efda european fusion development agreement wong.pdfpbli (at the cooling time of 50d) 1....

Y. Poitevin & WSG2 WSG2 report to TBWG-14, Naka, 15-17 Dec. 2004

1

EFD A EUROPEAN FUSION DEVELOPMENT AGREEMENT

WSG2 @ TBWG-14 Members

Y. Poitevin, J.F. Salavy…EU

Y. Wu, G. Zhang…PRC

S. Konishi, A. Kohyama…Japan

Y. Kim…Korea

C. Wong…USA


2


Status of Parties interest in PbLi-LAFS-He concepts

• 6 Parties remain interested in developing (or collaborate to thedevelopment) and testing LiPb-LAFS-He concepts in ITER

• 3 Parties propose their own TBM design within WSG2

Dual coolantDual-Coolant Lithium-Lead

(DCLL)

US

Single-He / Dual coolantDual Functional Lithium-Lead

(DFLL)

CH

Single-He coolantHelium-Cooled Lithium-Lead (HCLL)

EU

• 3 other Parties are willing to collaborate on tests & R&D (JA, KOR, RF)

LiPb

Outlet

LiPb

Inlet


3


TBM Design: Updated geometry overview


8


LiPb ancillary circuits: Rationales and Integration (2/2)(to be integrated in theup-to-date ITER

geometry)


12


LiPb ancillary circuits: Equipments designStorageStorage //drainingdraining

tanktank

Cold Cold traptrap andanddetritiationdetritiation unitunit

Pipe Pipe disconnectorsdisconnectors

Support for dilatations Support for dilatations accomodationaccomodation

1 Recall of Presentations for TBWG Meetings

• TBWG-11: Introduction,Status of China Related Activities (mainly on hybrid)

• TBWG-12: Basic conceptChina LiPb TBM & DEMO blankets

• TBWG-13: Preliminary design of DFLL-TBM (0.25MW/m2)China LiPb TBM (Dual-Functional Lithium-Lead)

• TBWG-14: More detailed Design of DFLL-TBM and DEMO(0.5MW/m2)

• Design Iteration for DEMO and TBM: still under way

DLL: He/LiPb Dual-cooled Lithium Lead BlanketCoolant 1: He-gas (R-T + P-directions) Coolant 2 & T-Breeder: LiPb (flowing in P-direction)

SLL: He-cooled Quasi-Static Lithium Lead Blanket

Single Coolant: He-gas (R-T + P-directions) T-Breeder: Quasi-Static LiPb: (slowly flowing in P-direction)

FDSASIPP

Reference Design of DLL/SLL Blanket for FDS-II

virtual movement

Animation :

3 Status of DFLL-TBM Design

• Structure/Flow/Assembling Sequence

• Neutronic (& activation) Analyses (TBR, heat, flux, dose, BHP)

• Thermalhydraulic (& MHD) Analyses (0.25 0.5MW/m2)

• Mechanic and Reliability Analyses

• Auxiliary system (LiPb, He) and Tritium Permeation Estimation

• Test Program and Work Schedule

LiPb

Inlet

LiPb

Outlet

LiPb

Flow

He-gas/LiPb Flows Scheme

FDSASIPP

Cooling System

He-gas Flow in FW and SP

Animation of He-gas Flowing Scheme for DFLL-TBM

LiPb Tank

TBM

Pump

Flow MeterGas injection

Gas injectionHe inlet

He outlet

Dump Tank Fill/Drain

Heating

HeHe Detritiation unit

He inlet

He outlet

LiPb/HeHeatExchanger

Quasi-StaticLiPb(SLL)

Dual-cooled(DLL)

Structure Outline

Back Plate2 (BP2)

radial-toroidalStiffening Plates (rtSP)

toroidal-poloidalStiffening Plates (tpSP)

radial-poloidalStiffening Plates (rpSP)

Back Plate3 (BP3)Back Plate4 (BP4)

First Wall (FW)

PbLi header PbLi inlet Pipe

PbLi sub-Pipe

He inlet Pipe

He outlet Pipe

Up-cover

Back Plate1 (BP1)

Structure: Coating/Insert

Coating: for SLL-functionThe Al2O3 coating is being considering

FCI: for DLL-functionSiC Flow Channel Insert may be selected to reduce the MHD pressure drop and as thermal insulator

