Recycling Issues Facing Target and RTL Materials of Inertial Fusion Designs L. El-Guebaly, P. Wilson, M. Sawan, D. Henderson, A. Varuttamaseni and the.

Slides:



Advertisements
Similar presentations
International Atomic Energy Agency IX.4.3. Waste management.
Advertisements

September 24-25, 2003 HAPL meeting, UW, Madison 1 Armor Configuration & Thermal Analysis 1.Parametric analysis in support of system studies 2.Preliminary.
Views on Neutronics and Activation Issues Facing Liquid-Protected IFE Chambers L. El-Guebaly and the ARIES Team Fusion Technology Institute University.
Feasibility of Recycling Hohlraum Wall Materials L. El-Guebaly, P. Wilson, D. Henderson, and A. Varuttamaseni Fusion Technology Institute University of.
Overview of radioactivity vs. chemical toxicity issues for Overview of radioactivity vs. chemical toxicity issues for potential target materials presented.
DAH, UW-FTI ARIES-IFE, April 2002, 1 Results from parametric studies of thin liquid wall IFE chambers D. A. Haynes, Jr. Fusion Technology Institute University.
Liquid Wall Thickness, Life, Pumping Power, COE trade-offs Wayne R. Meier and Ryan P. Abbott LLNL ARIES Meeting Oct. 2-5, 2002 PPPL.
Welcome to the second “official” Laser IFE workshop Discuss our progress in Laser IFE Address some key issues as a group Oxidation of graphite walls Filling.
Assessment of Chamber Concepts for IFE Power Plants: The ARIES-IFE study Farrokh Najmabadi for the ARIES Team IFSA2001 September 9-14, 2001 Kyoto, Japan.
Wayne R. Meier Lawrence Livermore National Lab Heavy Ion Fusion Modeling Update* ARIES e-Meeting October 17, 2001 * This work was performed under the auspices.
N. Alexander, P. Gobby, D. Goodin, J. Hoffer, J. Latkowski, A. Nobile, D. Petti, R. Petzoldt, A. Schwendt, W. Steckle, D. Sze, M. Tillack Presented by.
P. Gobby, A. Nobile, J. Hoffer, A. Schwendt and W. Steckle Concepts for Fabrication of Inertial Fusion Energy Targets.
ARIES Meeting April 22-23, 2002 U. Wisconsin, Madison Work performed under the auspices of the U. S. Department of Energy by University of California Lawrence.
Impact of Liquid Wall on Fusion Systems Farrokh Najmabadi University of California, San Diego NRC Fusion Science Assessment Committee November 17, 1999.
Design Windows for IFE Chambers and Target Injection Farrokh Najmabadi for the ARIES Team US/Japan Workshop on Target Fabrication December 3-4, 2001 General.
Action Items For ARIES-IFE Study Farrokh Najmabadi ARIES Project Meeting June 19-21, 2000 University of Wisconsin, Madison Electronic copy:
Safety assessment for Safety assessment for potential target materials: radioactivity vs. chemical toxicity presented by: Susana Reyes ARIES Group Meeting.
October 24, Remaining Action Items on Dry Chamber Wall 2. “Overlap” Design Regions 3. Scoping Analysis of Sacrificial Wall A. R. Raffray, J.
ARIES-IFE Assessment of Operational Windows for IFE Power Plants Farrokh Najmabadi and the ARIES Team UC San Diego 16 th ANS Topical Meeting on the Technology.
A. Schwendt, A. Nobile, P. Gobby, W. Steckle Los Alamos National Laboratory D. T. Goodin, Neil Alexander, G. E. Besenbruch, K. R. Schultz General Atomics.
Fusion Technology Institute University of Wisconsin - Madison NRL IFE Concepts Project 9/19/ Output Calculations for Laser Fusion Targets ARIES Meeting.
