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 32, Issue 6 - Dec 2000
Volume 32, Issue 5 - Oct 2000
Volume 32, Issue 4 - Aug 2000
Volume 32, Issue 3 - Jun 2000
Volume 32, Issue 2 - Apr 2000
Volume 32, Issue 1 - Feb 2000
Selecting the target year
-Radionuclides by the PVA-PMAA System
Won, Hui-Jun ; Ahn, Byung-Gil ; Jung, Chong-Hun ; Kim, Gye-Nam ; Oh, Won-Zin ;
Nuclear Engineering and Technology, volume 32, issue 3, 2000, Pages 205~213
A series of laboratory experiments was conducted to investigate the fixation characteristics of poly(vinylalcohol)-poly(methacrylic acid)(PVA-PMAA) mixed solution on the soluble
- radionuclides. Using the potentiometric titration technique, it was found out that the PVA and PMAA in a solution form intermacromolecular complex. The mobilized portion of each radionuclide by water from sand surface treated with a fixative was measured by
-ray spectroscopy. The mobilized portion of minor radionuclides such as 241Am, 154Eu, 155Eu and 144Ce were higher than those of 134Cs and 137Cs. The capability of PVA-PMAA system was better among the candidate solutions for the fixation of total
-radioactivity. 134,137Cs which is composed of more than 85 % of total
-radioactivity could be fixed effectively by the PVA-PMAA solution.
MARS/MASTER Solution to OECD Main Steam Line Break Benchmark Exercise III
Jeong, Jae-Jun ; Joo, Han-Gyu ; Chung, Bub-Dong ; Ha, Kwi-Seok ; Lee, Won-Jae ; Cho, Byung-Oh ; Zee, Sung-Quun ;
Nuclear Engineering and Technology, volume 32, issue 3, 2000, Pages 214~226
In an effort to assess the performance of KAERI's coupled 3D kinetics - system T/H code, MARS/MASTER, Exercise III of the OECD main steam line break benchmark is solved. The analysis model of the reference plant, TMI-1 - a 2772 MWth B&W plant, consists of three major components: a core neutronics model involving 241
28 neutronic nodes, a vessel 3D T/H model consisting of 374 hydrodynamic volumes, and a 1D system T/H model containing 157 hydrodynamic volumes. The results show that there is a significant amount of flow mixing occurring in the upper and lower plenum regions and the core power distribution evolves to a highly localized shape due to the presence of a stuck rod, as well as the asymmetric flow distribution. It is judged that MARS/MASTER properly captures these drastic 3-dimensional effects. Comparisons with other results submitted to OECD confirm the accuracy of the MARS/MASTER solution.
Development of a Mass Estimation Algorithm Using the Impact Test Data of Nuclear Power Plant
Kim, J.S. ; I.K. Hwang ; Lee, D.Y. ; C.S. Ham ; Kim, T.H. ;
Nuclear Engineering and Technology, volume 32, issue 3, 2000, Pages 227~234
It is known that loose parts in the reactor coolant system (RCS) cause serious damage to the systems. This paper is concerned with estimating the mass of a loose part in the steam generator of a nuclear power plant. We developed the mass estimation algorithm based on the Hertz theory in order to estimate the mass of the loose parts and applied the algorithm to the impact test data of YGN3. The mass estimation values were compared with real values in order to verify the algorithm. The result showed that the average error of the mass estimation value is less than 27%.
Current Conservation Factors for Consistent One-Dimensional Neutronics Modeling
Lee, Kibog ; Joo, Han-Gyu ; Cho, Byung-Oh ; Zee, Sung-Quun ;
Nuclear Engineering and Technology, volume 32, issue 3, 2000, Pages 235~243
A one-dimensional neutronics formulation is established within the framework of the nonlinear analytic nodal method such that it can result in consistent one-dimensional models that produce the same axial information as their corresponding reference three-dimension81 models. Consistency is achieved by conserving axial interface currents as well as the planar reaction rates of the three-dimensional case. For current conservation, flux discontinuity is introduced in the solution of the two-node problem. The degree of discontinuity, named the current conservation factor, is determined such that the surface averaged axial current of the reference three-dimensional case can be retrieved from the two-node calculation involving the radially collapsed group constants and the discontinuity factor. The current conservation factors are derived from the analytic nodal method and various core configurations are analyzed to show that the errors in K-eff and power distributions can be reduced by a order of magnitude by the use of the current conservation factor with no significant computational overhead.
