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.

Slides:



Advertisements
Similar presentations
1 Summary Slides on FNST Top-level Technical Issues and on FNSF objectives, requirements and R&D Presented at FNST Meeting, UCLA August 18-20, 2009 Mohamed.
Advertisements

First Wall Heat Loads Mike Ulrickson November 15, 2014.
PhD studies report: "FUSION energy: basic principles, equipment and materials" Birutė Bobrovaitė; Supervisor dr. Liudas Pranevičius.
Introduction Superconductors are a class of material that when cooled to low temperatures, conduct electricity with zero resistance. The main use of superconductors.
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.
Study on supporting structures of magnets and blankets for a heliotron-type fusion reactors Study on supporting structures of magnets and blankets for.
Introduction condition of a tokamak fusion power plant as an advanced technology in world energy scenario ○ R.Hiwatari, K.Tokimatsu, Y.Asaoka, K.Okano,
Critical Issue on Plasma Equilibrium for CS-less Tokamaks Kichiro Shinya Toshiba Corporation Japan-US Workshop on Fusion Power Plants and Related Advanced.
September 15-16, 2005/ARR 1 Status of ARIES-CS Power Core and Divertor Design and Structural Analysis A. René Raffray University of California, San Diego.
Physics of fusion power Lecture 14: Anomalous transport / ITER.
Summary and Closing Remarks Farrokh Najmabadi University of California San Diego Presentation to: ARIES Program Peer Review August 18, 2000 UC San Diego.
LPK Recent Progress in Configuration Development for Compact Stellarator Reactors L. P. Ku Princeton Plasma Physics Laboratory Aries E-Meeting,
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.
The shield block is a modular system made up of austenitic steel SS316 LN-IG whose main function is to provide thermal and nuclear shielding of outer components.
Development of the New ARIES Tokamak Systems Code Zoran Dragojlovic, Rene Raffray, Farrokh Najmabadi, Charles Kessel, Lester Waganer US-Japan Workshop.
US-Japan Workshop on Fusion Power Plants and Related Advanced Technologies High Temperature Plasma Center, the University of Tokyo Yuichi OGAWA, Takuya.
Physics Issues and Trade-offs in Magnetic Fusion Power Plants Farrokh Najmabadi University of California, San Diego, La Jolla, CA APS April 2002 Meeting.
Magnetic Fusion Power Plants Farrokh Najmabadi MFE-IFE Workshop Sept 14-16, 1998 Princeton Plasma Physics Laboratory.
Y. ASAOKA, R. HIWATARI and K
Introduction to BIM BIM Curriculum 01.
CASIPP Design of Cryogenic Distribution System for CFETR CS model coil Division of Cryogenic Engineering and Technical Institute of Plasma Physics Chinese.
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.
Offline Programming to Online using IPS
Basic Input Output System
Progress on the MuCool and MICE Coupling Coils * L. Wang a, X. K Liu a, F. Y. Xu a, A. B. Chen a, H. Pan a, H. Wu a, X. L. Guo a, S. X Zheng a, D. Summers.
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.
Kaschuck Yu.A., Krasilnikov A.V., Prosvirin D.V., Tsutskikh A.Yu. SRC RF TRINITI, Troitsk, Russia Status of the divertor neutron flux monitor design and.
TORE SUPRA Association EURATOM-CEA 2 nd GOTA-PPE meeting Julien WAGREZ 1 06 December 2009 EFDA ITER - Goal Oriented Training Program Port Plug Engineering.
ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.
Chapter 9 CAD & Parameters
HT-7 ASIPP Density Modulation Experiment within Lithium coating on HT-7 Tokamak Wei Liao,Yinxian Jie, Xiang Gao and the HT-7 team Institute of Plasma Physics,
Page 1 of 11 An approach for the analysis of R&D needs and facilities for fusion energy ARIES “Next Step” Planning Meeting 3 April 2007 M. S. Tillack ?
ITER Control System Technology Study Klemen Žagar
ARIES Project Meeting, L. M. Waganer, Dec 2007 Page 1 Restructuring System Cost Accounts and Algorithms L. Waganer December 2007 ARIES Project.
Magnet Spacers Design Automation Roxie2Catia Catia Forum – Sept. 29th 1.
Overview of the KSTAR commissioning M. Kwon 3 June, 2008.
EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT 16th TOFE Madison, Sept , EUROPEAN TECHNOLOGICAL EFFORT IN PREPARATION OF ITER CONSTRUCTION ROBERTO.
Divertor Design Considerations for CFETR
OPERATIONAL SCENARIO of KTM Dokuka V.N., Khayrutdinov R.R. TRINITI, Russia O u t l i n e Goal of the work The DINA code capabilities Formulation of the.
RF simulation at ASIPP Bojiang DING Institute of Plasma Physics, Chinese Academy of Sciences Workshop on ITER Simulation, Beijing, May 15-19, 2006 ASIPP.
