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T : 목차정보

Journal of the Korean Nuclear Society = 원자력학회지 10건

  1. [국내논문]   The Leaching Behavior of Unirradiated $UO_2$ Pellets in Wet Storage and Disposal Conditions  

    Park, Geun-Il ; Lee, Hoo-Kun
    Journal of the Korean Nuclear Society = 원자력학회지 v.28 no.4 ,pp. 349 - 358 , 1996 , 0372-7327 ,

    초록

    The leaching behavior of uranium from unirradiated CANDU UO $_2$ fuel pellet in the spent fuel wet storage and disposal conditions has been investigated. A modified IAEA leach test method was used, and then the extent of leaching was monitored by analysis for uranium in the leachant. The leach test has been performed in various leachants(demineralized water and boric acid solution at pH=6, synthetic granite groundwater) for a long-term period of 5.4 years, and the effect of temperature on the leach rate of uranium has been analyzed. The leach rates of uranium at $25^{\circ}C$ were dependent on the leachants. Over initial 100 days of leach periods, the leach rate in groundwater was the highest in three leachants and no significant differences of leach rates ore observed in the demineralized oater and boric acid solution. But these leach rates in three leachants around 2,000 days at $25^{\circ}C$ appeared to be reached the steady rates in the range of 1~5 $\times$ 10 $^{-8}$ g/ $\textrm{cm}^2$ day. The leach rate of uranium in groundwater shooed to be independent of the temperature, but those in both demineralized water and boric acid solution increased with temperature. These results show that the leaching behavior of uranium from UO $_2$ fuel in both the demineralized water ann boric acid may be controlled tv the surface oxidative.dissolution reaction of UO $_2$ and the leach rate of uranium in groundwater at room temperature could mainly be controlled by the complex reaction of dissolved uranyl ions with carbonate ions and no variation of leach rate of UO $_2$ in groundwater with temperature may be due to the local deposition of passivating uranyl phases on the surface.

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  2. [국내논문]   Feasibility Study on KSNP Adaption of French Digital Protection System  

    Koo, Jun-Mo ; Lee, Young-Ryul ; Jung, Ho-Chang ; Chang, Ik-Ho ; Han, Jai-Bok
    Journal of the Korean Nuclear Society = 원자력학회지 v.28 no.4 ,pp. 359 - 365 , 1996 , 0372-7327 ,

    초록

    Upgrade of nuclear power plant I&C systems by using digital technology has been implemented to overcome the obsolescence of existing equipment and improve plant availability in many advanced countries. For upgrade of the Plant Protection System(PPS) based on conventional analog technology in the UCN 3&4 and YGN 5&6, French modernized Digital Integrated Protection System(DIPS) with proven technology is reviewed and evaluated for the adaptability into PPS. This paper contains the results of feasibility study for the design of digital PPS using French DIPS technology. Based on the results of evaluations, the system architecture of digital PPS is designed and described.

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  3. [국내논문]   Effect of High Temperature Treatment and Subsequent Oxidation anil Reduction on Powder Property of Simulated Spent Fuel  

    Song, Kun-Woo ; Kim, Young-Ho ; Kim, Bong-Goo ; Lee, Jung-Won ; Kim, Han-Soo ; Yang, Myung-Seung ; Park, Hyun-Soo
    Journal of the Korean Nuclear Society = 원자력학회지 v.28 no.4 ,pp. 366 - 372 , 1996 , 0372-7327 ,

    초록

    The simulated spent PWR fuel pellet which is corresponding to the turnup of 33,000 MWD/MTU is prepared by adding 11 fission-product elements to UO $_2$ . The simulated spent fuel pellet is treated at 40 $0^{\circ}C$ in air (oxidation), at 110 $0^{\circ}C$ in air (high-temperature treatment), and at $600^{\circ}C$ in hydrogen (reduction). The product is treated through additional addition and reduction up to 3 cycles. Pellets are completely pulverized by the first oxidation, and the high-temperature treatment causes particle and crystallite to grow and surface to be smooth, and thus particle size significantly increases and surface area decreases. The reduction following the high-temperature treatment decreases much the particle size by means of the formation of intercrystalline cracks. The particle size decreases a little during the second oxidation and reduction cycle and then remains nearly constant during the third and fourth cycles. Surface area of pounder increases progressively with the repetition of oxidation and reduction cycles, mainly due to the formation of Surface cracks. The degradation of surface area resulting from high-temperature treatment is restored by too subsequent resulting oxidation and reduction cycles.

