1234 25th IAEA FUSION ENERGY CONFERENCE FIP/3-5Ra+FIP/3-5Rb - - PowerPoint PPT Presentation

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1234 25th IAEA FUSION ENERGY CONFERENCE FIP/3-5Ra+FIP/3-5Rb - - PowerPoint PPT Presentation

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1234 25th IAEA FUSION ENERGY CONFERENCE FIP/3-5Ra+FIP/3-5Rb PIP/3-5Ra + FIP/3-5Rb Current Status of Chinese Solid Tritium Breeder TBM Improved Design and Analyses of CN HCCB TBM K.M. Feng 1 *, C.H. Pan 2 , X.R. Duan 1 , C. Xing 2 , X.Y. Wang,

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SLIDE 1

Current Status of Chinese Solid Tritium Breeder TBM

Presentation at the 25th IAEA Fusion Energy Conference - IAEA CN-221.

  • Oct. 13-20, 2014, Russian Federation, Saint Petersburg

1) Southwestern Institute of Physics, Chengdu, China 2) ITER Chinese Domestic Agency, CNDA, Beijing 100862, China

Co-Institutes:

1). China Academy of Engineering Physics (CAEP), Mianyang, P.R. China 2). Institute of Nuclear Energy Safety Technology (INEST). CAS, Hefe, P.R. China 3). Baoji Haibao Special Metal Materials Co. Ltd., Baoji, P.R. China

25th IAEA FUSION ENERGY CONFERENCE FIP/3-5Ra+FIP/3-5Rb

Improved Design and Analyses of CN HCCB TBM

K.M. Feng1*, C.H. Pan2, X.R. Duan1, C. Xing2, X.Y. Wang, G.S. Zhang1, Y.J. Chen1, Y.J. Feng1, P.H. Wang1, Z.X. Li1, G. Hu1, Z. Zhao1, X.F. Ye1, L. Zhang1, Q.J. Wang1, Q.X. Cao1, F.C. Zhao1, F. Wang1, Y. Liu1, M.C. Zhang1, Y.L. Wang1, M. Bai1, J. Wang1, B. Xiang, Y. Yu1, G. Yu, Y.F. Cheng,

  • L. Yang, and Chinese HCCB TBM team

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PIP/3-5Ra + FIP/3-5Rb

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SLIDE 2

Outline

  • 1. Introduction
  • 2. CN HCCB TBS Design Progress
  • 3. CN HCCB TBS R&D Progress
  • 4. Test Plan and Time Schedule
  • 5. Summary
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SLIDE 3

 ITER provides an unique opportunity to test tritium breeding blanket mock- ups in integrated Tokamak operating conditions.  Helium-cooled ceramic breeder (HCCB) test blanket module is the primary

  • ption of the Chinese ITER TBM program.

 China as Port Master (PM) in port number 2 and the HCCB TBM concept Leader (TL) will test her own TBMs at different ITER operation phases.  In order to reduce the effects of magnetic field ripple, the TBM design has been updated with reduced RAFM mass.  Related R&D on key components, materials, fabrications and mock-up test have being implemented.  China ITER DA have signed the HCCB TBS TBMA with ITER IO in February 2014.  The Conceptual Design Review (CDR) for CN HCCB TBS was hold in July 2014

Introduction

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SLIDE 4

TBM Concepts and Port-Sharing

 CN HCCB TBM will demonstrate the required functions and technical feasibility for Chinese DEMO breeding blanket in ITER operation condition.  The HCCB-TBS TBM Arrangement (TBMA)was signed on Feb. 13th in the ITER council chamber by ITER DG Motojima and Director Luo of the CN DA.  This is a very fundamental step forward for the Chinese TBM Program.

Port No. and PM TBM Concept TBM Concept A (PM : EU) HCLL (TL : EU) HCPB (TL : EU) B (PM : JA) WCCB (TL : JA) HCCR (TL: KO) C (PM : CN) HCCB (TL : CN) LLCB (TL : IN)

 Six TBM systems to be installed in three ITER test ports

PM : Port Master, TL : TBM Leader

HCLL : Helium-cooled Lithium Lead (Helium/LiPb) HCPB : He-cooled Pebble Beds (Helium/Ceramic/Be) WCCB : Water-cooled Ceramic Breeder (Water/Ceramic/Be) HCCR: Helium Cooled Ceramic Reflector (Helium/Ceramic/Be/Gr.) HCCB : Helium Cooled Ceramic Breeder (Helium/Ceramic/Be) LLCB : Lithium-Lead Ceramic Breeder (LiPb & He, Dual-Coolant)

The signing ceremony of CN TBS

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SLIDE 5

General HCCB-TBS Testing Program Objectives

.

