State-of-the-Art 3-D Assessment of Elements Degrading TBR of ARIES-ACT SiC/LiPb Blanket

Similar documents
Preliminary ARIES-RS-DCLL Radial Build for ASC

Impact of Medium-Temperature Magnet and 2-FP Configuration on Radial Build

UPDATES ON ARIES-ACT1 POWER CORE CONFIGURATION

PRELIMINARY ACT-2 POWER CORE DESIGN DEFINITION

INTEGRATION OF THE MODULAR DUAL COOLANT PB-17LI BLANKET CONCEPT IN THE ARIES-CS POWER PLANT

Preliminary Neutronics Assessment of Molten Salt Blanket Concepts

Neutronic Performance Issues of the Breeding Blanket Options for the European DEMO Fusion Power Plant

Approaches to Maintenance. S. Malang

DEMO FUSION CORE ENGINEERING: Blanket Integration and Maintenance

Dual-Cooled Blanket Modular Replacement Design Approach

CONFIGURATION DESIGN AND MAINTENANCE APPROACH FOR THE ARIES-CS STELLARATOR POWER PLANT

Alternative Design Options for a Dual-Cooled Liquid Metal Blanket for ARIES-ACT2

Key Stellarator Engineering Issues and Constraints

ITER Shield Blanket Design Activities At SWIP

Pumping Systems for ITER, FIRE and ARIES

High Availability Remote Maintenance Approach for the European DEMO Breeder Blanket options

Facilities. Presented by Jim Irby for the C-Mod Group

ITER Vacuum Vessel Loads. Jake Blanchard October 2011

Status of ITER at the Transition to Construction

KSTAR Assembly. National Fusion Research Center, Daejeon, Korea

Overview of the ITER In-Vessel coil (IVC)

EU Procurement of In Vessel Components for ITER

Costing of Test Articles Ancillary Equipment and Costing Methodology

Evaluation of the Adequacy of Lithium Resources for Fusion Reactor with the Aspect of Li-ion Battery-Driven Vehicles

THE Gersh Budker Prize PRIZE FOR.THE SUCCESSFUL CONSTRUCTION AND COMMISSIONING OF THE SPALLATION NEUTRON SOURCE

Asymmetry of W7-X magnet system introduced by torus assembly

Supported by. NSTX Liquid Lithium Divertor Status, Plans, and Future Liquid Lithium R&D Needs

IMPROVED BWR CORE DESIGN USING HYDRIDE FUEL

U.S. BACKGROUND IN ITER FUELING SYSTEMS AND FUTURE CONTRIBUTIONS

Neutronics of Prismatic Fluoride Salt Cooled High Temperature Reactors

Conceptual Design Report on JT-60SA Fuelling System Gas Fuelling System

NOTICE. The above identified patent application is available for licensing. Requests for information should be addressed to:

VEX ELECTROMAGNET. Make It Real CAD Engineering Challenge

ABB Next Level Big shift in power attractive opportunities

Nuclear Thermal Propulsion (NTP) Engine Component Development

An Indian Journal FULL PAPER ABSTRACT KEYWORDS. Trade Science Inc. Research progress and status quo of power electronic system integration

Progress of the JT-60SA Project

CFD analysis of WCLL breeding blanket module design

DESCRIPTION OF THE DELPHI SUBCRITICAL ASSEMBLY AT DELFT UNIVERSITY OF TECHNOLOGY

AIR CLASSIFIERS FOR INDUSTRIAL MINERALS CTM SERIES

Re evaluation of Maximum Fuel Temperature

Tyre Endurance/Low Pressure Test

Improving predictive maintenance with oil condition monitoring.

Towards Resource Efficient Electric Vehicle Sector in India. Souvik Bhattacharjya Fellow, Centre for Resource Efficiency & Governance TERI, New Delhi

Fueling System Proposal for KSTAR

Innovative Centrifugal Compressor Design

5 th NEAESF. Outline

Costing of Test Articles Ancillary Equipment and Costing Methodology

Technical specification. Stabilizer WR 2000 XL

The modifications to the Europa to accept the new tank were minimal and consisted of:

Successful Deployment of ecall Live Crash Test

Frameless Torque Motor Series

Projected Fueling Efficiency and Implications for a DEMO Fusion Reactor

Western Alberta Transmission Line (WATL) HVDC Project

SD-CT Electronic Control Units

Ricardo-AEA. Passenger car and van CO 2 regulations stakeholder meeting. Sujith Kollamthodi 23 rd May

Breed Averages, Percentiles and Genetic Trends as of the week of August 21 st are shown below.

