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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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❙ 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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❙ 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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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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❙ 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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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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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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❙ 283 ❙ 4. DESIGN OF NUCLEAR RE
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❙ 291 ❙ 4. DESIGN OF NUCLEAR RE
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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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5.4.2. Sources of risk 5.4.3. Evalu
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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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6. Safety Classification Of Structu
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Safety functions necessary to preve
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6. Safety Classification Of Structu
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6.1.3. Principal Safety Classes 6.
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6. Safety Classification Of Structu
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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. 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. 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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❙ 473 ❙ 8-A. Deterministic Acci
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❙ 475 ❙ 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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❙ 481 ❙ 8-A. Deterministic Acci
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Table 8‐3 Typical Initial Conditi
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❙ 485 ❙ 8-A. Deterministic Acci
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❙ 487 ❙ 8-A. Deterministic Acci
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❙ 489 ❙ 8-A. Deterministic Acci
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8.5.3. Decrease in Reactor Coolant
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❙ 493 ❙ 8-A. Deterministic Acci
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or by operator error, often during
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❙ 497 ❙ 8-A. Deterministic Acci
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❙ 499 ❙ 8-A. Deterministic Acci
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❙ 501 ❙ 8-A. Deterministic Acci
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8-B. Deterministic Accident Analysi
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❙ 607 ❙ 9. Probabilistic Safety
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Assessment -vs- demonstration. PSA
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❙ 611 ❙ 9. Probabilistic Safety
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❙ 619 ❙ 9. Probabilistic Safety
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✼✼✼ REFERENCES ✼✼✼ ❙
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10-A. Limiting Conditions for Opera
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Table 10.2 Operational Modes of Ulj
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C O N T E N T S 11.1. THE HUMAN FAC
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11. Human Performance: A Perspectiv
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11. Human Performance: A Perspectiv
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11. Human Performance: A Perspectiv
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Methods Questions/Evaluations propo
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documented by pencil goes through.
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11. Human Performance: A Perspectiv
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B. Model of Mistake 11. Human Perfo
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C. Model of Slips 11. Human Perform
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11. Human Performance: A Perspectiv
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They can belong to one of these fam
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C O N T E N T S | Table of Contents
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12. Surveillance Programmes 12.1. C
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❙ 749 ❙ 12. Surveillance Progra
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❙ 751 ❙ 12. Surveillance Progra
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12.2.2. Surveillance of integrity o
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Containment spray systems; Chemical
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High energy piping and associated p
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❙ 759 ❙ 12. Surveillance Progra
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failure of which might put in jeopa
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❙ 771 ❙ 12. Surveillance Progra
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The grading criteria for detection
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❙ 777 ❙ 12. Surveillance Progra
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monitors are part of the safety sys
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❙ 783 ❙ 12. Surveillance Progra
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inspection. ❙ 789 ❙ 12. Surveil
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12.5.4. Example of Regulatory Inspe
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maximum flow in addition to rated f
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C O N T E N T S 1. The Overview of
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15. Operational Safety Regional Bas
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15.3. OPERATING ORGANIZATION AT KOR
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16. In‐Plant Accident Management
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16.5.3. Reference source terms Tabl
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17. Radiological Emergency Planning
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❙ 953 ❙ 17. Radiological Emerge
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2. Emergency Classification and Res
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❙ 957 ❙ 17. Radiological Emerge
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C O N T E N T S | Table of Contents
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19. Decommissioning 19.1. IAEA SAFE
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❙ 973 ❙ 19. Decommissioning res
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from regulatory control. ❙ 999
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❙ 1001 ❙ 19. Decommissioning as
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material (of the order of 300 μSv
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methods of decommissioning the nucl
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✼✼✼ REFERENCES ✼✼✼ ❙
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❙ 1009 ❙ 19. Decommissioning 19
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20. Waste Management Regional Basic
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20. Waste Management 20.1. INTRODUC
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shall be appropriately taken into a
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❙ 1023 ❙ 20. Waste Management d
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20.5.3. Solidification of waste The
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❙ 1033 ❙ 20. Waste Management T
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Nuclide Half‐life Decay character
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For disposal of LILW from NPPs, the
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❙ 1039 ❙ 20. Waste Management c
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C O N T E N T S 21.1. DEFINITION AN
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Licensing Process of Nuclear Facili
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❙ 1097 ❙ Licensing Process of N
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C O N T E N T S | Table of Contents
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C O N T E N T S 1. Introduction to
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Introduction Of e‐FAST and Exerci
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❙ 1145 ❙ Introduction Of e‐FA
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❙ 1147 ❙ Introduction Of e‐FA
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[Fig. 1.6] Schematic of RCS(Reactor
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[Fig. 1.9] Schematic diagram of BOP
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❙ 1153 ❙ Introduction Of e‐FA
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2.1.3. e‐FAST Function [Fig. 2.3]
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2.2 USER MANUAL 2.2.1. General Guid
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[Fig. 2.4] e‐FAST for KSNP 2.2.2.
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14.1~2 Main Steam Line Break Inside
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Summary [Fig. 2.6] Trend graph of v
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❙ 1165 ❙ Introduction Of e‐FA
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[Table 3.1] Simulation result for p
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[Fig. 3.1] Trend of major system pa
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[Fig. 3.3]Trend of major system par
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Nuclear Safety Information Center (
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| List of Tables | Table 1. Informa
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Operational Performance Information
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2.5. References Operational Perform