Reactor Technology --- Materials, Fuel and Safety

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1 Reactor Technology --- Materials, Fuel and Safety UCT EEE4101F / EEE4103F April 2015 Emeritus Professor David Aschman Based on lectures by Dr Tony Williams Beznau NPP, Switzerland, 2 x 365 MWe Westinghouse, 1969/71

2 Course Structure Unit 1: Reactor materials Unit 2. Reactor types Unit 3: Health physics, Dosimetry, Environment Unit 4: Reactor safety Unit 5: Nuclear fuel production Unit 6: Waste issues David Aschman UCT - Reactor Technology 2

3 Unit 1: Reactor Materials In this unit we shall discuss: Introduction to the functionality of a reactor core What are the main components in a reactor core What are their required properties Which materials are used The difference between thermal and fast reactors David Aschman UCT - Reactor Technology 3

4 Nuclear Power Plant fundamntals David Aschman UCT - Reactor Technology 4

5 Energy from Fission and Fusion High binding energy, high stability, energy release upon formation E=mc 2 Fission Fusion Kinetic energy of fission products 175 MeV Kinetic energy of fission neutrons 5 MeV prompt heat useful Prompt γ radiation 7 MeV fission products γ + β + radiation 7+6 MeV decay heat 200 MeV Neutrinos 10 MeV not useful David Aschman UCT - Reactor Technology 5

6 Energy release of Fission Reaction 200 MeV 1 ev = J nuclei/mol h f -19 TJ/mol h f -80 TJ/kg Energy carrier Reaction enthaply, MJ/kg Factor Fissile material 80'000'000 1 Oil '900'000 Gas 44 1'800'000 Coal '300'000-2'700'000 Lignite <20 >4'000'000 1 kg fissile material (e.g. U-235) corresponds to ~3000 t Coal A cube with sides 3.7cm A cube with sides 8.4m David Aschman UCT - Reactor Technology 6

7 Neutron Economy reactor critical = power constant 100 % fissions 100 % fast neutrons moderation therm. neutr. Of the ~ 2.5 neutrons emitted per Fission, exactly 1 has to be available to cause another fission = criticality fast leakage neutrons escape the reactor absorption of fast neutrons (in U-238, moderator, construction materials) thermal leakage neutrons escape the reactor absorption of thermal neutrons (in U-238, moderator, construction materials) absorption of thermal neutrons in control rods David Aschman UCT - Reactor Technology 7

8 A Simple Reactor Model Leibstadt NPP, Switzerland, 1200 MWe, General Electric BWR6, 1984 David Aschman UCT - Reactor Technology 8

9 1 barn = 1 x cm 2 Nuclear Cross-sections: Elastic Scattering, Inelastic Scattering, Absorption, Fission Thermal Scattering Thermal Absorption Thermal Fission Fast Absorption Fast Fission U235 Pu239 U238 Aluminium Berylium Graphite Iron Zirconium Lead Hydrogen Deuterium Helium Nitrogen Sodium Potassium Lithium Boron Cadmium Xenon Hafnium The macroscopic cross-section is important for functionality (Σ=ρσ) David Aschman UCT - Reactor Technology 9

10 Ratios of Macroscopic Scattering to Macroscopic Absorption Σs/ Σa Aluminium Berylium Graphite Iron Zirconium Lead Sodium Hafnium David Aschman UCT - Reactor Technology 10

11 David Aschman UCT - Reactor Technology 11

12 Elastic scattering Fission and Absorption David Aschman UCT - Reactor Technology 12

13 Main Components of Reactor Core Fuel Cladding Coolant Moderator (in some cases same as coolant) Control & shutdown system Criteria: Temperature, neutronics, mechanics, David Aschman UCT - Reactor Technology 13

14 Properties of Core Materials Fuel (Pellets) Chemically inert up to high temperatures Mechanically stable up to high temperatures Retention of fission products Stable under irradiation Good heat transfer properties "Suitable" neutronics properties First barrier against release Typical materials Uranium Dioxide, Uranium Carbide, Uranium Metal David Aschman UCT - Reactor Technology 14

15 Properties of Core Materials David Aschman UCT - Reactor Technology 15

16 Properties of Core Materials Cladding Heat transfer medium from fuel to coolant Second barrier against release Mechanically stable to high temperatures Chemically stable with fuel and coolant Stable under irradiation Neutronically "suitable" Typical materials: Zirconium Alloy, Steel, Magnesium Alloy David Aschman UCT - Reactor Technology 16

17 Properties of Core Materials Each BWR fuel assembly produces on average 5MW for 5 years And therefore each rod 50kw. There are a number of processes which need to be taken into account both when designing fuel and when storing it Fission product gas production Cladding corrosion Hydriding of cladding Changes in fuel pellet structure Plenum Fuel Pellet Typically some % of fission Gas is released into the plenum Fuel Cladding David Aschman UCT - Reactor Technology 17

18 Properties of Core Materials David Aschman UCT - Reactor Technology 18

19 Cladding Thickness = 600 um David Aschman UCT - Reactor Technology 19

20 David Aschman UCT - Reactor Technology 20

21 David Aschman UCT - Reactor Technology 21

22 The most common reason for fuel rod failure today is debris fretting David Aschman UCT - Reactor Technology 22

23 David Aschman UCT - Reactor Technology 23

24 In general, the majority of fuel failures today result from "debris fretting". Typically a failure rate betwen 1x10-5 and 1x10-6 is observed David Aschman UCT - Reactor Technology 24

25 Properties of Reactor Materials Coolant Must be a fluid during operation Must be able to provide sufficient heat removal (large heat capacity, good heat transfer, large volumes,..) Chemically inert for cladding and reactor Neutronically suitable Typical Materials Light Water, Heavy Water, Carbon Dioxide, Helium, Molten Metal, Molten Salt David Aschman UCT - Reactor Technology 25

26 Main Components of Reactor Core Moderator Large scattering cross section Small absorption cross section Suitable for use at high pressures and temperatures Low atomic weight High density Chemically inert with Coolant Typical materials: light water, heavy water, graphite, David Aschman UCT - Reactor Technology 26

27 Main Components of Reactor Core Control & Shut down System Must operate reliably and quickly Must remain operable under all conceivable accident scenarios Must be appropriate for the type of spectrum in the reactor David Aschman UCT - Reactor Technology 27

28 Unit 1: Reactor Materials Review We understand the requirements such that a reactor core will function We know which are the main components in a reactor core We know which are their required properties We know which materials are typically used David Aschman UCT - Reactor Technology 28

Reactor Technology: Materials, Fuel and Safety 14 th 17 th April 2009 Dr. Tony Williams

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