27th iaea fec

27th IAEA FEC

Design Optimization and Safety

Assessment of CN HCCB TBS

Xiaoyu WANG

Southwestern Institute of Physics (SWIP), China

On behalf of CN TBM team

CNTBM program: Helium Cooled Ceramic Breeder Test Blanket System (HCCB TBS)

Leaded by CN DA

Supporting Institutes:

1). Southwestern Institute of Physics (SWIP), China

2). China Academy of Engineering Physics (CAEP), China

3). Institute of Nuclear Energy Safety Technology(INEST), China

Outline

Introduction

System Overview

Design Optimization and R&D Progress

Safety Assessment

Summary

2

Introduction

The ITER facility could offer a unique opportunity to

demonstrate the feasibility to test tritium breeding

blanket technology in a tokamak reactor and to test

Tritium producing components.

Verification of tritium breeding technology by Test

Blanket Module (TBM) program is one of the

engineering goals for ITER.

CN TBM Program was established by CN DA in 2009

and the Helium Cooled Ceramic Breeder (HCCB)

TBM concept was selected.

CN TBM Program is the first step toward the future

breeding blanket for CFETR and DEMO.3

General Objectives of CN HCCB-

TBM Program

4

General

Objective

s

Diagnostics

and control

Power

removal

Safety

Tritium

technology

Integral

performance

ITER

HCCB DEMO

The objectives of CN HCCB TBS is to test the tritium breeding blanket

technology in the tokamak operation conditions provided by ITER.

MaintenancePIEHCCB TBM

5

System Overview

TBM set Pipe Forest (PF) Ancillary Equipment Unit

Tritium Extraction System (TES)

Helium Cooling System

(HCS)

Coolant Purification System

(CPS)HCCB TBS Schematic

Core component: HCCB TBM

Parameters Values

Neutron wall load 0.78 MW/m2

Surface heat flux 0.3 MW/m2

Structural materialCLAM/CLF-1 ~1.3ton

(<550ºC)

Tritium Breeder Li4SiO4 pebble bed (<900ºC)

Neutron MultiplierBeryllium pebble bed

(<650ºC)

Coolant

Helium (8MPa) 1.04 kg/s

(Normal)

FW(300ºC/370ºC)

Breeding zone (370ºC/500ºC)

Purge gas Helium with H2

TPR 0.061g/FPD

⚫ Design features• Four sub-modules concept

- Manufacturability

- PIE/ transportation

• U shape breeding zone

- Reduce the structural material

Design of HCCB TBM

Main design parameters

Design Optimization and R&D

Progress

8

Design Optimization for HCCB TBM-set

Design optimization of TBM

Manufacturing feasibility

Engineering performance

Preliminary engineering

assessment of TBM

Neutronics

Hydraulic

Thermal

EM analysis

Structural

9

Design optimization of HCCB TBM

Neutronics analysis Thermal analysis

EM analysis Hydraulic and structural analysis

Design Optimization for HCCB TBM-set

Design optimization of TBM shield

Manufacturing feasibility:

Engineering performance:

Preliminary engineering

assessment of TBM shield

Thermal-hydraulic

Structural

Modal

10

Design optimization of TBM shield

Thermal and structural analysis for pipes Thermal and structural analysis for shield

Material Development

Industrialized manufacture process of RAFM steel (CLF-1 and

CLAM) has been finalized and will be qualified by CN DA.

Up to 5000h, 550℃ thermal aging experiment was performed.

11

Several 5-ton ingots of CLF-

1 steel and CLAM steel

have been fabricated into

plates and forgings by

industrialized manufacture

process.

Two types(Full annealing and Isothermal annealing) of

annealing process were developed.

Material Development

New facility for Li4SiO4 fabrication has been constructed, which will

ensure the fabrication capability for the HCCB TBM.

Facility for thermo-mechanical properties testing of pebble beds

under multi-physics field was under construction.

The X-ray computed tomography (CT) was used to investigate the

packing structures of mono-sized and binary-sized pebble beds. The

CT experimental results agreed well with DEM simulation results.

