A SysML Model of the Tokamak Subsystems involved in a DEMO pulse

Similar documents
Observation of Cryogenic Hydrogen Pellet Ablation with a fast-frame camera system in the TJ-II stellarator

DEMO-EUROFusion Tokamak, Design of TF Coil Inter-layer Splice Joint

Evolving the JET Virtual Reality System for Delivering the JET EP2 Shutdown Remote Handling Task

Modelling ITER Asymmetric VDEs through asymmetries of toroidal eddy currents

Non-linear radio frequency wave-sheath interaction in magnetized plasma edge: the role of the fast wave

Design and R&D for an ECRH Power Supply and Power Modulation System on JET

Non-Axisymmetric Ideal Equilibrium and Stability of ITER Plasmas with Rotating RMPs

Disruption Classification at JET with Neural Techniques

Realization, Installation and Testing of the Multichannel Reflectometer s Transmission Lines at ICRF Antenna in Asdex Upgrade

Commissioning and first operation of the pulse-height analysis diagnostic on Wendelstein 7-X stellarator

3.4 Poloidal Field Power Supply Systems for the EAST Steady State Superconducting Tokamak

Effect of ICRF Mode Conversion at the Ion-Ion Hybrid Resonance on Plasma Confinement in JET

Foundations for Knowledge Management Practices for the Nuclear Fusion Sector

Real-time Systems in Tokamak Devices. A case study: the JET Tokamak May 25, 2010

A Pathway to DEMO - Activities for DEMO in Korea

A Design Study of Stable Coil Current Control Method for Back-to-Back Thyristor Converter in JT-60SA

The Installation, Testing and Performance on the JET Coils on the Enhanced Radial Field Amplifier (ERFA)

Design and Construction of the JET ITER-Like ICRF High Power Prototype Antenna

Implementing Agreement for Co operation in Development of the Stellarator Heliotron Concept (SH IA) Strategic Plan

Task on the evaluation of the plasma response to the ITER ELM stabilization coils in ITER H- mode operational scenarios. Technical Specifications

Gyung-Su Lee National Fusion R & D Center Korea Basic Science Institute

Enquiries about copyright and reproduction should in the first instance be addressed to the Culham Publications Officer, Culham Centre for Fusion

Improvements in the fast vertical control systems in KSTAR, EAST, NSTX and NSTX-U

Fault Analysis of ITER Coil Power Supply System

Real-Time Control of ELM and Sawtooth Frequencies: Similarities and Differences

GaAs Photo-Multiplier for LIDAR Thomson Scattering

Outline: The work leading to this presentation has been funded partially by Fusion for Energy under the contract F4E-OFC-280.

A roadmap to the realization of fusion energy

Contributions of Advanced Design Activities to Fusion Research

Neutron Measurements on JET using an NE213 Scintillator with Digital Pulse Shape Discrimination

Korean Fusion Energy Development Strategy*

GA A22776 THE DESIGN AND PERFORMANCE OF WAVEGUIDE TRANSMISSION LINE COMPONENTS FOR PLASMA ELECTRON CYCLOTRON HEATING (ECH) SYSTEMS

System Upgrades to the DIII-D Facility

2.3 PF System. WU Weiyue PF5 PF PF1

Mission and Goals 2017/18

1. Title of CRP: Elements of Power Plant Design for Inertial Fusion Energy

TOKAMAK T-15MD: experience of scientific and technical project realization in RUSSIA

A Modular Commercial Tokamak Reactor with Day Long Pulses

DEMO work in future. Association Euratom-Tekes. Leena Aho-Mantila VTT Technical Research Centre of Finland. Euratom-TEKES Annual Seminar 2013

Design of the COMPASS Upgrade Tokamak

The Holy Grail of Energy? A Content and Thematic Analysis of the Presentation of Nuclear Fusion on the Internet

Technical Readiness Level For Plasma Control

GA A25824 A NEW OVERCURRENT PROTECTION SYSTEM FOR THE DIII-D FIELD SHAPING COILS

GA A23281 EXTENDING DIII D NEUTRAL BEAM MODULATED OPERATIONS WITH A CAMAC BASED TOTAL ON TIME INTERLOCK

TCP on Solar Power and Chemical Energy Systems (SolarPACES TCP)