RAMF steel (China Low Activation Martensitic steel)PbLi eutectic

Structural materialBreeder/multiplier

Pol. 1832 mm x Tor. 626 mm x Rad. 585 mm (without external headers)Gap of TBM/Frame = 20 mm

TBM dimensions

SLL-TBMDLL-TBMScenario

Thickness: 32 mm； 8 parallel cooling channels; (8 x 16) mm2, pitch 17.5mmQHe = 0.287 kg/s; VHe =26 m/s；Tin/out (He) = 404/450 °C

QHe = 1.252 kg/s; VHe =26 m/s；Tin/out (He) = 404/450 °C

He: Pin = 8 Mpa; Qtot = 1.538kg/sTin/out = 300/450 °C; LiPb: VTBM=~0mm/s

Thickness: 32 mm； 8 parallel cooling channels; (8 x 16) mm2, pitch 17.5mmQHe = 0.287 kg/s; VHe =26 m/s；Tin/out (He) = 404/406 °C

Covers

QHe = 1.251 kg/s; VHe =26 m/s；Tin/out (He) = 404/406 °C

Stiffening platestpSP+rpSP+tpSP

U-shape; Thickness: 30 mm (5/15/10)Toroidal He cooling; 4 paths; Cooling channels: (15 x 20 )mm2, pitch 25 mmTin/out (He) = 300/404 °C; QHe = 1.538 kg/s; VHe = 47 m/s

First Wall

He: Pin = 8 Mpa; Qtot = 1.538kg/sTin/out = 300/406 °C; LiPb: Tin/out = 300/450 °C; Ave. VLL1=15mm/s, VLL2=5mm/s, VLL3=2mm/s ; Vpipe=0.14m/s; Max.Qtot=13kg/s

Coolants

0.78 MW/m2

0.5MW/m2

1.2MW

Neutron Wall LoadingHeat FluxTotal deposited power

Main Design Parameters

Thermal / Stress Analysis in FW

• Max. temperature in FW structure is 544℃ (<Permitted T of RAFM =550 ℃) for He outlet temp. 450℃ and FW heat flux 0.5MW/m2. • Max. Von Misses stress in FW is 347MPa (<3Sm=351MPa at 550 ℃) and Max. Displacement is 0.9mm.

Probability Reliability AnalysisLeakage probability

PFM ModelFW failure probability

11

1,0(!

k}P{x

C/

8.0

0)(f

m

/

Mq

Mk

a

eQ

kkeMKdNda

ta

aea

−

−

−

−=

……===

∆×=

≥

>=

）

，λ

λ

10000 15000 20000 25000 30000 35000 40000

0.0

0.1

0.2

0.3

0.4

0.5

0.6

0.7

FW RP RT TP BP CP Leakage

Y A

xis

Title

X axis title

10000 15000 20000 25000 30000 35000 40000

0.0

0.1

0.2

0.3

0.4

0.5

0.6

T5 T7 T10

Failu

re P

roba

bilit

y

Cycle Number

PSA Model

Too many assumption ?

Too many assumption?

Fracture probability

PbLi (at the cooling time of 50d)1. Pb206(n,a)Hg2032. Pb204(n,2n)Pb203(b+)Tl203(n,2n)Tl202

RAFM (at the cooling time of 50d)1. Fe54(n,p)Mn54,2. Ta181(n,γ)Ta182,3. Fe58(n, γ )Fe59RAFM without impurities(at the cooling time of 10y)1. Fe56(n,2n)Fe55,2. Fe54(n,p)Mn54RAFM with impurities(at the cooling time of 10y)1. Co59(n, γ)Co60m(IT)Co602. Fe56(n,2n)Fe55,3. Fe54(n,p)Mn54

Activation Level of Structure & Coolant(500MW, 59.84days ~0.13MWa/m2, )

1E-5 1E-4 1E-3 0.01 0.1 11E-8

1E-7

1E-6

1E-5

1E-4

1E-3

0.01

0.1

Dec

ay H

eat(K

w/k

g)

Cooling Tim e(yr)

RAFM with im puritiesRAFM without im purity LiPb

1E-5 1E-4 1E-3 0.01 0.1 1 10 1001E-8

1E-7

1E-6

1E-5

1E-4

1E-3

0.01

0.1

1

10

100

1000

10000

100000

Dos

e ra

te(S

v/hr

)

