[en] More than half of the information relevant to the nuclear control is considered to be geospatially related. Therefore the need for building a geospatial information system (GIS) in the field of the nuclear control is increased. High resolution commercial satellite images with positional information covering wide areas such as nuclear sites are regarded as one of the fundamental information for building a relevant GIS. This paper discusses the geographic file formats, the Shapefile and the geodatabase in regard to the Additional Protocol

[en] From the studies of XRD, TMA, VSM and TEM of optimally annealed Nd_xFe_yB_z (2≤x≤13, 76≤y≤88, 5.5≤z≤22) melt-spun alloys, the main phases are identified to be α-Fe, Fe₃B, Nd₂Fe₂₃B₃ and Nd₂Fe₁₄B. The coercivity is sensitively dependent on the Nd content. The energy product contour shows two peaks at 12 MGOe of Nd₄Fe₇₇B₈ and 17.5 MGOe of Nd₁₀Fe₈₂B₈, respectively

[en] From XRD, TMA, VSM and TEM studies, the Nd₂Fe₈₀B₁₈ permanent magnet has Fe₃B, α-Fe and Nd₂Fe₁₄B of, respectively, 40, 30 and 30 wt% with _iH_c=1.1 kOe, B_r=1.5 T and (BH)_max=8 MG Oe. The Nd₁₀Fe₈₂B₈ p.m has a homogeneous fine Nd₂Fe₁₄B phase of 70 nm and soft α-Fe and Fe₃B phases of 15 nm with the remanence of 1.0 T due to the exchange coupling between nanocomposites

[en] Export Licenses on Trigger List items(INFCIRC/254 Part 1) and Dual-use items (INFCIRC/254 Part 2) are issued by Ministry of Science and Technology and Ministry of Commerce, Industry and Economy, separately. The Paper will study the necessity for shifting the divided responsibilities relate to licensing and control of each Ministry into one Ministry. In order to prospect such long-term planning or vision, the paper will review on US and Japan nuclear export system in brief. After analysis on their systems, it intends to extract any points to be used for improvement of nuclear export control system in our country

[en] The methodology of safety analyses for CANDU reactors in Canada, a vendor country, uses a combination of best-estimate physical models and conservative input parameters so as to minimize the uncertainty of the plant behavior predictions. As using the conservative input parameters, the results of the safety analyses are assured the regulatory requirements such as the public dose, the integrity of fuel and fuel channel, the integrity of containment and reactor structures, etc. However, there is not the comprehensive and systematic procedures for safety analyses for CANDU reactors in Korea. In this regard, the development of the safety analyses procedures for CANDU reactors is being conducted not only to establish the safety analyses system, but also to enhance the quality assurance of the safety assessment. In the first phase of this study, the general procedures of the deterministic safety analyses are developed. The general safety procedures cover the specification of the initial event, selection of the methodology and accident sequences, computer codes, safety analysis procedures, quality assurance in the safety analysis, etc

[en] In this paper the background, status and general description of severe accident management guidelines (SAMG) are explained. Especially the SAMG development and validation process for Kori-1 nuclear power plant which is the first Westinghouse type are explained. Mitigation strategy of Kori-1 SAMG is consistent with that of KSNP. Plant-specific features of Kori-1 are reflected into the Kori-1 SAMG strategies. The Kori-1 SAMG is validated with simulated severe accident scenario by Kori-1 plant operators. Transition from Emergency Operating Procedure (EOP) to SAMG, major mitigation strategies and validation process are explained

[en] In this study, a base work to construct the database of the domestic and foreign GSIs were done through performing the deviation of GSIs for the PHWR by investigating the development trend of international joint studies and the GSIs of 4 countries as the PHWR state and examined the IAEA acceptance of GSIs classification for the GSIs of Canada, Korea Republic of, Argentina and India. We evaluated the possibility of application of the safety issue for PHWR by investigating causes, contents and follow-up measures of each items. To evaluate the domestic application validity of the safety issue, we made the investigation matrix for the safety issue of each countries and also are reflecting new results in investigation matrix by examining IAEA PHWR GSI development trend. We intended to derive the GSIs which are most appropriate in our PHWR by examining every issues. The derived GSIs are divided into the design parts and the operation parts. And they have to be solved as soon as possible

[en] Remote monitoring (RM) as unattended surveillance is one of alternative regime to fulfill safeguards tasks through its field trials and technical advances. The IAEA has installed digital surveillance or remote monitoring (RM) systems at 11 of 12 LWRs in operation since RM tasks under the MSSP (Member State Support Program) initiated. During the 8th Joint Review Meeting in 1999, the IAEA and Korea agreed to establish a working group of the enhanced cooperation between both sides in anticipation of integrated safeguards. Since it would take several years for the implementation of integrated safeguards in Korea, it was agreed to seek mutually beneficial approaches, taking advantage of Korean SSAC experties as well as ongoing digital surveillance camera upgrades, capable of remote data transmission. Prior to the full-scale implementation, a rehearsal planned to last until April 2001, in order to obtain practical experience at the selected 3 LWRs. During September/October 2000, SSAC-alone inspection activities was performed as a part of the reheasal and SSAC reports and working papers were completed. In November 2000 and March 2001, SSAC inspectors jointly did the rehearsal with IAEA inspectors. This paper focuses on Remote Monitoring based National Safeguards Inspection and its Perspective on the national safeguards inspection in Korea

[en] Three kinds of shield containers for Tc-99m generator have developed by KNT(Korea Nuclear Technology), named Ultra Tech-I, II and III. Their maximum loading capacities are 1.5, 3.0 and 10.0 Ci, respectively. In the design process, MCNP-4b computer code was utilized to evaluate the shielding capability of the containers. The calculation results from MCNP-4b were applied to detail design of the mock-up containers and compared to external dose rate from the mock-up. Consequently, calculation and dose rate measurement agreed with each other and they were well within the allowed dose rate by regulation. The containers developed by KNT will be employed as the source container of the Tc-99m generator when its production starts from this November at KAERI

[en] Combining the current-voltage and the capacitance-voltage characteristics, yields a new method for extracting parasitic resistances in MOSFETs. In addition to the separated gate-bias-dependent parasitic source and drain resistances (R_S, R_D), a gate-bias-dependent parasitic gate resistance (R_G), which is known to be most crucial to high-frequency and high-speed performance but which is very hard to extract, can be accurately extracted. The device parameters determined for LDD MOSFETs were compared with those obtained using a previously reported extraction method, and the validity of the new method was verified