1

Preliminary Design of China ITER TBM

with Helium-Cooled and Solid Breeder Concept

Preliminary Design of China ITER TBM

with Helium-Cooled and Solid Breeder Concept

Presented By: K.M. Feng

(On behalf of CH HCSB TBM Team)

Presented at 3rd PRC/US MCF Collaboration workshop – Dalian, China, May 18-19, 2006` 1

2

Outline

I. Introduction

II. Design Progress

III. Performance Analysis

IV. R&D and Test Plans

V. Possible Collaborations

VI. Summary

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ITER will pay a very important role in first integrated blanket testing in fusion environment. Some DEMO blanket relevant technologies, such as tritium-breeding self-sufficiency, exaction of high-grade heat, safety requirement, and design criteria will be demonstrated in ITER test blanket modules (TBMs).

China planed to develop independently own TBM for testing during ITER operation period based on China’s DEMO definition and development strategy.

The preliminary design and analysis of HC-SB TBM have been carried out recently. Possible collaborations on TBM R&D with other partiers have been proposed.

I. IntroductionI. Introduction

4

ITER,TBM and DEMO

5

Definition of DEMO in China The DEMO in China is to demonstrate the safety,

reliability and environment feasibility of the fusion power plants, meanwhile to demonstrate the prospective economic feasibility of the commercial fusion power plants.

Utilization of fusion energy have still a long way to go towards an economically commercial power plant. DEMO in China should be an indispensable step prior to the commercial application.

In addition, China is interested in non-electric applications of fusion energy, such as HLW disposal and hydrogen production, etc.; we expect that these applications will benefit the ultimate development of the fusion power plants.

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Two options of breeding blanket with ceramic and lead lithium-lead breeders might be chosen as China’s DEMO blanket concepts under the conditions of meeting the requirement of the neutronics, thermo-hydraulics and mechanics aspects.

Selection of DEMO Blanket

HC-SB DEMO Blanket(SWIP) DCLL DEMO Blanket(ASIPP)

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Selected HCSB DEMO Parameters

Chinese HC-SB Demo Parameters

Fusion power/electric power (MW) 2000 / ~ 600MWe

Major radius (m) 7.0m

Minor radius (m) 2.5m

Neutron wall load (MW/m2) ~ 2.0

Surface heating (MW/m2) ~0.3

Tritium breeding ratio (TBR) >1.1

Availability (%) 50-70

Divertor peak load (MW.a/m2) 8.0 (water-cooled)

Plasma operation mode Continuous

HC-SB DEMO Blanket Design

23

The assembly view of HCSB-DEMO blanket

The isometric view The bird view

24The explosive view of HCSB-DEMO blanket

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II. Design progressII. Design progress of of CH CH HC-SB EM-TBMHC-SB EM-TBM

10

It is in agreement with other parties’s design, HC-SB TBM design is based on a vertical half-port space in test Port C;

630mm(d) X 660mm(w) X 890mm(h)

Test Port Space for CH HC-SB TBM

HCS

TWCS

HC-SB

EM-TBM

(I)

HC-SB

EM-TBM

(II)

Port C

HC-SB TBM

11

Originally Design of CH HC-SB TBM

（ 2004 Version ）

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1-beryllium armor, 2-multiplier zone, 3-sidewall, 4-U-shaped shell, 5-cooling pipes, 6-breeder zone, 7-backplane, 8-He coolant(hot leg), 9-measure access, 10-attachment, 11-purged, 12-He coolant (cold leg)

Outline view for CH originally HC-SB TBM design

Be

SolidBreeder

Back-plane

He He

13

Exploded 3-D view of Modified Design of HC-SB TBM (2005 Version)

Structure and components design in detail is on going.

