Regional Basic Professional Training Course in Korea

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Regional Basic Professional Training Course (BPTC) on Nuclear Safety the noble gases, krypton and xenon, along with tritium (from ternary fission), will migrate out of the fuel matrix to the fission gas plenum within the cladding. Also, the volatile fission products, primarily, iodine and cesium, which are vapors at normal operating temperature, will migrate out of the fuel matrix and tend to collect in the fuel‐cladding gap as elements and compounds. Changes in fuel temperature, such as those associated with power changes, lead to release of fission gases trapped within the microstructure of the fuel, probably because of thermal diffusion and fuel cracking. This fission gas release is postulated to result in high mechanical loading of the cladding and possible cladding failure. Aside from the fission gases and volatile fission products, the fission products and transuranic elements are contained in the matrix unless near‐melting temperatures are encountered. The extent and kinetics of fission product release from fuel melting during an accident is an active research area in several countries. 3.5.2.2. The cladding Description The UO2 fuel pellets are contained within a metal cladding tube that serves to maintain the fuel geometry and to prevent release of fission products and actinides into the coolant. In current water‐cooled reactors, the cladding is an alloy of zirconium called Zircaloy (or a proprietary variation of this alloy), chosen because of its good structural and corrosion properties, and its low neutron absorption. The cladding tube is typically of the order of five meters long and 0.95 cm (PWR) to 1.30 cm (BWR) in diameter, while the fuel pellet stack (the “fuel column”) is about 3.5 to 3.7 meters long. Space is provided within the cladding to accommodate fission gas release from the fuel without excessive internal pressure build‐up. The cladding tube is closed by welded end‐caps to create a hermetic seal. ❙ 180 ❙
Cladding failure ❙ 181 ❙ 3. Basic Principles Of Nuclear Safety Failure of the cladding barrier can occur due to defects in end‐cap welds or in the cladding tube itself. Such failures are relatively rare compared to the number of fuel rods in a reactor. Other potential failure mechanisms include pellet‐cladding mechanical interaction or high pressure due to fission gas release in transients, flow‐induced or mechanical vibrations, or excessive cladding corrosion. Cladding failures can be detected promptly by detection of fission product radioactivity or delayed neutrons in the coolant. While plant technical specifications may allow operation with up to a specified fraction of defective fuel, prudent operating practice and ALARA principles dictate that failed fuel be removed at the earliest practical time to minimize contamination of the primary coolant system with accompanying radiation exposure to the plant operating and maintenance staff. 3.5.2.3. The primary coolant system Description In a PWR, the primary coolant system pressure boundary consists of the reactor pressure vessel, the coolant piping, the steam generators, and main coolant pumps, along with some auxiliary systems including the pressurizer, chemical and volume control systems (CVCS), and parts of the emergency core cooling and residual heat removal systems, depending on the design and operating details. The primary coolant system is intended to be leak‐tight, except for controlled outflow, for example, through the main coolant pump seals, or the CVCS. Under normal conditions, the radioactive inventory of the primary coolant system consists of radionuclides that have leaked from defective fuel, plus activated corrosion products. An important class of design basis accidents involves loss of integrity of the pressure boundary. This class includes the large‐break loss‐of‐coolant accident (LBLOCA), and the small‐break loss‐of‐coolant accident (SBLOCA). So long as these accidents do not lead to core
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1. Nuclear Reactor Principles · 1
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1. Nuclear Reactor Principles Regio
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Table 1.2. Average cross sections f
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1. Nuclear Reactor Principles ❙ 7
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energy of the fuel nuclei. ❙ 9
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❙ 11 ❙ 1. Nuclear Reactor Princ
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1 Bq = 2.7x10 -5 µCi = 2.7x10 -8 m
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1.1.5. Natural radioactive series
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238 U 92+ 1 n0 -----> 135 Te 52 + 9
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σ t = σ s + σ a = σ elastic +
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FIG. 1.10. And here in the 1keV to
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1.2.3.2. Neutron emission in fissio
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Three possible states could then be
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TABLE 1.3. Slowing down efficiency
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1 UNGG/AGR CANDU PWR/BWR TABLE 1.5.
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✼✼✼ REFERENCES ✼✼✼ ❙
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2.1. Introduction C O N T E N T S 2
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2. Radiation Protection 2.1. Introd
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2.2.1. Exposure ❙ 61 ❙ 2. Radia
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❙ 63 ❙ 2. Radiation Protection
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2.2.4. Effective dose ❙ 67 ❙ 2.
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schematically in Fig. (2.7). ❙ 77
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The great utility of the G‐M tube
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protection conditions. These factor
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2.6.2. Effects of dose, dose‐rate
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2.7. Principles of Radiological Pro
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❙ 115 ❙ N 0 = N 2 1 t / t 1/ 2
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ln 10 = μ t1/10 ≈ 3 · ln 2 = 3
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C O N T E N T S | Table of Contents
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Fig. 1 Committees for IAEA Safety S
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Regional Basic Professional Trainin
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Page 227 and 228: ❙ 221 ❙ 4. DESIGN OF NUCLEAR RE
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administrative control. ❙ 231 ❙
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❙ 233 ❙ 4. DESIGN OF NUCLEAR RE
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Design basis accidents ❙ 237 ❙
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Single failure criterion ❙ 239
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Deterministic approach The determin
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accidents, with account taken of th
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Fuel elements and assemblies Fig. 4
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Reactor shutdown ❙ 251 ❙ 4. DES
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functional in the event of a severe
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4.1.5.4. Instrumentation and contro
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4.1.5.9. Radiation protection Gener
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Operation at a power level < 1 MW.