Direct Injection Ethanol Boosted Gasoline Engines: Biofuel Leveraging For Cost Effective Reduction of Oil Dependence and CO 2 Emissions

Cooperative Autonomous Driving and Interaction with Vulnerable Road Users

TerraPower s Molten Chloride Fast Reactor Program. August 7, 2017 ANS Utility Conference

Shape - Typical designs with sector angles of pi/2 [90 degrees], and 2pi/3 [120 degrees] are shown below.

Ghassan Y. Antar University of California San Diego

Session Four Applying functional safety to machine interlock guards

NORTH SLOPE BOROUGH Department of Public Works P.O. Box 350 Barrow, Alaska 99723

Efficient, intelligent, autonomous Applying low emission vehicles

Effectiveness of ECP Brakes in Reducing the Risks Associated with HHFT Trains

Abatement under the EU ETS? Evidence from selected sectors

Germany s Water Footprint of Transport Fuels

The Smart Meter rollout programme

SEMI FLEXIBLE SOLAR PANELS by Van Williams

Gear Drive Solutions a Dedicated and Reliable Partner

Technical Committee Motor Vehicles 15 September RDE 3 discussion

Used Vehicle Supply: Future Outlook and the Impact on Used Vehicle Prices

Automotive Aftermarket Giorgio Brusco

Thermal Management: Key-Off & Soak

Thermal analysis of IRT-T reactor fuel elements

Design of A New Non-Contact Screw Seal and Determination of Performance Characteristics

The Smallest Automated Transmission Possible

Replacing Cast Aluminum Wheels with Hayes Lemmerz Flex Steel Wheels Technical and Marketing Challenges

About Reasonably Achievable Balance between Economy and Safety indices in WWERs

Innovating hydraulic systems and tools for the wind energy industry

Danfoss Turbocor compressors Making a world of difference

The Renewable Energy Market Investment Opportunities In Lithium. Prepared by: MAC Energy Research

Course Outcome Summary

Development and Performance Evaluation of High-reliability Turbine Generator

1 MICHELIN INVESTOR DAY Shenyang, China November 10, HuiFeng LU

Christian Theis 52 nd GRB, 6-8 September 2010, ASEP outline. Summary & Conclusion

The role of CVR in the fuel inspection at Temelín NPP

Design of closing electromagnet of high power spring operating mechanism

A Helium Cooled Particle Fuelled Reactor for Fuel Sustainability. T D Newton, P J Smith, Y Askan. Serco Assurance. Work Sponsored by BNFL

Smart grids: how do we get there?

Palm Oil Processors and Traders Operational Profile 1.1 Please state your main activity(ies) within the supply chain Post-refinery processor Ingredien

Addressing ambiguity in how electricity industry legislation applies to secondary networks

CONSIDERATIONS REGARDING THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR. PART 1 - PRESENTATION OF THE FUEL CHANNEL

Sports Car Brake Cooling Simulation with CAD-Embedded CFD

CNS Fuel Technology Course: Fuel Design Requirements

FRM II Converter Facility

ME Thermoelectric -I (Design) Summer - II (2015) Project Report. Topic : Optimal Design of a Thermoelectric Cooling/Heating for Car Seat Comfort

2011 NDIA GROUND VEHICLE SYSTEMS ENGINEERING AND TECHNOLOGY SYMPOSIUM POWER AND MOBILITY (P&M) MINI-SYMPOSIUM AUGUST 9-11 DEARBORN, MICHIGAN

What do autonomous vehicles mean to traffic congestion and crash? Network traffic flow modeling and simulation for autonomous vehicles

Transcription:

State-of-the-Art 3-D Assessment of Elements Degrading TBR of ARIES-ACT SiC/LiPb Blanket L. El-Guebaly, A. Jaber, L. Mynsberge and the ARIES-ACT Team Fusion Technology Institute University of Wisconsin-Madison http://fti.neep.wisc.edu/uwneutronicscenterofexcellence ANS 20 th Topical Meeting on the Technology of Fusion Energy August 27-31, 2012 Nashville, TN, USA

ARIES Designs (1988 2012) 2

ARIES-ACT Design Two Blanket Designs DCLL ηth ~ 45% (presented @ ISFNT-2011) SiC/LiPb ηth ~ 60% R= 5.5 m; a= 1.375 m; A= 4; 16 TF magnets; 16 Toroidal modules; SiC/LiPb blanket. No blanket behind divertor (only LiPb manifolds for inboard blanket). ARIES breeding requirements: calculated 3TBR = 1.05 with 6Li enrichment < 90%.