Modeling of Mixed-Phasing Antenna-Plasma Interactions Applied to JET A2 Antennas

Plasma Control at JET

A High Resolution IR/Visible Imaging System for the W7-X Limiter

Strategic Research Cluster on Electric Propulsion H2020 Space call text 2016 & related Guidelines document

Couplings used for torque transmission in propulsion or auxiliary plants

A REGULATED POWER SUPPLY FOR THE FILAMENTS OF A HIGH POWER GYROTRON

Abstract. PEGASUS Toroidal Experiment University of Wisconsin-Madison

GA A27238 MEASUREMENT OF DEUTERIUM ION TOROIDAL ROTATION AND COMPARISON TO NEOCLASSICAL THEORY IN THE DIII-D TOKAMAK

FAST RAMP-UP AND ADAPTIVE MANUFACTURING ENVIRONMENT

A POLICY in REGARDS to INTELLECTUAL PROPERTY. OCTOBER UNIVERSITY for MODERN SCIENCES and ARTS (MSA)

Mission and Goals 2018/19

TOROIDAL ALFVÉN EIGENMODES

Systematic cavity design approach for a multi-frequency gyrotron for DEMO and study of its RF behavior

P. Koert, P. MacGibbon, R. Vieira, D. Terry, R.Leccacorvi, J. Doody, W. Beck. October 2008

INITIAL RESULTS FROM THE MULTI-MEGAWATT 110 GHz ECH SYSTEM FOR THE DIII D TOKAMAK

Fact Sheet IP specificities in research for the benefit of SMEs

GA A25836 PRE-IONIZATION EXPERIMENTS IN THE DIII-D TOKAMAK USING X-MODE SECOND HARMONIC ELECTRON CYCLOTRON HEATING

Pedestal Turbulence Dynamics in ELMing and ELM-free H-mode Plasmas

Outline of optical design and viewing geometry for divertor Thomson scattering on MAST

COUNCIL OF THE EUROPEAN UNION. Brussels, 18 May /06 Interinstitutional File: 2005/0044 (CNS) RECH 130 ATO 48 COMPET 129

2. Composing and characteristics of EAST

UNIT-III LIFE-CYCLE PHASES

Real time control of the sawtooth period using EC launchers

Greenlining and Bluelining of Ergon Energy Substation Drawings

Status of Japanese DA

ATS seminar Riikka Virkkunen Head of Research Area Systems Engineering

What does this all mean?

GA A22963 RECENT DEVELOPMENTS ON THE HIGH POWER ECH INSTALLATION AT THE DIII D TOKAMAK

PLASMA STUDIES AT HIGH NORMALIZED CURRENT IN THE PEGASUS EXPERIMENT

Effects of outer top gas injection on ICRF coupling in ASDEX Upgrade: towards modelling of ITER gas injection

D1.10 SECOND ETHICAL REPORT

Testing of the Toroidal Field Model Coil (TFMC)

Experiments with real-time controlled ECW

THE USE OF A SAFETY CASE APPROACH TO SUPPORT DECISION MAKING IN DESIGN

Roadmap Panel. 11:00 13:00 Tuesday, 17 September Auditorium Palau de Congressos de Barcelona. Moderated by Mohamed Abdou

Technology readiness evaluations for fusion materials science & technology

Characterisation of local ICRF heat loads on the JET ILW

Expression Of Interest

ECRH Beam Optics Optimization for ITER Upper Port Launcher

Strategy for the engineering integration of the ESS accelerator

API COPM CPMA Chapter 20.X

Study of Plasma Equilibrium during the AC Current Reversal Phase on the STOR-M Tokamak

Observation of high-frequency secondary modes during strong tearing mode activity in FTU plasmas without fast ions

3.10 Lower Hybrid Current Drive (LHCD) System

The use of technical readiness levels in planning the fusion energy development

in the New Zealand Curriculum

The main FP7 instruments. Aurélien Saffroy. 6 Dec

Knowledge Capture, Cross Boundary Communication and Early Validation with Dynamic A3 Architectures

Long Pulse EBW Start-up Experiments in MAST

Realization of Fusion Energy: How? When?

