Go to the main menu
Skip to content
Go to bottom
REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
> Journal Vol & Issue
Nuclear Engineering and Technology
Journal Basic Information
Journal DOI :
Korean Nuclear Society
Editor in Chief :
Volume & Issues
Volume 17, Issue 4 - Dec 1985
Volume 17, Issue 3 - Sep 1985
Volume 17, Issue 2 - Jun 1985
Volume 17, Issue 1 - Mar 1985
Selecting the target year
Gamma-Ray Spectrometric Determination of Burnup Distribution and Cooling Time of Spent PWR Fuel Assemblies
Young-Gil Lee ; Jae-Shik Jun ;
Nuclear Engineering and Technology, volume 17, issue 1, 1985, Pages 1~7
Non-destructive gamma-ray spectrometry was carried out on the spent PWR fuel assemblies at the spent fuel pool of reactor-site. Attention was focused on the determination of burnup distribution and cooling time. For the measurement of burnup distribution, the concentration ratio of
Cs was used and the results showed these ratios varied with the positions of assemblies in the core during their irradiation. For the measurement of cooling time,
Cs was used and the results were agreed considerably well with the operator declared cooling time.
A Debris Bed Model with Gab Inflow and Gas Upflow for Debris/Water/Concrete Interaction and Its Application under Severe Accident Condition in LWR.
Jong In Lee ; Jin Soo Kim ; Byung Hun Lee ;
Nuclear Engineering and Technology, volume 17, issue 1, 1985, Pages 8~15
A model for thermal interactions of debris/water with gas flow from within and below debris bed was presented for severe accident analysis in LWR. The consumption of steam, production of hydrogen in the debris bed, generation of gases from below debris bed and generation of chemical heat are included in the conservation equations. The model has been incorporated in the MARCH code to estimate the gas production due to both metal/oxidation and hot debris/concrete interaction. The results indicate that the hydrogen source can potentially give a significant impact on the containment pressure transient and the conductive heat loss to concrete and the convective gas cooling in the debris bed have a small effect on the debris bed coolability. However, the reheating and melting of the debris particles could be delayed by the interaction of debris with concrete.
Fast Running System Code Development to Simulate Transient Behavior of Pool-Type LMFBRs
Youg Bum Lee ; Soon Heung Chang ; Mann Cho ;
Nuclear Engineering and Technology, volume 17, issue 1, 1985, Pages 16~24
A computer model is developed capable of simulating the transient behavior of a pool-type liquid metal-cooled fast breeder reactor (LMFBR). The model, SIMFARP, is a fast running computer code which may be used to simulate the loss of power to any pump(s), a complete loss-of-forced cooling, and the natural circulation behavior. Eight governing equations are derived and a Runge-Kutta algorithm is applied to integrate the eight differential equations. The developed computer program is applied to two cases; loss of electric power to any pump(s), and loss of all external electric supply power without scram in Super-Phenix-I.
Liquid Film Thickness Measurement by An Ultrasonic Pulse Echo Method
Jong Ryul Park ; Jong-Ryul Park ; Se Kyung Lee ;
Nuclear Engineering and Technology, volume 17, issue 1, 1985, Pages 25~33
The main purpose of this work is to investigate the effects of the wall thickness, the ultrasonic frequency, and the acoustic impedance of wall material on the liquid-film thickness measurement by an ultrasonic pulse echo method. A series of liquid-film thickness measurements in a horizontal air-water stratified system was performed employing a plate-type and a tube-type test sections. Measurements were repeated changing (1) the wall thickness of the test section and (2) the transducer frequency. Also, in an effort to improve the accuracy of the measurement and to exam me the effect of acoustic impedance of wall material on the measurement by an ultrasonic technique, two different stand-off rods, one made of stainless steel and the other polyacrylate, were used in the liquid-film thickness measurement. These experimental results are discussed and compared with the actual film thicknesses.
Experimental Investigation of Parametric Effects on the Void Fraction Measurement and Flow Regime Characterization by Capacitance Transducers -Part I : Stationary Test-
Moon-Hyun Chun ; Chang-Kyung Sung ;
Nuclear Engineering and Technology, volume 17, issue 1, 1985, Pages 34~44
The main purpose of this work is to study the effects of (1) configuration, size, and materials of electrodes, (2) flow pattern, (3) electrode position with respect to a dielectric boundary on the void fraction measurement and flow regime characterization by capacitance transducers. From the experimental results, relationships between the measured relative capacitance and void fraction are obtained for both annular and stratified flow systems under static condition, and this result is compared with theoretical predictions. From this study it can be concluded that (1) the strip-type electrodes are more sensitive than ring-type electrodes for both annular and stratified flows, (2) electrode size does not affect the relative capacitance vs. (1-
) curve, and (3) electrode position is important for stratified flows but it has no effect on annular flows.
Filmwise Reflux Condensation Length and Flooding Phenomena in Vertical U-Tubes
Moon-Hyun Chun ; Jee-Won Park ;
Nuclear Engineering and Technology, volume 17, issue 1, 1985, Pages 45~52
A two inverted U-tubes condenser was constructed from transparent materials to study the heat removal capability of steam generators under filmwise reflux condensation mode. Essentially, two sets of experiments were performed: (1) the first dealt with the reflux condensation length, and (2) the second dealt with the flooding points with and without the presence of a noncondensible gas in the steam flow, and the effect of the flooding time. In addition, experimental results are compared with the predictions of analytical models.
Possible Containment Failure Mechanisms in Severe Core Meltdown Accidents
Kang Yul Huh ; Jong In Lee ; Jin Soo Kim ;
Nuclear Engineering and Technology, volume 17, issue 1, 1985, Pages 53~67
The severe core meltdown accident, which is not included as a design basis accident, has high consequence and low probability of occurrence and turns out to be a major risk factor in the overall risk assessment. The physical mechanisms of containment failure in core meltdown accidents are identified as steam explosion, debris bed coolability, hydrogen burning, steam spike and concrete interaction. The state of technology review is made for each subtopic about the previous and current researches for better understanding of the phenomenon.
SGOG/EPRI PWR 증기발생기 2차계 화학세척 공정
Nuclear Engineering and Technology, volume 17, issue 1, 1985, Pages 68~82