Cooling Time(yr)

RAFM with impuritiesRAFM without impurity LiPb

Limit for maintenance

Limit in the hall

natural ground

Dominant Radioactive Paths: Dose Rate at FW/LiPb-zone

Decay Heat at FW/LiPb-zone

LiPb auxiliary system for DFLL

LiPb Tank

TBM

Cold Trap

Detritiation unit

Pump

Flow MeterGas injection

Gas injection

Flow Meter

He inletHe inlet

He outlet He outlet

LiPb/HeHeatExchangerHe Purge

Hot Trap

Magnetic Trap

Plugging meter

CT Heat Exchanger

C Tdraining

Dump Tank Fill/Drain

Heating MT draining

H Tdraining


20


Neutronic Study on the Korean TBM Concepts

Yonghee Kim

Korea Atomic Energy Research Institute

Beomseok Han

Seoul National University

TBWG-14, December 14-17, 2004, Naka, Japan

Neutronic Study on on He-Cooled Molten Lithium

(HCML) Blanket

- Presented at the 24th SOFT -


21


Blanket without Spectral Shifter

• Radial Builds of Inboard (IB) and Outboard (OB)

Plasma

R=405 cm

VV filler (90% BFS, 10% He)

Back shield

VV

Outer shield Inner shield

Back wall(80% FS, 20% He)

Blanket

FWGap

Plasma

R=840 cm

Thickness, cm 0.5 40 6 1 25 35 2 3 10 3 2 5

(83% nat. Li, 10% He, 7% FS)(85% FS, 10% W, 5% He)

(95% BFS, 5% He)(20% FS, 40% B4C, 40% Pb)

- Natural Lithium (6.58 w/o Li-6) as T Breeder

- FW and Structural Material : Eurofer

- Borated FS in Shield, 3 w/o Boron


22


Cross Sections of Li (ENDF-B/VI)


23


2 4 6 8 10 12 14 16 18 20 221.24

1.26

1.28

1.30

1.32

1.34

Natural Li-6, 6.58 w/o

TB

R

Li-6 weight percent

TBR

• Impacts of Li-6 Enrichment on Blanket Parameters (25cm Graphite)

0 1 2 3 4 5 6 7 8 9 10

1.20

1.22

1.24

1.26

1.28

1.30

1.32

1.34

Tri

tium

Bre

edin

g R

atio

Radial Postion(cm)

Natural Li(6.58w/o Li-6) High-Enriched Li(13w/o Li-6) Low-Enriched Li(3.0w/o Li-6)

Performance of Graphite-Reflected Blanket

Radial position (rear breeder)=3cm


26


The EU preliminary testing program

15

PIE

3000

9

15

3000

10

10,11,12,

13,14

2500

High duty D-T

8

5

3

Fab

6

2

2,4,5

H-plasma

1

Post-exam.

Tests

FabFabrication

IN-TBM

Post-exam.

12,13,147 (opt),

10,11

Tests

FabFabrication

TT-TBM

PIEPost-exam.

7,96,8Tests

Fabrication

NT-TBM

PIEPost-exam.

Tests

Fab, 1, 3Fabrication

EM-TBM

150010007501Equiv. burn

Low duty D-TD-plasmaBack. & conditioning

ITER Operation

7654-1Op. year


27


The EU preliminary testing program

As long as possible

idemReproducibility of preceding tests, reliability15

6 monthsIdemT permeation into coolant: PbLi flow, extraction14

3 monthsIdemT permeation into coolant: PbLi flow, no extraction13

Dedicated burn time required30 consecutive pulses

D-T plasma w/ nominal pulse length (400s) and dwell time (1400s)

T permeation into coolant: no PbLi flow, no extraction

12

10 pulsesD-T plasma (pulse length > 100 s)Stress distribution for code validation11

10 pulsesD-T plasmaTemperature fields for ode validation10

3 monthsD-T plasmaT inventory (experimental conditions TBD)9

3 monthsD-D plasmaD permeation into FW coolant, verification of D-D surface heat flux data

8

10 pulsesD-T plasma (no long pulses required)

Calibration of T source (n, ?flux), test of extractor with D

7

Tests of 3 differents D concentration6 monthsVacuum in plasma chamberH/D permeation from PbLi into coolant6

Plasma op. required to reproduce magnetic field. Need special sensors for magnetic field

4 weeksDuring plasma pulsesMHD pressure drop as a function of PbLi flow rate5

H plasma10 days (10 pulses)

During plamsa pulsesHeat extraction from FW, verification of H-H surface heat flux data

4

3 monthsVacuum in plasma chamberFunctionalities, safety, thermal kinetics of ancillary circuits

3

During the whole BPP, but relevant demonstration has to be obtained before D-D/T

Whole BPPResistance against EM forces2

To be checked with ITER: plasma heating tests can cause damages.

