Elements of Strategy on Modelling Activities in the area of Test Blanket Systems

Similar documents
Tritium Transport Modelling: first achievements on ITER Test Blanket Systems simulation and perspectives for DEMO Breeding Blanket

HCLL Test Blanket Module Test program in ITER

Tritium Technologies of ITER and DEMO breeding blankets

Role and Challenges of Fusion Nuclear Science and Technology (FNST) toward DEMO

Experimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related to Indian Test Blanket Module for ITER

Concept of Multi-function Fusion Reactor

Tritium Fuel Cycle Safety

Aiming at Fusion Power Tokamak

SOME CONSIDERATION IN THE TRITIUM CONTROL DESIGN OF THE SOLID BREEDER BLANKET CONCEPTS

Summary Tritium Day Workshop

Tritium Safety of Russian Test Blanket Module

Perspective on Fusion Energy

1 FT/P5-15. Assessment of the Shielding Efficiency of the HCLL Blanket for a DEMOtype Fusion Reactor

EU PPCS Models C & D Conceptual Design

Preliminary Safety Analysis of CH HCSB TBM

Neutronic Activation Analysis for ITER Fusion Reactor

Neutronics experiments for validation of activation and neutron transport data for fusion application at the DT neutron generator of TU Dresden

A SUPERCONDUCTING TOKAMAK FUSION TRANSMUTATION OF WASTE REACTOR

Neutronics analysis of inboard shielding capability for a DEMO fusion reactor

Design concept of near term DEMO reactor with high temperature blanket

Preliminary system modeling for the EUROfusion Water Cooled Lithium Lead blanket

Adaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source

Tritium Control and Safety

FLOW ANALYSIS IN THE HCLL-TBM ITER CHANNELS INCLUDING MHD AND HEAT TRANSFER

Fusion: The Ultimate Energy Source for the 21 st Century and Beyond

Neutronics experiments for validation of activation and neutron transport data for fusion application at the DT neutron generator of TU Dresden

Fusion Reactor Research Activities at SWIP (1)

Fusion Nuclear Science - Pathway Assessment

Activation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB

Study of Impacts on Tritium Breeding Ratio of a Fusion DEMO Reactor

Seminar Chengdu, China Southwestern Institute of Physics (SWIP)

The PPCS In-Vessel Component Concepts (focused on Breeding Blankets)

Plasma Wall Interactions in Tokamak

Aspects of Advanced Fuel FRC Fusion Reactors

Physics of fusion power. Lecture 14: Anomalous transport / ITER

Tritium Inventories and Tritium Safety Design Principles for the Fuel cycle of ITER

Fusion/transmutation reactor studies based on the spherical torus concept

Transmutation of Minor Actinides in a Spherical

Yuntao, SONG ( ) and Satoshi NISHIO ( Japan Atomic Energy Research Institute

Issues for Neutron Calculations for ITER Fusion Reactor

Fusion Development Facility (FDF) Mission and Concept

Toward the Realization of Fusion Energy

Design optimization of first wall and breeder unit module size for the Indian HCCB blanket module

The Development and Application of One Thermal Hydraulic Program Based on ANSYS for Design of Ceramic Breeder Blanket of CFETR

Safety considerations for Fusion Energy: From experimental facilities to Fusion Nuclear Science and beyond

Mission Elements of the FNSP and FNSF

FUSION NEUTRONICS EXPERIMENTS AT FNG: ACHIEVEMENTS IN THE PAST 10 YEARS AND FUTURE PERSPECTIVES

ENEA Experience in PbLi Technologies

Basics of breeding blanket technology

TECHNICAL NOTE related to the Market survey on Water Holding Tanks for the Water Detritiation System (WDS) Prepared by Reviewed by Approved by ---

In-Vessel Tritium Inventory in Fusion DEMO Plant at JAERI

THERMAL ANALYSIS OF A SOLID BREEDER TBM UNDER ITER OPERATIONAL CONDITIONS. A. Abou-Sena, A. Ying, M. Youssef, M. Abdou

Breeding Blanket Modules testing in ITER: An international program on the way to DEMO

Tritium Plant in ITER and F4E Contribution. G. Piazza ITER Department, Fusion for Energy

Technological and Engineering Challenges of Fusion

Neutron Testing: What are the Options for MFE?

10.1 Functions, Basic Configuration and System Boundaries

ITER DIAGNOSTIC PORT PLUG DESIGN. N H Balshaw, Y Krivchenkov, G Phillips, S Davis, R Pampin-Garcia

Electrical Resistivity Changes with Neutron Irradiation and Implications for W Stabilizing Shells

EUROFUSION WPBB-CP(16) F. Hernandez et al.

DEMO Concept Development and Assessment of Relevant Technologies. Physics and Engineering Studies of the Advanced Divertor for a Fusion Reactor

PREPARATION OF HEXCALIBER TESTS AND PRELIMINARY THERMO-MECHANICAL ANALYSES

Fusion Fuel Cycle. ing. Stefan Ionut SPIRIDON. Association Days, Institutefor Cryogenics and Isotopes Technologies Rm.

