1 / 20

System Engineering to Design a Cooling Water System for a Fusion Reactor

System Engineering to Design a Cooling Water System for a Fusion Reactor. Seokho H. Kim Jan Berry Juan Ferrada Kirby Wilcher Karen McElhaney US-ITER, Oak Ridge National Laboratory Presented at 2008 AIChE Annual Conference, Philadelphia, PA Presented by OAK RIDGE NATIONAL LABORATORY

hamlin
Download Presentation

System Engineering to Design a Cooling Water System for a Fusion Reactor

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript

  1. System Engineering to Design a Cooling Water System for a Fusion Reactor Seokho H. Kim Jan Berry Juan Ferrada Kirby Wilcher Karen McElhaney US-ITER, Oak Ridge National Laboratory Presented at 2008 AIChE Annual Conference, Philadelphia, PA Presented by OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831-6283 managed by UT-BATTELLE, LLC for the U.S. DEPARTMENT OF ENERGY under contract DE-AC05-00OR22725

  2. Overview • ITER is an international effort to construct and operate a burning plasma device that can generate up to 500 MW of fusion power. • Based on the Tokamak design concept • Burns deuterium-tritium mixture • ITER configuration • ITER TCWS has 7 cooling loops • First Wall/Blanket (FW/BLK) => 3 loops • Divertor/Limiter (DIV/LIM) => 1 loop • Vacuum Vessel (VV) => 2 loops • Neutral Beam Injectors (NBI) => 1 loop • Systems engineering for TCWS designConceptual design => Preliminary design => Final design

  3. ITER Core Central Solenoid Nb3Sn, 6 modules Cryostat 24 m high x 28 m dia. Toroidal Field Coil Nb3Sn, 18, wedged Vacuum Vessel 9 sectors Blanket 440 modules Poloidal Field Coil Nb-Ti, 6 Port Plug heating/current drive, test blankets limiters/RH diagnostics Torus Cryopumps, 8 Divertor 54 cassettes Major plasma radius 6.2 m Plasma Volume: 840 m3 Plasma Current: 15 MA Typical Density: 1020 m-3 Typical Temperature: 20 keV Fusion Power: 500 MW Machine mass: 23350 t (cryostat + VV + magnets) - shielding, divertor and manifolds: 7945 t + 1060 port plugs - magnet systems: 10150 t; cryostat:  820 t

  4. ITER Cooling Water System (CWS) • Functional requirements: • Remove heat from in-vessel components, vessel, heating systems and diagnostics • Maintain coolant temperatures, pressures, and flow rates to limit component temperatures and retain thermal margins • Remove decay heat during shutdown periods • Provide baking for in-vessel components • Maintain required water chemistry conditions • Allow draining, refilling and drying for maintenance • Confine radioactive inventories • Remove heat from plant auxiliary systemsReject all the above heat to the environment • CWS consists of: • TCWS, CCWS, CHWS, HRS

  5. Physical TCWS Scope: Well DefinedInterface with India: Well Coordinated US Scope IN Scope

  6. Systems Engineering for TCWS Design • Conceptual design • System requirements are defined • Design basis is developed (the system requirements have to be met) • An optimized & cost effective design concept has to be ensured • Preliminary design • The requirements for a configuration item including system interfaces are properly defined and documented • Engineering analyses and R&D are carried out to ensure the design concept meeting the requirements (i.e., structure, seismic, thermo-hydraulic, etc.) • Engineering specialty studies are completed (i.e., RAMI, value engineering, constructability assessment, ES&H) • A firm basis is finalized to proceed with detailed design • Detail (final) design • The design documentation to support procurement is developed. • Procedure / drawings for fabrication/assembly/installation/testing & inspection is developed and documented

  7. Conceptual Design will Develop Design Basis / Concept Existing design does not meet the requirement for availability and reliability, and needs to be revised and optimized with newly available information/knowledge on client systems Revised Conceptual Design will produce: SRD Process Flow Diagram (PFD) Limited T-H models Limited system interfaces Conceptual Design Description Document (CDDD) PCR or DCR based on RAMI / value engineering

  8. SRD of TCWS will Include: Functional description, basic configuration & system boundaries Design requirements Structural/mechanical/seismic/thermo-hydraulic/ chemical/material/etc. Safety requirements Safety criteria, limits, monitoring, etc. Operation and maintenance requirements including RAMI Quality requirements Codes & Standards

  9. Steady-State Thermo-Hydraulic Model is Developed • SS design parameters / operational performance are determined • 4 PHTS => Steady State / Transient Models • CVCS => Steady State Model • Drain & Drying (D&D) => Steady State / Transient Model • Transient models will be developed during the preliminary design phase.

  10. DIV/LIM PHTS with ND550 Main Pipe

  11. All the Interfaces are Identified 693 3360.8 • Limited-ICD • Main information includes functional & physical interfaces • All the interfaces will be marked in PFDs • Client system interfaces are identified

  12. Process Flow Diagram (PFD) is Developed CVCS Nitrogen CWS 11 2 4 13 12 CCWS 3 FW/BLK Modules FW/BLK Modules 10 5 6 8 7 9 1 CVCS Upper Port Cooling Upper Port Cooling 14 Equatorial Port Cooling Equatorial Port Cooling Helium Supply Draining & Refilling Electric Interface Electric Interface N-VDS CCWS-1 N-VDS N-VDS CCWS-1 N-VDS CVCS CVCS Drying Drain Drain Drain Drain Process Flow Diagram of FW/BLK PHTS (page 1) Availability Notice This document was created under the ITER International Partnership. While this document was developed for the purpose of the ITER project, it may be shared with interested parties. There are no specified limitations on the distribution of this document. 

