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Introduction of the HTR-10
Fubing CHEN, Jun SUN
INET, Tsinghua University, Beijing, China
August 25, 2016
Outline
HTR-10: 10MW high temperature gas-
cooled reactor-test module
1 History of HTR-10
2 Technical Features of HTR-10
3 Operation of HTR-10
4 Validation calculation on HTR-10
5 Conclusion remarks
1 History of HTR-10
1.1 HTR Roles in China
1.2 HTR-10 Objectives
1.3 HTR-10 Milestones
1.4 Development Organization
1.1 HTR Roles in China
Supplement to LWR, for nuclear power
generation
Providing process steam for heavy oil
recovery and petrochemical industry
As process heat resource for coal
gasification and liquefaction as well as
hydrogen production
1.2 HTR-10 Objectives
To acquire the experience of HTR design,
construction and operation
To develop and verify the TRISO fuel elements technology
To verify the inherent safety features of the modular HTR
To demonstrate the co-generation, gas cycle, steam cycle
To develop the high temperature process heat application technology
1.3 HTR-10 Milestones
March 14,1992: Project approval by Government
Dec 1992-Dec 1994: PSAR
June 14,1995-Dec. 2000: Construction
Dec 15,1998-Nov.17,2000: FSAR
Dec.1,2000: Physical critical
Jan 7, 2003: Electricity output to grid
Jan 29, 2003: Full power operation
Oct.15,2003: safety demonstration experiments CR withdrawal without Control Rod Drop, helium blower
trip without Control Rod Drop, flap close failure ,…
1.4 Development Organization
Main technical developer: Institute of Nuclear and New Energy Technology
(INET), Tsinghua University
Domestic development Teams: research, design, manufactures, construction,
operation,…
The whole HTR industrial system is mature
International cooperation is helpful
HTR-10 is supported by Central government, through 863 high-technology project –China MOST
2 Technical features of HTR-10
2.1 HTR-10 main parameters
2.2 HTR-10 core layout
2.3 HTR-10 highlights
2.1 HTR-10 main parameters
Thermal power MW 10
Reactor core diameter cm 180
Average core height cm 197
Primary helium pressure MPa 3.0
Average helium temperature at reactor inlet/outlet oC 250/700
Helium mass flow rate at full power kg/s 4.3
Average core power density MW/m3 2
Number of control rods in side reflector 10
Number of absorber ball units in side reflector 7
Nuclear fuel UO2
Heavy metal loading per fuel element g 5
Enrichment of fresh fuel element % 17
Number of fuel elements in core 27,000
Fuel loading mode multi-pass
Max. fuel temperature at normal operation oC 919
Average discharge burn-up GWd/tHM 80
2.1 HTR-10 main parameters
Height of RPV m 11
Inner diameter of RPV m 4.2
Helium blower pressure raise kPa 60
Number of SG units/tubes 30
Heat transfer area of SG m2 55
Feed water temperature oC 104
Steam pressure MPa 3.5
Steam temperature oC 435
Steam flow rate t/h 12.5
Electric power MW 2.5
2.2 HTR-10 core layout
Pebble bed
Helium cooled,
graphite moderated
Modular High-
Temperature Gas-
Cooled reactor
Inherent safety
Steam cycle
Side by side
arrangement of RPV &
SG
HTR-10 reactor building
Mixing structure at the
core bottom
The core cross section of side
reflector structure
2.3 HTR-10 highlights
Sphere TRISO fuel technology
Fuel handling system
Passive decay heat removal system
Digitalized Instrumentation and
Control system
Demonstration on inherent safety
characteristics of Modular HTR
Irradiation experiment on Sphere
TRISO fuel
UO2 kernel
Sphere Fuel Elements