NB: tests 1 to 4 run in // with all tests

1 monthPrior to day-1Installation of TBM, leak tests, remote handling tests

1

CommentMin. durationTest requirementsTest description#


28


CH - Preliminary Test Program of DFLL-TBM

HighDT

HighDT

HighDT

LowDT

LowDT

LowDT

DDHHHHHHDDDDHH

>101098765 4321ITER

Operation(y)-1-2-3

– EM-test– Structure– Stress & Temp.– Code &Data– Auxiliary system – Neutron flux

– Nuclear heat– Dose rate– T-breeding– Code &Data

– T-permeation– T-control – FCI performance

– Thermofluid MHD– Material Irradiation– Synergic nuclear effects– Reliability and Safety

in EAST:H-plasma– D-plasma(1000sec, 1015n/s)– H,D Permeation Test– Heat Load test on FW– EM & MHD Test– Corrosion and Coasting Test

in EAST:

D-plasma(pulse 1000sec, 1015n/s)– H,D Permeation Test– Heat Load test on FW– EM & MHD Test– Corrosion and Coasting Test

Pre-TBM-1 (SLL-function) Pre-TBM-2 (DLL-function)

EM-TBM (SLL-function):

Tritium-TBM(SLL-Function) Integral-TBM

(DLL-Function)

Neutronics-TBM(SLL-Function)


29


-Radiation

damage ~1 dpa in the FCI & structure

- Corrosion and compatibility in nuclear field

-Tritium control

-Tritium breeding and neutronics

-Integrated performance

-Preliminary reliability

-FCI thermal performance and scaled FCI stress

-Initial flow corrosion

-Tritium permeation

-Tritium prod. and neutron flux

-Magnetic field pert. due to FS

-Structure deformation and reliability in FW heat flux and EM loads under tokamak operation

-Some MHD flow tests

Integrated TBM

Thermofluid-MHD TBM

EM/Struct/Neutronics TBM

MHD TBM

- Ancillary system & TBM checkout

- Initial fluid flow and MHD tests

- FW tests

High Duty DT Plasma PhaseLow Duty DT Plasma PhaseD-

PlasmaH-Plasma Phase

Toroidal Field

Year 10Year 9Year 8Year 7Year 6Year 5Year 4Year 3Year 2Year 1Year 0

US DCLL TBM Testing During 1st Phase of ITER

First Plasma

Full Field and surface

heat flux

Full Nuclear Heating

FluenceAccumulation

Down time


30


Testing program – First expressions of interest from Parties

• EU has defined a testing program (list of tests) for HCLL TBM

Reduced time schedule has still to be assessed for time sharing

List of tests to be performed, adapted to each phase of ITER operation

• CH has recently presented a preliminary testing program. CH plans to test in early phase the SLL-function and, in later phase, the DLL-function

• US expresses interest in collaboration and a preliminary test program plan has been prepared.

• JA, KOR expressed interest in collaboration on SiC/SiC insert development and testing (to be included in Dual Coolant type TBM programs)

• RF expressed interest in R&D collaboration (ex. PbLi technology)


31


Preliminary outputs for WSG2 testing program

• A coordinated testing program in ITER has not been achieved yet due to insufficient design details and corresponding test programs

• However, considering:the assumption that all TBMs have to be delivered on time,the number and duration of tests to be performed (see EU, US examples),the specificity of tests with regard to TBM design (EM load, MHD, permeation, etc.) and the differences in the three TBM designs,Time sharing of module testing could be limited by TBM testing requirement and replacement time

• => A minimum of 2 half-ports is required for achieving all test objectives within each specified ITER plasma phase, possibly up to 3 half-ports may be required.

• Today, some flexibility is provided within Port B and C, 2 He lines (2x2 pipes) are dedicated in those Ports for DC concepts (also suitable for Single He coolant).

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