12Li4SiO4 fabrication process

Pebble bed packing structure by CT and DEM simulation

TBM Fabrication Technology

Semi-prototype mockup of TBM was successfully fabricated and

tested by NDT. Pressure test and helium leakage test will be

performed.

A small mockup of external frame with inner plate in TBM shield was

fabricated and tested by RT. Another mockup of double-layer pipe

was under fabrication.

13Fabrication processes for semi-prototype of HCCB TBM

Component sample

for TBM shield

Progress on systems integration

Updated functional analysis of HCCB TBS for normal operation and

maintenance, including functional break down and IDEF0.

Re-defined HCCB TBS operation state and shift scheme.

14

To account the total

bred tritium accurately

and confine hazard

56.5.2

To extract and recovery

tritium, distribute service and

confine hazard

56.5.1

To cool the HCCB TBM,

distribute service and confine

hazard

56.5.3

To deposit and transfer heat, breed

tritium, shield radiation, maintain

vacuum boundary and confine

hazard

56.5.4

To provide monitoring

and control for HCCB

TBS

56.5.5

To measure neutron

parameters and confine

hazard

56.5.6

To ensure

maintainability

56.5.7

To demonstrate and test the operation of

the HCCB Test Blanket System

56.5

TITLE:NODE: NO.: 1A56.5 To demonstrate and test the operation of the HCCB Test Blanket System

56.5.1

To extract and recovery tritium, distribute service

and confine hazard

56.5.2

To account the total bred tritium accurately and

confine hazard

56.5.3

To cool the HCCB TBM, distribute service and

confine hazard

56.5.4

To deposit and transfer

heat, breed tritium, shield

radiation, maintain

vacuum boundary and

confine hazard

56.5.5

To provide monitoring and control for HCCB TBS

56.5.6

To measure neutron parameters and confine

hazard

Power supply from PBS43

CA from 56.00.CA

He from PBS 56.00.He

Purified coolant He from PBS 56.C5.HP

He to PBS 56.C5.HP

Chilled water from PBS56.00.WH Cooling water

PBS 56.CP.W1

PBS 56.C5.HE PBS 56.C5.TEPBS56.C5.TA PBS56.C5.NA

Tritiated gas to PBS32.DTThrough PBS56.00.TP

CA (PC)

GN2 from PBS56.00.GN

He coolant

He coolant

LN2 from PBS56.00.LN

Purge Gas

LN2

Cooling water to PBS 56.C5.HP

CA (PC)

LN2

CA (14-L2-24)

GN2

H2

He

Measurement Gas

Tritiated gas/Vacuumed gas

Control signals and data

GN2 (GB purge gas)

GN2 (GB purge gas)

GN2 (GB purge gas) To PBS 32.DT

Coolant andCapsule

High-Concentration Tritiated gas to PBS 32.EP

Low-Concentration Tritiated gas to PBS 32.DT

GN2CA (14-L2-24)

GN2

CA (14-L2-24)

Vacuumed gas

Power supply

Power supply

Power supply

Power supply

Tritiated gas to LDS


HCCB TBM-set

Cooling water From PBS 26.PH.BD Through vacuum vessel

I&C integration


Signals and data

Signals and data

Cooling water from PBS 56.00.WA

He

H2

He

Ne from PBS32.SD

Signals and data to

CODAC (PBS 45)

Signals and data

to CIS (PBS 46)

Control signal and data from CODAC (PBS45)

Control signal and data from CIS (PBS46)

Purge Gas

Tritiated gas after measurement

Signals and data

to CODAC (PBS 45)

Cooling water to PBS 56.C5.HP

He to PBS 56.C5.HP

Tritiated gas to LDS CA (PC)

Signals and data

He coolant

Coolant andCapsule

Purge Gas

Ne from PBS32.SD

GN2 (GB purge gas)

GN2 (GB purge gas)

Coolant andCapsule

Coolant andCapsule

Signals and data

Signals and data

Signals and data

Signals and data

Signals and data

Vacuumed gas

GN2 (GB purge gas) to PBS 32.DT

Cooling water

Chilled water

GN2

LN2 Cooling water

Signals and data to

CODAC (PBS 45)Signals and data to

CIS (PBS 46)

