Presentation is loading. Please wait.

Presentation is loading. Please wait.

EU DEMO Design Point Studies

Published byReynard Holt Modified over 6 years ago

Similar presentations

Presentation on theme: "EU DEMO Design Point Studies"— Presentation transcript:

1 EU DEMO Design Point Studies
R. Kemp1, D. J. Ward1, G. Federici2, R. Wenninger2,3 and J. Morris1 1CCFE, Culham Science Centre, Oxfordshire OX14 3DB, United Kingdom 2EFDA PPPT, Boltzmannstr.2, Garching (Germany) 3IPP, Boltzmannstr.2, Garching (Germany)

2 EU DEMO Design Point Studies
Conceptual power plant design Systems codes What is DEMO? Design point development Design choices Pulsed vs steady-state Aspect ratio Uncertainties Further steps 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

3 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg
Systems codes Used to develop many conceptual designs with a range of materials and technology assumptions Every major plant system is modelled: Site and buildings Heat and power systems Magnets (TF and PF) Shield and vessel Blanket Divertor Plasma Fusion power Confinement Pressure and density limit Radiation Bootstrap current Etc. etc. Used to determine power plant costs and ultimately cost of electricity. Used for conceptual design and economic studies. EU systems studies use PROCESS, based at CCFE1. 1Kovari et al, PROCESS: a systems code for fusion power plants – part 1: physics, accepted to FED 2014 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

4 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg
Systems codes Fast calculations 0D models Simplified generomak physics for many systems simultaneously Use guidelines, correlations Gives overall operational design point – the major plant parameters 1D/2D models Equilibrium, current drive Assume profiles, boundaries Calibrate design point Detailed models: 1D/2D/3D, engineering analysis E.g. MHD, SoL physics, kinetic studies Calculate transport (core and edge), evolve profiles self-consistently Confirm and refine design point Slow complex calculations 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

5 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg
What is DEMO? Ultimate goal of fusion research – to supply electricity Economically Sustainably Safely At some point, we must demonstrate that fusion is a credible energy source. This is what DEMO is intended to do. Targets: Production of significant electrical output for significant time Tritium self-sufficiency Operation of all supporting/enabling technologies for commercial fusion power, bearing in mind: safety, reliability, availability, maintainability, inspectability Does not have to be technologically or physically optimised: e.g. target availability of 30%, not cheapest electricity Batistoni et al, Report of the ad hoc group on DEMO activities, CCE-FU 49/6.7, 2010 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

6 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg
EU Roadmap for DEMO Currently in conceptual design phase Very aggressive timeline Based on ITER Physics Basis1 1 See Wenninger et al, Advances in the Physics Basis for the European DEMO Design, PPC/P4-19 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

7 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg
What is DEMO? Federici et al, Overview of EU DEMO design and R&D activities, FED 89, 2014 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

8 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg
What is DEMO? EU view: ITER should demonstrate Robust burning plasma physics regimes Conventional divertor solution Validation of breeding blankets “Early DEMO” with well-established technology and regimes of operation (i.e. inductive) Modest but equal extrapolation in all areas (i.e. no magic solutions to technical problems) Based on current materials, technology, and physics knowledge 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

9 Heating and current drive
DEMO targets / limits Values are inputs to systems codes: either targets or limits (except recirculating power) Divertor power limit achieved through impurity doping and high radiation fraction (other solutions may be available) Value DEMO1 Notes Physics bN limit 3.0 Total bN, performance usually limited by H-factor instead H98-factor limit 1.1 Radiation-corrected (uncorrected ‘experimental’ factor is ~0.1 lower) q0 / q95 1.0 / 3.0 <nline>/nG 1.2 Assuming nG is a pedestal limit; tGLF predictive transport simulations indicate density peaking Operation Pulsed / 2 hr Heating and current drive Power (MW) 50 DEMO1 power principally for burn control; extra probably required to reach burn Ebeam (keV) 1000 Higher energy gives higher gCD hWP 0.4 Wallplug efficiency, hWP = Pinj/Pelectrical Divertor Pdiv/R0 (MW m-1) 17.0 DEMO1 based on ITER values Balance of plant Precirc (MW) 300 Principally current drive and coolant pumping hth 37% ~150MW coolant pumping power gives overall plant efficiency of ~24% Pe,net (MW) 500 Ultimate electrical output target 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

10 Design point development
* * Detailed modelling includes physics and engineering Giruzzi et al, Modelling of pulsed and steady-state DEMO scenarios, TH/P1-14 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

