Regional Basic Professional Training Course in Korea

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Regional Basic Professional Training Course (BPTC) on Nuclear Safety As we showed in 1.2.3.2 all neutrons are not emitted immediately after fission. In fact, a small proportion of delayed neutrons are emitted following beta decay of fission products (between about 0.08 seconds and 58.2 seconds after fission). Usually, the delayed neutrons are grouped in families (usually 6 families are considered) according to the half-lives of fission products precursors. For instance, Table 1.7 gives, for a thermal neutron-induced fission on 235 U, the proportion of delayed neutrons emitted (normalized to one neutron emitted by fission) is in each families (βi) and the associated half-life TABLE 1.7. Proportion of delayed neutrons in each families (normalized to one neutron emitted by fission) and the associated half-life in thermal neutron induced fission of 235U Family 1 2 3 4 5 6 T1/2 0.18 0.49 2.23 5.97 21.84 54.50 β i 24*10 -5 123*10 -5 117*10 -5 ❙ 50 ❙ 263*10 -5 108*10 -5 45*10 -5 The Table 1.8 gives, for thermal neutrons-induced fissions the proportion of delayed neutrons for different fissioning nuclides. TABLE 1.8. Proportion of delayed neutrons for different fissioning nuclides Nuclide 235U 239Pu 241Pu 238U 240Pu 232Th β 680*10 -5 210*10 -5 490*10 -5 1470*10 -5 270*10 -5 490*10 -5 In order to describe delayed neutrons in kinetic equations, we must describe the decay process of the different precursor families. Let Ci the concentration of precursor i and λi the corresponding decay constant. The number of delayed neutrons emitted is the same as the overall beta decay activity. The proportion of prompt neutrons is (1-β).
❙ 51 ❙ 1. Nuclear Reactor Principles where ρ is the reactivity defined earlier. A graphical resolution of this equation is presented in Figure 1.25. For a given reactivity ρ we get 7 possible ω values. Six of them have negative values and describe transitory terms and the last one has the same sign as ρ. If ρis positive, there is an exponential increase of neutron population and if ρ is negative there is a decrease. This is similar to what was found without delayed neutrons. To illustrate the influence of these delayed neutrons, let us take numerical values. For instance, if ρ is quite small, the general solution is: to be compared with: ω = ρ / l in the case of kinetic equation without delayed neutrons. The added term in the denominator corresponds to the average time of delayed neutron emission. This is added to the average neutron lifetime in the reactor (which is very short). Delayed neutrons slow then the kinetic behaviour of neutron multiplication. Consider the same numerical example as before, with ρ= 10 pcm, we find that the
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❙ 101 ❙ 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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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 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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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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13.Maintenance Management in KHNP R
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15. Operational Safety 15.1. IAEA S
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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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conventional hazards at the point o
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commissioning process. ❙ 869 ❙
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Monitoring of initiatives in progre
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16. In‐Plant Accident Management
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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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✼✼✼ REFERENCES ✼✼✼ ❙
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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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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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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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