Upload
sophia-fowler
View
219
Download
1
Tags:
Embed Size (px)
Citation preview
1
Hee cheon NO
Nuclear System/Hydrogen Lab.
KAIST
Chapter1: Nuclear Reactor Heat Transport System
2
Contents
Chapter 1 Nuclear reactor heat transport sys-
tem
1.1 Nuclear fuel
1.2 Reactor vessel
1.3 Reactor core and fuel assembly
1.4 Rod cluster control assembly
4
Pellet hourglassing and Pellet-Cladding Mechanical In-teraction(PCMI)
1.1 Nuclear fuel
dish/cham-fer
7
Intergranular SCC
1.1 Nuclear fuel: Intergranular SCC
8
Transient cladding ballooning: LOCA
1.1 Nuclear fuel: Cladding Ballooning & rup-ture
stress
strain
ulti-mate tensile stress
9
1.1 Nuclear fuel: Cladding rupture
Post-CHF operation: Non-LOCA
Reactivity-Ini-tiated Acci-dent(RIA)
11
APR1400
Typical 4 loop Rx ves-sel
1.2 Reactor vesselRCB: Rx Containment Building; TGB: Turbine/Generator Building; AB: Auxiliary Building; CB: Compound Building
NSSS
upper core plate
Lower plenum
Upper head
Upper plenum
13
1.2 Reactor vesselEstimation of core mass flow rate:
( ) ( ) ,
(1 )
( ) sec
( );
p p hot cold RCP primary losss feedwater steam feedwater p
p core bypss core p bypass
SG feedwater steam feedwater
Rx p p hot cold c
m c T T Q Q m h h m
m m m m m F
where
Q m h h ondary calorimetric
Q m c T T Q
( )
/
ore core p hot cold
bypass bypss p
m c T T
F bypass flow fraction m m
Flow paths APR1400 설계값
Vessel flow rate 20,991.2 kg/secGuide tube 154.9 kg/secCore shroud annulus 84.2 kg/secOutlet nozzle gap 288.9 kg/secAlignment key 101.9 kg/secAPR Bypass overall 629.9 kg/sec
3.0%UK EPR:
5.5%
15
1.2 Reactor vessel: irradiation specimen (Nil-ductility transition T)
16
Typical 4-Loop core1.3 Reactor core and fuel assembly
APR
cladding volume(m^3)
3.72 Zr mass in fuel(Kg) Zr mass in struc(kg)
Zr total mass(kg) 29647 24197 5450