Thermal Analysis of High Level Radioactive Waste Repository Using a Large Model
Park, Jeong-Hwa ; Kuh, Jung-Eui ; Sangki Kwon ; Kang, Chul-Hyung ;
Nuclear Engineering and Technology, volume 32, issue 3, 2000, Pages 244~253
A Simple Large Model (SLM), which can be used to make thermal calculation for a deep geological repository with finite number of HLW canisters, was developed. In order to develop the SLM, a Simple Basic Model (SBM), which will be a unit of the SLM, was optimized first. The SBM was optimized to achieve the same maximum buffer temperature as that of the Detailed Basic Model (DBM) representing the real geometric aspects of the repository. In contrast to the models with the assumption of infinite number of canisters which cannot consider boundary effect, the SLM can model the real repository with finite number of canisters and thus consider the boundary effect. Thermal results from the SLM can be used to evaluate the reliability of the models, which do not consider boundary effect. This model can also be used to simulate the thermal layout design and to analyze the thermal safety of a deep geological repository as well as an underground laboratory.
ESR Signal in Different Cuts of Irradiated Chicken, Pork and Beef
Nam, Hye-Seon ; Yang, Jae-Seung ; Ly, Sun-Yung ;
Nuclear Engineering and Technology, volume 32, issue 3, 2000, Pages 254~260
Electron spin resonance (ESR) spectroscopy was used to detect irradiated meat containing bones (chicken, pork and beef）, to investigate the effect of irradiation dose on the ESR signal intensity and to identify the stability of radicals under 9 weeks of storage. Chicken, pork and beef were irradiated with doses 0, 1, 3, 5 and 7 kGy at room temperature using a Co-60 irradiator. Bones were pieced and dried, which were placed in a quartz tube within an Electron paramagnetic resonance (EPR) spectrometer resonator cavity. The irradiated bone presented an asymmetric absorption in shape, different from that of a non-irradiated one. The signal intensity of smaller animals are lower than larger species. Variation was observed between samples of the same species depending on the calcification status of the bone. Moreover different irradiation doses produced different signal areas that make possible to estimate the absorbed dose of treated meat. The ESR signal stability after irradiation was stable in even after a 9 week storage at room temperature.
An Integrated On-Line Diagnostic System for the NORS Process of Maiden Reactor Project: The Design Concept and Lessons Learned
Kim, Inn-Seock ;
Nuclear Engineering and Technology, volume 32, issue 3, 2000, Pages 261~273
During an extensive review made as part of the Integrated Diagnosis System project of the Maiden Reactor Project, MOAS (Maryland Operator Advisory System) was identified as one of the most thorough systems developed thus far. MOAS is an integrated on-line diagnosis system that encompasses diverse functional aspects that are required for an effective process disturbance management: (1) intelligent process monitoring and alarming, (2) on-line sensor data validation and sensor failure diagnosis, (3) on-line hardware (besides sensors) failure diagnosis, and (4) real-time corrective measure synthesis. The MOAS methodology was used at the Maiden Man-Machine Laboratory HAMMLAB of the OECD Maiden Reactor Project. The performance of MOAS, developed in G2 real-time expert system shell for the high-pressure preheaters of the NORS process in the HAMMLAB, was tested against a variety of transient scenarios, including failures of the control valves and sensors, and tube leakage of the preheaters. These tests showed that MOAS successfully carried out its intended functions, i.e., quickly recognizing an occurring disturbance, correctly diagnosing its cause, and presenting advice on its control to the operator. The lessons learned and insights gained during the implementation and performance tests also are discussed.
Water Balance Evaluation of Final Closure Cover for Near- surface Radioactive Wastes Disposal Facility
Keunmoo Chang ; Park, Joo-Wan ; Yoon, Jeong-Hyoun ; Park, Heui-Joo ; Kim, Chang-Lak ;
Nuclear Engineering and Technology, volume 32, issue 3, 2000, Pages 274~282
The simulation of water balance was conducted for suggested four alternative multi-layer cover design of near-surface radioactive waste disposal facility under domestic climate condition. The analysis was also conducted for the most favorable one out of four alternative cover design under conservative scenarios. Until 100 years after closure of disposal vault, the infiltration flux for the most favorable cover design was negligible even under doubling of the ambient precipitation condition. When the degradation of asphalt and geomembrane after 100 years of closure was considered, the infiltration flux significantly increased almost to the design criteria of cover system in I' Aube disposal facility. And it was found that the hydraulic conductivity of bentonite/sand as a bottom barrier should be no greater than 1
cm/sec recommended by U.S. EPA.