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1 Hee cheon NO Nuclear System/Hydrogen Lab. KAIST Chapter1: Nuclear Reactor Heat Transport System
2 Contents Chapter 1 Nuclear reactor heat transport system 1.1 Nuclear fuel 1.2 Reactor vessel 1.3 Reactor core and fuel assembly 1.4 Rod cluster control assembly
3 Fuel rod 1.1 Nuclear fuel
4 Pellet hourglassing and Pellet-Cladding Mechanical Interaction(PCMI) 1.1 Nuclear fuel dish/chamfer
5 Fuel cracking 1.1 Nuclear fuel
6 Example of fuel failure mechanisms 1.1 Nuclear fuel
7 Intergranular SCC 1.1 Nuclear fuel: Intergranular SCC
8 Transient cladding ballooning: LOCA 1.1 Nuclear fuel: Cladding Ballooning & rupture stress strain ultimate tensile stress
9 1.1 Nuclear fuel: Cladding rupture Post-CHF operation: Non-LOCA Reactivity-Initiated Accident(RIA)
10 PCMI 1.1 Nuclear fuel
11 APR1400 Typical 4 loop Rx vessel 1.2 Reactor vessel RCB: Rx Containment Building; TGB: Turbine/Generator Building; AB: Auxiliary Building; CB: Compound Building NSSS upper core plate Lower plenum Upper head Upper plenum
Reactor vessel Estimation of core mass flow rate: Flow paths APR1400 설계값 Vessel flow rate 20,991.2kg/sec Guide tube kg/sec Core shroud annulus 84.2 kg/sec Outlet nozzle gap kg/sec Alignment key kg/sec APR Bypass overall kg/sec3.0% UK EPR: 5.5%
Reactor vessel: irradiation specimen (Nil-ductility transition T)
16 Typical 4-Loop core 1.3 Reactor core and fuel assembly APR cladding volume(m^3)3.72Zr mass in fuel(Kg)Zr mass in struc(kg) Zr total mass(kg)
17 core and fuel 1.3 Reactor core and fuel assembly
18 Assembly 1.3 Reactor core and fuel assembly
Reactor core and fuel assembly
20 Assembly(PLUS7) 1.3 Reactor core and fuel assembly
21 Assembly(PLUS7) 1.3 Reactor core and fuel assembly
22 Assembly 1.3 Reactor core and fuel assembly
23 Spacer grid 1.3 Reactor core and fuel assembly
Reactor core and fuel assembly
Rod cluster control assembly
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