MELCOR model development for ARIES Safety Analysis

Unpressurized steam reactor. Controlled Fission Reactors. The Moderator. Global energy production 2000

Studies on bi-directional hydrogen isotopes permeation through the first wall of a magnetic fusion power reactor

Conceptual Design of Advanced Blanket Using Liquid Li-Pb

Thermal optimization of the Helium-Cooled Lithium Lead breeding zone layout design regarding TBR enhancement

I. Kodeli 1. INTRODUCTION

Which Superconducting Magnets for DEMO and Future Fusion Reactors?

for the French fusion programme

Fusion Nuclear Science and Technology Challenges and Required R&D

First Workshop on MFE Development Strategy in China January 5-6, 2012

GA A23168 TOKAMAK REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO

Nuclear Analysis of the HCLL Blanket Concept for the European DEMO Using the TRIPOLI-4 Monte Carlo Code

Overview of Pilot Plant Studies

Status of the Concept Design of CFETR Tokamak Machine

CFD simulation of the magnetohydrodynamic flow inside the WCLL breeding blanket module

Thermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules

Tritium processing system for the ITER Li/V Blanket Test Module

Progress and Status of ITER Solid Breeder Test Blanket Module in in China

Helium Catalyzed D-D Fusion in a Levitated Dipole

Studies of Next-Step Spherical Tokamaks Using High-Temperature Superconductors Jonathan Menard (PPPL)

Development of high intensity D T fusion neutron generator HINEG

Characterization of waste by R2S methodology: SEACAB system. Candan Töre 25/11/2017, RADKOR2017, ANKARA

Validation Of COMSOL Multiphysics For Magneto-hydro-dynamics (MHD) Flows In Fusion Applications

Fusion Neutronics, Nuclear Data, Design & Analyses - Overview of Recent FZK Activities -

The FTU facilities. Regarding the the control and data acquisition system, last year we carried out the following activities:

Tritium Inventories and Containment Philosophy for the Fuel cycle of ITER

Introduction to the Tritium Workshop Day and

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

Nuclear Fusion and ITER

Nuclear Energy in the Future. The ITER Project. Brad Nelson. Chief Engineer, US ITER. Presentation for NE-50 Symposium on the Future of Nuclear Energy

The Role of Multiple Effects/Interactions in a Science Based Blanket/FW R&D pathway

Present status of fusion neutronics activity and comments to neutron diagnostics for TBM

The Path to Fusion Energy creating a star on earth. S. Prager Princeton Plasma Physics Laboratory

MELCOR Analysis of Helium/Water/Air Ingress into ITER Cryostat and Vacuum Vessel

Neutronics calculations for the ITER Collective Thomson Scattering Diagnostics

5. Thick Liquid Blanket Concept 5.1 Introduction Ralph Moir 5.2 Idea Description and Rationale Alice Ying/ Ralph Moir/ Karani Gulec 5.2.

Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power

Transcription:

Elements of Strategy on Modelling Activities in the area of Test Blanket Systems I. Ricapito, TBM & MD Project Team, ITER Department, F4E, Barcelona (Spain) Barcelona, Sept 17 th 2014 Information Day FPA-611 TBS simulation tools 1

CONTENT Short recall on the main breeder blanket functions Intro to Test Blanket Systems and their mission Some elements of modelling strategy in the F4E TBM Project 2

Before starting. Presentation of the TBM-Project Team TBMs and Materials Development Project Team Leader Y. Poitevin Admin. Assistant: B. Gomez Integration Engineering COO: M. Ferrari Safety & Licensing analyses TPO: D. Panayotov TBM Sets COO: M. Zmitko* TPO: J. Vallory TPO: J. Galabert TPO: Y. Carin PPO: L. Romano + QAO: C. Annino LSO: I. Costin. Ancillary Systems, Instrument., modelling tools COO: I. Ricapito** TPO: P. Calderoni TPO: D. Ugolini * TRO for the delivery of HCPB-TBS to IO ** TRO for the delivery of HCLL-TBS to IO 3

Breeding Blanket: Functions Functions of the Breeding Blanket /1 Blanket Shield Vacuum vessel Radiation Plasma Neutrons First Wall T breeding zone Coolant Magnets TOKAMAK: toroidal-radial view HCLL-DEMO reactor (2007, CEA) THREE ESSENTIAL FUNCTIONS IMPLEMENTED BY THE BREEDING BLANKET A. Tritium breeding to achieve the tritium self-sufficiency B. Nuclear to thermal power conversion C. Neutron/γ-ray shielding 4