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Structure Design for EM-TBNBe armor: 2 mm Max Temp. 514OCFirst wall thickness: 30 mm Material: Eurofer Max T: 506OC Cooling tube: 18x14.5mmUnit cells: 3X3 sub-modulesHe pressure: 8 MPa

664mm

Integration view of structure design

Sub-modules0.190 m in toroidal0.420 m in radial0.260 m in poloidal

664mm

890mm

630mm

15

Schematic view of CH HC-SB EM-TBM

Outside of structure Cross-section of module Coolant manifold

Sub-module structure View of the back-plane Configuration of Sub-modules

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Connection of Up-down Modules

HC Pipe (outlet)

HC Pipe (inlet)

Connection

•Modularizing structure

•Parallel connecting two modules

Up module

Down module

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Connection of ComponentsHe outlet of FW He inlet of FW

Structure View of FW and Backplane

He

He

He outlet of FW

He inlet of FW

He CollectionOf Grid

He outlet of FW

He inlet of FW

Flow path of Coolant (1)

Purgemanifold

Flow path of Coolant (2)U-shaped first wall

Sub-modules

Back-plane

Test Blanket Module Port Plug Frame Plumbing Interface 2

HC-SB EM-TBM in frame

FW attachment

TBM in ITER frameFlow path of coolant

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Structure View of Back-plane

He outlet

Purge outlet

Measure Channel

Purge inlet

He inlet

Purge Collectionmanifold

Purge Supplymanifold

He Supplymanifold

He Collectionmanifold

He Middlemanifold

The back-plane closes the sub-module box from the near

side, provides the support for the mechanical attachment

at the interface with the ITER Port Plug and forms a

manifold system for others part of TBM

Arrangement of back-plane

Top view of manifold

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Assembly of HC-SB EM-TBM in frame

TBM module Frame

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HCSB TBM integrated assembly

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Items NT-TBM EM-TBM

Configuration BOT (Breeder Out of Tube) Modules: 3×3 Sub-modules Modules: 3×3 Sub-modules

First wall area

Neutron wall loading

Surface heat flux

0.664 m(W)×0.890 m(H) 0.591 m2.

0.78 MW/m2

0.3 MW/m2 (normal condition)

0.5 MW/m2 (extreme condition)

0.591 m2 + 0.591 m2 (Vertical).

0

0.1 MW/m2 (normal condition)

0.3 MW/m2 (extreme condition)

Total heat deposition surface heat flux included 0.76 MW 0.177 MW

Globe TBR Lithium orthosilicate, Li4SiO4 1.15 (1-D), 80% Li-6

Tritium production rate ITER operation condition 2.23 ×10-2 g/d

Sub-module dimension (P)× (T) × (R) 260 mm×190 mm×420 mm 260 mm×190 mm×420 mm

Ceramic breeder (Li4SiO4)

Two size

Thickness

Max. Temperature

Diameter: 0.5~1 mm, pebble bed

90 mm (four zones)

737 ℃

SiC pebble bed, 0.5~1 mm

Neutron multiplier

(Beryllium)

Two size

Thickness

Max. Temperature

Diameter: 0.5~1 mm, Pebble bed

200 mm(five zones)

617 ℃

Al pebble bed, 0.5~1 mm

Be armor Thickness

Max. Temperature

2mm

543 ℃2mm

514 ℃

Structure Material Ferritic steel

Max. Temperature

EUROFER

530 ℃

EUROFER

506 ℃

Coolant helium (He)

Pipes size

Pressure

Pressure drop

Temperature range (inlet/outlet)

Mass flow

Diameter (OD/ID)

8 Mpa

0.294 MPa

300/500 ℃0.73 kg/s

85/80 mm

8 Mpa

0.051 MPa

300/411 ℃0.31 kg/s

85/80 mm

He purge flow (He) Pressure

Pressure drop

0.12 MPa

0.02 MPa

Design parameters for the HC-SB TBM

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Schematic views of Coolant flow

Coolant flow in the sub-module Coolant flow in FW

Back-plate

Coolant Flow Direction

Back-plate

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HC-SB TBM Auxiliary System

HC-SB

TBM

HC-SB

TBM HCS CPS

VV Port Cell TWCS vault

Tritium Building

BC

TES

TMS

NMS

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HC-SB TBM Auxiliary Sub-system Design