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of these exchangers, the water is c
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Fig. 4.11. HANARO Core Pool Fig. 4.
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4.2.6.2.3 Reactor Systems ❙ 295
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4.2.6.5. Neutron Activity Analysis
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❏ physical separation. ❙ 303
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5. Siting Considerations Regional B
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5.4.2. Sources of risk 5.4.3. Evalu
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6. Safety Classification Of Structu
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Safety functions necessary to preve
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6.1.3. Principal Safety Classes 6.
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function; 6. Safety Classification
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the safety function would be requir
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6.3.2. Description of Quality Group
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6.4.3. Seismic category 1: 6.4.3.1.
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7. Quality Assurance Regional Basic
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7.5.1. Manufacture Quality Assuranc
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C O N T E N T S 8.1. INTRODUCTION |
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❙ 471 ❙ 8-A. Deterministic Acci
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guidelines for this categorization.
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Table 8‐3 Typical Initial Conditi
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8.5.3. Decrease in Reactor Coolant
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or by operator error, often during
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8-B. Deterministic Accident Analysi
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| List of Tables | Table 8.7‐1 Ru
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❙ 509 ❙ 8-B. Deterministic Acci
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SG Containment RCP RCP RCP SIT SIT
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8.2.5. Evaluation Model ❙ 521 ❙
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Figure 8.7‐7 Flow chart of KREM
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Cladding Temperature (K 1300 1200 1
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8.8.1.6. Loop Seal Formation and Cl
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to ECCS injection time using CEFLAS
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Table 8.8‐2 SBLOCA Break Spectrum
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F TEMPERATURE, o 0 100 200 300 400
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8.8.2.2.3 RELAP5‐sEM Methodology
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9. Probabilistic Safety Analysis Re
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9.4. LEVEL 2 PSA 9.4.1. Objectives
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❙ 627 ❙ 10-A. Limiting Conditio
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performance, correct set points, an
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injecting borated water into the pr
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Positive reactivity insertion rates
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10.4.3.3. Canadian type NPP ❙ 655
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2) Safety Limits and Safety System
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the technical specifications is not
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10-B. Technical Specifications for
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10.7.7.1. Monitoring Systems 10-B.
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10.8.1. Reactor Core Parameters 10-
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10.8.6. Emergency Power 10-B. Techn
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authorized by responsible authority
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11. Human Performance: A Perspectiv
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Figure 11.1 Model of violation Figu
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12. Surveillance Programmes Regiona
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12.4. IMPLEMENTATION 12.4.1. Genera
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13.Maintenance Management in KHNP R
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15. Operational Safety 15.1. IAEA S
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❙ 831 ❙ 15. Operational Safety
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and modified if required. ❙ 837
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15.2.2. Organization and functions
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− Temporary and permanent plant m
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Operating procedures and instructio
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Off‐normal conditions are easily
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15.2.6. Work authorizations ❙ 859
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conventional hazards at the point o
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15.2.7. Accident management ❙ 863
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commissioning process. ❙ 869 ❙
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Event reports and root cause analyz
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Material regarding evaluation of ex
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Monitoring of initiatives in progre
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16. In‐Plant Accident Management
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❙ 895 ❙ 16. In‐Plant Accident
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16.2.2. Safety Functions ❙ 899
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is to place the plant in a safe, st
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each a final stable and controlled
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16.3.5. Review of Korean SAMG by KI
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this stage. Control rod degradation
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Pressurization of the containment
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Fractional Relase Fractional Relase
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19. Decommissioning Regional Basic
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| List of Tables | Table 1. Stages
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20.1. Introduction C O N T E N T S
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21. Safety Culture Regional Basic P
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21. Safety Culture 21.1. DEFINITION
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FIG. 21.1. Basic elements of safety
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❙ 1059 ❙ 21. Safety Culture Ult
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Obtaining useful information from o
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terms of what they do. There is an
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Consequently, people also understan
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❙ 1067 ❙ 21. Safety Culture 21.
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organization e.g. contractors. ❙
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21.4. MANAGEMENT OF SAFETY 21.4.1.
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subdivided in 4 sub‐objectives, w
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21.4.4. Specific safety management
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21.4.4.5. Self assessment ❙ 1089
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AtomCARE Regional Basic Professiona
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AtomCARE 1. OVERVIEW OF NATIONAL RA
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❙ 1121 ❙ AtomCARE The RETAC of
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❙ 1123 ❙ AtomCARE secondary rad
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❙ 1125 ❙ AtomCARE actions by pr
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2.1.4. Component Modules (Configura
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Classification Major Functions Tech
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❙ 1131 ❙ AtomCARE containment b
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❙ 1133 ❙ AtomCARE b) Monitors a
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a) Calculates the distribution of t
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❙ 1137 ❙ AtomCARE telephone or
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Introduction Of e‐FAST and Exerci
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| List of Figures | Fig. 1.1 Schema
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C O N T E N T S 1.1. OVERVIEW OF TH
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❙ 1181 ❙ Nuclear Safety Informa
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1. Overview of OPiS C O N T E N T S
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Regional Basic Professional Training Course in Korea

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