Irradiation experiment result
1.0E-09
1.0E-08
1.0E-07
1.0E-06
1.0E-05
1.0E-04
1.0E-03
1.0E-02
0 1000
0
2000
0
3000
0
4000
0
5000
0
6000
0
7000
0
8000
0
9000
0
1E+0
5
1E+0
5
燃耗/(MWd/t)
Xe135释放率(R/B)
二号盒
三号盒
五号盒
Pulse pneumatic driving fuel handling system
空冷器
反应堆
水冷壁
Passive decay heat removal system
水冷壁 /Surface
cooler
空冷塔/Air
Cooler
Full digitalized I&C system
Digitalized reactor protection system
Digitalized control system
Digitalized main control room
First one in China
Safety demonstration of MHTGR
Control rod withdrawal, bypass RPS,
(ATWS)
Shutdown reactor automatically
3 Operation of HTR-10
3.1 Commissioning
3.2 Operation
3.3 Safety experiments
3.1 Commissioning
1995.6.14 First pour of concrete
2000.4 —Phase A Commissioning test
2000.11.20—First fuel load( Phase B1)
2000.12.1—First physical criticality
2000.12.4—Zero power test (Phase B2)
2001.2.21—Low power test (Phase B3)
2002.10—Phase C test
2003.1.7— Connect to grid
2003.1.26— Full power operation
2003.10.15— Safety experiment
2003.12—Power operation (Heating, co-generation)
3.2 Operation
Operation history
Measurement
Nuclear power, temperature distribution, He/steam flow rate/Temperature/Pressure
Operation performance
Normal operation
Transients
Shutdown
Startup
Operation history - overview
Year
Operation Time
(days)
Integrated Power
(MWD)
2003 106 258.9
2004 168 708.5
2005 149 821.4
2006 97 532
2007 49 182.6
Total 569 2503.4
Core parameters measured in HTR-10
Reactor power
Core internal temperature
Primary loop pressure
Helium inlet/outlet temperature
Thermal couples
Temperature measurement in
pressure vessels
0
500
1000
1500
2000
2500
3000
3500
4000
0 5 10 15 20 25
时间(h)
功率
(kw)
0
100
200
300
400
500
600
700
0 5 10 15 20 25
时间(h)
温度(℃) 热氦温度
冷氦温度
0
50
100
150
200
250
300
350
400
450
0 5 10 15 20 25
时间(h)
温度(℃) 蒸汽温度
给水温度
0
0.2
0.4
0.6
0.8
1
1.2
1.4
1.6
0 500 1000 1500 2000
时间(s)
流量(kg/s)
Startup process
Transient (change of Helium flow rate)
0.50
0.70
0.90
1.10
1.30
1.50
1.70
0 200 400 600 800 1000 1200 1400 1600 1800
秒
kg/s
氦流量
水流量
2500
2700
2900
3100
3300
3500
0 200 400 600 800 1000 1200 1400 1600 1800
秒
kw
Nuclear power will follow the change of helium flow rate
very fast, because of temperature feedback
Fast change in steam temperature and cold helium
temperature, because of once-through steam generator
0.50
0.70
0.90
1.10
1.30
1.50
1.70
0 200 400 600 800 1000 1200 1400 1600 1800
秒
kg/s
氦流量
水流量
2500.00
2700.00
2900.00
3100.00
3300.00
3500.00
0 200 400 600 800 1000 1200 1400 1600 1800
秒
kw
50
150
250
350
450
550
650
750
0 200 400 600 800 1000 1200 1400 1600 1800
秒
℃
热氦温度
给水温度
冷氦温度
蒸汽温度
Transient (change of feed water flow rate)
Steam parameter is sensitive to
the feed water flow rate,
less sensitive for nuclear power
and hot helium temperature
Transient (pull up control rod)
1608
1610
1612
1614
1616
1618
1620
1622
0 50 100 150 200 250
3000
3050
3100
3150
3200
0 50 100 150 200 250
秒
kw
50
150
250
350
450
550
650
750
850
0 50 100 150 200 250
秒
℃
堆芯出口温度
热氦温度
冷氦温度
Because of external positive reactivity,
nuclear power change very fast, but will
stabilize after 200s, because of
temperature feedback
Less change in helium temperature
3.3 Safety experiments
Helium blower trip Trip the blower,
RPS is actuated, (reactor shutdown), decay heat is removed passively
Turbine generator trip Trip the turbine, close of steam valve,
RPS actuates, decay heat is removed passively
Loss of off-site power Cut off power supply,
