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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!