Programmatic issues to be studied in advance for the DEMO planning Date: February 2013 Place:Uji-campus, Kyoto Univ. Shinzaburo MATSUDA Kyoto Univ.
OPERATIONAL SCENARIO of KTM Dokuka V.N., Khayrutdinov R.R. TRINITI, Russia O u t l i n e Goal of the work The DINA code capabilities Formulation of the.
Magnet for ARIES-CS Magnet protection Cooling of magnet structure L. Bromberg J.H. Schultz MIT Plasma Science and Fusion Center ARIES meeting UCSD January.
ITER In-Vessel Coils (IVC) Interim Design Review Thermal Structural FEA of Feeders A Brooks July 27, 2010 July 26-28, 20101ITER_D_353BL2.
Task 6: Short Period Nb 3 Sn Superconducting Helical Undulator Jim Clarke/George Ellwood 28/11/2012.
CASE (Computer-Aided Software Engineering) Tools Software that is used to support software process activities. Provides software process support by:- –
Work with TSC Yong Guo. Introduction Non-inductive current for NSTX TSC model for EAST Simulation for EAST experiment Voltage second consumption for different.
US-Japan Workshop on Fusion Power Plants and Related Advanced Technologies February 23-24, 2010 at USCD in USA Platform on integrated design of fusion.
FIRE Engineering John A. Schmidt NSO PAC Meeting February 27, 2003.
ZHENG Guo-yao, FENG Kai-ming, SHENG Guang-zhao 1) Southwestern Institute of Physics, Chengdu Simulation of plasma parameters for HCSB-DEMO by 1.5D plasma.
1 ASIPP Sawtooth Stabilization by Barely Trapped Energetic Electrons Produced by ECRH Zhou Deng, Wang Shaojie, Zhang Cheng Institute of Plasma Physics,
ITER Liquid Helium Plants Status and Test Protocol ICEC June 29th, 2015 / Grenoble / FranceY. FABRE.
MICE CC Magnet Cryostat Design Overview Derun Li Center for Beam Physics Lawrence Berkeley National Laboratory MICE CC Cryostat Design Review LBNL, February.
HL-LHC Meeting, November 2013D2 Status and Plans – G. Sabbi 1 D2 Conceptual Design Status and Next Steps G. Sabbi, X. Wang High Luminosity LHC Annual Meeting.
Magnetics Program Highlights VLT Conference Call September 13, 2000 presented by J.V. Minervini MIT Plasma Science and Fusion Center.
Tatiana Kozlova, Novosibirsk State University Supervisor: Darryl Orris, TD/Test & Instrumentation Department AC loss measurements of superconducting quadrupole.
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
CHATS-AS 2011clam1 Integrated analysis of quench propagation in a system of magnetically coupled solenoids CHATS-AS 2011 Claudio Marinucci, Luca Bottura,
Cryogenic Heat loads Analysis from SST-1 Plasma Experiments N. Bairagi, V. L. Tanna and S. Pradhan SST-1 Mission Institute for Plasma Research, Bhat, Ganhinagar.
Appendix A 12.0 Workbench Environment
US Participation in the
Study on Plasma Startup Scenario of Helical DEMO reactor FFHR-d1
Construction and Status of Versatile Experiment Spherical Torus at SNU
Produktentwicklung und Maschinenelemente
Preparation of activation experiments for ITER material characterization and data validation in the Deuterium–Tritium JET campaign T. Vasilopoulou &
The European Power Plant Conceptual Study Overview
Integrated Modeling Approach and Plans
Analysis of Technical and Programmatic Tradeoffs with Systems Code
Stellarator Program Update: Status of NCSX & QPS
Conceptual design of the Cryogenic System of Comprehensive Research Facility for Key Fusion Reactor Core Systems Liangbing Hu Sep.4.
Presentation transcript:

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 in Uji, JAPAN Institute of Plasma Physics Chinese Academy of Sciences (ASIPP) University of Science and technology of China (USTC)

ASIPP Contents Introduction – Need of a system code – Highlights of a system code Configuration – Control module – Physical module – Engineering module – Standard and material database – Integration platform Example: TF and VV workflow – TF coil engineering module GUI demo Summary

ASIPP Introduction CFETR (China Fusion Engineering Test Reactor) aims at the fusion power plant, which requires long duty time and self- sufficient fuel supply, many groups join this project and cooperation. To increase the design efficiency among different design groups and fit the requirement of commercial operation of fusion energy, the design process should be integrated and standardized as much as possible. A system code could greatly realize the functions, it reflects the experience deposition of the fusion device from experimental to commercial.