21Flow scheme of the HCS system

HC-SB TBM

3 . 5 x2.5m2

Dust filter

Main HX

recuperator

Electric heater

Circulator

Valve

Draft layout of the helium cooling subsystem in the TCWS

TWCSHCS

TBM

Helium Cooling System (HCS)

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Neutron Measurement System (NMS)

Schematic diagram of neutron fluxes

and spectra measurement system

micro-fission chamber

micro-fission chamber assembly 23Space Arrangement in TCWS for HCS subsystem

Space requirement:

A minimum net foot print area of 16 m2 in the TCWS vault, 0.5m3 in transfer cask, will be needed

Space requirement:

A minimum net foot print area of 16 m2 in the TCWS vault, 0.5m3 in transfer cask, will be needed

HCS TMS TES

CPS NMS TCWS

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Coolant Purification System (CPS)

1

3 a

4

6 a 6b

7a 7b

8

９

He , 30 0 ℃

3 00 ℃H e, 1 0M P a

5

E S

E S

3 b

1 0

H e

2 a2 b

Layout of the CPS

Flow chart of the CPS

2200

1500

1200

1－gas flow controller; 2a/2b－impurities getter bed; 3a/3b－tritium getter bed; 4－heater; 5－cooler; 6a/6b－buffer bank; 7a/7b－ionizationchamber;

8－gas chromatograph9—circulator; 10—ZrCobed

Space requirement:A space of 1500mm×1200mm×2200mm (L×W×H) is neededfor its assembly, maintenance and operation of the CPS.

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Tritium Extraction Subsystem (TES)

4 b

9 b

34 a

E S

6

7

8 a 8 b

9 a 1 0

1 1 a

1 2

E S

1 3 a

1 4 b

1 4 a

9 c

1 5H e

1 1 b

1 6

H 2

T r i t i u m E x t r a c t i o n S y s t e m f o r T B M

1 3 b

1 3 c

4 c

1

2 a

2 b

1 T B M2 a / 2 b F i l t e r3 C o o l e r4 a / 4 b / 4 c I o n i z a t i o n C h a m b e r5 C o l d T r a p6 W a t e r C o l l e c t o r7 R e c u p e r a t o r8 a / 8 b M o l e c u l a r S i e v e s9 a / 9 b / 9 c B u f f e r1 0 H o t M g B e d1 1 a / 1 1 b C o m p r e s s o r1 2 P d / A g P e r m e a t e r1 3 a / 1 3 b / 1 3 c G e t t e r B e d1 4 a / 1 4 b I S S1 5 H e a t e r1 6 M a k e - u p U n i t

C h e c k v a v l eO p e n v a v l eC l o s e d v a v l eP r e s s u r e r e d u c i n g v a v l e

E S E v a c u a t i o n s y s t e m

± ±

± 5

V 1V 2

Flow chart of the TES sub-system Lay-out of the TES sub-system

Space Requirem ent:

The TES system must be installed in a glove box.

The size of the G love Box is: 5.5m× 1.2m× 5.5m (L× W× H).30

Tritium Measurement System (NMS)

The schematic of the gas flow calorimeter

Flow chart of the TMS

Layout of the TMS

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Neutronics Measurement System Design

Schematic diagram of neutron fluxes and spectra measurement system and

cooling loop for NT-TBM

micro-fission chamber

micro-fission chamber assembly

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Iii. Performance Analysis for EM-TBMIii. Performance Analysis for EM-TBM

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A. Neutronics design B. Thermo-hydraulic Analysis C. Thermo-Mechanical Analysis D. Preliminary E-M analysis; E. Preliminary LOCA, LOFA analysis, etc.,

Above performance analysis have been completed. Others calculation and performances analyses are on going.Related results have been given in the CH HC-SB TBM DDD report last year.

