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Regional Basic Professional Training Course in Korea
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Summary<br />
[Fig. 2.6] Trend graph of variables<br />
❙ 1163 ❙<br />
Introduction Of e‐FAST and Exercise<br />
This function is to show the current value of variables <strong>in</strong> a format of summary report.<br />
These variables are composed of 10 summary groups and each summary page displays 11<br />
variables respectively as shown <strong>in</strong> [Fig. 2.7].<br />
[Fig. 2.7] Summary report of essential variables
<strong>Regional</strong> <strong>Basic</strong> <strong>Professional</strong> <strong>Tra<strong>in</strong><strong>in</strong>g</strong> <strong>Course</strong> (BPTC) on Nuclear Safety Plot Rx Core : 3D Reactor Core trend CEA : Control Element Assembly trend and control Secondary : from Steam Generator to Grid MFWS 1,2 : Ma<strong>in</strong> Feedwater System AFWS : Auxiliary Feedwater System Electric : Electric systems such as Generator, Switchyard etc. [Fig. 2.5] MIMIC of e‐FAST This function is to show the event progress for ma<strong>in</strong> variables. If you select the desired variable summary, 4 trend graphs shall be provided respectively and the trend of variables shown <strong>in</strong> the graph is available up to 4 with different colors. And currently 11 submenus are provided as shown <strong>in</strong> [Fig. 2.6]. ❙ 1162 ❙
Summary [Fig. 2.6] Trend graph of variables ❙ 1163 ❙ Introduction Of e‐FAST and Exercise This function is to show the current value of variables <strong>in</strong> a format of summary report. These variables are composed of 10 summary groups and each summary page displays 11 variables respectively as shown <strong>in</strong> [Fig. 2.7]. [Fig. 2.7] Summary report of essential variables
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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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❙ 13 ❙ 1. Nuclear Reactor Princ
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❙ 15 ❙ 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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❙ 23 ❙ 1. Nuclear Reactor Princ
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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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❙ 29 ❙ 1. Nuclear Reactor Princ
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❙ 31 ❙ 1. Nuclear Reactor Princ
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1.2.3.2. Neutron emission in fissio
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❙ 35 ❙ 1. Nuclear Reactor Princ
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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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❙ 43 ❙ 1. Nuclear Reactor Princ
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❙ 45 ❙ 1. Nuclear Reactor Princ
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❙ 47 ❙ 1. Nuclear Reactor Princ
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❙ 51 ❙ 1. Nuclear Reactor Princ
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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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❙ 65 ❙ 2. Radiation Protection
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2.2.4. Effective dose ❙ 67 ❙ 2.
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❙ 69 ❙ 2. Radiation Protection
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❙ 71 ❙ 2. Radiation Protection
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❙ 73 ❙ 2. Radiation Protection
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❙ 75 ❙ 2. Radiation Protection
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schematically in Fig. (2.7). ❙ 77
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❙ 79 ❙ 2. Radiation Protection
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The great utility of the G‐M tube
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❙ 83 ❙ 2. Radiation Protection
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❙ 85 ❙ 2. Radiation Protection
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❙ 87 ❙ 2. Radiation Protection
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❙ 89 ❙ 2. Radiation Protection
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❙ 91 ❙ 2. Radiation Protection
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protection conditions. These factor
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2.6.2. Effects of dose, dose‐rate
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❙ 97 ❙ 2. Radiation Protection
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2.7. Principles of Radiological Pro
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❙ 101 ❙ 2. Radiation Protection
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❙ 109 ❙ 2. Radiation Protection
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❙ 111 ❙ 2. Radiation Protection
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❙ 113 ❙ 2. Radiation Protection
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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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✼✼✼ REFERENCES ✼✼✼ ❙
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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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C O N T E N T S | Table of Contents
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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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❙ 227 ❙ 4. DESIGN OF NUCLEAR RE
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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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❙ 241 ❙ 4. DESIGN OF NUCLEAR RE
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❙ 243 ❙ 4. DESIGN OF NUCLEAR RE
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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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❙ 255 ❙ 4. DESIGN OF NUCLEAR RE
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❙ 257 ❙ 4. DESIGN OF NUCLEAR RE
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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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❙ 263 ❙ 4. DESIGN OF NUCLEAR RE
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❙ 267 ❙ 4. DESIGN OF NUCLEAR RE
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4.1.5.9. Radiation protection Gener
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❙ 271 ❙ 4. DESIGN OF NUCLEAR RE
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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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❙ 297 ❙ 4. DESIGN OF NUCLEAR RE
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4.2.6.5. Neutron Activity Analysis
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❙ 301 ❙ 4. DESIGN OF NUCLEAR RE
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❏ physical separation. ❙ 303
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5. Siting Considerations Regional B
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C O N T E N T S | Table of Contents
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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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6. Safety Classification Of Structu
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function; 6. Safety Classification
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6. Safety Classification Of Structu
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6. Safety Classification Of Structu
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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. Safety Classification Of Structu
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6. Safety Classification Of Structu
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6.4.3. Seismic category 1: 6.4.3.1.
