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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 27, Issue 6 - Dec 1995
Volume 27, Issue 5 - Aug 1995
Volume 27, Issue 4 - Aug 1995
Volume 27, Issue 3 - Jun 1995
Volume 27, Issue 2 - Apr 1995
Volume 27, Issue 1 - Feb 1995
Selecting the target year
Nonlinear Stochastic Stability for Steam Generator Water Level Control System
Park, You-Cho ; Chung, Chang-Hyun ; Oh, Je-Kyun ;
Nuclear Engineering and Technology, volume 27, issue 2, 1995, Pages 155~164
The steam generator water level control system is studied as a class of randomly sampled nonlinear control systems. The sampling interval and the loop amplification factor are considered as random variables in order to take the operator behavior in account. Stochastic stability using Lyapunov method is used without determining such Lyapunov function. The derived stability criterion is verified with time-domain simulation using the data of CANDU type nuclear power plant, Wolsung 1.
RCS Overpressure Protection Analysis Using SEBIM POSRV
Kim, Chong-Hoon ; Seo, Jong-Tae ;
Nuclear Engineering and Technology, volume 27, issue 2, 1995, Pages 165~175
The overpressure protection system for PWR should be designed with sufficient capacity to limit the pressure to less than 110％ of the reactor coolant system design pressure during the most severe abnormal operational transient. In this study, the feasibility of adopting the SEBIM POSRV instead of the current spring loaded pop-opening safety valves to the ABB-CE designed 2825 MWt PWR is investigated for its overpressure protection capability. The required SEBIM POSRV size as well as its opening/closing setpoints are determined through a series of computer analyses using the LTC code which has been used for the overpressure protection analysis for Yonggwang units 3&4. The analysis results show that the overpressure protection system with monobloc SEBIM POS-RV can maintain the RCS pressure below 110％ of the design pressure demonstrating its overpressure protection capability for the ABB-CE designed 2825 MWt PWRs.
Interpretation of Migration of Radionuclides in a Rock Fracture Using a Particle Tracking Method
Chung Kyun Park ; Pil Soo Hahn ; Douglas J. Drew ;
Nuclear Engineering and Technology, volume 27, issue 2, 1995, Pages 176~188
A particle tracking scheme was developed in order to model radionuclide transport through a tortuous flow Held in a rock fracture. The particle tacking method may be used effectively in a heterogeneous flow field such as rock fracture. The parallel plate representation of the single fracture fails to recognize the spatial heterogeneity in the fracture aperture and thus seems inadequate in describing fluid movement through a real fracture. The heterogeneous flow field une modeled by a variable aperture channel model after characterizing aperture distribution by a hydraulic test. To support the validation of radionuclide transport models, a radionuclide migration experiment was performed in a natural fracture of granite.
I are used as tracers. Simulated results were in agreement with experimental result and therefore support the validity of the transport model. Residence time distributions display multipeak curves caused by the fast arrival of solutes traveling along preferential fracture channels and by the much slower arrival of solutes following tortous routes through the fracture. Results from the modelling of the transport of nonsorbing tracer through the fracture show that diffusion into the interconnected pore space in the rock mass has a significant effect on retardation.
An Improved Heat Transfer Prediction Model for Turbulent Falling Liquid Films with or Without Interfacial Shear
Park, Seok-Jeong ; Chun, Moon-Hyun ;
Nuclear Engineering and Technology, volume 27, issue 2, 1995, Pages 189~202
An improved method is presented for the prediction of heat transfer coefficients in turbulent fall-ing liquid films with or without interfacial shear for both heating or condensation. A modified Mudawwar and El-Masri's semi-empirical turbulence model, particularly to extend its use for the turbulent falling film with high interfacial shear, is used to replace the eddy viscosity model incorporated in the unified approach unposed by Yih and Liu. The liquid film thickness and asymptotic heat transfer coefficients against the film Reynolds number for wide range of interfacial shear predicted by both present and existing methods are compared with experimental data. The results show that in general, predictions of the modified model agee more closely with experimental data than that of existing models.
Small Break LOCA Analysis for RCP Trip Strategy for YGN 3&4 Emergency Procedure Guidelines
Seo, Jong-Tae ; Bae, Kyoo-Hwan ;
Nuclear Engineering and Technology, volume 27, issue 2, 1995, Pages 203~215
A continued operation of RCPs during a certain small break LOCA may increase unnecessary inventory loss from the RCS causing a severe core uncovery which might lead to a fuel failure. After TMI-2 accident, the CEOG developed RCP trip strategy called “Trip-Two/Leave-Two” (T2/L2) in response to NRC requests and incorporated it in the generic EPG for CE plants. The T2/L2 RCP trip strategy consists of tripping the first two RCPs on low RCS pressure and then tripping the remaining two RCPs if a LOCA has occurred. This analysis determines the RCP trip setpoint and demonstrates the safe operational aspects of RCP trip strategy during a small break LOCA for YGN 3&4. The trip setpoint of the first too RCPs for YGN 3&4 is calculated to be 1775 psia in pressurizer pressure based on the limiting small break LOCA with 0.15 ft
break size in the hot leg. The analysis results show that YGN 3&4 can maintain the core coolability even if the operator fails to trip the second too RCPs or trips at worst time. Also, the YGN 3&4 RCP trip strategy demonstrates that both the 10 CFR 50.46 requirements on PCT and the ANSI standards 58.8 requirements on operator action time can be satisfied with enough margin. Therefore, it is concluded that the T2/L2 RCP trip strategy with a trip setpoint of 1775 psia for YGN 3&4 can provide improved operator guidance for the RCP operation during accidents.