Coolant andCapsule

Purge Gas

Coolant and Capsule

Control signals and dataControl signals and data


He

Safety signals to CSS-N (PBS48)

Safety signals to CSS-N (PBS-48)




Safety signals from PBS48 (PSS-N)

He

Safety signals from PBS48

Safety signals from CSS-N (PBS48)

Safety signals from CSS-N (PBS48)

Control signal and data from CSS-OS (PBS48)

Signal and data to CSS-OS (PBS48)

Signals and data to CSS-OS (PBS48)

Signals and data to CSS-OS (PBS48)

Neutron load from Plasma

Heat load from Plasma

Connection with Port Plug


Signals and data

to CIS (PBS 46)

Purge Gas

Vacuumed gas from PBS 56.C5.HP

H2 from PBS32.SD trough PBS56.00.TP

High-Concentration Tritiated gas from PBS 56.C5.HP

Tritiated gas to PBS32.DT

Signals and data

GN2 (GB purge gas)

Signals and data


Tritiated gas after measurement

High-Concentration Tritiated gas from

PBS 56.C5.HP

Coolant and Capsule

GN2 (GB purge gas)


First installation

Maintenance

Shutdown

WaitingBaking

Standby

NOS

TOS

Transitions of the HCCB TBS PSOS

Functional breakdown

of HCCB TBS (level 1)

IDEF0 of HCCB TBS (level 1)

15

Press on I&C design and R&D

Mini-CODAC/CODAC

Plant system host

Slow controllerFor supvision

Slow controller for HCS

Slow controller for CPS

Slow controller for TES/TAS

Slow controller for NAS

I/O module I/O module I/O module I/O module

EPICS CA

TCPT_SENDT_RECV

TCP S7

PN PN PN PN

Interlock Controller

Safety Controller

Central Interlock

Controller

Central Safety Controller

I/O module I/O module

PN

TCP S7

Fast controller

I/O module

PCle

HCCB-TBS Integration I&C scope

HCCB-TBS Subsystem I&C scope

ITER central I&C scope

I&C architecture of HCCB TBS Control of HeCEL-1 helium loop by mini-CODAC

TES/TAS

Controller

TES/TAS

quipment Device

NAS Sensor

Device

CPS Tool

Device

CPS Tool

Controller

NAS Sensor

Controller

HCS Device

Controller

Networks

TBS quipment

Low-Level Control System

TBS control System

Field Wiring

CODAC Networks

Plant System

Host

Plant Interlock

System

Plant Safety

System

CIN

CSN

CODAC CIS CSS

Integration

Controller

PON

HCS quipment

Device

TBS control and operation concept

RHA testing

Transmitter-probe separation and long

distance signal transmission testing

Safety Assessment

19

20

Overview of Safety assessment and

demonstration

Nuclear analysis

21

HCCB TBS neutronics model

integrated into ITER C-model

The Concern The Methods

The Results

• HCCB TBM+Port Cell+ITER C-

Model

• ITER neutron sources

• ITER irradiation scenarios

• MC code, FENDL 2.1

• FISPACT and EAF-2007 library

• Direct One-Step Method.

• Neutron fluxes spectrum

• Tritium production rates

• Nuclear heat

• Neutron activation and

• Decay heat

• Contact dose rate

• Shutdown dose rate10

010

110

210

310

410

510

610

710

810

910

1010

1110

1

102

103

104

105

106

107

108

109

1010

1011

Act

ivity

In

ven

tory

(B

q/k

g)

Shutdown Time (s)

Shield

Pipe Forest

Bio-shield (concrete)

AEU

• Shielding functions

• Activation

• Decay heat

• Dose rate

• Rad-waste characteristics.

