operation to avoid the condensation-induced waterhammer incidents in the long horizontal pipe systems
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Korean Nuclear Society, Taejon (Korea, Republic of); 958 p; 1994; p. 305-311; 1994 autumn meeting of the KNS; Seoul (Korea, Republic of); 29 Oct 1994; Available from KNS, Taejon (KR); 12 refs, 4 figs
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AbstractAbstract
[en] An equipment with the size in linear scale of one tenth of the steam generators for the Westinghouse 900 MWe nuclear power plants is utilized to study the swell and shrink effects of the water level. The cyclic feature of the level swell and shrink occurring in the low power operation of the nuclear power plants is realized by a sequence of the steam dump valve control. Analyzing the results of the experiments, we found that a simple mathematical model, based on the amount of steam generated during the depressurization, provides a good approximation for predicting the swell and shrink of the measured water level
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Korean Nuclear Society, Taejon (Korea, Republic of); 958 p; 1994; p. 223-228; 1994 autumn meeting of the KNS; Seoul (Korea, Republic of); 29 Oct 1994; Available from KNS, Taejon (KR); 4 refs, 3 figs
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[en] Recently a number of severe fuel degradation events, seemingly due to internal secondary hydriding, have been reported. These fuel failures initiated an international joint research. In this paper fundamental aspects of, influential factors to, and current issues on zircaloy cladding hydriding are discussed
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Korean Nuclear Society, Taejon (Korea, Republic of); 958 p; 1994; p. 535-542; 1994 autumn meeting of the KNS; Seoul (Korea, Republic of); 29 Oct 1994; Available from KNS, Taejon (KR); 11 refs, 4 figs
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[en] We solve the neutron diffusion equation by Wavelet Galerkin(WG) method using orthonormal bases of compactly supported wavelets that are constructed by Daubechies. The solution is expanded in Daubechies scaling functions. The method is applied to several test problems in reactor physics. With increasing Daubechies order and dilation order, the accuracy of the solution improves. The WG method appears to be good at describing strongly heterogeneous problems, but it requires further study to reduce computing time
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Korean Nuclear Society, Taejon (Korea, Republic of); 958 p; 1994; p. 79-84; 1994 autumn meeting of the KNS; Seoul (Korea, Republic of); 29 Oct 1994; Available from KNS, Taejon (KR); 4 refs, 9 figs
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[en] This paper explores guidelines for safety and licensing requirements for the next generation CANDU in Korea. The requirements are discussed in the context of the CANDU 9, based on the Bruce/Darlington design but incorporating safety improvements. The paper concludes that the CANDU 9 will meet the international licensing requirements currently being developed for advanced reactor designs, and that the guidelines proposed are therefore a reasonable starting point for discussions with the Korean regulatory bodies
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Korean Nuclear Society, Taejon (Korea, Republic of); 958 p; 1994; p. 513-520; 1994 autumn meeting of the KNS; Seoul (Korea, Republic of); 29 Oct 1994; Available from KNS, Taejon (KR); 3 refs, 1 tab
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[en] A mathematical model for fatigue crack propagation under the influence of residual stress has been developed which is remarkably applicable to the prediction of any kind of fatigue behaviors under residual stress fields. Since the model describes the interaction of microstructure, mechanism, and mechanics, fatigue crack propagation can be predicted in terms of readily available mechanical or physical properties of the structural material. It is also shown that an excellent correlation can be found between the present model based on the energy balance concept and experimental data, provided that residual stress distribution, process zone size, and tearing modulus are given. The present model shows that increase in compressive residual stresses ahead of crack tip can profoundly reduces catastrophic failures of the important machine and structural parts of reactor components
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Korean Nuclear Society, Taejon (Korea, Republic of); 958 p; 1994; p. 613-621; 1994 autumn meeting of the KNS; Seoul (Korea, Republic of); 29 Oct 1994; Available from KNS, Taejon (KR); 9 refs, 4 figs
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AbstractAbstract
[en] The diversion cross-flow between the square-arrayed nuclear subchannels has been analyzed with the low-Reynolds number k-ε turbulence model. Anisotropic algebraic Reynolds stress model was used to accurately predict the secondary flow. The code developed in this study is formulated with the finite element method and has been verified successfully through comparison with available experimental data. A correlation of the lateral pressure loss coefficients has been established on the basis of the numerical results for the diversion cross-flow. This correlation is formed as a function of the ratio of the lateral flow velocity to the donor subchannel axial velocity, the Reynolds number based on the recipient subchannel axial velocity and pitch-to-diameter
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Korean Nuclear Society, Taejon (Korea, Republic of); 958 p; 1994; p. 271-276; 1994 autumn meeting of the KNS; Seoul (Korea, Republic of); 29 Oct 1994; Available from KNS, Taejon (KR); 6 refs, 4 figs
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Jeong, Jae Jun; Chung, Young Jong; Chang, Won Pyo; Yoo, Kun Joong
Proceedings of the KNS autumn meeting1994
Proceedings of the KNS autumn meeting1994
AbstractAbstract
[en] In the present study realistic PCT has been evaluated under LBLOCA using the best estimated codes with the limiting input variables, in order to freeze input for Advanced Design Features(ADF) function evaluation. Since the NSSS is not known at this time, YGN 3/4 has been chosen as reference plant. From this approach lower PCT by 244 K has been obtained comparing that of FSAR, however, the overall ECCS capabilities would rather be evaluated after conduction of SBLOCA analysis
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Korean Nuclear Society, Taejon (Korea, Republic of); 958 p; 1994; p. 417-424; 1994 autumn meeting of the KNS; Seoul (Korea, Republic of); 29 Oct 1994; Available from KNS, Taejon (KR); 6 refs, 9 figs, 2 tabs
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