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Progress and Preliminary R&D Plans of China Solid Breeder TBM

Progress and Preliminary R&D Plans of China Solid Breeder TBM

K.M. Feng

Presented at 13th Ceramic Breeder Blanket Interaction Workshop – Santa Barbara, CA, USA

Nov. 30-Dec. 2, 2005

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ContentsI. IntroductionII. Design Progress of CH HC-SB TBMIII. Preliminary R&D and Test PlansIV. Possible Collaboration with Other PartiesV. Summary

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A description design and it’s performance analysis of CH HC-SB TBM have been carried out recently.

A design description document (DDD) of the HC-SB TBM have been completed recently. The relevant R&D, test plans based on the TBM design were proposed.

China hopes to widely collaborate with other ITER parties under TBWG framework, and expects to deliver a HC-SB TBM to ITER on day one. Possible collaboration field on TBM R&D with partiers have been given.

I. Introduction

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II. Design and AnalysesII. Design and Analyses of of CH CH HCHC--SB TBMSB TBM

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Present design is based on the ¼ port size on Port C;However, It is easily extended to a half-port-space module.

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

Assumed Port Position for CH HC-SB TBM Module

HCS

TWCS

CH

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Modular Design on StructureBe armor: 2 mm

Max Temp. 543OCFirst wall:thickness: 30 mm

Material: EuroferMax T: 530OCCooling tube: 18x14.5mm

Unit cells: 3X3 sub-modulesHe pressure: 8 MPa

664mm

Integration view of structure design

Sub-modules

0.190 m in toroidal0.420 m in radial0.260 m in poloidal

664mm

890mm

630mm

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Main Characteristics

1. Modular structure design improve and strengthen the safety performance, reliability, maneuverability of test in ITER, and disassembly feasibility, more easy to replace the sub-module;2. The BOT with ceramic pebble bed concept, Be as neutron multiplier are used in the design; 3. A U-shaped double-shell FW structure is used;4. Each cell as a sub-module has relative independently cooling circuit (8 MPa He) and purge gas circuit (0.1 Mpa ). The cooling model in series connection from FW to sub-modules are used; 5. Each sub-module is a closed box by the top-lower plates with two side-plates.

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Schematic view of CH HC-SB TBM

Outside of structure Cross-section of module Coolant manifold

Sub-module structure

Cross-section of sub-module

Configuration of Sub-modules

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Exploded 3-D view of HC-SB TBM

Structure and components design in detail is on going.

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section plane

Cooling tube of FW

Heat exchangerCoolant manifoldU-shaped double-shell FW structure

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Interface Description

Test port general arrangement TBM module assembly

Equatorial test port area with transporter Transporter side wall pipe arrangement Equatorial port and pipe area

HCS sub-system in TCWS

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Design parameters for the HC-SB TBM

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HC-SB TBM Auxiliary Sub-system

TBM HCS CPS

VV Port Cell TWCS vault

Tritium Building

BC

TES

TMS

NMS

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Schematic views of Coolant flow

Coolant flow in the sub-moduleToroidal cross-section Coolant flow in FW

Back-plate

Coolant Flow DirectionBreeding zone Arrangement Back-plate

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HC-SB TBM Auxiliary Sub-system

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

TWCSHCSTBM

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 TCWS27

Coolant Purification System (CPS)

1

3a

4

6 a 6b

7a 7 b

8

９

He , 30 0 ℃

3 00 ℃

H e, 1 0M P a

5

E S

E S

3b

1 0

H e

2a2 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－ionization chamber;

8－gas chromatograph9—circulator; 10—ZrCo bed

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)

4b

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

H2

T r i t i u m E x t r a c t i o n S y s t e m fo 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 le r4 a /4 b / 4 c I o n i za t i o n C h a m b e r5 C o ld T ra p6 W at e r C o l l e c to r7 R ec u p e r a to r8 a /8 b M o le c u l a r S ie v e s9 a /9 b / 9 c B u ff e r1 0 H o t M g B e d1 1 a /1 1 b C o m p r e ss o r1 2 P d /A g P e r m e a te r1 3 a /1 3 b /1 3 c G e t t e r B e d1 4 a /1 4 b I SS1 5 H e a te r1 6 M a k e - u p U n i t

Ch e c k v av l e

Op e n v a vl e

Cl o s ed va v l e

Pr e s su r e r e du c i n g v a v le

E S Ev a c ua t io n sy s t e m

± ±

± 5

V 1V 2

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

Space Requirement:The TES system must be installed in a glove box.