CR drops, blower is tripped, RPS is actuated, decay heat is removed passively
3.3 Safety experiments
Loss of heat sink ATWS
Break the power supply to helium blower
RPS is actuated, bypass the emergency
trip breaker, to simulate ATWS accident
Reactor is shutdown because of negative
feedback
Decay heat is removed passively
3.3 Safety experiments
Control rod withdrawal ATWS
Pull up CR continuously, (power raise)
RPS is actuated, bypass the emergency
trip breaker, to simulate ATWS accident
Reactor is shutdown because of negative
feedback
Decay heat is removed passively
3.3 Safety experiments
Blower flap fail to close
Manually trip the reactor,
RPS is actuated, reactor is shutdown
Keep the blower flap open intentionally
Decay heat is removed passively
Safety valve do not open
Summary on safety experiments
These experiments are open for experts(HTR-2004) and public
These experiments demonstrate the inherent safety features of modular HTR
These experiments are valuable for the purpose of public acceptance
These experiments are valuable for the purpose of code verification
4 Validation calculation on HTR-10
4.1 Works done before
4.2 New requirement from HTR-PM
4.3 New plan
4.1 Works done before
Physical criticality
IAEA CRP
IAEA-TECDOC-1382, Evaluation of high
temperature gas cooled reactor
performance: benchmark analysis related
to initial testing of HTTR and HTR-10
VSOP, MCNP, …
Results are exciting
4.1 Works done before
CRP-3
VGM、GT-MHR、HTR-10、HTTR、SANA
IAEA-TECDOC-1163, Heat Transport and
Afterheat Removal for Gas Cooled Reactors
Under Accident Conditions
Decay heat
Results are exciting
CRP-5
HTR-10、HTTR、PBMR、PBMM、…
Some results in IAEA-TECDOC-1382
Waiting for new IAEA TECDOC
4.2 New requirements from HTR-PM
Take HTR-10 as prototype Same configuration, same
technology, larger size,…
Use proven codes for licensing: VSOP, THERMIX, TINTE, PANAMA, CFD, …
Requires further V&V Collect all experience gained
before
New V&V on HTR-10 data
New V&V on new test facility
4.2 New requirements from HTR-PM
Codes for HTR are not qualified as codes for LWR Requirement for code V&V is extended in recent
years
Operation data is limited
New demand for code improvement, and V&V again
Full 3D
Whole plant
HTR-10 is a suitable platform for code V&V
HTR-PM demonstration plant itself has the roles of code V&V
4.3 New plans
Long term operation of HTR-10 in future is planned Focus on steam cycle
I&C will be upgraded
New measurement systems are planned to install
Operation experience feedback for components
Operation data for V&V of safety analysis code V&V on operation data is also a challenge work, especially
for small reactor like HTR-10
Besides more experiment rigs for HTR-PM 10MW Helium loop, steam generator, fuel handling system,
pebble bed equivalent conductivity coefficient, …
Fuel irradiation and PIE
5 Conclusion remarks
The design, construction, commissioning, operation, safety experiment on HTR-10 is very successful
The configuration of HTR-10 is very simple
Operation of HTR-10 is very stable
The components in HTR-10 work well
Inherent safety of modular HTR can be demonstrated in HTR-10
5 Conclusion remarks
HTR-10, the only pebble bed Modular HTR in the world, can act as the test bed for the commercial plant project for China and world
Long term operation and operation experience feedback is planned
Upgrade of some components are planned
International cooperation is highly appreciated
Thanks for your attention!