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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 34, Issue 6 - Dec 2002
Volume 34, Issue 5 - Oct 2002
Volume 34, Issue 4 - Aug 2002
Volume 34, Issue 3 - Jun 2002
Volume 34, Issue 2 - Apr 2002
Volume 34, Issue 1 - Feb 2002
Selecting the target year
Neutron Cross Section Evaluation on Mo-95, Tc-99, Ru-101 and Rh-1()3 in the Fast Energy Region
Lee, Y. D. ; J. H. Chang ;
Nuclear Engineering and Technology, volume 34, issue 6, 2002, Pages 533~544
The neutron induced nuclear data for Mo-95, Tc-99, Ru-101 and Rh-103 was calculated and evaluated in the fast energy region. The energy dependent optical model potential parameters were extracted based on the recent experimental data and applied up to 20 MeV. The s-wave strength function was calculated from the parameters. Spherical optical model, statistical model in equilibrium energy, multistep direct and multistep compound model in pre-equilibrium energy and direct capture model were used in the calculation. The theoretically calculated cross sections were compared with the experimental data and the evaluated files The model- calculated total and capture cross sections were in good agreement with the reference experimental data. The direct capture contribution improved the capture cross sections in pre- equilibrium region. The evaluated cross section results were compiled to ENDF-6 format and will improve the ENDF/B-Vl.
Development of Anticosmic Shielded Ultra Low Background Gamma Spectrometer for Precise Measurement of Environmental Radioactivity
Byun, Jong-In ; Park, Yun-Ho ; Kwak, Seung-Im ; Hwang, Han-Yull ; Chung, Kun-Ho ; Park, Gun-Sik ; Park, Doo-Won ; Lee, Chnag-Woo ;
Nuclear Engineering and Technology, volume 34, issue 6, 2002, Pages 545~552
We developed an ultra low background gamma ray spectrometer particularly suitable for experiment which require lower detection limit. The background of a germanium spectrometer is suppressed by applying active and passive shielding technique at the same time. The active shielding devices consist of plastic scintillating plates of 50 mm thick and anti-coincidence electronic system. The shielding is made of 150 mm thick walls of very low activity lead,20 mm with activity of <10 Bq/kg and 130 mm with activity of <50 Bq/kg. The observed background count rates are 1.2
without and with the active shielding, respectively, overall the energy regions from 30 keV to 3 MeV The cosmic ray induced background is suppressed by a rate of 0.8
at the present work. The detection efficiency curve necessary to obtain the radioactivity of environmental samples has been precisely determined on the energy regions from 80 to 2000 keV with a 10
ml marinelli beaker sample, consisting of the calibrated radionuclides
Y. Virtues Of the method are demonstrated by measuring the activity of
Cs contained in the powdered milk.
Robust Controller with Adaptation within the Boundary Layer Application to Nuclear Underwater Inspection Robot
Park, Gee-Yong ; Yoon, Ji-Sup ; Hong, Dong-Hee ; Jeong, Jae-Hoo ;
Nuclear Engineering and Technology, volume 34, issue 6, 2002, Pages 553~565
In this paper, the robust control scheme with the improved control performance within the boundary layer is proposed. In the control scheme, the robust controller based on the traditional variable structure control method is modified to have the adaptation within the boundary layer. From this controller, the width of the boundary layer where the robust control input is smoothened out can be given by an appropriate value. But the improved control performance within the boundary layer can be achieved without the so-called control chattering because the role of adaptive control is to compensate for the uncovered portions of the robust control occurred from the continuous approximation within the boundary layer Simulation tests for circular navigation of an underwater wall-ranging robot developed for inspection of wall surfaces in the research reactor, TRIGA MARK III, confirm the performance improvement. Notational Conventions Vectors are written in boldface roman lower-case letters, e.g., x and y. Matrices are written in upper-case roman letters, e.g., G and B. And ∥.∥ means the Euclidean norm.
Assessment of Nuclear Characteristics of NAA ＃1 Irradiation Hole in HANARO Research Reactor for Application of the
Moon, Jong-Hwa ; Kim, Sun-Ha ; Chung, Yong-Sam ; Dung, Ho-Mahn ;
Nuclear Engineering and Technology, volume 34, issue 6, 2002, Pages 566~573
Neutron activation analysis based on
-standardization method＃ (
o-NAA) is Com as one of the most remarkable progresses of the NAA with advantages of experimental simplicity, high accuracy, excellent flexibility with respect to irradiation and counting conditions, and suitability for computerization. This study was carried out to determine the reactor neutron spectrum parameters, i.e.
and f as the main factors of irradiation quality at NAA ＃1 irradiation hole on HANARO research reactor, to evaluate peak detection efficiency of the gamma-ray spectrometer for the use in the
experiments and to compare the measured concentration results with the certified values of some SRMs applying the experimentally determined to-parameters.ers.