Breeding Blanket: Functions Functions of the Breeding Blanket /2 Function C: shielding Function A: tritium breeding Function B: power conversion Neutron flux radially has to decrease around 1 order of magnitude to protect VV and magnets In the plasma: T + D 4 He + n (17.6 MeV) Breeding blanket materials are heated-up because: a) Heat flux from plasma b) Nuclear heat generated by neutrons slowingdown and nuclear reactions with Li. The thermal power is then extracted by a suitable coolant and converted into electrical power through a conventional turbine-alternator group 5

Test Blanket Systems and their mission The TBM project provides test blankets to test and validate design concepts of tritium breeding blankets relevant to a power-producing reactor. HCLL-TBS HCPB-TBS ITER Project Requirements 6

Test Blanket Systems and their mission Fuelling Systems (FS) Tritium Extraction System (TES) Coolant Processing System (CPS) Cooling zone Breeder zone Storage & Delivery System (SDS) Isotope Separation System (ISS) Protium release Water Detritiation Systems (WDS) Tokamak Exhaust Processing (TEP) Detritiation Systems (DS) Accountancy System (AS) Pumping Systems (PS) Off-gas release Simplified block diagram with TES and CPS integrated in the main ITER fuel cycle 7

Test Blanket Systems and their mission The major overall testing objectives for each TBS shall be : validation of the structural integrity theoretical predictions under combined and relevant loads validation of the tritium breeding predictions validation of tritium recovery process efficiency validation of the T-inventories prediction in blanket materials validation of thermal predictions for strongly heterogeneous breeding blanket concepts with volumetric heat sources validation of blanket power removal predictions demonstration of the integral performance of the blankets systems Exploitation at maximum extent of the TBS experimental campaign in ITER requires a strong prediction capability developed in advance 8

SCOPE Developing Modelling Activities_1 Preliminarily foreseen modeling areas: Thermo-hydraulics, MHD, chemistry of Pb-16Li Tritium transport in solids, liquids, gases and interfaces Structural analysis of TBS components (including Pebble Beds thermo-mechanics) EM analysis of ferromagnetic structures Helium thermo-hydraulics Neutronics Depending on the stage of the project, modelling tools will be used in: - Correlative way for pre-validation against ad-hoc designed experimental tests - Predictive way to provide support to the TBS design /design of experiments in ITER - Correlative way during the ITER campaign, to extract relevant physical and engineering data - Predictive way to provide support to the design of DEMO BB 9

SCOPE Developing Modelling Activities_2 Final Objective is the production of an integrated model, to be exploited and validated during the different ITER operational phases Multi-physics Modelling Integration Test Program Instrumentation Development Modelling Integration will not be matter of this first phase of development nor of the FPA-611 10

Developing Modelling Activities_3 System Level (TBS) Hierarchy of the modelling layers will be compliant with the hierarchy of the elements in the systems to be modelled Sub-Systems Level (TBM, HCS, TES, PbLi-loop, T-Acc, etc.) Component Level (i.e. getter in TES, oxidizer in CPS, MSB in PSA configuration, etc.) Physics Modelling (i.e. transport through CB, permeation through steel pipe, etc) The System level tool consists of different Sub-system Tools Each Sub-system level tool consists of different Component Tools Each Component level tool contains one or more Physics Modelling sub-routines 11

Developing Modelling Activities_4 Preliminary Development Plan for Tritium Modelling Time Span Tritium Modeling Activities are currently the most advanced because of the implications for the conceptual design and preparation of the HCLL/HCPB- TBS Preliminary Safety Reports First Work Package: PHYSICS 1.1 Development of physics modelling subroutines 1.2 Implementation of physical parameter database through dedicated experiments on lab-scale level (separated effects) 1.3 Analysis of multiple effect impacting TT 2013-2017 Second Work Package: COMPONENTS and Sub-SYSTEMS 2.1 Development of component model tools 2.2 Development of sub-system model 2.3 Experiments on TBS main components (mainly multiple effects) 2015-2021 Third Work Package: INTEGRATION and Pre-VALIDATION 3.1 Integration of the component/sub-system tools into a unique system tool 3.2 Integrated experiments, also for multiple effects, before ITER for pre-validation 3.3 Integrated experiments during ITER H-H, H-He and D-D phases for pre-validation 2019-2023 Fourth Work Package: Validation against DT Experiments 12

Developing Modelling Activities_5 First TBS-related modelling activities have been carried out on EM (OPE-06-06-12 L1 TO12) and tritium modeling (GRT-254, GRT-542) have been carried out (successfully) in the last years at F4E n. 3 eight-hours shifts of back to back pulses, n. 3 values of Pb-16Li flow-rates Time evolution of the Maxwell, Lorentz and total forces for the HCLL TBM during MFD-II 13

Concluding Remarks I. Modelling strategy covering all duration of the TBM project is still preliminary and will be consolidated along the development f the Project II. Modelling integration is not in the scope of the first part of development III. Wide scope, covering (very) different areas, then requiring a large portfolio of technical skills IV. In the perimeter of Modelling there are also experimental activities for model/code validation V. Modelling Activities driven by TBS Project milestones, as they are in support of the TBS design and design of experiment 14