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6. Safety Classification Of Structu
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6. Safety Classification Of Structu
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6. Safety Classification Of Structu
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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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❙ 479 ❙ 8-A. Deterministic Acci
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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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❙ 519 ❙ 8-B. Deterministic Acci
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8.2.5. Evaluation Model ❙ 521 ❙
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❙ 523 ❙ 8-B. Deterministic Acci
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❙ 525 ❙ 8-B. Deterministic Acci
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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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❙ 531 ❙ 8-B. Deterministic Acci
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❙ 533 ❙ 8-B. Deterministic Acci
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❙ 537 ❙ 8-B. Deterministic Acci
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to ECCS injection time using CEFLAS
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❙ 541 ❙ 8-B. Deterministic Acci
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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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❙ 547 ❙ 8-B. Deterministic Acci
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8.8.2.2.3 RELAP5‐sEM Methodology
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❙ 551 ❙ 8-B. Deterministic Acci
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❙ 553 ❙ 8-B. Deterministic Acci
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performance, correct set points, an
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2) Safety Limits and Safety System
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13.Maintenance Management in KHNP R
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❙ 799 ❙ 13.Maintenance Manageme
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❙ 801 ❙ 13.Maintenance Manageme
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C O N T E N T S | Table of Contents
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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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❙ 845 ❙ 15. Operational Safety
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15.2.2. Organization and functions
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− Temporary and permanent plant m
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❙ 851 ❙ 15. Operational Safety
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Operating procedures and instructio
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❙ 855 ❙ 15. Operational Safety
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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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❙ 865 ❙ 15. Operational Safety
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❙ 867 ❙ 15. Operational Safety
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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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❙ 875 ❙ 15. Operational Safety
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❙ 881 ❙ 15. Operational Safety
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Monitoring of initiatives in progre
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❙ 885 ❙ 15. Operational Safety
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C O N T E N T S | Table of Contents
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16. In‐Plant Accident Management
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❙ 895 ❙ 16. In‐Plant Accident
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❙ 897 ❙ 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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❙ 905 ❙ 16. In‐Plant Accident
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❙ 911 ❙ 16. In‐Plant Accident
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16.3.5. Review of Korean SAMG by KI
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❙ 915 ❙ 16. In‐Plant Accident
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❙ 921 ❙ 16. In‐Plant Accident
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this stage. Control rod degradation
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❙ 925 ❙ 16. In‐Plant Accident
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❙ 927 ❙ 16. In‐Plant Accident
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❙ 929 ❙ 16. In‐Plant Accident
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Pressurization of the containment
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❙ 933 ❙ 16. In‐Plant Accident
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❙ 935 ❙ 16. In‐Plant Accident
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❙ 943 ❙ 16. In‐Plant Accident
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Fractional Relase Fractional Relase
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✼✼✼ REFERENCES ✼✼✼ ❙
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C O N T E N T S | Table of Contents
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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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❙ 1073 ❙ 21. Safety Culture opp
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❙ 1077 ❙ 21. Safety Culture cou
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❙ 1079 ❙ 21. Safety Culture All
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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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❙ 1085 ❙ 21. Safety Culture pro
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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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❙ 1091 ❙ 21. Safety Culture as
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C O N T E N T S | Table of Contents
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- Page 1145: Introduction Of e‐FAST and Exerci
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