We Addressed Several Breeding-Related Questions that Puzzled Fusion Community for Decades Breeding-related questions: How does blanket structure (first wall, side, and back walls, cooling channels, etc.) degrade TBR? Which change to blanket thickness and/or Li enrichment is more enhancing to TBR? How does advanced physics (that requires embedding stabilizing shells within blanket) degrade breeding? Could required TBR be achieved in presence of several design elements (such as plasma heating and current drive ports) that compete for best available space for breeding? Does blanket offer flexible approach to handle any shortage and surplus of T? Past studies answered some questions by addressing individual issues one at a time. Our state-of-the-art 3-D analysis examined all questions collectively in integral fashion to account for inter-dependence and synergistic effects. 4

Questions Addressed with Sophisticated 3-D Neutronics Codes UW Computational Nuclear Engineering Research Group (CNERG) developed most innovative computational tool in recent years. DAGMC code permits fully accurate modeling of complex devices by integrating CAD geometry directly with 3-D MCNP code. To point out terms that contribute to decrease/increase in TBR, we also developed a novel stepwise approach that allows adding various blanket components step-by-step. This unique capability allows fully accurate presentation of blanket geometry with high fidelity in 3-D TBR results. 5

Stepwise Approach Build CAD model from scratch, starting with FW/divertor skeleton Couple CAD with MCNP using DAGMC code No homogenization within breeding zones In multiple steps, add: FW and other walls for blanket Other design elements (shield, assembly gaps, stabilizing shells, penetrations, etc.) Record impact of 7 individual design elements on TBR Vary Li enrichment from natural to 90% to determine operating enrichment. 1.8 1.79 If calculated TBR 1.05, adjust: Blanket thickness Li enrichment. Overall TBR 1.6 1.4 1.2 1.392 1.3841.345 1.198 1.144 1.076 1.050 ARIES-ACT-SiC One module (22.5 o ) (Courtesy of X. Wang (UCSD)) 1 1 2 3 4 5 6 7 8 6

1-D Infinite Cylinder (to estimate maximum achievable TBR for 100 % LiPb; 90% Li enrichment; no structure) 2 m thick LiPb Breeder Li 15.7 Pb 84.3 Shield 7

1-D Infinite Cylinder (to estimate maximum achievable TBR for 100 % LiPb; 90% Li enrichment; no structure) 1.8 1.79 90% Enriched Li-6 1. 1-D infinite Cylinder: 100% LiPb breeder surrounded with FS shield Overall TBR 1.6 1.4 1.2 1 1 2 3 4 5 6 7 8 8 Required Calculated TBR = 1.05

3-D Toroidal Model: Li 15.7 Pb 84.3 Confined Radially/ Vertically to Blanket. Shield and Divertor Added 35 cm LiPb 5% Shield / Steel Ring (80% ODSFS, 20% He) 32% Upper half of 1/32 th module with three reflecting boundaries at both sides and at midplane 63% Neutron Source 9 1/64 th of ARIES-ACT-1 torus

3-D Toroidal Model: Li 15.7 Pb 84.3 Confined Radially/ Vertically to Blanket. Shield and Divertor Added Overall TBR 1.8 1.6 1.4 1.2 1.79 22% drop 1.392 90% Enriched Li-6 1. 1-D infinite Cylinder: 100% LiPb breeder surrounded with FS shield 2. 3-D Toroidal Model: LiPb confined to 35 cm IB blanket and 30+45 cm OB blanket 1 1 2 3 4 5 6 7 8 10

2 cm Wide Assembly Gaps Between Modules (purple)

Overall TBR 1.8 1.6 1.4 2 cm Wide Assembly Gaps Between Modules 1.79 0.6% drop 1.392 1.384 90% Enriched Li-6 1. 1-D infinite Cylinder: 100% LiPb breeder surrounded with FS shield 2. 3-D Toroidal Model: LiPb confined to 35 cm IB blanket and 30+45 cm OB blanket 3. Add assembly gaps between blanket modules 1.2 1 1 2 3 4 5 6 7 8 12

Segment Blankets into Sectors and Curve FW and BW of each Sector OB Max OB-I radial blanket thickness = 30 cm Max OB-II radial blanket thickness = 45 cm IB Maximum radial blanket thickness = 35 cm PLASMA 13

Overall TBR 1.8 1.6 1.4 1.79 Segment Blankets into Sectors and Curve FW and BW of each Sector 1.392 3% drop 1.3841.345 90% Enriched Li-6 1. 1-D infinite Cylinder: 100% LiPb breeder surrounded with FS shield 2. 3-D Toroidal Model: LiPb confined to 35 cm IB blanket and 30+45 cm OB blanket 3. Add assembly gaps between blanket modules 4. Curve IB and OB blanket sectors 1.2 1 1 2 3 4 5 6 7 8 14