INTERNATIONAL STANDARD

Computer-Based Project in VLSI Design Co 3/7

Faster, Hotter MHD-Driven Jets Using RF Pre-Ionization

GA A24030 ECE RADIOMETER UPGRADE ON THE DIII D TOKAMAK

POLICY SIMULATION AND E-GOVERNANCE

Transcription:

EUROFUSION WPPMI-CP(16) 15445 I Jenkins et al. A SysML Model of the Tokamak Subsystems involved in a DEMO pulse Preprint of Paper to be submitted for publication in Proceedings of 29th Symposium on Fusion Technology (SOFT 2016) This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission.

This document is intended for publication in the open literature. It is made available on the clear understanding that it may not be further circulated and extracts or references may not be published prior to publication of the original when applicable, or without the consent of the Publications Officer, EUROfusion Programme Management Unit, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK or e-mail Publications.Officer@euro-fusion.org Enquiries about Copyright and reproduction should be addressed to the Publications Officer, EUROfusion Programme Management Unit, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK or e-mail Publications.Officer@euro-fusion.org The contents of this preprint and all other EUROfusion Preprints, Reports and Conference Papers are available to view online free at http://www.euro-fusionscipub.org. This site has full search facilities and e-mail alert options. In the JET specific papers the diagrams contained within the PDFs on this site are hyperlinked

A SysML Model of the Tokamak Subsystems involved in a DEMO pulse. Ian Jenkinsa, Paul Cursona, Robert Feltona a Culham Centre for Fusion Energy, Culham Science Centre, Abingdon, Oxon, OX14 3DB, UK A model has been developed using the systems modelling language, SysML to provide a mechanism for analysing the inherent complexity of Tokamak subsystem modes of operation during specific Tokamak states on DEMO. By capturing the attributes and functions of the various subsystems for each substate during a DEMO pulse the model is able to illustrate, using a series of diagrams, how various subsystems are composed along with aspects of subsystem generalisation and specialisation. It can also provide details of tokamak behaviour during a pulse using a state machine. In future the model will be expanded to give details about the state transition criteria, an examination of additional (contingency) cases and will be expanded to contain additional subsystems. Keywords: System engineering, system modelling, SysML author s email: ian.jenkins@ukaea.uk

1. Introduction A project on the scale of DEMO requires a formal systems engineering approach. Mapping the interfaces, dependencies and relationships between subsystems permits an understanding of a conceptual design from a set of complementary and consistent perspectives. It also helps to prevent clashes and incompatibility between subsystems at a later stage of engineering design. The first stage of this work has focussed on the DEMO Plasma Operation State (POS), where the tokamak executes a pulse sequence (shown schematically in Fig. 1). The pulse sequence has been analysed as a series of substates from pre pulse through to post pulse dwell and for each of the substates within the POS, information gained from experience on JET has been used to create a matrix detailing which subsystems will be active. This involves attempting to define, characterise and, if possible, quantify the salient attributes and functions for each required subsystem. For instance, while the TF system will remain on and at constant current throughout a pulse sequence, the PF system will only commence operation in the pre pulse substate with the function (amongst possible others) of charging the solenoid. These functions will be associated with a matrix which will contain the attributes of the current waveforms in each of the poloidal shaping coils and the central solenoid. For each subsequent substate, the associated functions of the PF, such as ramping the solenoid current during the plasma initiation substate and shaping the plasma once established in subsequent substates, will each be associated with their own attribute matrices. This process has been repeated for several proposed sub systems on DEMO which have analogues on JET, and the resulting information has been incorporated into a model using the Object Management Group Systems Modelling Language, OMG SysML [1]. This forms part of a broader Based Systems Engineering (MBSE) activity within the DEMO WPPMI. plasma pulse. Parameters: Ip: Plasma Current; ΦOH: Ohmic Heating Flux; ne: Electron Density; fhe: Helium fraction; Paux: Power for auxiliary heating; Pfus: Fusion Power Times / Events: RC: Recharge Coil; RU: Ramp Up: BT: Burn Termination; RD: Ramp Down; PD: Pump Down; SOP: Start of Pulse; SOB: Start of Burn; EOB: End of Burn 2. The Tokamak Model 2.1 Definitions. The model is an abstraction, or logical construct, that allows modelling specific features of interest. Here, several diagrams serve to illustrate a number of different perspectives, or views. This section provides a snapshot in time of this model to facilitate understanding of the Tokamak subsystem modes and states from a number of different perspectives. It should be borne in mind that this is very much on ongoing investigation, and that the modelling approach offers a flexible foundation for further analysis in this field. The following definitions should be borne in mind (see also [2]): A Property is a specific feature of a system (or subsystem) that can take on different values and is represented by a noun. A Mode of Operation shows what a system (or subsystem) does and is represented by a verb. (Modes of Operation have associated goals and outcomes.) Parameters may be used to describe Properties that relate specifically to the Mode of Operation. A Function is linked to a Mode of Operation to describe associated behaviour, and must occur within one or more system (Tokamak) states, where associated parameter values are consumed or modified during operations. 2.2 Tokamak Composition. A Tokamak Composition Diagram (Fig. 2) is a structural diagram showing the Composition of the Tokamak in terms of composition (symbol ) and specialisation (symbol ). Note in particular that for example the Gas Injection and Pellet Injection subsystems are both of the general type Fuel Injection subsystem. This is a useful abstraction in modelling and exploited when describing subsystem behaviours and data (see also [3]). Fig. 1.Schematic showing sequence of events in a