Evaluation of Mechanical Properties of RPV Clad by Small Punch Tests
Lee, Joo-Suk ; Kim, In-Sup ;
Nuclear Engineering and Technology, volume 34, issue 6, 2002, Pages 574~585
The microstructural characteristics and its related mechanical properties of RPV cladding have been investigated using small punch (SP) tests. SA508 Cl.3 RPV steel plates were overlay cladded with the type ER309L welding consumables by submerged arc welding process. Although the RPV clad material had a small portion of 5 ferrite phase, it still showed the ductile to brittle transition behavior The transition temperature was determined by the SP test and it depended on the content of
phase, specimen size, and determination methods. The fracture appearance of SP specimen was changed from circumferential to radial cracking as test temperature became low, and below the transition temperature region, ER309L cladding usually fractured along the 6 ferrite by the low temperature failure of ferrite phase.
Reevaluation of Seismic Fragility Parameters of Nuclear Power Plant Components Considering Uniform Hazard Spectrum
Park, In-Kil ; Choun, Young-Sun ; Seo, Jeong-Moon ; Yun, Kwan-Hee ;
Nuclear Engineering and Technology, volume 34, issue 6, 2002, Pages 586~595
The Seismic probabilistic risk assessment (SPRA) or seismic margin assessment (SMA) have been used for the seismic safety evaluation of nuclear power plant structures and equipments. For the SPRA or SMA, the reference response spectrum should be defined. The site-specific median spectrum has been generally used for the seismic fragility analysis of structures and equipments in a Korean nuclear power plant Since the site-specific spectrum has been developed based on the peak ground motion parameter, the site-specific response spectrum does not represent the same probability of exceedance over the entire frequency range of interest. The uniform hazard spectrum is more appropriate to be used in seismic probabilistic risk assessment than the site- specific spectrum. A method for modifying the seismic fragility parameters that are calculated based on the site-specific median spectrum is described. This simple method was developed to incorporate the effects of the uniform hazard spectrum. The seismic fragility parameters of typical NPP components are modified using the uniform hazard spectrum. The modification factor is used to modify the original fragility parameters. An example uniform hazard spectrum is developed using the available seismic hazard data for the Korean nuclear power plant (NPP) site. This uniform hazard spectrum is used for the modification of fragility parameters.
Improvement in the DNBR Modeling of RETRAN for Safety Analyses of Westinghouse Nuclear Power Plants
Cheong, Ae-Ju ; Kim, Yo-Han ;
Nuclear Engineering and Technology, volume 34, issue 6, 2002, Pages 596~609
Korea Electric Power Research Institute has developed the in-house safety analysis methodologies for non-LOCA(Loss Of Coolant Accident) events based on codes and methodologies of vendors and Electric Power Research Institute . According to the new methodologies, analyses of system responses and calculation of DNBR(Departure from Nucleate Boiling Ratio) during the transient have been carried out with RETRAN code and a sub-channel analysis code, respectively. However, it takes too much time to calculate DNBR for each case using the two codes to search for the limiting case from sensitivity study. To simplify the search for the limiting case, accordingly, RETRAN code has been modified to roughly calculate DNBR using hot channel modeling. The W-3 correlation is already included in RETRAN as one of the auxiliary DNBR models. However, WRB-1 and WRB-2 correlations required to analyze some Westinghouse type fuels are not considered in RETRAN DNBR models. In this paper, the RETRAN DNBR models using the correlations have been developed and the partial and complete loss of forced reactor coolant flow events have been analyzed for Yonggwang units 1 and 2 with the new methodologies to validate the models. The results of the analyses have been compared with those mentioned in the chapter 15 of the Final Safety Analysis Report.
Conceptual Data Modeling on the KRR-1&2 Decommissioning Database
Park, Hee-Seoung ; Park, Seung-Kook ; Lee, Kune-Woo ; Park, Jin-Ho ;
Nuclear Engineering and Technology, volume 34, issue 6, 2002, Pages 610~618
A study of the conceptual data modeling to realize the decommissioning database on the HRR-1&2 was carried out. In this study, the current state of the abroad decommissioning database was investigated to make a reference of the database. A scope of the construction of decommissioning database has been set up based on user requirements. Then, a theory of the database construction was established and a scheme on the decommissioning information was classified . The facility information, work information, radioactive waste information, and radiological information dealing with the decommissioning database were extracted through interviews with an expert group and also decided upon the system configuration of the decommissioning database. A code which is composed of 17 bit was produced considering the construction, scheme and information. The results of the conceptual data modeling and the classification scheme will be used as basic data to create a prototype design of the decommissioning database.