11 Design choices – pulsed vs steady-state
Increasing pulse length requires significant current drive power Increasing recirculating power reduces net electrical power or requires higher fusion power Increased injected power and fusion power means higher power density and greater loads on divertor Pulsed is “easy option” Plenty of data, but difficult to control current profile Cyclic stresses on components Energy storage required? Steady-state preferred for power plant but requires high fBS scenarios, efficient and reliable CD systems… “Early DEMO” is pulsed, but EU also exploring steady-state machine 0 MW 100 MW 150 MW 175 MW 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

12 Design choices – aspect ratio
TF coils A = 2.6 A = 3.1 A = 3.6 Scan of varying aspect ratios with scenario and engineering analysis (Minimised major radius) Transport modelling, access requirements, engineering feasibility Cost estimates: lower A has lower field – cheaper magnets? Trade-offs / limitations at each design point E.g. Low aspect ratio size set by pulse length; large aspect ratio size by confinement 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

13 Design choices – aspect ratio
Magnets are significant fraction of cost (~30%) Reducing magnetic field can reduce costs But other considerations including cost of larger VV/shield/blankets, increased RH costs for larger components… 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

14 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg
Uncertainties Major uncertainties in extrapolation of physics Particularly treatment of radiation1 Choice of scenario uncertain (diagnostics and control, H&CD, stability of high radiation fraction…) Effects of TF ripple on plasma/fast particle confinement force larger coils – effects on access/RH/etc. What is appropriate value? Divertor protection 1Ward et al, International Systems Code Benchmark for DEMO, 2nd IAEA DEMO Programme Workshop, Vienna, Dec. 2013 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

15 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg
Further steps Incorporation of uncertainties into PROCESS systems code to assess robustness of operating point Development of DEMO Physics Basis and DEMO operating scenario to ensure best chance of success Further development of DEMO workflow to pass plant operating points through successively more detailed analysis in integrated way. 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

16 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg
Summary EU DEMO operating points based on “near-term” physics and technology Results in a ‘conservative’, low power-density design DEMO not intended to be a commercial power plant but proof of concept Established workflow for evaluation of operating points from many angles and assessing conflicts/issues not captured by systems code Evaluation of areas where we need to know more; where uncertainties have greatest impact on performance Comprehensive scoping of operating space taking place to establish DEMO operating point “most likely to succeed” 25th IAEA Fusion Energy Conference / October 2014 / St Petersberg

Download ppt "EU DEMO Design Point Studies"

Similar presentations

ASIPP Zhongwei Wang for CFETR Design Team Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies February 26-28, 2013 at Kyoto University.

ASIPP Zhongwei Wang for CFETR Design Team Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies February 26-28, 2013 at Kyoto University.
Conceptual design of a demonstration reactor for electric power generation Y. Asaoka 1), R. Hiwatari 1), K. Okano 1), Y. Ogawa 2), H. Ise 3), Y. Nomoto.

Conceptual design of a demonstration reactor for electric power generation Y. Asaoka 1), R. Hiwatari 1), K. Okano 1), Y. Ogawa 2), H. Ise 3), Y. Nomoto.
Introduction condition of a tokamak fusion power plant as an advanced technology in world energy scenario ○ R.Hiwatari, K.Tokimatsu, Y.Asaoka, K.Okano,

Introduction condition of a tokamak fusion power plant as an advanced technology in world energy scenario ○ R.Hiwatari, K.Tokimatsu, Y.Asaoka, K.Okano,
June 14-15, 2007/ARR 1 Trade-Off Studies and Engineering Input to System Code Presented by A. René Raffray University of California, San Diego With contribution.

June 14-15, 2007/ARR 1 Trade-Off Studies and Engineering Input to System Code Presented by A. René Raffray University of California, San Diego With contribution.
2010 US-Japan Workshop on Fusion Power Plants and Related Advanced Technologies at UCSD CA, US, Feb.23-24, 2010 1 Commissioning scenario including divertor.

2010 US-Japan Workshop on Fusion Power Plants and Related Advanced Technologies at UCSD CA, US, Feb.23-24, Commissioning scenario including divertor.
Contributions of Burning Plasma Physics Experiment to Fusion Energy Goals Farrokh Najmabadi Dept. of Electrical & Computer Eng. And Center for Energy Research.

Contributions of Burning Plasma Physics Experiment to Fusion Energy Goals Farrokh Najmabadi Dept. of Electrical & Computer Eng. And Center for Energy Research.
Page 1 of 14 Reflections on the energy mission and goals of a fusion test reactor ARIES Design Brainstorming Workshop 24-25 April 2005 M. S. Tillack.

