Regional Basic Professional Training Course in Korea

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Regional Basic Professional Training Course (BPTC) on Nuclear Safety TABLE 1.6. : Mass and activity balances of transuranium nuclei present in a PWR fuel (initial mass is 1 ton, burn-up 33000MWd/Mut) Activity (Bq) Mass (g) Reactor Shutdown After 3 years Uranium 956000 7.25E+17 1.33E+11 Neptunium 553 7.07E+17 7.03E+11 Plutonium 8940 1.78E+16 3.54E+15 Americium 124 7.14E+15 2.21E+13 Curium 44 1.35E+15 9.66E+13 Berkelium 2.3E-6 4.07E+8 1.11E+7 Californium 0.97E-3 3.85E+6 2.63E+6 Total 965000 1.46E+18 3.66E+15 As shown in Table 1.6 Pu is the major contributor to the activity in burned fuel. But as discussed earlier, Pu has also two fissile isotopes and could thus be used as a fuel. The best way for Pu utilization, from the neutronic point of view would be a fast reactor since the number of neutrons emitted by absorption is about 2.25, thus allowing breeding. However, the production of Pu in thermal reactors is higher than its consummation in fast reactors (the development of these reactors faced some technological and political problems). It was then suggested to use plutonium based fuel in standard light water reactors (usually known as plutonium recycling). This operation supposes the separation of the different components of irradiated fuel (fission products, uranium and plutonium), which is called fuel reprocessing. 1.3.2.3. Formation of fission products and consequent poisoning effects In subsection 1.2.3.3 we showed the fission fragments yields for some fissioning systems. ❙ 44 ❙
❙ 45 ❙ 1. Nuclear Reactor Principles Once emitted by fission, these fragments emit prompt neutrons, decay by beta mode and, since they are produced in a reactor, absorb neutrons and continue their transformations. There are different routes of production or destruction of a particular nuclide; the decay of the nuclide, the transmutation by neutron absorption, the production from fission, the production by decay of precursors, the production by neutron reactions on other nuclides. This can be written in the general form as: Where λi is the decay constant of nuclide i, and σiis its absorption cross-section. The first summation (index k) is done over all fissile isotope k with the corresponding fission cross-section σ k f and Y k i the direct fission yield of nuclide i from fission of isotope k. The second sum is done over all fission products leading to nuclide i either by decay (corresponding constant λ ji ) or absorption (cross section σ ji ). There are a huge number of fission products. The most famous ones are 135 Xe and 149 Sm because they have very large absorption cross-sections in the thermal range (about 3 million barns for 135 Xe and forty thousand barns for 149 Sm). Once created, these fission products contribute to neutron absorption in the fuel and thus have direct implications in reactor operations. This is the reason why we usually speak about fission products as poisoning nuclides. The following diagram (all data taken from JEF-PC version 2) gives the production and the destruction of 135 Xe. Horizontal arrows show beta decay with the corresponding half-life and vertical arrows show direct production by fission with the corresponding fission yield for a thermal neutron-induced fission of 235 U. Although not represented, each one of these nuclides may be destructed by capture. Nevertheless, except for 135 Xe,
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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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❙ 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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10.8.6. 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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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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16. In‐Plant Accident Management
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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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