ARIES-IFE: An Integrated Assessment of Chamber Concepts for IFE Power Plants Mark Tillack for the ARIES Team 19th IEEE/NPSS SOFE January 22-25, 2002 Atlantic.
Thermal Control Techniques for Improved DT Layering of Indirect Drive IFE Targets M.S. Tillack and J.E. Pulsifer University of California, San Diego D.T.
Highlights of ARIES-IFE Study Farrokh Najmabadi VLT Conference Call April 18, 2001 Electronic copy: ARIES Web Site:
Aug. 8-9, 2006 HAPL meeting, GA 1 Open Discussion on Advanced Armor Concepts Moderated by A. René Raffray UCSD HAPL Meeting GA, La Jolla, CA August 8-9,
1 ARIES IFE - Some Concluding Comments on Thick Liquid Walls Wayne Meier, Ryan Abbott, Jeff Latkowski, Ralph Moir, Susana Reyes ARIES Project Meeting September.
Summary of FS Lifetime Assessment and Activation Analysis L. El-Guebaly Fusion Technology Institute University of Wisconsin - Madison ARIES E-Meeting October.
1 Radiation Environment at Final Optics of HAPL Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI HAPL GIMM Conference Call.
Initial Activation Assessment for ARIES Compact Stellarator Power Plant L. El-Guebaly, P. Wilson, D. Paige and the ARIES Team Fusion Technology Institute.
Distribution of Advanced Design Research FY02 FY03 (Current) ARIES (IFE & MFE) System Studies1,9661,939 Socio-economic Studies UCSD/UW/RPI 1,189.
A. Schwendt, A. Nobile, W. Steckle Los Alamos National Laboratory D. Colombant, J. Sethian Naval Research Laboratory D. T. Goodin, N. Alexander, G. E.
The High Average Power Laser Program in DOE/DP Coordinated, focussed, multi-lab effort to develop the science and technology for Laser Fusion Energy Coordinated,
Development of the FW Mobile Tiles Concept Mohamed Sawan, Edward Marriott, Carol Aplin University of Wisconsin-Madison Lance Snead Oak Ridge National Laboratory.
Mid-long term R&D step by step plan in order to implement the recycling at the maximum extension possible Gunnar Olsson and Lise-Lotte Spontón TW5-TSW-001,
The High Average Power Laser Program Coordinated, focussed, multi-lab effort to develop a rep-rate laser facility for Inertial Fusion Energy and DP needs.
Fusion-Fission Hybrid Systems
Neutronics Parameters for Preferred Chamber Configuration with Magnetic Intervention Mohamed Sawan Ed Marriott, Carol Aplin UW Fusion Technology Inst.
Reducing the Costs of Targets for Inertial Fusion Energy G.E. Besenbruch, D.T. Goodin, J.P. Dahlburg, K.R. Schultz, A. Nobile 1, E.M. Campbell General.
LA-UR “Mini-Workshop” on Coordination of IFE Target Thermo-Mechanical Modeling and DT Ice Experiments LANL, UCSD, and General Atomics at Los Alamos.
1 Solid Breeder Blanket Design Concepts for HAPL Igor. N. Sviatoslavsky Fusion Technology Institute, University of Wisconsin, Madison, WI With contributions.
Plan to Develop A First Wall Concept for Laser IFE.
San Diego Workshop, 11 September 2003 Results of the European Power Plant Conceptual Study Presented by Ian Cook on behalf of David Maisonnier (Project.
Study on recycling of fusion activated materials: Identify activation levels, characteristics and decay time requirements of irradiated material (deliverable.
Target Materials Selection and Constraints on Chamber Conditions Bill Rickman, Dan Goodin, Remy Gallix Presented by Ron Petzoldt ARIES Town Meeting On.