Page 1 of 14 Reflections on the energy mission and goals of a fusion test reactor ARIES Design Brainstorming Workshop April 2005 M. S. Tillack.
Burning Plasma Gap Between ITER and DEMO Dale Meade Fusion Innovation Research and Energy US-Japan Workshop Fusion Power Plants and Related Advanced Technologies.

Burning Plasma Gap Between ITER and DEMO Dale Meade Fusion Innovation Research and Energy US-Japan Workshop Fusion Power Plants and Related Advanced Technologies.
Proposals for Next Year’s MFE Activities C. Kessel, PPPL ARIES Project Meeting, Sept. 24, 2000.

Proposals for Next Year’s MFE Activities C. Kessel, PPPL ARIES Project Meeting, Sept. 24, 2000.
Characteristics of Commercial Fusion Power Plants Results from ARIES-AT Study Farrokh Najmabadi Fusion Power Associates Annual Meeting & Symposium July.

Characteristics of Commercial Fusion Power Plants Results from ARIES-AT Study Farrokh Najmabadi Fusion Power Associates Annual Meeting & Symposium July.
Optimization of a Steady-State Tokamak-Based Power Plant Farrokh Najmabadi University of California, San Diego, La Jolla, CA IEA Workshop 59 “Shape and.

Optimization of a Steady-State Tokamak-Based Power Plant Farrokh Najmabadi University of California, San Diego, La Jolla, CA IEA Workshop 59 “Shape and.
US-Japan Workshop on Fusion Power Plants and Related Advanced Technologies High Temperature Plasma Center, the University of Tokyo Yuichi OGAWA, Takuya.

US-Japan Workshop on Fusion Power Plants and Related Advanced Technologies High Temperature Plasma Center, the University of Tokyo Yuichi OGAWA, Takuya.
IEA Workshop, San Diego October 2003 Summary of the European SERF-3 Programme David Ward, Ian Cook Culham Science Centre on behalf of GianCarlo Tosato.

IEA Workshop, San Diego October 2003 Summary of the European SERF-3 Programme David Ward, Ian Cook Culham Science Centre on behalf of GianCarlo Tosato.
DEMO Parameters – Preliminary Considerations David Ward Culham Science Centre This work was jointly funded by the EPSRC and by EURATOM.

DEMO Parameters – Preliminary Considerations David Ward Culham Science Centre This work was jointly funded by the EPSRC and by EURATOM.
Physics Issues and Trade-offs in Magnetic Fusion Power Plants Farrokh Najmabadi University of California, San Diego, La Jolla, CA APS April 2002 Meeting.

Physics Issues and Trade-offs in Magnetic Fusion Power Plants Farrokh Najmabadi University of California, San Diego, La Jolla, CA APS April 2002 Meeting.
Highlights of ARIES-AT Study Farrokh Najmabadi For the ARIES Team VLT Conference call July 12, 2000 ARIES Web Site:

Highlights of ARIES-AT Study Farrokh Najmabadi For the ARIES Team VLT Conference call July 12, 2000 ARIES Web Site:
Role of ITER in Fusion Development Farrokh Najmabadi University of California, San Diego, La Jolla, CA FPA Annual Meeting September 27-28, 2006 Washington,

Role of ITER in Fusion Development Farrokh Najmabadi University of California, San Diego, La Jolla, CA FPA Annual Meeting September 27-28, 2006 Washington,
21st Fusion Energy Conference, Chengdu, 16-21 October 2006 1 Critical Physics Issues for Tokamak Power Plants D J Campbell 1, F De Marco 2, G Giruzzi 3,

21st Fusion Energy Conference, Chengdu, October Critical Physics Issues for Tokamak Power Plants D J Campbell 1, F De Marco 2, G Giruzzi 3,
Power Extraction Research Using a Full Fusion Nuclear Environment G. L. Yoder, Jr. Y. K. M. Peng Oak Ridge National Laboratory Oak Ridge, TN Presentation.

Power Extraction Research Using a Full Fusion Nuclear Environment G. L. Yoder, Jr. Y. K. M. Peng Oak Ridge National Laboratory Oak Ridge, TN Presentation.
Y. Sakamoto JAEA Japan-US Workshop on Fusion Power Plants and Related Technologies with participations from China and Korea February 26-28, 2013 at Kyoto.

Y. Sakamoto JAEA Japan-US Workshop on Fusion Power Plants and Related Technologies with participations from China and Korea February 26-28, 2013 at Kyoto.

Similar presentations

Ads by Google