Areva EPR

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INTRODUCTION In a nuclear power plant, the reactor is the part of the facility in which the heat, necessary to produce steam, is generated by fission of atom nuclei. The produced steam drives a turbine generator, which generates electricity. The nuclear steam supply system is therefore the counterpart of coal, gas or oil-fired boilers of fossil-fuelled plants. In a Pressurized Water Reactor (PWR) like the EPR, ordinary water is utilized to remove the heat formed inside the reactor core by the nuclear fission phenomenon. This water also slows down (or moderates) neutrons (constituents of atom nuclei that are released in the nuclear fission process). Slowing down neutrons is necessary to keep the chain reaction going (neutrons have to be moderated to be able to break down the fissile atom nuclei). The heat produced inside the reactor core is transferred to the turbine through the steam generators. From the reactor core coolant circuit (primary circuit) to the steam circuit used to feed the turbine (secondary circuit), only heat is transferred and there is no water exchange. The primary water is pumped through the reactor core and the primary side of the steam generators, in four parallel closed loops, by electric motor-powered coolant pumps. Each loop is equipped with a steam generator and a coolant pump. The reactor operating pressure and temperature are such that the cooling water does not evaporate and remains in the liquid state, which intensifies its cooling efficiency. A pressurizer controls the pressure; it is connected to one of the loops. Pressurizer Primary Pump Steam Generator Control Rod Drive Mechanism The feedwater entering the secondary side of the steam generators absorbs the heat transferred from the primary side and evaporates to produce saturated steam. The steam is dried in the steam generators then routed to the turbine to drive it. Then, the steam is condensed and it returns as feedwater to the steam generators. The generator, driven by the turbine, generates electricity. Transformer † The following chapters will provide detailed explanation about the description and operation of PWR nuclear power stations based on the EPR reactor. Reactor Core Vessel Feedwater Pump Reheater Cooling Water Generator Condenser High Voltage Electrical Lines Primary system Secondary system: – Steam – Water 04 I I 05
TABLE OF CONTENTS page 08 page 44 page 52 page 54 EPR NUCLEAR ISLAND >EPR LAYOUT >PRIMARY SYSTEM >REACTOR CORE >FUEL ASSEMBLIES >CONTROL ASSEMBLIES >REACTOR PRESSURE VESSEL AND INTERNAL STRUCTURES >STEAM GENERATORS SAFETY >NUCLEAR SAFETY Three protective barriers Defense in depth >EPR SAFETY Design choices for reducing the probability of accidents liable to cause core melt Design choices for limiting the consequences of a severe accident EPR CONSTRUCTION >EPR CONSTRUCTION TIME SCHEDULE Design features Construction and erection methods Commissioning tests PLANT OPERATION, MAINTENANCE & SERVICES A 92% availability factor over the entire plant life A high level of operational maneuverability An enhanced radiological protection Plant services Continuously improving service to customers page 58 CONCLUDING REMARKS >REACTOR COOLANT PUMPS AND MAIN COOLANT LINES >PRESSURIZER >SYSTEMS Chemical and volume control Safety injection / residual heat removal In-containment refueling water storage tank Emergency feedwater Other safety systems Component Cooling Water Essential Service Water Other systems Power supply Fuel handling and storage >INSTRUMENTATION & CONTROL SYSTEM EPR I & C overall architecture Role of the I & C systems 06 I I 07
Page 1 and 2: EPR
Page 3 and 4: • EDF (Electricité de France), a
Page 5: FOREWORD Security of energy supply
Page 9 and 10: EPR LAYOUT page 10 >PRIMARY SYSTEM
Page 11 and 12: Water outfall Switchyard Water inta
Page 13 and 14: 2 t +8.50m 1 2 3 4 5 6 1 2 8 6 1 5
Page 15 and 16: CHARACTERISTICS DATA Reactor coolan
Page 17 and 18: In-core instrumentation 12 lance yo
Page 19 and 20: 17 x 17 fuel assembly CHARACTERISTI
Page 21 and 22: Plug connector Upper limit position
Page 23 and 24: Reactor pressure vessel and interna
Page 25 and 26: Heavy reflector The heavy reflector
Page 27 and 28: Steam generator cutaway Secondary m
Page 29 and 30: Reactor coolant pump cutaway 1 2 3
Page 31 and 32: CHARACTERISTICS DATA Main coolant l
Page 33 and 34: CHARACTERISTICS DATA Pressurizer De
Page 35 and 36: SAFETY INJECTION / RESIDUAL HEAT RE
Page 37 and 38: OTHER SAFETY SYSTEMS The Extra Bora
Page 39 and 40: FUEL HANDLING AND STORAGE The react
Page 41 and 42: Computer-generated image of the EPR
Page 43 and 44: Limitation functions and protection
Page 45 and 46: NUCLEAR SAFETY The fission of atomi
Page 47 and 48: EPR SAFETY The first important choi
Page 49 and 50: Optimized management of accidental
Page 51 and 52: The dedicated corium spreading and
Page 53 and 54: EPR CONSTRUCTION TIME SCHEDULE The
Page 55 and 56: PLANT OPERATION, MAINTENANCE & SERV
Page 57 and 58:
Operators have developed ambitious
Page 59 and 60:
EPR Key to power station cutaway 1
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Areva EPR

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