Preliminary Performance Analysis for EM-TBM

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Performance Analysis for HC-SB TBM (Con’t)

Calculation Model

Temperature on Flow Channel Flow scheme

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Coolant Flow Scheme

Temperature distribution of FW(Coolant velocity in FW outlet is 69m/s)

Normal Condition, Max. T=453 0C Extreme Condition, Max. T=513 0C

Normal Condition, Max. T=340 0C Extreme Condition, Max. T=422 0C

Temperature distribution The displacement vector sum

The stress distribution

Peak stress is 63.5 MPa

[1].Temperature at FW outlet is fixed at 4110C for test of high temperature performance of FW.

Components

Normal condition Extreme condition

EM-TBM NT-TBM EM-TBM NT-TBM

Neutron surface loading [MW/m2] 0 0.78 0 0.78

Surface heat flux [MW/m2] 0.1 0.3 0.3 0.5

Helium pressure [MPa] 8 8 8 8

Helium inlet/outlet temperature [°C] 300/411 300/500 300/411 300/500

Total power (surface heat flux included) [MW] 0.059 0.64 0.177 0.76

Power from surface heat flux [MW] 0.059 0.18 0.177 0.30

Power from nuclear heating [MW] 0 0.46 0 0.46

Total Mass flow rate of helium [kg/s] 0.10 0.62 0.31 0.73Mass flow rate of helium in

FW [kg/s] 0.10 0.62 0.31 0.73

Single sub-module [kg/s] 0.011 0.065 0.032 0.077

Top and bottom plates [kg/s] 0.0057 0.03 0.017 0.04

Velocity of helium in

FW [m/s] 9.0 58 27 69

Sub-module [m/s] 2.4 15 7.2 18

Pressure drop of coolant in module [MPa] 0.0066 0.21 0.051 0.29

Pressure drop in FW [MPa] 0.0059 0.19 0.045 0.26

Pressure drop in sub-module [MPa] 0.00068 0.02 0.0052 0.03

Main Design Parameters of HC-SB EM-TBM[1]

[2]. Coolant velocity in FW outlet is fixed at 69m/s, to test the hydromechanics performance of FW channel.

ComponentsNormal condition Extreme condition

EM-TBM NT-TBM EM-TBM NT-TBM

Neutron surface loading [MW/m2] 0 0.78 0 0.78

Surface heat flux [MW/m2] 0.1 0.3 0.3 0.5

Helium pressure [MPa] 8 8 8 8

Helium inlet/outlet temperature [°C] 300/313.4 300/500 300/341 300/500

Total power (surface heat flux included) [MW] 0.059 0.64 0.177 0.76

Power from surface heat flux [MW] 0.059 0.18 0.177 0.30

Power from nuclear heating [MW] 0 0.46 0 0.46

Total Mass flow rate of helium [kg/s] 0.85 0.62 0.83 0.73Mass flow rate of helium in

FW [kg/s] 0.85 0.62 0.83 0.73

Single sub-module [kg/s] 0.089 0.065 0.087 0.077

Top and bottom plates [kg/s] 0.047 0.03 0.046 0.04

Velocity of helium in

FW [m/s] 69 58 69 69

Sub-module [m/s] 18 15 18 18

Pressure drop of coolant in module [MPa] 0.31 0.21 0.31 0.29

Pressure drop in FW [MPa] 0.28 0.19 0.28 0.26

Pressure drop in sub-module [MPa] 0.033 0.02 0.031 0.03

Main Design Parameters of HC-SB EM-TBM (con’t)[2]

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Safety Analysis of CH HC-SB TBM

Direction: The relevant safety analysis is need to meet the requirements in GSSR and French Nuclear Safety Authority (NSA); For each component all the possible failure modes, in the various operating phases, will be evaluated.

Progress: Some results of safety analysis are presented in the CH HC-SB TBM DDD report last year.