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  4. [국내논문]   Structural Integrity Evaluation of CANFLEX Fuel Bundle by Hydraulic Drag Load  

    Kang, H. Y. ; Sim, K. S. ; Lee, J. H. ; Kim, T. H. ; Jun, J. S. ; Chung, C. H. ; Park, J. H. ; Suk, H. C.
    Journal of the Korean Nuclear Society = 원자력학회지 v.28 no.4 ,pp. 373 - 378 , 1996 , 0372-7327 ,

    초록

    The simulated spent PWR fuel pellet which is corresponding to the turnup of 33,000 MWD/MTU is prepared by adding 11 fission-product elements to UO $_2$ . The simulated spent fuel pellet is treated at 40 $0^{\circ}C$ in air (oxidation), at 110 $0^{\circ}C$ in air (high-temperature treatment), and at $600^{\circ}C$ in hydrogen (reduction). The product is treated through additional addition and reduction up to 3 cycles. Pellets are completely pulverized by the first oxidation, and the high-temperature treatment causes particle and crystallite to grow and surface to be smooth, and thus particle size significantly increases and surface area decreases. The reduction following the high-temperature treatment decreases much the particle size by means of the formation of intercrystalline cracks. The particle size decreases a little during the second oxidation and reduction cycle and then remains nearly constant during the third and fourth cycles. Surface area of pounder increases progressively with the repetition of oxidation and reduction cycles, mainly due to the formation of Surface cracks. The degradation of surface area resulting from high-temperature treatment is restored by too subsequent resulting oxidation and reduction cycles.

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  5. [국내논문]   Interfacial Wave Characteristics for Countercurrent Stratified Air-Water Flow in a Horizontal Pipe  

    Chung, Heung-June ; Chun, Se-Young ; Chung, Moon-Ki ; No, Hee-Cheon
    Journal of the Korean Nuclear Society = 원자력학회지 v.28 no.4 ,pp. 379 - 389 , 1996 , 0372-7327 ,

    초록

    To experimentally investigate the several wave patterns for the horizontal countercurrent stratified air-water flow, a series of systematic experimental studies have been performed. The experiments are carried out in a horizontal pipe with 4m in length and 102mm in inner diameter. The oater and air superficial velocities vary from 0.0004 to 0.0204 and from 0 to 6m/s, respectively. The instantaneous water thickness is measured by parallel-wire conductance probes, and the wave field is recorded by high speed video camera. Also, to evaluate the wave effect on interfacial friction factor, the pressure drop is measured. Statistical data anal)sis is accomplished in order to obtain the fundamental wave parameters such as un amplitude, length and velocity, and spatial growth factor. By using these statistical parameters, the wave regime boundaries can be verified.

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  6. [국내논문]   Development of Piping Analysis Procedure of a PWR Surge Line for Stratified Flow  

    Yu, Y. J. ; Jheon, J. H. ; Yoon, K. S. ; Park, S. H. ; Kim, D. H.
    Journal of the Korean Nuclear Society = 원자력학회지 v.28 no.4 ,pp. 390 - 396 , 1996 , 0372-7327 ,

    초록

    To experimentally investigate the several wave patterns for the horizontal countercurrent stratified air-water flow, a series of systematic experimental studies have been performed. The experiments are carried out in a horizontal pipe with 4m in length and 102mm in inner diameter. The oater and air superficial velocities vary from 0.0004 to 0.0204 and from 0 to 6m/s, respectively. The instantaneous water thickness is measured by parallel-wire conductance probes, and the wave field is recorded by high speed video camera. Also, to evaluate the wave effect on interfacial friction factor, the pressure drop is measured. Statistical data anal)sis is accomplished in order to obtain the fundamental wave parameters such as un amplitude, length and velocity, and spatial growth factor. By using these statistical parameters, the wave regime boundaries can be verified.