Laser IFE Program Workshop Naval Research Laboratory February 6 & 7, 2001 A. Nobile, J. Hoffer, A. Schwendt, W. Steckle, D. Goodin, G. Besenbruch and K.
The Plan to Develop Laser Fusion Energy John Sethian Naval Research Laboratory July 19, 2002.
HAPL Concrete Shielding Requirements Mohamed Sawan UW Fusion Technology Inst. HAPL Project Meeting UW-Madison October 22-23, 2008.
Laser IFE Meeting November 13-14, 2001 Crowne Plaza Hotel, Pleasanton, CA Work performed under the auspices of the U. S. Department of Energy by University.
1. ID Target Aerosol limits 2. Tracking and Laser Aerosol Limits 3. Foam Mechanical Properties 4. Target Injection Accuracy 5. Future ARIES Target Task.
John Sethian Naval Research Laboratory June 20, 2000 A Vision for Direct Drive Laser IFE: NS A vision for Laser Direct Drive Fusion Energy.
1 Neutronics Assessment of Self-Cooled Li Blanket Concept Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI With contributions.
FAST MOLTEN SALT REACTOR –TRANSMUTER FOR CLOSING NUCLEAR FUEL CYCLE ON MINOR ACTINIDES A.Dudnikov, P.Alekseev, S.Subbotin.
1 Neutronics Parameters for the Reference HAPL Chamber Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI With contributions.
Top level overview of target fabrication tasks High Average Power Laser Program Workshop Princeton Plasma Physics Laboratory October 27 and 28, 2004 Presented.
A. Schwendt, A. Nobile, P. Gobby, W. Steckle Los Alamos National Laboratory D. T. Goodin, G. E. Besenbruch, K. R. Schultz General Atomics Laser IFE Workshop.
The Neutronics of Heavy Ion Fusion Chambers Jeff Latkowski and Susana Reyes 15 th Heavy Ion Inertial Fusion Symposium Princeton, NJ June 9, 2004 Work performed.
Fuel Cycle Research Thrust Using A Full Fusion Nuclear Environment
Associazione EURATOM ENEA sulla FUSIONE Monitoring Meeting of the Tasks TW5-TSW-001, 001B, June 2006, SCKCEN, Mol, Belgium Monitoring Meeting.
Study on recycling of fusion activated materials: Identify activation levels and decay time requirements of irradiated material (deliverable 3) R. Pampin.
Radiological Issues for Thin Liquid Wall Options L. El-Guebaly, P. Wilson, and D. Henderson Fusion Technology Institute University of Wisconsin - Madison.
Heavy Ion Fusion Target Materials Selection and Removal of Tungsten Carbide from Flibe Ron Petzoldt, Bill Rickman, Dan Goodin, and Lloyd Brown ARIES Meeting.
Khalid Aldhahri Omar Alrajeh Daniel Marken Thomas White CLEAN AIR POWER ASU with Oxy-fuel Combustion for Zero Emission Energy University of Wyoming College.
1 Radiation Environment at Final Optics of HAPL Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI HAPL Meeting ORNL March.
The ESS Target Station Eric Pitcher Head of Target Division February 19, 2016.
Preliminary Decommissioning Plan for the Canadian Light Source
Action Items from ARIES IFE Meeting, GA, July 1-2, 2002 (DRAFT)
Neutronics Issues for Final Optics of HAPL Mohamed Sawan, Ahmad Ibrahim, Tim Bohm, Paul Wilson Fusion Technology Institute University of Wisconsin,
Comments on ARIES-ACT 10/20/2010 Pre-Strawman
University of California, San Diego
Action Items from ARIES IFE Meeting, UW, April 22-23, 2002 (DRAFT)
Presentation transcript:

Recycling Issues Facing Target and RTL Materials of Inertial Fusion Designs L. El-Guebaly, P. Wilson, M. Sawan, D. Henderson, A. Varuttamaseni and the ARIES and Z-Pinch Teams Fusion Technology Institute University of Wisconsin - Madison With input from: I. Sviatoslavsky, G. Kulcinski, J. Santarius (UW), C. Olson, G. Rochau, C. Morrow (SNL), A. Nobile, A. Schwendt (LANL) D. Goodin, R. Petzoldt (GA), P. Peterson (UCB) N. Taylor (UKAEA) HI-2004 Symposium June 7-11, 2004 Princeton, NJ

2 Advise IFE designers on best option to manage HI hohlraum wall radwaste and Z-pinch RTL radwaste: –One-shot use, then dispose in repository, or –Recycle during plant life (45-50 y) Highlight pros and cons of once-through and recycling scenarios. Develop irradiation history and timeline for recycling approach. Examine conservative recycling approach without slag or transmutation product removal. Monitor waste level and dose to equipment during recycling. Determine economic impact of recycling approach. Objectives

3 Representative IFE-HI Power Plant Flibe Jets Hohlraum Wall (60% of target mass) Foams LLNL Close-Coupled Target Design DT Capsule HIB HYLIFE-II (Thick Liquid Wall Concept)

4 Z-Pinch Power Plant Target Flibe Jets Flibe Foam Recyclable Transmission Lines (RTL) Top diameter = 1 m Bottom diameter = 0.1 m Length = 5 m Carbon Steel thickness = cm 50 kg* / RTL ––––––––––––––––––––– * Needed for high electric efficiency. Chamber (12 units / plant)

5 ARIES-IFE-HI Z-Pinch Target Yield 460 MJ 3000 MJ Rep Rate4 Hz0.1 Hz # of Units per Plant112 * # of Shots per FPY126 million38 million Au/Gd Hohlraum Wall or RTL Thickness 15  m0.635 mm Mass of Hohlraum Wall or RTL0.1 g / target 50 kg / RTL Volume of Hohlraum Wall or RTL0.008 cm 3 / target 6000 cm 3 / RTL Availability85%85% Plant Lifetime 40 FPY 40 FPY (47 y) (47 y) Key Parameters ____________ * Latest design calls for 10 units per plant.

6 Pros: –Low inventory of radwaste. –Negligible material cost. Cons: –May generate high-level waste that violates ARIES top-level requirements. –Require radioactive storage facility in target fab. –Need purification system to deliver highly pure materials. –No hands-on and no personnel access to target fab. –Slow, remotely controlled process. –Costly process. Pros and Cons of Recycling Scenario Do not recycle unless process offers advantages

7 Recycling is not a “must” requirement for IFE-HI designs Hohlraum Wall Materials Represent < 1% of IFE-HI Waste Stream

8 It is acceptable among ARIES team members that hohlraum wall materials should not be recycled. However, we developed a recycling approach to understand the problem and highlight the cost penalty and design complexity added to HI designs. Among wide range of candidate hohlraum wall materials, we selected three materials for this study: –Gold/Gadolinium (50/50 wt%) –Tungsten –Lead Hohlraum Wall Recycling?!

9 IFE-HI Target Recycling Process (Hohlraum Wall Materials Spend ≥ 2 days Outside Chamber) Cooling Period Heat recovery, T extraction, and Filtration process Target Final Assembly Facility (cryogenic Environment) DT Filled Capsules Target Injection (3 -10 s) Hohlraum Debris, Liquid Vapor, Buffer Gas, and Others Hohlraum Wall Fabrication Facility Chamber t 1 (~1 min) t 2 (? ; < 2 y) t 3 (1 d) t 4 (1 d) Liquid Breeder + Others Buffer Gas, D, T, and Transmutation Products Hohlraum Debris Other Hohlraum Materials

10 Waste disposal rating (WDR) 1 (for Class C low-level waste) Clearance Index 1 (for waste containing traces of radionuclides) Recycling dose 3000 Sv/hr (for advanced remote handling equipment) Codes and data: –DANTSYS Neutral-particle transport code: –ALARA Pulsed activation code: Exact modeling of all pulses (~10,000) –FENDL-2 Nuclear Data: 175 neutron and 42 gamma group structure Design Criteria and Codes

11 One-Shot Use Scenario Recycling Scenario WDRCIWDR * Gold/Gadolinium2 x x10 5 Tungsten 2 x Lead 2 x ___________________________ * No cooling period. No transmutation product removal. One-Shot Use Scenario Generates Very Low Level Waste White recycling Generates High-Level Waste

