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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
> Journal Vol & Issue
Nuclear Engineering and Technology
Journal Basic Information
Journal DOI :
Korean Nuclear Society
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Volume & Issues
Volume 16, Issue 4 - Dec 1984
Volume 16, Issue 3 - Sep 1984
Volume 16, Issue 2 - Jun 1984
Volume 16, Issue 1 - Mar 1984
Selecting the target year
General Derivation of Two-Fluid Model
Hee Cheon No ;
Nuclear Engineering and Technology, volume 16, issue 1, 1984, Pages 1~10
General time-volume averaged conservation equations and jump conditions for two-phase flows are derived here. The time-averaged equations for a single phase region in two-phase flow are obtained from local instant balance equations by a technique often used for single phase turbulent flow equations. The results obtained by integrating the time averaged equations over a flow volume are spatially averaged twice; first, they are averaged over a single phase region of the k-th phase and then averaged over the total volume of the k-th phase, in a flow volume. The mass, momentum, and energy conservation equations are obtained from the general time-volume averaged equations. The advantages of the present model are explained by comparing it with Ishii's model (1) and Banerjee's model (2). Finally, the assumptions and approximate terms of the equations of the THERMIT-6S are clarified.
Decay Beat Removal and Operator's Intervention During A Very Small L()CA
Hee Cheon No ;
Nuclear Engineering and Technology, volume 16, issue 1, 1984, Pages 11~17
Sample calculations were done for KORI-1 to develop a better understanding of what happens after very small LOCA (
). For a water-side break with the break size larger than 0.006 ft
, fluid-loss through break exceeds the makeup. If the break size is larger than 0.008ft
, decay heat can be completely removed through break. Based on these results, it was concluded that KORI-1 is fairly safe for the whole spectrum of sizes in very small LOCA. However, for the reactor with 900 MWe or 1200 MWe, a certain spectrum of sizes in very small LOCA should be carefully considered. In the accident sequence the transition from natural circulation to pool boiling or from pool boiling to natural circulation may be troublesome to the operator or in the safety analysis. Operator's intervention was discussed; primary pump shutoff, HPI pump shutoff, break isolation, and opening relief valve. It was proved that continuous operation of HPI pumps after shutdown will not threaten the integrity of the primary system.
Some Improvements of Gamma-ray Measurement for the Determination of the Boron Content
Nak Bae Kim ; Hae-Ill Bak ;
Nuclear Engineering and Technology, volume 16, issue 1, 1984, Pages 18~20
The detection limit of boron has been lowered further in the capture gamma-ray measurement after preconcentration of boron by placing natural lithium brick in front of Ge(Li) detector. The experimental detection limit is found to be 0.30ppm, 0.18ppm, 0.045ppm and 0.090ppm for the samples of aluminum, steel, uranium dioxide and graphite, respectively. An alternate counting technique kas been also used for neglecting the error caused by the fluctuation of neutron flux during counting.
A Stream Line Method to Remove Cross Numerical Diffusion and Its Application to The Solution of Navier-Stokes Equations
Soon Heung Chang ;
Nuclear Engineering and Technology, volume 16, issue 1, 1984, Pages 21~28
The reduction of the truncation error including numerical diffusion, has been one of the most important tasks in the development of numerical methods. The stream line method is used to cancel cross numerical diffusion and some of the non-diffusion type truncation error. The two-step stream line method which is the combination of the stream line method and finite difference methods is developed in this work for the solution of the govern ing equations of incompressible buoyant turbulent flow. This method is compared with the finite difference method. The predictions of both classes of numerical methods are compared with experimental findings. Truncation error analysis also has been performed in order to the compare truncation error of the stream line method with that of finite difference methods.
Removal of Aerosol Through Fibrous Filter as a Function of Particle Size and Velocity
Sang Hoon Lee ; Kwan Sik Chun ; Hoo Keun Lee ;
Nuclear Engineering and Technology, volume 16, issue 1, 1984, Pages 29~35
Filtration efficiency tests were conducted on a fiberglass mat filter with DOP aerosol having a diameter from 0.l
in the face velocity range of 1cm/sec to 10cm/sec. Filtration of submicron particles by a fibrous filter is characterized by a face velocity. The size of DOP aerosol which has a minimum removal efficiency decreases with increasing the velocity. A numerical solution of the diffusion equation is obtained for a fiberglass mat filter by using "Kuwabara's cell model" for the flow field and Von Mises Transformation for the actual flow around a fiberglass. The present theoretical results agree quite well with the experimentals for fiberglass mat. This result could be contributed to predict the removal efficiency on an air filter and to optimize the operating condition of an air purification system with a filter. a filter.
Technical Review on Statistical Thermal Design of PWR Core
Ki In Han ;
Nuclear Engineering and Technology, volume 16, issue 1, 1984, Pages 36~46
Studied are the statistical thermal design (STD) methods that have been developed to satisfy the design basis which protects a pressurized water reactor (PWR) core against departure from nucleate boiling (DNB) during normal operations and anticipated transients. The objective of the statistical thermal design is to quantify the thermal design margin and to remove any excess conservatism from the DNB ratio calculations through statistically combining design parameter uncertainties, while still maintaining a high level of core protection. This report describes and compares the STD methods developed by the two U.S. reactor vendors (Westinghouse and B & W). Included are the characteristics of STD, statistical treatment of uncertainties, DNB design limit development methodology and the sample application of the STD technique to core thermal design analysis. It is observed that the STD methods developed by the two vendors are similiar to each other in principle, but different in the treatment of the uncertainties associated with the design parameters. The statistical thermal design is found to significantly improve the thermal design margin.