  13. Process Flow Diagram of FW/BLK PHTS (page 2) Availability Notice This document was created under the ITER International Partnership. While this document was developed for the purpose of the ITER project, it may be shared with interested parties. There are no specified limitations on the distribution of this document. 

  14. Conceptual Design Description Document (CDDD) is Being Prepared • CDDD • Description of TCWS subsystems (FW/BLK, VV, NBI & DIV/LIM PHTSs, D&D, CVCS) and their design basis • Process control scheme (T, P, m, PRZ water level) • Safety control (parameters to shut down plasma, water radiation monitoring, etc.) • Limited RAMI (modularity / flexibility, to determine # of Hx / pump combination) • Operational mode and analysis (to be continued during the Preliminary design phase) • PCR or DCR based on RAMI, value engineering, etc.

  15. Conceptual Design Process will be Completed Without Transient / Operational Analysis that is Planned to be Performed During the Preliminary Design Phase T-H Functional Requirements (SRD) Functional Interfaces (ICD) Limited RAMI Operational Mode Analysis Steady State TH Model FW/BLK, VV, DIV/LIM, NBI, CVCS, D&D Process Control Analysis Transient TH Model FW/BLK, VV, DIV/LIM, NBI, D&D CDDD FW/BLK, VV, DIV/LIM, NBI, CVCS, D&D, Safety / Process Control, Limiter RAMI, etc. Client System Geometry Model PFD September 2008 P&ID I&C

  16. Summary • Systems engineering to TCWS design is consistent to the project level SE guidelines • US-ITER is now completing the conceptual design • PFDs are being produced • Baseline document is being written • Study on optimization & value engineering is planned

  17. Process Flow Diagram of DIV PHTS CVCS Nitrogen CWS 3 11 10 9 CCWS 2 DIV Cassettes DIV Cassettes 6 1 4 5 7 8 CVCS 12 Port Limiters Port Limiters Helium Supply Draining & Refilling Electric Interface Electric Interface N-VDS N-VDS CCWS-1 N-VDS N-VDS CCWS-1 Drain Drain Drain Drain Drying CVCS CVCS Availability Notice This document was created under the ITER International Partnership. While this document was developed for the purpose of the ITER project, it may be shared with interested parties. There are no specified limitations on the distribution of this document. 

  18. FW/BLK PRT Compressed Air N-VDS N-VDS Hydrogen Radwaste Nitrogen Demi Water LHX CCWS-1 CCWS-1 Radwaste VCT PR Radwaste RP OMF HTMF IX FW/BLK PHTS FW/BLK PHTS Electric Draining Demi Water FW/BLK Pressurizer Draining Draining Refilling 5 7 1 2 2 3 4 9 8 6 Draining Process Flow Diagram of FW/BLK CVCS Abbreviations: HTMF – high-temperature mechanical filter PR – pressure reducer LHX – letdown heat exchanger IX – ion exchanger OMF – outlet mechanical filter VCT – volume control tank PRT – pressure relief tank RP – recharging pump Availability Notice This document was created under the ITER International Partnership. While this document was developed for the purpose of the ITER project, it may be shared with interested parties. There are no specified limitations on the distribution of this document.  Note: sum of flow in points “8” and “9” should be equal to the flow in point “7”.

  19. DIV/LIM PRT Hydrazine Compressed Air N-VDS N-VDS Hydrogen Radwaste Nitrogen Demi Water LHX CCWS-1 CCWS-1 Radwaste VCT PR Radwaste RP OMF HTMF IX DIV/LIM PHTS DIV/LIM PHTS Electric Draining Demi Water DIV/LIM Pressurizer Draining Draining Refilling 6 7 1 2 2 3 4 5 9 8 Draining Process Flow Diagram of DIV CVCS Abbreviations: HTMF – high-temperature mechanical filter PR – pressure reducer LHX – letdown heat exchanger IX – ion exchanger OMF – outlet mechanical filter VCT – volume control tank PRT – pressure relief tank RP – recharging pump Availability Notice This document was created under the ITER International Partnership. While this document was developed for the purpose of the ITER project, it may be shared with interested parties. There are no specified limitations on the distribution of this document.  Note: sum of flow in points “8” and “9” should be equal to the flow in point “7”.

  20. N-VDS Vacuum Compressed Air N-VDS N-VDS Radwaste Nitrogen Demi Water LHX CCWS-1 CCWS-1 Radwaste VCT VDG Radwaste RP OMF HTMF IX NBI PHTS NBI PHTS Electric Draining Demi Water Hydrogen Draining Draining Refilling 4 6 1 5 3 7 2 Draining Process Flow Diagram of NBI CVCS Abbreviations: HTMF – high-temperature mechanical filter LHX – letdown heat exchanger IX – ion exchanger OMF – outlet mechanical filter VCT – volume control tank VDG – vacuum degasifier RP – recharging pump Availability Notice This document was created under the ITER International Partnership. While this document was developed for the purpose of the ITER project, it may be shared with interested parties. There are no specified limitations on the distribution of this document. 

More Related