A safety working group (SWG) in China for licensing, QA and safety report of CH TBM, which consists of State Nuclear Safety Bureau, State Environment Protection Bureau and design institutions, will be organized soon. A systematic approach ( FMEA) will be established after determining all components and sub-systems;

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Safety Analysis (con’t)

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Safety Analysis of CH HC-SB TBM (cont.)? activity and decay heat analysis

Total activity generated and contribution from each material

Total afterheat generated from each material

A total activity of 5.43×105 Ci is attained at shutdown with a contribution of 5.39× 105Ci from the structure, 3.7×103Ci from the Li4SiO4.

At shutdown, the total decay heat is ~8.77× 10-3 MW with a contribution of 8.71× 10-3 MW and 6.36× 10-5 MW from structure material and Li4SiO4, respectively.

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Safety Analysis for CH HC-SB TBM (cont.)? LOCA and reliability analysis

Pressure transients from different models vs. time

Temperature changes of materials after the end of blow-down

LOCA analysis shows depressurization of the TBM helium coolant occurs within 10 to 15 s. Contribution to the pressure build-up in the VV is small (17.8 kPa). Tritium and activation products released from the TBM into the VV are insignificant compared to the total amount mobilized from non-TBM components. The TBM FW temperature can be kept, after the disruption burst has decayed variant to the reference case, with postulated unlimited steam access to the pebble beds, the estimated hydrogen production is the order of g only and the chemical heat is negligible.

Deformation Equivalent Stress

39

Simplified 1/4 sub-moduleSeparated model

MODEL A MODEL B

Safety Analysis of CH HC-SB TBM (cont.)? electromagnetic analyses models

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Safety analysis of CH HC-SB TBM (cont.)? electromagnetic analysis

The simplified 3-D model The maximum induced eddy currents under CDII The maximum stresses components of model B

The maximum stresses of model A The EM torques of model A and model B The EM torques of the nine sub-modules

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Safety Analysis for CH HC-SB EM-TBM (cont.)? Preliminary LOFA analysis for EM-TBM

e=0. 7

0

100

200

300

400

500

600

700

800

900

1000

0. 1 1 10 100 1000 10000 100000

Ti me/ s

Temp

erat

ure/

o C

Fi r st Wal lBack Wal lHot t est Poi nt

e=0. 3

0

200

400

600

800

1000

1200

1400

0. 1 1 10 100 1000 10000 100000

Ti me/ s

Temp

erat

ure/

o C

Fi r st Wal lBack Wal lHot t est Poi nt

Plasma no disruption: ex-vessel TBM coolant leaks

The two figures show temperature changes of materials after loss of flow accident. The smaller heat radiation emissivity of material is , the rapider temperatures of material increase. Under this accident condition, the auxiliary coo l sys tem is necessa ry to decrease the tem perature o f TBM shel l.

44

Plasma disruption: in-vessel TBM coolant leaks

e=0. 7

0

100

200

300

400

500

600

700

0. 1 1 10 100 1000 10000 100000

Ti me/ s

Te

mp

er

at

ur

e/oC

Fi r st Wal lBack Wal lHot t est Poi nt

e=0. 3

0

100

200

300

400

500

600

700

0. 1 1 10 100 1000 10000 100000

Ti me/ s

Temp

erat

ure/

o C

Fi rst Wal lBack Wal lHot test Poi nt

Safety Analysis for CH HC-SB EM-TBM (cont.)? Preliminary LOCA analysis for EM-TBM

This figure shows temperature changes of m aterials after the end of blow -down. When heat radiation emissivity of material is 0.7, the peaking value of FW is about 623 OC at the transient time of about 1s.

This figure shows temperature changes of materials after the end of blow-down. W hen heat radiation emissivity of material is 0.3 , the peaking value of FW is about 623 OC, too, at the transient time of about 1s. But curves have different change trends after 1000s.