General Testing Program Objectives

Provide operational data base for TBS Control system for the

  • peration of blanket

systems

Diagnostics for the

monitoring of blanket systems Blanket power removal predictions Safe operation and maintenance of systems Fusion neutron irradiation for materials Power production and transfer of blanket system and components Maintenance and exchange of blanket components Integral performance of blanket systems ITER

Sub-module DEMO

T B M

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SLIDE 6
  • Introduction
  • CN HCCB TBS Design Progress
  • CN HCCB TBS R&D Progress
  • Test Plan and Time Schedule
  • Summary

Outline

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SLIDE 7

CN HCCB TBM design - History

  • A series of the Chinese HCCB TBM designs have been carried-out since 2004 within

the port space limitation and technical requirements specified by ITER IO.

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SLIDE 8

Original HCCB TBM Design

  • TBM Box structure: 2X6 Sub-module arrangement
  • Structure material: RAFM (CLF-1);
  • Tritium breeder: Li4SiO4 pebble bed, 80%Li-6 ;
  • Neutron multiplier: Be pebbles bed;
  • Coolant and purge gas: Helium gas
  • Coolant pressure: 8MPa
  • Coolant temperature: 300 OC(inlet) -500 OC (outlet)
  • Tritium production ratio (TPR): 0.0505g/d

Integration View

Cross-section of Sub-module

Assembly scheme of Sub-Modules

Basic design characteristics:

  • Original design of CN HCCB TBM (2X6 sub-modules

arrangement) before 2009.

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SLIDE 9

TBM design – updated to current design

Parameters Values Neutron wall load 0.78 MW/m2 Surface heat flux 0.3 MW/m2 Structural material CLAM/CLF-1 ~1.3ton (<550ºC) Tritium Breeder Li4SiO4 pebble bed (<900ºC) Neutron Multiplier Beryllium pebble bed (<650ºC) Coolant Helium (8MPa) 1.04 kg/s (Normal) FW(300ºC/370ºC) Breeding zone (370ºC/500ºC) Purge gas Helium with H2

  • Four sub-modules concept
  • Manufacturability
  • PIE/ transportation
  • U shape breeding zone
  • Reduce the structural material

 In order to simplify sub-module structure; reduce RAFM mass and increase TPR

performance, the design of CN HCCB TBM in 2012.

 Main optimization results：

  • All structure material RAFM
  • Total mass of FAFM is reduced to ~1.3t from 1.8t
  • TPR is increased to about 0.066g/d from 0.050g/d

Updated design with 1X4 SM

Main design parameters

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SLIDE 10

Sub-module

 A TBM contains 4 sub-modules.  Each sub-module has one FW, two caps in top and bottom, middle rib, manifold.  4 inner cooling plates in U shape in the sub-module.  Tritium breeder Li4SiO4 and neutron multiplier Be pebbles are distributed between these structure parts. Outside View Explosive view of sub-module Cross section View (R-T) Cross section View (R-P)

TBM design - Current Design of sub-module

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SLIDE 11

TBM shield design

Parameters Values

Structural material SS316LN-IG Coolant Water (4MPa) 0.1 kg/s (Normal) 70ºC/125ºC Dead weight ~5 tons Water volume 0.98 m3 Water fraction ~40% Nuclear heating 20.3 kW

  • Welded box structure concept
  • Manufacturability

Design parameters

 TBM shield is composed of the flange, plates, caps, pipes, etc.

 There are totally 7 pipes passing through; double-wall pipes are considered for thermal isolation, and the area between walls will be pumped into vacuum.

Schematic diagram

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SLIDE 12

Configuration Scheme of HCCB TBS

TBM set PF AEU TES HCS CPS

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SLIDE 13

Auxiliary (HCS,TES,CPS) design

Parameters Values (HCS) Main structural material Supporting structure material SS316L SS304 Primary coolant circuit

  • Pressure
  • Total flow rate
  • Pressure drop
  • Inlet/outlet temperature

Helium 8 MPa 1.04 kg/s ~0.5 MPa 370ºC/500ºC Interface with CCWS

  • Pressure
  • Total low rate
  • Inlet/outlet temperature

Water 0.8 MPa 21.3 kg/s 31ºC/43ºC Tritium related system Values (TES, CPS)

  • Purge gas
  • Tritium purification efficiency
  • Impurity removal efficiency
  • Tritium extraction efficiency

He ≥ 95% ≥ 90% ≥ 90%

Design parameters

HCS Design

 Based on requirements of heat removal, tritium extraction, coolant purification, and I&C from TBM module and the performance, the basic operation parameters of HCS, TES,CPS and I&C are proposed.