ASIPP Need of a system code Data communications between different groups cost time Each group has their own understanding on the information Different strategies may be made according to the members’ experience Accumulated margin in each step may make the design difficult to converge Due to the lack of a fixed plan, schedule can not be ensured

ASIPP Highlights of a system code Automatic data transfer between different modules in standard formats Independent design modules with good flexibility of software choice No need for specific software training Inheritance of mature design experience, automatic and manual judgments and iteration Complete material and standard reference Easy and clear control panel and workflow

ASIPP Configuration The system code consists of 5 main modules – Control module (interface, judgment and iteration) – Physical module – Engineering module – Standard database – Material database The software tools run on the code include CAD, physical codes (DINA, EFIT, B2…) and engineering tools (ANSYS, FLUENT, ADAMS…), user-defined tools are also valid.

ASIPP Configuration of the code

ASIPP Control module This is the key module of the system code, it covers the design workflow, transfers standardized data, makes choice and judgment and control optimization iteration. Only this module has human-machine interface to the user, who is not required to be professional with the calculation software, then his attention could be focused on the key issues like defining design parameters and making decision.

ASIPP Physical module This module defines the reactor’s physical design, including these sub-modules – Plasma transport calculation; – MHD equilibrium calculation; – MHD stability calculation; – Heating power calculation; – Neutron distribution calculation; – System economical effect estimation. These modules do not only setup and optimize the reactor’s concept, but also send data to the engineering module as load specification.

ASIPP Engineering module This module turns a concept reactor to a reality one, the sub-modules include – Magnet design (TF, PF, CS) – Blanket and divertor design – Vacuum vessel design – Cryostat/thermal shield design – Remote handling design – Cost estimation

ASIPP Standard and material database A series of standards must be setup for the reactor to ensure the design quality; the standard module includes both general industry standards and fusion specific ones, user-defined rules can also be added for special problems. All modules should share standard material properties and R&D results, the material database allows the user to select in a dropdown list, meanwhile user-defined property is supported for optimization.

ASIPP Integration platform The system code is not only a software, but also a platform, the physical and engineering module call many other tools to do analysis, and these tools can be adjusted or replaced, with fixed I/O format of data/conclusion. This character rises the flexibility, allows the user to modify the system code with kinds of resources, for example, EFIT calculates coil current, manual code sets up skeleton, CATIA generates the model and ANSYS performs mechanical analysis.

ASIPP Example: TF coil TF coil design module workflow Material limit Mechanical standard Physical check Material property

ASIPP Example: VV VV design module workflow: Material propertyHeat load to VVTS Mechanical standard

ASIPP Menu Magnet design Conductor design Structure design Physical input: Major radius=? m Minor radius=? m Toroidal field= ? T Engineering input: Blanket envelop=? m Vacuum vessel thickness=? m VVTS thickness=? m Distance between components= ? M Number of coils=? DO Superconducting Resistive Working condition input: Temperature=? K Envelop from last step: Number of turn=? Outer diameter=? m Current per turn=? kA Peak magnetic field=? T Choose material: NbTi, Nb 3 Sn… Assumed pulsed thermal load=? J Conductor parameters: Number of SC wire; Number of Cu wire; Quench temperature margin Geometry input: Supporting structure concept design Load from previous step: EM loads in normal operation, fast charge… Choose case material: SS316L, Inconel alloy… Choose design criteria: ASME, RCC… Structural results Judgment

ASIPP Summary A system code could increase the design efficiency and ensure the quality, meanwhile make the progress fit the schedule. The control module summarizes existing experience and guides the design process. The calculation tools in the physical and engineering modules are free to adjust or replaced. Common standard and material database unites baseline information and saves time for checking. The system code is easy to use and update, the user can focus on the critical issues.

ASIPP Thank you for your attention!