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  7. [국내논문]   Signal Generation due to Alpha Particle in Hydrogenated Amorphous Silicon Radiation Detectors  

    Kim, Ho Kyung ; Cho, G.
    Journal of the Korean Nuclear Society = 원자력학회지 v.28 no.4 ,pp. 397 - 404 , 1996 , 0372-7327 ,

    초록

    The hydrogenated amorphous silicon (a-Si:H) holds good promise for radiation detection from its inherent merits over crystalline counterpart. For the application to alpha spectroscopy, the induced charge collection in a-Si:H pin detector diodes was simulated based on a relevant non-uniform charge generation model. The simulation was performed for the initial energy and the range of incident alpha particles, detector thickness and the operational parameters such as the applied reverse bias voltage and shaping time. From the simulation, the toal charge collection was strongly affected by hole collection as expected. To get a reasonable signal generation, therefore, the hole collection should be seriously considered for detector operational parameters such as shaping time and reverse voltage etc. For the spectroscopy of alpha particle from common alpha sources, the amorphous silicon should have about 70 $\mu$ m thickness.

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  8. [국내논문]   Numerical Analysis for Unsteady Thermal Stratified Turbulent Flow in a Horizontal Circular Cylinder  

    Ahn, Jang-Sun ; Ko, Yong-Sang ; Park, Byeong-Ho ; Youm, Hag-Ki ; Park, Man-Heung
    Journal of the Korean Nuclear Society = 원자력학회지 v.28 no.4 ,pp. 405 - 414 , 1996 , 0372-7327 ,

    초록

    In this paper, the unsteady 2-dimensional turbulent flow model for thermal stratification in a pressurizer surge line of PWR plant is proposed to numerically investigate the heat transfer and flow characteristics. The turbulence model is adapted to the low Reynolds number K- $\varepsilon$ model (Davidson model). The dimensionless governing equations are solved by using the SIMPLE (Semi-Implicit Method for Pressure Linked Equations) algorithm. The results are compared with simulated experimental results of TEMR Test. The time-dependent temperature profiles in the fluid and pipe nil are shown with the thermal stratification occurring in the horizontal section of the pipe. The corresponding thermal stresses are also presented. The numerical result for thermal stratification by the outsurge during heatup operation of PWR shows that the maximum dimensionless temperature difference is about 0.83 between hot and cold sections of pipe well and the maximum thermal stress is calculated about 322MPa at the dimensionless time 28.5 under given conditions.

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  9. [국내논문]   Optimum Design of the Wolsong Tritium Removal Facility  

    Ahn, Do-Hee ; Lee, Han-Soo ; Chung, Hong-Suk ; Song, Myung-Jae ; Son, Soon-Hwan
    Journal of the Korean Nuclear Society = 원자력학회지 v.28 no.4 ,pp. 415 - 422 , 1996 , 0372-7327 ,

    초록

    Tritium removal from tritiated heavy water in a PHWR is the most effective way in reducing workers' internal dose and radioactivity emissions from Wolsong NPP. The optimum design of the Wolsong TRF (Tritium Removal Facility) was carried out using an approximate short-cut method with an assumption that the TRF, designed to extract 8 MCi per year of elemental tritium from a heavy oater feedstream, uses Liquid Phase Catalytic Exchange (LPCE) front-end process and Cryogenic Distillation (CD) process.

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  10. [국내논문]   Design of Improved Detection Instrumentation for the Annulus Gas System for Wolsong 2  

    Kim, Seog-Nam ; Koo, Jun-Mo ; Chang, Ik-Ho ; Jung, Ho-Chang ; Han, Sang-Joon
    Journal of the Korean Nuclear Society = 원자력학회지 v.28 no.4 ,pp. 423 - 430 , 1996 , 0372-7327 ,

    초록

    The improved and advanced Annulus Gas System(AGS) has been developed for Wolsong 2 to satisfy the requirements of the regulatory body. The Atomic Energy Control Board(AECB) required a shorter detection time following a small leak from a pressure tube and/or calandria tube. This paper describes licensing requirements, functional requirements and detail design description for the AGS. The Wolsong unit No. 1 AGS was designed to operate as a stagnant system normally requiring only pressure regulation and having provisions for purging. no improved AGS involves the adoption of gas recirculation in AGS, duplication of dew point indicators with additional instrumentation and sampling provisions to prompt operator action. The improved system operates in the recirculation mode with continuous dew point measurement for leak detection. An AGS with improved detection instrumentation is provided.

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