Analysis of a Two-Phases System of Mass Transfer and Electro-Reduction of Uranium(VI) in Nitric Acid-Hydrazine Media
Kim, K.W. ; Yoo, J.H. ; Park, H.S. ; Kim, J.D. ; H.Aoyagi ; Z. Yoshida ;
Nuclear Engineering and Technology, volume 27, issue 2, 1995, Pages 216~225
Simulation for a dynamic analysis of the electrolytic preparation of U(IV) in two-phases system, which consisted of mass transfer of U(VI) from TBP phase into HNO
solution and electrolytic re-duction of U(VI) to U(IV) at a cathode in aqueous phase, was carried out in order to establish the most suitable operating condition and best electrode area as basic design data for the system. It was found that maintaining an appropriate mass transfer rate was more significant rather than enlarging the surface area of the cathode for more effective production yield of U(IV). The electrode area and the operation time affected deeply the production composition of U(IV) in the resulting aqueous phase. And optimal electrode areas ore evaluated to meet production criteria of U(IV) of resulting solution in several system conditions. Though about 0.37M HNO
was preferable to prepare the solution of U(IV), nitric acid concentration should be higher than 0.5M to prevent a hydrolysis of U(IV) in the aqueous phase.
Effect of an Increased Wall Thickness on Delayed Hydride Cracking in Zr-2.5Nb Pressure Tube
Jeong, Yong-Hwan ; Kim, Young-Suk ;
Nuclear Engineering and Technology, volume 27, issue 2, 1995, Pages 226~233
The wall thickness of a pressure tube is increased in order to reduce the probability of failure in a pressure tube of CANDU type reactor. It is presented here that the variation of wall thickness changes stress, hydrogen concentration and delayed hydride cracking in Zr-2.5Nb pressure tube. When the wall thickness is increased from 4.2 mm to 5.2 mm, the stress exerted on the tube and the deuterium taken up during operation are reduced by 19％. Further, the calculated allowable depth of the surface flaw over which delayed hydride cracking(DHC) is susceptible increases by 50％. DHC initiation is controlled by the stress and by the hydrogen concentration in the pressure tube. The results are therefore very significant in such a respect that increased wall thickness may reduce DHC initiation. Ac the wall thickness increases the hydrostatic tension will increase. Its impact on the acceleration of the crack growth rate of DHC deserves further studies.
Determination of Trace Elements in Airborne Particulates by Instrumental Neutron Activation Analysis
Chung, Yong-Sam ; Chung, Young-Ju ; Jeong, Eui-Sik ; Cho, Seung-Yeon ;
Nuclear Engineering and Technology, volume 27, issue 2, 1995, Pages 234~247
Trace elements in airborne particulates were analyzed by instrumental neutron activation analysis (INAA) under the optimum analytical condition. Neutron irradiation for sample was done at the irradiation hole(neutron flux 1
.s) of TRIGA MARK-III research reactor in the Korea Atomic Energy Research Institute. For the verification of the analytical method, NIST SRM-1648 and NIES CRM No.8 ore chosen and analyzed. The accuracy and precision of the analysis of 40 and 24 trace elements in the samples were compared with the certified and reported values, respectively. The analytical method was found to be reliable enough when the analytical data of NIES sample were compared with those of different counties. In the analytical result of two or both of standard reference materials, relative standard deviation wes within the 15％ except a few elements and the relative error was within the 10％. We used this method to analyze 30 trace elements in airborne particulates collected with the high volume air sampler(PM-10) at too different locations and also confirmed the possibility to use this method as a routine monitoring tool to find out environmental pollution sources.
CASK, BUGLE80, BUGLE93을 이용한 원자로 압력용기 중성자 조사량 분포 비교
Nuclear Engineering and Technology, volume 27, issue 2, 1995, Pages 248~259
국내 원전의 방사성폐기물 발생량 예측과 폐기물 종류별 동굴내 배치계획
Nuclear Engineering and Technology, volume 27, issue 2, 1995, Pages 260~268
신형원자로로서의 일체형 가압경수로 설계특성 분석
Nuclear Engineering and Technology, volume 27, issue 2, 1995, Pages 269~279