SiC/LiPb Materials Assigned to Walls OB IB PLASMA 15

SiC/LiPb Materials Assigned to Walls Overall TBR 1.8 1.6 1.4 1.2 1.79 1.392 1.3841.345 11% drop 1.198 90% Enriched Li-6 1. 1-D infinite Cylinder: 100% LiPb breeder surrounded with FS shield 2. 3-D Toroidal Model: LiPb confined to 35 cm IB blanket and 30+45 cm OB blanket 3. Add assembly gaps between blanket modules 4. Curve IB and OB blanket sectors 5. Add blanket walls 1 1 2 3 4 5 6 7 8 16

W Stabilizing Shells Added to IB & OB (purple) 4 cm thick IB Vertical Stabilizing shell. Continuous toroidally. 100% W-TiC. 4 cm thick OB Vertical Stabilizing (VS) shell. Continuous toroidally. 100% W-TiC. OB Z = 1.76 2.81 m. 1 cm thick OB Kink shell. Segmented toroidally. OB Z = 0 1.42 m. OB IB 17

W Stabilizing Shells Added to IB & OB Overall TBR 1.8 1.6 1.4 1.2 1.79 1.392 1.3841.345 1.198 4.5% drop 1.144 90% Enriched Li-6 1. 1-D infinite Cylinder: 100% LiPb breeder surrounded with FS shield 2. 3-D Toroidal Model: LiPb confined to 35 cm IB blanket and 30+45 cm OB blanket 3. Add assembly gaps between blanket modules 4. Curve IB and OB blanket sectors 5. Add blanket walls 6. Add stabilizing shell 1 1 2 3 4 5 6 7 8 18

Vary Li-6 Enrichment 1.2 Overall TBR 1.1 1.0 0.9 0.8 0.7 Required TBR 0.6 0 20 40 60 80 100 6 Li Enrichment (%) 19

Vary Li-6 Enrichment Overall TBR 1.8 1.6 1.4 1.2 1.79 1.392 1.3841.345 1.198 1.144 6% drop 1.076 90% Li-6 enrichment 1. 1-D infinite Cylinder: 100% LiPb breeder surrounded with FS shield 2. 3-D Toroidal Model: LiPb confined to 35 cm IB blanket and 30+45 cm OB blanket 3. Add assembly gaps between blanket modules 4. Curve IB and OB blanket sectors 5. Add blanket walls 6. Add stabilizing shell 7. 58% Li-6 enrichment 1 1 2 3 4 5 6 7 8 20

Penetrations Footprints at FW: Plasma control, heating, and fueling: 2 m 2 ICRF (or 0.5 m 2 EC) 2 m 2 LH Diagnostics: 3 m 2 0.008 m 2 fueling ducts --------- Total 7.0 m 2 (or 5.5 m 2 ) Fraction of OB surface area = ~ 7.0 m 2 2.24% 313 m 2 Maximum fraction could reach 4% of OB area. We considered 4% of OB FW area (12 m 2 ) for ARIES-ACT penetrations 21

Including Penetrations Overall TBR 1.8 1.6 1.4 1.2 1 1.79 1.392 1.3841.345 1.198 1.144 2.4% drop 1.076 1.050 1 2 3 4 5 6 7 8 22 90% Li-6 enrichment 1. 1-D infinite Cylinder: 100% LiPb breeder surrounded with FS shield 2. 3-D Toroidal Model: LiPb confined to 35 cm IB blanket and 30+45 cm OB blanket 3. Add assembly gaps between blanket modules 4. Curve IB and OB blanket sectors 5. Add blanket walls 6. Add stabilizing shell 7. 58% Li-6 enrichment 8. Add penetrations (4% of OB FW area)

Isometric View of Detailed Blanket (Upper half of 1/32 th (11.25 o ) toroidal module) Overall TBR = 1.05 6 Li enrichment = ~ 60% LiPb manifolds behind lower divertor could increment TBR by few percent. 23

General Observations and Conclusions 3-D analysis showed progressive reduction of theoretical TBR (~1.8) down to more realistic TBR (1.05) when real geometry of LiPb/SiC blanket is addressed. Main findings and results: ARIES-ACT blanket complies with ARIES breeding requirements (calculated TBR of 1.05 with 60% 6 Li enrichment (< 90%)) Limiting the blanket coverage radially and vertically has the largest impact on TBR (22%) Shaping the blanket and adding the SiC structure have a 14% reduction in TBR Inclusion of stabilizing shells has ~5% impact on TBR Adding penetrations and assembly gaps has smaller (3%) but still significant impact on TBR. Because many uncertainties in operating system govern achievable breeding level during plant operation, it is a must requirement for any blanket design to have flexible approach. Most attractive scheme for LiPb breeder is to operate with 6 Li enrichment < 90% and increase/decrease 6 Li enrichment online shortly after plant operation. This scheme helps mitigate concerns about danger of placing plant at risk due to T shortage as well as problem of handling and safeguarding any surplus of T. 24