CPS Design TES Design

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SLIDE 14

Design integration – with IO joint design

Layout of ITER machine of the Ports for TBMs Test Port Arrangement for CN HCCB TBM

 The sub-systems includes a Helium-cooled System (HCS), a Tritium Extraction System (TES), a Coolant Purification System (CPS), connection pipes, and the AEU and pipe forest (PF), etc.

 Other interfaces/requirements including power, cooling water, signal process, maintenance strategy, et al. have been considered or are on-going.

Integration on Port Cell and AEU Pipe Forest with IN TBM

HCCB TBM

Port #2 PF

& AEU

Connecti

  • n Pipes

HCCB HCS

HCCB TES

IN-TBM CN-TBM AEU

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SLIDE 15

Related analyses

Neutronics model Neutron energy spectrum Power density distribution Temperature distribution Equivalent stress distribution

 In order to verify the design, related calculation and analyses have been performed.

– Neutronics analyses – EM analyses – Hydraulic analyses – Seismic analyses – Thermal analyses – Structural analyses – Safety analyses

IN-TBM CN-TBM

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SLIDE 16
  • Introduction
  • CN HCCB TBS Design Progress
  • CN HCCB TBS R&D Progress
  • Test Plan and Time Schedule
  • Summary

Outline

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SLIDE 17

R&D related to TBM set

1-ton Ingot

 RAFM steel - CLF-1 and CLAM

 Two RAFM steels CLF-1 and CLAM for Chinese TBM were produced by vacuum induction melting method.  Neutron irridiation test data up to 2.5 dpa was obtained by using the high flux test reactor in China. ► Establishment of the material properties databases including mechanical, physical and neutron irradiation properties, have been completed. ► Welding performance was tested. ► Qualification as CN HCCB TBM stricture material is

  • ngoing.

4.5-ton Ingot CLF-1 Steel CLAM Steel of vacuum smelting ingot

MPT/P8-7: P. Wang

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SLIDE 18

 Tritium Breeder – Li4SiO4

R&D related to TBM set

Li4SiO4 pebble Thermal conductivity of pebble bed SEM of pebble’s surface SEM micrographs of pebble

Properties Values Density 2.32 g/cm3 Open porosity (%) ~ 5.2 Closed porosity(%) ~ 1.78 Specific surface area (m2/g) 0.4626 Pore Radius (nm) 3.674

100 200 300 400 500 600 700 800 900 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 Thermal conductivity(W/m.K) Temperature(

0C)

Enoeda et al (2001 ) 0.25~0.63mm PF=62.5% Dall Done et al (1990) 0.5mm Dall Done et al (2000) 0.25~0.63mm PF=65% Dall Done et al (1994) 0.35~0.6mm PF=64.4% Our experimental data

 The ceramic breeder pebble of kg-class was fabricated by a melt spraying method.  Related properties were tested.  Main performance meets the requirement of HCCB TBM module design.

Fabrication facility Main properties of Li4SiO4

MPT/P8-6: Y. Feng

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SLIDE 19

 Neutron Multiplier– Beryllium

R&D related to TBM set

Beryllium pebble (D:1mm) Deformation of the Be pebbles for various applied mechanical loads SEM micrographs AFM micrograph

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 500 1000 1500 2000 Compressive Load (N) Deformation (mm) Diameter= 0.7 mm Diameter= 1.0 mm

0.1 0.2 0.3 0.4 100 200 300 400

Item Value Pebble diameter, (mm) ~1.0mm Density, (% T. D.) 98 Tap density, (g/cm3) 1.115 Sphericity, (%) 99.7 Specific surface area (m2/g) 0.5449

 The Be pebble of kg-class was fabricated by a REP method. Larger scaled fabrication of 10kg-class is progress.

REP Facility

Main properties of Be pebble

MPT/P8-6: Y. Feng

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SLIDE 20

 Manufacturing R&Ds for TBM module components have been investigated which include Hot press joining, EB welding, laser welding, tensile test and impact test, etc.