The size of the Glove 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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a. Neutronics calculationsb. Activation analysisc. Thermo-hydraulic Analysis d. Thermo-Mechanical Analysise. Preliminary E-M analysis;f. Preliminary LOCA, LOFA analysis, etc.,

Above performance analysis have been completed. The results in detail have been given in the CH HC-SB TBM DDD document.

Performance Analysis

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Performance Analysis (Con’t)

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Temperature distribution ofthe HC-SB test module

First wall

Peak Temp. : 543 OC

Sub-module

Temp. Range: 624-737 OC in the breeder zone;Peak Temp.: 522°C in sub-module cooling plate 18

Stress distribution of the HC-SB test module

First wall Sub-module

Max. Stress are 244 MPa in FW and 219 MPa in sub-module cooling plate. This analysis result of the cooling plate in the test module satisfies to the requirements of structure strength regulations.

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E-M and Accident Analyses

model induced eddy currents eddy currents vs. time

In-vessel LOCA shear stresses maximum stresses

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Neutronics Calculation

TBR = 1.15(1-D, Li-6 enriched of 80%) Power: 0.76MWTritium production: 0.033g/dPeak power: 8.9 MW/m3

Neutron flux distribution

Power density

0.0

2.0

4.0

6.0

8.0

10.0

12.0

220.0 230.0 240.0 250.0 260.0 270.0

Radial dis tance from center of plas ma /cm

Ene

rgy

dens

ity /

MW

/cm

3

ONEDANT

TWODANT

MCNP

Tritium production

Neutronics Thermo-hydraulic Thermo-mechanical

Safety and reliability E-M and accident analysisFlow scheme

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Safety and Reliability Analysis

Afterheat Activity

Deformation Equivalent Stress 27

Coolant Flow Scheme

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III. Test and R&D plansIII. Test and R&D plans

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Relevant R&D plans

Continuously improve HC-SB TBM designInterface of TBM, frame and auxiliary system design;Improve and develop relevant software and database;

Development of tritium measurement technology;

Development of neutron diagnostic technology;

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Relevant R&D plans (Con’t)

Manufacturing of key componentsSome necessary R&Ds are being performed for the ITER

shielding blanket task in China. Relevant fabrication technologyobtained will be useful for manufacturing of key components of TBM:

(1) HIP technology for joining different materials, such as Be/Cu;(2) NDT inspection method;(3) High heat flux (HFF) test facility and method, etc.

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The Structural Materials Development Strategy

Development of RAFMs for TBM in China is being performed;

Development of the ODS (oxide dispersion strengthened) steels and vanadium alloy steel are on going in China;

Long-term is to develop SiCf/SiC composites material for advanced fusion blanket concepts.

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Ceramic Breeder and Neutron MultiplierChina has studied tritium-processing technology supported by

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

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

Fabrication sample of the Li4SiO4 and Li2TiO3 pebblesFabrication of the ceramic powder

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Equipments and Technique for Ceramic Breederin CAEP

Melting-spraying unit for the production of Li4SiO4 pebbles

Separation System Control System

γ-LiAlO2 pebbles

Li2ZrO3 Pebbles

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Time schedule for ceramic breeder technologies

R&D Contents 2006 2007 2008 2009 2010 2011 2012 2013 2014

Designing of radiation capsule for material test, designing of tritium circuit

Tritium absorption and releasing behavior on tritium breeder

Property test ( mechanical,physical chemical and thermal property)

Structure and contents designing of tritium; breeder by computation simulation

Development of microspheres fabrication technique

2015

Development of radiation capsule for material test, development of tritium circuitProperty test ( radiation stability, tritium release behavior, tritium fabrication property)

Tritium breeder fabrication as designed by computation simulation

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Development of Neutron Multiplier

Main Chemical Composition of CH 2# and US S-65C**

**Data from the Sixth Smelt Factory of Hunan Province.

China has also large yielding capacity of Be and relevant experiences of neutron multiplier.China has built Be fabrication and manufactory in Ningxia Orient Non-ferrous Metal Group Co. A new project, to develop high quality Be in China, is being implemented for ITER.