100

101

102

103

104

105

106

107

108

109

1010

1011

107

108

109

1010

1011

1012

1013

1014

1015

1016

1017

Act

ivity

In

ven

tory

(B

q)

Shutdown Time (s)

Cover Board

First Wall

Breeding zones

Backplate

Total Activity Inventory

1700 1800 1900 2000 2100 2200 2300 2400 2500

0.0

0.2

0.4

0.6

0.8

1.0

1.2

Do

se

Ra

te (S

v/h

r)

Position (cm)

Previous

Current

Neutron spectrum Activation

Activation of othersShutdown dose rate

Irradiation for HCCB

TBS

Tritium safety analysis

22

Tritium analysis model


The Results

• Self-developed system

transport analysis code

• Modelling of all sub-systems and

interface systems

• Considered physics:

• balance, dissociation

• recombination

• Diffusion, trapping

• isotopic effects

• Permeation, absorption

• Tritium concentration in

different fluids in the system

• Tritium concentration in

atmosphere of different

confinement compartments

• Tritium concentration profile

in solid materials, tritium

inventories.

• Tritium permeation fluxes

through solid walls.

• Tritium removal rates

Tritium analysis results1st confinement barriers for in-vessel inventory: TBM shield, Frame, VV, pipe

forest, isolation valves;

1st confinement barriers for ex-vessel inventory: other pipes and component walls;

2nd confinement barriers: TES Glove boxes, ITER buildings, detritiation systems,

ventilation systems …

• Tritium→ confinement

• Tritium

• concentrations

• inventories

• releases

• → accident analysis

• → rad-waste analysis.

23

Accident analysis

Accident analysis model


The Results

• Thermal hydraulics codes like

RELAP5

• Modelling of TBM, HCS, TES

and interfacing systems

• Nuclear heating, plasma heat

flux and decay heat sources

• Safety controls

• Considering aggravating failures

of neighboring systems

• Transient helium mass

flow rates

• Transient pressure

• Transient temperature in

TBM and other heat

structures

• Helium release and

radioactive release

amounts

• Comparison with

acceptance criteria

• Postulated initiating events

(PIEs), : LOFA, In-vessel LOCA,

In-TBM Box LOCA, Ex-vessel

LOCA, Heat exchange break,

tritium process line break etc.,

• Transient thermal hydraulic

behavior in HCCB TBS and

impacts on surrounding

systems

• Check if the radioactive releases

are the within the release limits

• Check if the safety control

measures are appropriate to

mitigate the accident

consequences.

2Pump

18 Filter

6 Shell

14 Tube

16HeliumTube

102Water Shell

100Tmdpvol

105Tmdpjun

101Branch

103Branch

104Tmdpvol

106

2021

PressurisorTmdpvol

26 27 28

29

3031

2223

34

81

8283

8485

86

87 88 89 90

91

5Pipe

15 Pipe

17 Pipe19 Pipe

7Pipe

3Pipe

4

12Valve

8

13Pipe

11Pipe

24

9Pipe

Primary side（helium）

Secondary side（helium）

41

4243 44 45

52

53 54 55

56 57 5859

60

61

62

636465 66

71 72

73 74

210

211

111 112 113 114

115

116 117 118

119 120 121122

123

125

126

124

127128 129 130

131 132

133 134

141 142 143 144

145

146 147 148

149 150 151152

153

155

156

154

157158 159 160

161 162

163 164

171 172 173 174

175

176 177 178

179 180 181182

183

185

186187188 189 190

191 192

193 194

32 Pipe

10Heater

35

33 Pipe

25

First Wall

184

75

76

77

78

135

136

137

138

165

166

167

168

195

196

197

198

M1 M2 Cap→Rib→Cap M5 M4 CP M3 Pipe

79

80

139

140

169

170

199

200

201

202

203

204

205

206

207

208

36

3738

9293

94

67

He mass flow rate

at break point

Temperature

transient in TBM

Pressurization of Port Cell

Summary

CN HCCB TBS is one of the most important part of China fusion

development strategy toward DEMO.

The design of the HCCB TBS has been significantly optimized

based on the interface and manufacturability. The qualification of

materials and pre-qualification of fabrication processes are

planned to support the design.

According to the two main safety functions in HCCB TBS,

confinement and shielding, the safety of HCCB TBS covering

nuclear analysis, tritium analysis and accident analysis has

been assessed to ensure and demonstrate the design of main

safety functions, as well as supporting safety functions.

24

Thank you for your attention!

27th iaea fec

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