R&Ds related to TBM set

Hot press welding EB welding Tensile test Impact test U-shaped FW Sub-module component Sub-module Partition

 A medium-sized mock-up of U-shaped first wall is completed;

 Full scale first wall is under way.  Different fabrication method (EBW, HIP, TIG) are used for FW and components joint.

MPT/1-2: X. Liu

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SLIDE 21

R&Ds of auxiliary systems

TES testing system CPS testing loop

 Related tritium auxiliary systems and R&D performed in CAEP:  Some test facilities are under construction.

  • A hot metal bed circulation loop
  • A MS adsorption loop
  • A hydrogen isotope separation sub-system
  • Experiments for Impurity absorber bed
  • Experiments for oxidation bed

Layout of TES system

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SLIDE 22
  • Introduction
  • CN HCCB TBS Design Progress
  • CN HCCB TBS R&D Progress
  • Test Plan and Time Schedule
  • Summary

Outline

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SLIDE 23

HCCB TBMA Milestones

  • 1. TBS Design activities

– HCCB TBS CDR approval (Oct.2014) – HCCB TBS PDR approval (July 2016) – HCCB TBS FDR approval (April, 2018) – Amendment HCCB TBMA (July 2018) – Contract signature for HCCB TBS (Oct. 2019)

  • 2. TBS Qualification activities

– Materials qualification (Not in SMP milestone, but for FDR) – Manufacturing process qualification (April 2019)

  • 3. TBS delivery activities

– HCCB TBS delivery ITER site (Sep. 2021) – HCCB TBS acceptance tests in ITER site (Jun, 2022)  Current HCCB TBMA milestones is based on the current ITER construction,

  • peration plan.

 CN HCCB TBS Milestones may be adjusted according to the update of ITER plan.

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SLIDE 24

Testing Strategy for the CN HCCB TBS

Operation Phase Testing Description TBM type H-H Safety, thermal load of surface, E-M load, disruption EM-TBM D-D Neutron response data, Thermal behaviors TN-TBM D-T (Low duty) Structure behaviours, Nuclear response for D-T neutron, Tritium production, Tritium procedure validation TN-TBM D-T (High duty) Operational behaviours, Heat transfer, Tritium production and management. Overall reliability and

  • perational

performance NT/TM INT-TBM

 At least four kinds of TBM modules will be tested in ITER different

  • perating phases.
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SLIDE 25

HL HL-2A

ITER Operation and TBM Test Schedule

2019 2020 2021 2022 2023 2024 2025 2026 2027 2028 2029 2030 2031 2032 Construction First Plasma (current ITER SMP) ITER Commissioning and Operations

Start Torus Pump Down

Pump Down & Integrated Commissioning

First Plasma

Plasma Development and H&CD Commissioning

Nuclear License Blankets Divertor

DT Hybrid Scenario DT Non Inductive He H-Mode Studies Pre-Nuclear Shutdown & Divertor Change DT Plasma Exploration & DT H-Mode Studies Shutdown

Q=10 Q=10 Long Pulse

End of Magnet Commissioning Phase 2 Machine Assembly Commission, Cool & Vacuum

Plasma Restart

Phase 3 Machine Assembly / Regulatory Shutdown Full H&CD, TBM & Diagnostics Commissioning

Full Heating Power @ Short Pulse N Licensing validation 100% T-fuelling capability

D Plasmas on W Divertor D H-Mode Studies Trace-T Studies

100% Tritium throughput capability All TBMs installed

TBMs installation EM-TBM TN-TBM NT/TM-TBM INT-TBM

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SLIDE 26
  • Introduction
  • CN HCCB TBS Design Progress
  • CN HCCB TBS R&D Progress
  • Test Plan and Time Schedule
  • Summary

Outline

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SLIDE 27

 The TBM program is an important part of China fusion development Strategy, for which HCCB concept is the primary option.  The HCCB TBMA has been signed between ITER and CN DA. The CDR has been hold in 2014.  The design of HCCB TBS is developing in details according to the

  • schedule. R&D progress on structure material, function materials

(ceramic tritium breeder, neutron multiplier Be pebble), medium- sized FW mock-up, others components of the sub-module.  The R&D and test plan, delivery of CN HCCB TBS are scheduled. PD and FD design is under implementation.  Chinese HCCB TBM test will be implemented with the cooperation

  • f domestic and international institutions and industries.

Summary

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SLIDE 28

Thanks for your Attention !

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