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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
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Nuclear Engineering and Technology
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Journal DOI :
Korean Nuclear Society
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Volume & Issues
Volume 28, Issue 6 - Dec 1996
Volume 28, Issue 5 - Oct 1996
Volume 28, Issue 4 - Aug 1996
Volume 28, Issue 3 - Jun 1996
Volume 28, Issue 2 - Apr 1996
Volume 28, Issue 1 - Feb 1996
Selecting the target year
The Leaching Behavior of Unirradiated
Pellets in Wet Storage and Disposal Conditions
Park, Geun-Il ; Lee, Hoo-Kun ;
Nuclear Engineering and Technology, volume 28, issue 4, 1996, Pages 349~358
The leaching behavior of uranium from unirradiated CANDU UO
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
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
appeared to be reached the steady rates in the range of 1~5
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
fuel in both the demineralized water ann boric acid may be controlled tv the surface oxidative.dissolution reaction of UO
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
in groundwater with temperature may be due to the local deposition of passivating uranyl phases on the surface.
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 ;
Nuclear Engineering and Technology, volume 28, issue 4, 1996, Pages 359~365
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.
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 ;
Nuclear Engineering and Technology, volume 28, issue 4, 1996, Pages 366~372
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
. The simulated spent fuel pellet is treated at 40
in air (oxidation), at 110
in air (high-temperature treatment), and at
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.
Structural Integrity Evaluation of CANFLEX Fuel Bundle by Hydraulic Drag Load
H. Y. Kang ; K. S. Sim ; Lee, J. H. ; Kim, T. H. ; J. S. Jun ; C. H. Chung ; Park, J. H. ; H. C. Suk ;
Nuclear Engineering and Technology, volume 28, issue 4, 1996, Pages 373~378
The CANFLEX fuel bundle has been developed by KAERI/AECL jointly to facilitate the use of various fuel cycles in CANDU-6 reactor. The structural analysis of the fuel bundles by hydraulic drag force is performed to evaluate the fuel integrity during the refuelling service. The present analysis method is newly developed for the structural integrity valuation by studying FEM modelling for the fuel bundles in a fuel channel. As compared the results of the mechanical strength test the displacement value of endplate given by analysis results shoo6 to be good agreement within 15% under the maximum design drag load. As the results of analysis, it is shown to keep the structural integrity of CANFLEX fuel bundles under hydraulic drag load during the refuelling service.
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 ;
Nuclear Engineering and Technology, volume 28, issue 4, 1996, Pages 379~389
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.
Development of Piping Analysis Procedure of a PWR Surge Line for Stratified Flow
Y. J. Yu ; J. H. Jheon ; K. S. Yoon ; Park, S. H. ; Kim, D. H. ;
Nuclear Engineering and Technology, volume 28, issue 4, 1996, Pages 390~396
Piping Systems are usually designed for thermal expansion loads based on uniform temperatures at each cross section. However, in lines with low flow rates such as surge lines and spray lines, large transverse temperature gradients have been observed, resulting in too types of additional thermal stresses : (1) local thermal gradient stresses which are independent of routing and supports and (2) gross bending stresses due to induced pipe curvature which are routing and support system dependent. This paper presents a simplified method for analyzing a PER surge line for stratified flow.
Signal Generation Due to Alpha Particle in Hydrogenated Amorphous Silicon Radiation Detectors
Kim, Ho-Kyung ; Gyuseong Cho ;
Nuclear Engineering and Technology, volume 28, issue 4, 1996, Pages 397~404
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 ons simulated based on a relevant non-uniform charge generation model. The simulation was peformed 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 total 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
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 ;
Nuclear Engineering and Technology, volume 28, issue 4, 1996, Pages 405~414
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-
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.
Optimum Design of the Wolsong Tritium Removal Facility
Ahn, Do-Hee ; Lee, Han-Soo ; Chung, Hong-Suk ; Song, Myung-Jae ; Son, Soon-Hwan ;
Nuclear Engineering and Technology, volume 28, issue 4, 1996, Pages 415~422
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.
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 ;
Nuclear Engineering and Technology, volume 28, issue 4, 1996, Pages 423~430
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.