Activation & afterheat Reliability analysis E-M calculation model

E-M analyses LOCA analyses LOFA analyses

33

VI. Test and R&D plansVI. Test and R&D plansVI. Test and R&D plansVI. Test and R&D plans

34

Relevant R&D plans System Integration, Out-pile R&D

• Module fabrication technology

• Thermo-mechanical integrity of module

• Thermo-mechanical performance

• Thermal hydraulic research

System Integration, Out-pile R&D

• Module fabrication technology

• Thermo-mechanical integrity of module

• Thermo-mechanical performance

• Thermal hydraulic research

In-pile R&D

• Breeder/multiplier development

• Irradiation technology development

• Irradiation tests of blanket partial mockup

In-pile R&D

• Breeder/multiplier development

• Irradiation technology development

• Irradiation tests of blanket partial mockup

Tritium Recovery System Development

• Process and system development

for hydrogen pump,

• Coolant purification system

Tritium Recovery System Development

• Process and system development

for hydrogen pump,

• Coolant purification system

Neutronics / Tritium Production

Tests with 14MeV neutrons

• Neutronics performance of blanket

mockup and improvement of analysis accuracy

Neutronics / Tritium Production

Tests with 14MeV neutrons

• Neutronics performance of blanket

mockup and improvement of analysis accuracy

Material Development

• Irradiation data of RAFM (CLAM), etc.

• Environmental effect, etc.

Material Development

• Irradiation data of RAFM (CLAM), etc.

• Environmental effect, etc.

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Irradiation Test on High Flux Reactors

China has built a High Flux Engineering Test Reactor (HFETR) in the China Institute of Nuclear Power (CINP) . HFETR is a largest one in Asia.

Neutron Flux: Thermal neutrons : 6.2×1014 n/cm2•sec; (E<0.625eV) Fast neutrons : 1.7 ×1015 n/cm2•sec; (E>0.625eV) 235U of 90% enriched in U fuel. Total power: 125 MW (th)

In addition, there are two sets experiment reactors with power of 20MW and 40MW are constructing in CIAE and CAEP of China.

These facilities and their ability are useful for the irradiation experiment of the TBM structure materials, tritium breeders, neutron multiplier etc.

High Flux Engineering Test Reactor (HFETR)

36

High Temperature He Experiment Loop

A High Temperature He Experiment Loop (HTHEL) with 700 OC and 8-10 MPa, which is useful for HC-SB TBM design and R&D activities, is proposed to be built in SWIP.

China has built a high temperature gas-cooled reactor (HTGR). The technologies and experiences gained in HTGR project will be useful.

Temp.: 900 OC, Total Power: 10MW Pressure: 3 MPa

He Test Loop for HTGRHTHEL sketch map

37

Solid Breeder Technology China has studied tritium-processing technology supported by

national fusion program for many years. Knowledge accumulated in this field is useful for the TBM tritium technology.

Two kinds of ceramic breeder( Li4SiO4 , Li2TiO3 ), are developing in China.

Fabrication sample of the Li4SiO4 pebbles Fabrication of the ceramic powder

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General Design and R&D Schedule for HC-SB TBM

Items 06 07 08 09 10 11 12 13 14 15 Day 1

Design Phase

Detail design

Engineering design

Materials Development

Ceramic Breeder, Li4SiO4 , Li2TiO3

Structural material , (RAFS steel)

Neutron multiplier, Be

Performance Testing

In-pile testing

Out--pile testing

Tritium Technology

Tritium Extraction Technology

Tritium permeation Barriers

Coolant purification simulation loop

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Years 06 07 08 09 10 11 12 13 14 15TBM Sub-components qualification.

Small mock-ups fabrication

Test/qualification

TBM Functional tests

Small and medium size mock-ups fabrication

Small and medium sizes mock-ups tests

Full size mock-ups fabrication

Full size mock-ups tests

EM-TBM for installation

CH EM-TBM fabrication

CH EM- TBM acceptance tests

ITER OperationDay one

Time Schedule for CH HC-SB TBM Fabrication and Test

40

Proposed test facilities prior to TBMs installation in ITER

Facilities name Main objectives Parameters Location

A high temperature He Experiment Loop based on China HTGR technologies.

