Regional Basic Professional Training Course in Korea

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Regional Basic Professional Training Course (BPTC) on Nuclear Safety the database is rich in instrumental information or when sufficient data exist to convert reliably from intensity to magnitude. In this approach, attenuation relationships that express the ground motion parameter as a function of magnitude and distance from the site to the seismogenic source and site conditions are used. Deterministic or probabilistic approaches may be used to determine design‐basis ground motion SL‐2. In the deterministic approach, the maximum potential earthquake should be assumed to occur at the point on the seismogenic structure closest to the site. When the site is within the boundaries of a seismogenic structure, the maximum potential earthquake shall be assumed to occur under the site. In this case, special care should be taken to demonstrate that the seismogenic structure is not capable. When the maximum potential earthquake is not associated with specific seismogenic structure in the seismotectonic province that includes the site, it is assumed to occur at some agreed specific distance from the site where it is assumed that seismogenic structure does not exist and that the probability of earthquake occurring is very low. This distance may be in the range of a few, to tens of kilometres and depend on the best estimate of the focal depth. The probabilistic approach involves the following steps: idealization of the seismotectonic model in terms of source type, geometry and depth; for each source, identification of magnitude‐frequency or intensity‐frequency relationships, maximum magnitude or maximum intensity, attenuation relationships; choice of appropriate stochastic models; evaluation of the best estimate hazard curve with appropriate confidence intervals; for design‐basis, use of those levels of ground motion where probabilities of being exceeded meet the safety standard required. The characteristics of the design‐basis ground motions for SL‐1 and SL‐2 shall be expressed in term of response spectra having a range of damping values and compatible time histories. Several methods can be used to generate response spectra: standard response spectrum whose shape is obtained from many response spectra derived using ❙ 332 ❙
❙ 333 ❙ 5. SITING CONSIDERATIONS earthquake records and scaled to site specific value of ground acceleration (velocity or displacement); site specific response spectrum developed from strong motion records obtained at the site or at places having similar seismic, geological and soil characteristics; uniform confidence response spectrum resulting of regression studies of the attenuation of the ordinates of response spectra for different periods having the same confidence values for all periods considered. Time histories corresponding to both SL‐1 and SL‐2 shall be developed because of their use in applications such as studies of non‐linear behaviour of structures, soil‐structures interaction and equipment response. The duration of earthquake ground motion is determined mainly by the length and velocity of the fault rupture and can be correlated with magnitude. The generation of design time histories may be obtained by simulating ground motion; ground motion records obtained in the site vicinity or at other places having similar seismic, geological and soil characteristics. If no specific information is available on the peak acceleration of vertical ground motion in the site vicinity, it is assumed on a empirical basis, a ratio between vertical and horizontal directions, from ½ to 1 and may be largest in the near field. 5.3.2.5. Potential for surface faulting at the site On the basis of geological, geophysical, geodetic and seismological data, a fault shall be considered capable if it shows evidence of past movement or movement of a recurring nature within such a period (tens of thousands of years in highly active areas, much longer in less active areas) that it is reasonable to infer that further movement at or near the surface can occur. Sufficient surface and sub‐surface investigations should be obtained to show the absence of faults at or near the site, or, if faulting is present, to describe the direction, extent and history of movements on them and to estimate reliably the age of the youngest movement. In this case investigations should be made, including stratigraphical and topographical analyses, geodetic and geophysical surveys, trenching, boreholes, age dating of sediments or fault rocks, local seismological investigations and any other appropriate techniques to ascertain when movement last occurred. Where reliable
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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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❙ 221 ❙ 4. DESIGN OF NUCLEAR RE
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4.1.1.2. The concept of defence in
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4.1.2. Requirements for management
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administrative control. ❙ 231 ❙
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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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the safety function would be requir
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6. Safety Classification Of Structu
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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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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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❙ 799 ❙ 13.Maintenance Manageme
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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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