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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
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Nuclear Engineering and Technology
Journal Basic Information
Journal DOI :
Korean Nuclear Society
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Volume & Issues
Volume 35, Issue 6 - Dec 2003
Volume 35, Issue 5 - Oct 2003
Volume 35, Issue 4 - Aug 2003
Volume 35, Issue 3 - Jun 2003
Volume 35, Issue 2 - Apr 2003
Volume 35, Issue 1 - Feb 2003
Selecting the target year
Simulation of Multiple Steam Generator Tube Rupture (SGTR) Event Scenario
Seul Kwang Won ; Bang Young Seok ; Kim In Goo ; Yonomoto Taisuke ; Anoda Yoshinari ;
Nuclear Engineering and Technology, volume 35, issue 3, 2003, Pages 179~190
The multiple steam generator tube rupture (SGTR) event scenario with available safety systems was experimentally and analytically evaluated. The experiment was conducted on the large scaled test facility to simulate the multiple SGTR event and investigate the effectiveness of operator actions. As a result, it indicated that the opening of pressurizer power operated relief valve was significantly effective in quickly terminating the primary-to-secondary break flow even for the 6.5 tubes rupture. In the analysis, the recent version of RELAP5 code was assessed with the test data. It indicated that the calculations agreed well with the measured data and that the plant responses such as the water level and relief valve cycling in the damaged steam generator were reasonably predicted. Finally, sensitivity study on the number of ruptured tubes up to 10 tubes was performed to investigate the coolant release into atmosphere. It indicated that the integrated steam mass released was not significantly varied with the number of ruptured tubes although the damaged steam generator was overfilled for more than 3 tubes rupture. These findings are expected to provide useful information in understanding and evaluating the plant ability to mitigate the consequence of multiple SGTR event.
Effects of the Width and Location of a Flow Disturbing Plate on Pool Boiling Heat Transfer on a Vertical Tube
Kang Myeong-Gie ;
Nuclear Engineering and Technology, volume 35, issue 3, 2003, Pages 191~205
Effects of the width and location of a flow disturbing circular plate, installed at a vertical tube surface, on nucleate pool boiling heat transfer of water at atmospheric pressure have been investigated experimentally. Through the tests, changes in the degree of intensity of liquid agitation have been analyzed. The plate changes the fluid flow around the tube as well as heat transfer coefficients on the tube surface. It is identified that the plate width changes the rate of the circulating flow whereas its location changes the growth of the active agitating flow. Moreover, the flow chugging was observed at the downside of the plate.
Delayed Hydride Cracking Velocity of CANDU Zr-2.5Nb Tubes in High Temperature Water
Kim Young Suk ; Cho Sun Young ; Im Kyung Soo ; Cheong Yong Moo ; Kim Sung Soo ;
Nuclear Engineering and Technology, volume 35, issue 3, 2003, Pages 206~213
This study focuses on an understanding of the environmental effect on delayed hydride cracking velocity (DHCV) of CANDU Zr-2.5Nb tubes. To simulate DHC susceptibility of the Zr-2.5Nb tubes in reactor operating conditions, DHC tests were successfully carried out in pressurized water at 180 and
using a self-designed autoclave for the first time. Using 17 mm compact tension specimens electorlytically charged to 34 and 60 ppm H, 3 to 7 DHCV data were determined in water at both temperatures and compared to those determined in air that were already confirmed to be valid through a round robin test on DHCV of Zr-2.5Nb tubes sponsored by a IAEA coordinated research program. The pressurized water environment has little effect on DHCV of Zr-2.5Nb tube in water at both temperatures even though DHCV is slightly lower in water than that in air. The lower DHCV of the Zr-2.5Nb tube during short-term tests is discussed in viewpoint of the cooling rate from the peak temperature to the test temperature.
Development of a Teleoperated Manipulator System for Remote Handling of Spent Fuel Bundles
Ahn Sung Ho ; Jin Jae Hyun ; Yoon Ji Sup ;
Nuclear Engineering and Technology, volume 35, issue 3, 2003, Pages 214~225
A teleoperated manipulator system has been developed for remote handling of the spent fuel bundles. A heavy-duty power manipulator with high reduction ratio joints is used for the slave manipulator in the developed system since the handling tasks of the spent fuel bundles need power. Also, the universal type master manipulator, which has force reflecting capability, is used for precise remote manipulation. The power manipulators so frequently occur the control input saturation that the precise control performances are not achieved due to the windup phenomenon. An advanced bilateral control scheme compensating for the saturation is applied to the teleoperated manipulator system. The validity of the developed system is verified by the grid cutting and fuel transportation tasks from the mockup spent fuel bundle.