12 Au/Gd generates high-level waste that violates ARIES requirements Cooling Period Controls WDR and Dose All materials meet advanced RH limit with < 10 d cooling periods

13 Cooling Period Cooling Period for Recommended for WDR < 1 Dose < 3000 Sv/h Cooling Period Au/Gd> 2 y * 9.5 d –– * ( 158 Tb) ( 196 Au) Tungsten0 6.2 d 6.2 d ( 186m Re, 178n Hf) ( 184 Re) Lead13 d < 1 d 13 d ( 208 Bi, 202 Pb) ( 203 Pb, 202 Tl) ___________________ * Insignificant inventory reduction for cooling period exceeding 2 y. Recommended Cooling Periods that Satisfy Design Limits

14 One-Shot Use Recycling Scenario Cost per Target$ 0.4 $ 3.15 Change to COE~10 mills/kWh ~70 mills/kWh COE ~70 mills/kWh ~130 mills/kWh Recycling Doubles HI Cost of Electricity Doubling COE to recycle materials that present no waste burden to IFE-HI designs is unacceptable

15 HI Hohlraum walls represent small waste stream (< 1% of total nuclear island waste)  recycling is not a “must” requirement for IFE-HI concept. Use low-cost materials once-through and dispose as Class A LLW instead of using expensive materials (such as Au and Gd). One-shot use scenario offers: – Attractive safety features– Less complex design – Radiation-free target Fab– Lowest COE Target factory designers prefer dealing with non-radioactive hohlraum wall materials and this assessment supports the feasibility of no-recycling approach for HI concepts. IFE-HI Conclusions

16 Z-Pinch Power Plant Target Flibe Jets Flibe Foam Carbon Steel 50 kg / RTL Less intense neutron flux and softer spectrum at RTL result in much lower activity, WDR, CI, and dose.

17 RTL Recycling is a “Must” Requirement to Minimize Waste Stream and Enhance Economics Without RTL recycling Total RTL mass = 80 M Tons Fabricated Steel Unit Cost = $10/kg Total RTL cost = ~$800B With RTL recycling 1.5 day RTL inventory Total RTL mass = 8,000 Tons Total RTL cost ~ $80M

18 RTL Recycling Process (RTL Materials Spend ~1.5 day Outside Chamber) Cooling Period Heat recovery, T extraction, and separation processes Final RTL and Target Assembly Foam and Reflector Fabrication Cartridge Insertion Debris and Flibe RTL Fabrication and Inspection t 1 (~1 min) t 2 (?) t 3 (14 h) t 5 (10 s) Flibe + Others D, T and Transmutation Products RTL Debris Target Capsules Cooling Period Target Debris (W, Be, CH) t 4 (1 d) One Day Storage Chamber

19 RTL Results ResultsLimits WDR Class C Class A Clearance Index 100 y1 50 y Recycling dose rate ( Sv/hr)

20 RTL recycling is a “must” requirement for Z-pinch concept to minimize heavy metal throughput and enhance economics. Carbon Steel RTLs satisfy design requirements when recycled for entire plant life even without cooling period: – Class A low-level waste  Shallow land burial – Clearance index < 1  Release to commercial market after 50 y – Dose < 160 Sv/hr  No hands-on recycling Online removal of transmutation products helps meet design requirements with wide margin, but complicates recycling process and generates high level waste. Recycling process must be accomplished remotely in 1.5 day. Advanced remote handling equipment should be developed to handle high dose rate (200 Sv/hr or more). COE should reflect cost of RTL remote recycling. Z-Pinch Conclusions

21 Recycling offers advantages to Z-pinch while adds complexity and cost to HI systems. Recommendations: – Use low-cost hohlraum wall materials for HI targets once-through, then dispose in repositories. – Recycle RTLs of Z-pinch. Overall Conclusions