Regional Basic Professional Training Course in Korea

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C O N T E N T S | Table of Contents | 4.1. THE SAFETY OF NUCLEAR POWER PLANTS : Design (Based on IAEA REQUIREMENTS NS‐R‐1 [4.1]) 4.1.1. Safety objectives and defense‐in‐depth 4.1.2. Requirements for management of safety 4.1.3. Principal technical requirements 4.1.4. Requirements for plant design 4.1.5. Requirements for design of plant systems 4.2. RESEARCH AND TEST REACTORS 4.2.1. Introduction 4.2.2. Design considerations of research and test reactors 4.2.3. Description of OSIRIS‐reactor 4.2.4. Safety of research reactors and its relation to power reactor safety 4.2.5. Some severe accidents which have occurred in the past 4.2.6. HANARO Research Reactor 3.8.2. Other international conventions | List of Tables | Table 4.1. Core Parameters of OSIRIS Reactor (U3Si2) Table 4.2. HANARO Reactors Specifications
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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 174 and 175: Regional Basic Professional Trainin
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5. Siting Considerations ❙ 309
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❙ 311 ❙ 5. SITING CONSIDERATION
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evaluated. ❙ 315 ❙ 5. SITING CO
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5.1.4. Population and emergency pla
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determine their liquefaction potent
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5.3.3.1. Marine floods ❙ 335 ❙
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and its time of arrival at the site
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Dry deposit The rate of dry deposit
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etention of radioelements by sedime
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5.6.1. General 5.6. DEMOGRAPHY AND
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6. Safety Classification Of Structu
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6.5. ELECTRICAL EQUIPMENT CLASSIFIC
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C O N T E N T S 7.1. NUCLEAR QUALIT
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7.1.1. Definition 7. Quality Assura
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independence of inspection. ❙ 413
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❙ 415 ❙ 7. Quality Assurance 7.
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7.2.3. Statute Related to Review an
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6. Document control 7. Control of p
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1. ‥‥‥‥‥‥‥ : : 17. In
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Operator Production Specializatio n
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￭ CSA N286.3: Construction and In
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Table 1. Comparison of nuclear qual
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❙ 429 ❙ 7. Quality Assurance (2
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systems and components. ❙ 431 ❙
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❱ Article 78 (Test Control) ❙ 4
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❙ 439 ❙ 7. Quality Assurance (h
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❙ 441 ❙ 7. Quality Assurance co
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❙ 443 ❙ 7. Quality Assurance ot
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❙ 445 ❙ 7. Quality Assurance Su
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❙ 447 ❙ 7. Quality Assurance in
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7.4.1. Introduction 7.4. QUALITY AS
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7.4.3. Type of Audit ❙ 451 ❙ 7.
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❙ 453 ❙ 7. Quality Assurance Qu
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❙ 455 ❙ 7. Quality Assurance re
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❙ 457 ❙ 7. Quality Assurance ap
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7.5.1.2 Inspection Methods and Cont
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KINS/PI‐QM‐20 Welder qualificat
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8-A. Deterministic Accident Analysi
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| List of Tables | Table 8.1 Event
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Figure 8.8‐11 Core Level of 0.5 f
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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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❙ 991 ❙ 19. Decommissioning kno
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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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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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❙ 1045 ❙ 20. Waste Management s
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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 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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