TBM mock-ups test 500-700 OC and 8-10 MPa (adjustable)

SWIP/ (planning)

A facility for high heat flux properties test

Evaluation of plasma facing materials and components

Max. power density: 20 MW/m2,

Active cooling, control of the temperature of coolant from RT-150

SWIP/ (planning)

High Flux Engineering Test Reactor (HFETR)

Materials Test Thermal neutrons : 6.2×1014 n/cm2•sec; (E<0.625eV)Fast neutrons : 1.7 ×1015 n/cm2•sec; (E>0.625eV)

CINP/ (existing)

Facilities of tritium extraction, purification, permeation , and test

Tritium extraction and recovery experiment from the purge gas and coolant.

TBD CAEP,

CIAE & SWIP (planning)

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1. CH TBM Projects1. CH TBM Projects

1.1 Test Blanket Module1.1 Test Blanket Module

1.3.1 QA Management 1.3.1 QA Management

1.3.2 Safety & Licensing

1.3.2 Safety & Licensing

1.3.3 Test Plane Management

1.3.3 Test Plane Management

1.1.1 Design1.1.1 Design

1.2 Ancillary System1.2 Ancillary System 1.3 Project Strategy1.3 Project Strategy

1.3.4 Testing Relevant R&D

1.3.4 Testing Relevant R&D

1.1.2 Performance Analysis

1.1.2 Performance Analysis

1.1.4 Prototype Fabrication & Testing

1.1.4 Prototype Fabrication & Testing

1.1.5 TBM Fabrication & Assembly

1.1.5 TBM Fabrication & Assembly

1.2.1 Design, R&D1.2.1 Design, R&D

HCSHCS TESTESCPSCPS

MSMS

1.2.3 Fabrication & Assembly

1.2.3 Fabrication & Assembly

1.2.4 TBM integration installation

1.2.4 TBM integration installation

1.1.3 Technology Relevant R&D

1.1.3 Technology Relevant R&D

1.2.2 Testing integrationPerformance

1.2.2 Testing integrationPerformance

Work Breakdown Structure of HC-SB TBM

..\..\WBS系统\WBS(06-02-28).xls

Tritium technologies - Tritium extraction & - Tritium control and ISS

- Tritium loop qualification

- Tritium permeation Barriers

Ceramic breeder technologies

- Fabrication;

- Performance test;

- Irradiation test. Thermo-mechanics and helium flow test

Test of on the pebble bed thermo-mechanics and helium flow stability and distribution by means of a high temperature, high pressure He test loop.

Expected Collaboration on TBM R&D

43

Domestic Cooperation Units on R&D for HCSB TBM

SWIP Southwestern Institute of Physics

(TBMs)

SICCAS Shanghai Institute of Ceramics, Chinese Academy of Sciences

(Ceramic Breeder)

TUNETTinghua Uni, Institute

of Nucl. Energy Tech.(HCS)

TUNETTinghua Uni, Institute

of Nucl. Energy Tech.(HCS)

CAEPChina Academy of Engineering Physics

(CPS, TES)

CAEPChina Academy of Engineering Physics

(CPS, TES)

Ningxia Orient Non-ferrous Metal Group CO.,LTD

Be pebbles

44

V. SummaryV. Summary

New progress and status of CH HC-SB TBM are introduced briefly. By ITER TBM testing, demonstrative data of blanket functions will be obtained in fusion environment.

A preliminary design and analysis for CH HC-SB TBM has been preformed The detailed design and analysis of EM-TBM are ongoing.

Preliminary R&D program, timescale and milestones, up to the installation in ITER (2015), as well as the collaboration expected with other Parties are presented.

Relevant R&D on the key techniques will be preformed with the cooperation of domestic and international institutions and companies.

45

Thank you for your attention!