Type No. Elements (wt.%)Be BeO Fe C Al Mg

Grade 2# (CH) 99 0.80 0.05 - 0.075 0.015

S-65C VHP (US) 99 1.0 0.08 0.1 0.060 0.060

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Development of Tritium Technologies

Development of tritium extraction technologyDevelopment of tritium extraction technology- Instrumentation development;- Hydrogen isotope separation;- Tritium extraction;- He coolant purification simulation loop;- Tritium control technology;- Tritium release behaviour and required purge gas conditions.

Theoretical simulation and assessmentTheoretical simulation and assessment-- Tritium cycle modelling (tritium permeation, tritium inventory).

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Tritium Technologies (con’t)

Develop tritium permeation barrieramorphous TiN（TiC）films by IBAD;

Al2O3 film by ions coating-oxidation, CVD, explosive spray, etc.

- TPRF >1000 is obtained in specimen experiments.

- To be applied in practice in tritium permeation barrier.

Future R&D in the near future- Key technologies for components and subsystem - Tritium system loop test

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Tritium Processing Equipments in CAEP

Electrolytic Cell Hydrogen Purification Unit

Promising H,T and impurities on line analytical tools

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Tritium Permeation Barrier Study in CIAE

Process apparatus for the Fe-Al coating

Fe-Al layer

316L base

Microstructure of the Fe-Al coating

316L base

Fe-Al layer

0

20

40

60

80

100

0 20 40 60 80 100

与渗层表面距离(μm)

atom.%

Fe

Cr

Ni

Al

Mo

The composition profile in the coating

Fe-Al intermetallic compounds in the coating layer

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Time schedule for tritium technologies

2006 2007 2008 2009 2010 2011 2012 2013 2014

Component structure optimization

Demonstration system

CECE tritiated water disposal

On line analytic tools :MGC,QMS,…

ISS: TCAP, PMS

2015

Tritium emergency-responsesystem

Tritium permeation barrier

Integration and test of realsystem

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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)

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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 China.

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

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

He Test Loop for HTGRHTHEL sketch map

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Design and R&D Schedule for HC-SB TBMItems 06 07 08 09 10 11 12 13 14 15 Day 1

Design PhaseDetail design

Engineering design

Materials DevelopmentCeramic Breeder, Li4SiO4 , Li2TiO3

Structural material , (RAFS steel)

Neutron multiplier, Be

In-pile testing

Performance Testing

Out--pile testing

Tritium TechnologyTritium Extraction Technology

Tritium permeation Barriers

Coolant purification simulation loop

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Small-sized HC-SB TBM mock-up tests (scale 1:4 or larger)

Ceramic pebble bed thermo-mechanical test

First wall heat removal test and thermal cycle test

Prototype TBM mock-up test

Heat removal test and thermal cycle test

TBM check-out with the auxiliary systems prior to ITER installation

Out-of-pile Test

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Tritium release behavior and required sweep gas conditions;

Thermo-mechanical behavior of ceramic breeder and Be pebbles under neutron irradiation conditions;

Structure materials irradiation test;

Mechanical properties test of irradiated ferritic steel samples;

In-of-pile Test

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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

Typical cost estimation : about 0.1-0.2 Billion Chinese Yuan for one CH HC-SB TBM.

ITER OperationDay one

Time Schedule for CH HC-SB TBM Fabrication and Test

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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, Instituteof Nucl. Energy Tech.(HCS)

TUNETTinghua Uni, Instituteof Nucl. Energy Tech.(HCS)

CAEPChina Academy of Engineering Physics(CPS, TES, Breeder )

CAEPChina Academy of Engineering Physics(CPS, TES, Breeder )

Ningxia Orient Non-ferrous Metal Group CO.,LTD

Be pebbles

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V. SummaryV. Summary

New progress and status of CH HC-SB TBM since last TBWG meeting are introduced briefly.

Under the cooperation with domestic institutes, a preliminary design and analysis for CH HC-SB TBM module has been carried out. A design description document (DDD) have been completed recently.

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.

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Thank you for your attention!