Design Concept for ITER Test Blanket Module TBM from SWIP

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• Design Concept for ITER Test Blanket Module
  (TBM) from SWIP
• K.M. Feng and SWIP TBM team
• Presented at the academic meeting
• of the center for fusion science
• March. 23-24, 2004
• Southwestern Institute of Physics

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OUTLINE

• 1. Introduction
• 2. Design Concept
• 3. Test Port Allocation
• 4. Summary

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1. INTRODUCTION

• One of engineering objective for ITER project is
  to test Tritium Breeding Module (TBM) concepts.
  DEMO-relevant TBM will be inserted in three test
  ports.
• Some the ITER TBM concepts have been proposed by
  EU, RF and JA parties
• Main Concepts
• - Helium ceramic breeder concept main
  stream (database)
• - Liquid breeder concept attractive
  (simple structure)
• ITER Test Blanket Working Group (TBWG) oversees
  and coordinates designs of eventual machine
  users.
• China PT has decided to participate the ITER TBM
  program. Three preliminary TBM design concepts
  from SWIP have been prepared.

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Tritium Breeding Module in ITER
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2. Design Concepts

• Design requirements
• - Prospect to be used in DEMO reactor
• - Shielding for V V.,TFC in ITER
• - Within technical limits, e.g.
  temperature, stress limits, etc.
• - Structure should be simple for easy
  fabrication.
• Proposed concepts
• A. Liquid breeder (static concept)
• A1 Liquid LiPb / Ferritic Stee (CHT-9)
  /He
• A2 Liquid lithium / Vanadium / He
• B. Solid breeder concept
• Li4SiO4 / SS / He

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Static Breeder TBM design

• Static liquid breeder concept is attractive
  for its structural simplicity. On the other hand,
  the issues inherent in liquid breeder self-cooled
  concept , such as, MHD pressure drop and
  corrosion, etc. might be avoided.
• Some design studies of static liquid breeder
  concepts in SWIP had been performed in the past
  decade (Supported by the 863 program).
• SWIP has built and operated a liquid metal
  experiment loop (LMEL) which is useful for the
  design and experiment of ITER TBM concepts.

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Fig.1 Schematic of the Helium-cooled static
liquid breeder TBM concept
Option 1 LiPb / Ferritic Steel (HT-9)/He
BOT concept Breeder Outside Tube
Plasma Side
Test Port Size
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Fig.2 TBM concept of Helium-cooled static liquid
breeder
Coolant Manifold
Liquid LiPb Breeder
Coolant (He) Tube
First Wall
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Main parameters of helium-cooled static liquid
breeder concept
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Fig. 3 Energy deposition along radial direction
(normalized to one fusion source neutron)
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Performance Analysis

• The thermal constraint for this blanket is that
  the temperature at interface of structure and
  LiPb should be lower than 450?C to avoid
  excessive corrosion.
• The local TBR is calculated by 1-D transport code
  to be 1.45 and the peak energy deposition is 966
  eV/cm3 per fusion neutron.
• The peak interface temperature is estimated to be
  about 440?C.

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Fig.4 Schematic of the Liquid lithium /
vanadium TBM concept
Option 2 Liquid lithium / Vanadium / He

• This concept have attractive advantages due to
  the low activation and its structure simplicity.
  Some limits for lithium set by ITER should be
  considered in design.
• To assure an adequate tritium breeding ratio,
  TBR, beryllium is adopted as neutron multiplier
  natural lithium is used as tritium breeder.

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Performance Analysis

• The 1-D neutronics calculation gives a local TBR
  of 1.39 and a peak energy deposition of 1172
  eV/cm3 per fusion neutron, which corresponds to a
  peak power density of 8.15 W/cm3 under a neutron
  wall loading of 0.78 MW/m2.
• A preliminary estimation gives a peak temperature
  at the interface of LLi and structural material
  of 480? C, which is allowable from the view-
  point of corrosion.
• For the safe operation of ITER, the quantity of
  liquid lithium is limited to lt 35 l to limit
  hydrogen production to 2.5 kg.
• As a result, the size of this TBM is chosen to be
  43x40x30 cm3.

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Possible and Favored Concept! (cooperation
with domestic institutes, CAEP)
Solid breeder TBM Concept

• He Cooled Solid Breeder with FS is main stream
  and has foundation of the world RD database. We
  will adopt SB/He/FM concept as own option of TBM
  module.
• China TBM Working Group plan to develop an
  independent HCSB sub-module under the framework
  of ITER TBM program in the near future. The
  relevant technology and experiment will be
  developed step by step.

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B. He Cooled Solid Breeder TBM design
Fig.5 Schematic of the Helium-cooled solid
breeder TBM design concept
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Fig.6 TBM design concept for Helium-Cooled Solid
Breeder
Coolant /He Manifold
Solid Breeder
Coolant Tube
First Wall
Li4SiO4
Pebble bed size d 0.5 - 1.0 mm
Ribbed Panel Structure
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Two Types of Coolant Manifolds
Coolant Out
Solid Breeder Zone
First Wall
First Wall
Coolant In
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Fig.7 Energy deposition along radial direction
for solid breeder blanket
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Main parameters of helium-cooled solid breeder
TBM concept
Design Constraints

• The temperature of solid breeder should be
  within the temperature window allowed (450-900
  ?C).
• To meet this requirement, a large number of
  cooling plates is needed due to the low thermal
  conductivity of the solid breeder.

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China Proposed Independent HCSB TBM module
He Cooled Solid Breeder
3. Allocation of TBM Test Ports
EU
Share with RF
JA
Fig.8 ITER test port 1 (for HCSB)

• This allocation scheme has been accepted by the
  TBSG-1
• (at TBWG-12 meeting, March 9-11, Naka Joint
  Work Site)

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Test port allocation in TBWG-10
- Three ports for three parties at TBWG-10 -
Three ports for six parties at present (TBWG-12)
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Test Port division for the HCSB at TBSG-12
EU
RF
KO US
CH
JA
Part 1
Part 2
TBD
in the TWCS vault
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4. Summary

• Three SWIP preliminary TBM concepts have been
  proposed. Merits of these concepts are owing to
  the simple structure and have a high TBR.
• SWIP plans to develop a TBM of its HCSB-favored
  TBM concept during the ITER testing phase. Detail
  of Design Description Document (DDD) will be
  finished within 1-2 years.
• This is a great challenge for us due to the TBM
  will be inserted into the test port on Day one of
  ITER operation (not in D -T phase).

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Thank You!
Information Center Building of SWIP
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Key Problem

• The relevant RD
• - Fabrication technique of the solid
  breeder
• - Tritium recovery, processing
• - Temperature control of tritium
  extraction system
• - Tritium permeation barrier , etc.
• Two options for TBM module in China
• Option 1 SB/He/FM concept (SHSB) (SWIP)
• Option 2 Liquid LiPb Blanket (CLLB)
  Concept (ASIPP)
• SWIPs TBM program will face to a great
  challenge
• - lack of the RD experience
• - limited time (the DDD document will
  be finished within 1-2 years)
• - support of personnel and cost

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Five TBM Working Sub-Groups

• Solid ceramic breeder/ He / FS (TBSG-1)
• Solid ceramic breeder/ water / FS (TBSG-2)
• Liquid lithium-lead / FS (TBSG-3)
• Liquid lithium / Vanadium (TBSG-4)
• Molten Salt (Flibe) / FS (TBSG-5)
• Cost Estimation
• Cost for a TBM module will be 50 million (US )