Regional Basic Professional Training Course in Korea

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C O N T E N T S | Table of Contents | 8.7. LARGE BREAK LOSS-OF-COOLANT ACCIDENT (LBLOCA) 8.7.1. Background 8.7.2. Rules and regulation for ECCS Performance in Korea 8.7.3. ECCS Design 8.7.4. Thermal‐Hydraulic Behaviours during LBLOCA 8.7.5. Evaluation Model 8.8. OVERVIEW OF SBLOCA ANALYSIS 8.8.1. General Behavior 8.8.1.1. Before the reactor trip 8.8.1.2. Reactor trip 8.8.1.3. Boil‐off in the core 8.8.1.4. Upset of SG heat transfer 8.8.1.5. Blowdown 8.8.1.6. Loop Seal Formation and Clearing 8.8.1.7. Steam binding 8.8.2. Analysis of SBLOCA of Korean Nuclear Power Plants 8.8.2.1. Acceptance Criteria [2] 8.8.2.2. SBLOCA Analysis Methods and Results
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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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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 9.1. BASIC CONCEPT
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9.1.1. Background 9. Probabilistic
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❙ 561 ❙ 9. Probabilistic Safety
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that are important for safety and d
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Some typical uses of level 2 PSA ar
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Release of fission products during
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e indicated according to their spec
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several pumps due to an inappropria
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Parts common to a number of systems
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9.4.3. Level 1 - level 2 interface
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In-vessel processes during the late
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y data, analyses and consideration
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examples of useful insights of PSAs
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Assessment -vs- demonstration. PSA
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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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Methods Questions/Evaluations propo
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documented by pencil goes through.
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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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They can belong to one of these fam
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12. Surveillance Programmes 12.1. C
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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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failure of which might put in jeopa
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12.3.6. Equipment ❙ 773 ❙ 12. S
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The grading criteria for detection
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12.4.1. General 12.4. IMPLEMENTATIO
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monitors are part of the safety sys
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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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19. Decommissioning 19.1. IAEA SAFE
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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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❙ 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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❙ 1017 ❙ 20. Waste Management h
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shall be appropriately taken into a
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20.5.3. Solidification of waste The
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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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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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[Fig. 1.6] Schematic of RCS(Reactor
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[Fig. 1.9] Schematic diagram of BOP
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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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[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
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