Fig. 2. Tokamak Composition Diagram Fig. 3. Tokamak Subsystems and Behaviours 2.3 Tokamak Subsystems Methods and Data. A Tokamak Subsystems and Behaviours diagram (Fig. 3) is another structural diagram showing each of the Tokamak subsystems. Each subsystem has attributes (row beneath the title), and methods. Most methods will have associated parameters. Note this is a static model; the actual behaviour manifest in use of the methods executed with specific parameter values requires another perspective (not yet analysed). Also, note the use of the generalisation relationship for the Cyclotron subsystem, which defines the method L to H transition, inherited by Electron and Ion Cyclotron subsystems. 2.4 Tokamak State Machine. The Tokamak State Machine Diagram (Fig. 4) is a behaviour diagram showing the Tokamak states during a plasma pulse. The state transitions are only those applicable to a successful outcome, in that no disruptions, for example, have occurred. Note that, within each state, a do / <Function> is defined. These have not yet been further analysed, but are included here to illustrate that each state has associated with it a high level function, i.e. each state is active in some way. In future work, these high level functions shall be responsible for the overall behaviour during each state, and shall feature the low level subsystem methods (modes)

Fig. 4. Tokamak State Machine Diagram.

3. Summary and Future Work The Tokamak SysML model provides a mechanism for analysing the inherent complexity of Tokamak subsystem modes of operation during specific Tokamak states on DEMO. The model makes explicit the types of data, and the relationships between these types of data, also offering a mechanism for presenting particular views of interest, based on this underlying data. It captures information which can be scrutinised now for completeness and conflicts and will be a (the) reference for successive engineers and scientists over the next 20+ years. The work so far has created a partial model describing Tokamak composition, state machine (changes that may occur in logical time), subsystem modes and associated data. Going forward, a view should be developed for the dynamic aspects of the system, covering, where possible: Acknowledgments This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014 2018 under grant agreement No 633053 and from RCUK Energy Programme [grant number EP/I501045]. To obtain further information on the data and models underlying this paper please contact PublicationsManager@ccfe.ac.uk. The views and opinions expressed herein do not necessarily reflect those of the European Commission. References [1] http://www.omgsysml.org/ [2] The specification of specific run time values for the data associated with each mode. Exploring how, for a given Tokamak state, the modes of each of the subsystems collaborate, or run alongside each other. How the transitions occur between each of the Tokamak states. Although the scope of work so far has been limited to describing Tokamak composition, Modes of Operation, and state behaviour (for successful transitions) during the high level POS, future work for the POS should cover the specification of parameter values for each Mode of Operation, state transition criteria, and an examination of additional (contingency) cases. The model will also increase its breadth by extending to include other subsystems e.g. gas processing, balance of plant, breeder blanket etc. and will also be updated with experience from ITER. The application of SysML modelling to the Tokamak States and Modes analysis has proved be a very effective method for capturing and encoding the key concepts involved, and highlighting where further work needs to be done. [3] https://ww w.researc hgate.net/ publicatio n/2697109 22_On_a_ Useful_Ta xonomy_o f_phases_ Modes_an d_states_i n_system s_enginee ring https://ww w.researc hgate.net/ publicatio n/2788217 29_Propos al_for_a_ Standardiz ed_functi onal_arch itecture_f or_use_in _Plant_Sy stems_en gineering