Discharge Characteristics of a KSTAR NBI Ion Source
Chang Doo-Hee ; Oh Byung-Hoon ;
Nuclear Engineering and Technology, volume 35, issue 3, 2003, Pages 226~233
The discharge characteristics of a prototype ion source was investigated, which was developed and upgraded for the NBI (Neutral Beam Injection) heating system of KSTAR (Korea Superconducting Tokamak Advanced Research). The ion source was designed for the arc discharge of magnetic bucket chamber with multi-pole cusp fields. The ion source was discharged by the emission-limited mode with the control of filament heating voltage. The maximum ion density was 4 times larger than the previous discharge controlled by a space-charge-limited mode with fully heated filament. The plasma (ion) density and arc current were proportional to the filament voltage, but the discharge efficiency was inversely proportional to the operating pressure of hydrogen gas. The maximum ion density and arc current were obtained with constant arc voltage (
and 1200 A, respectively. The estimated maximum beam current was about 35 A, extracted by the accelerating voltage of 80kV.
Experimental and Simulated Efficiency of a HPGe Detector in the Energy Range of
Park Chang Su ; Sun Gwang Min ; Choi H.D. ;
Nuclear Engineering and Technology, volume 35, issue 3, 2003, Pages 234~242
The full energy peak efficiency of a hyper pure germanium (HPGe) detector was calibrated in a wide energy range from 0.06 to 11 MeV. Both the experimental technique and the Monte Carlo method were used for the efficiency calibration. The measurement was performed using the standard radioisotopes in the low energy region of
keV, which was further extended up to 11 MeV by using the
reactions. The GEANT Monte Carlo code was used for efficiency calculation. The calculated efficiency had the same dependency on the r-ray energy with the measurement, and the discrepancy between the calculation and the measurement was minimized by fine-tuning of the detector geometry. From the calculated result, the efficiency curve of the HPGe detector was reliably determined particularly in the high energy region above several MeV, where the number of measured efficiency points is relatively small despite the wide energy region. The calculated efficiency agreed with the measurement within about
. In addition to the efficiency calculation, the origin of the local minimum near 600 keV on the efficiency curve was analyzed as a general characteristics of a HPGe detector.
Conceptual Design of a Remote Monitoring and Control System for Nuclear Power Plants
Lee Seung Jun ; Kim Jong Hyun ; Seong Poong Hyun ;
Nuclear Engineering and Technology, volume 35, issue 3, 2003, Pages 243~250
Nuclear power plants (NPPs) will be highly connected network enabled systems in the future. Using the network and web enabled tools, NPPs will be remotely monitored by operators at any time from any place connected to the network via a general web browser. However, there will be two major issues associated with this implementation. The first is the security issue. Only the authorized persons need to be allowed to access the plant since NPP is a safety-critical system. However, the web technology is open to the public. The second is the network disturbance issue. If operators can not access the plant due to network disturbances, the plant will come into the out-of-control situation. Therefore, in this work, we performed a conceptual design of a web-based remote monitoring and control system (RMCS) considering these issues.
Parametric Study on Design Factors of the Shutdown Cooling Heat Exchanger Using the Taguchi Method
Kim Seong Hoon ; Ryu Seung Yeob ; Choi Byung Seon ; Yoon Juhyeon ; Bae Yoon Yeong ; Zee Sung Kyun ;
Nuclear Engineering and Technology, volume 35, issue 3, 2003, Pages 251~259
The Taguchi method was applied to investigate the effect of design factors on the performance of the shutdown cooling heat exchanger in the SMART-P. This method provided the simulation matrix for the KDESCENT program and an efficient tool for analyzing the simulation results. Levels of the design factors were selected by the effectiveness-NTU method. From 18 runs with the KDESCENT program, it was found that the performance of the system was greatly influenced by the inlet temperature at the shell side and the mass flow rate of the reactor coolant at the tube side. After applying the Taguchi method, we identified the important design factor that should be controlled and designed carefully. This method provides an efficient way to estimate the influence of each design factor on a system performance.