Feasibility of Recycling Hohlraum Wall Materials L. El-Guebaly, P. Wilson, D. Henderson, and A. Varuttamaseni Fusion Technology Institute University of.

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Presentation transcript:

Feasibility of Recycling Hohlraum Wall Materials L. El-Guebaly, P. Wilson, D. Henderson, and A. Varuttamaseni Fusion Technology Institute University of Wisconsin - Madison With input from M. Sawan, R. Peterson, I. Sviatoslavsky, E. Mogahed (UW), D. Goodin, K. Schultz, A. Nikroo (GA), A. Nobile, A. Schwendt (LANL), L. Waganer (Boeing), R. Raffray, D.K. Sze (UCSD), M. Billone (ANL), R. Moir (LLNL), D. Petti (INEEL), S. Malang (FZK), and N. Taylor (UKAEA) ARIES Meeting April , 2002 UW

2 Address feasibility of recycling candidate hohlraum wall materials: MassCost * Resources (tons/FPY) (M$/FPY) Problem? Au/Gd (reference)1580 yes, Gd Au21210 W21 Pb12 Hg15 Ta180.6 Pb/Ta/Cs10 Hg/W/Cs11 Pb/Hf13 Hf142.6 Solid k3?? Solid k4?? ___________________ * 10$/g-Au $/g-Gd, $/g-Hf, $/g-Ta, per Waganer (Boeing) Objectives

3 Objectives (cont.) Lacking info on economic/resources problem, develop recycling approach for all hohlraum wall materials using ARIES design criteria and requirements Analyze two extreme cases: –One-shot use of hohlraum wall materials then dispose in repositories –Recycle without transmutation removal system Recommend design solutions for materials exihibiting recycling problems Investigate means for dealing with large quantity of radioactive EOL

4 HIB Target Parameters Capsule Radius * 2.34 mm Hohlraum Wall Thickness * 15  m Target yield MJ Rep Rate4 Hz # of Shots 126 million shots/FPY Plant Lifetime 40 FPY (47 y) Availability85% Volume of Hohlraum Wall cm 3 /target 1.1 m 3 /FPY 43 m 3 /40 FPY Mass of Hohlraum Materials 3-21 tons/FPY tons/40 FPY ____________ * D. Callahan-Miller and M. Tabak, Phys of Plasmas, Vol 7, p 2083, May 2000 Hohlraum Wall Foams LLNL Close-Coupled Target Design Capsule HIB

5 Hohlraum Wall Materials Represent < 1% of IFE Waste Stream Recycle costly/rare materials to reduce inventory by factor of 10 or more

6 Cooling Period Heat recovery, T extraction, and Filtration process Hohlraum Wall Recycling Process Target Final Assembly Facility (cryogenic Environment) DT Filled Capsules Target Injection (3 -10 s) Hohlraum Debris, LW Vapor, Buffer Gas, and Others Hohlraum Wall Fabrication Process toto t 1 (~1 min) t 2 (? ; < 2 y) t 3 (1 d) t 4 (1 d) Chamber LW Materials Buffer Gas, T, and Transmutation Products Hohlraum Debris Other Hohlraum Materials

7 Cooling Periods  2 y Reduce Hohlraum Inventory by Factor of 10 or more Inventory varies linearly with cooling period Steady-state inventory accounts for: –2 d back-up –t 2 +1 d –2 d for recycling –Short time in chamber 2 d backup inventory is needed to account for repair of recycling system; e.g., m 3 (80 kg of Au/Gd) Store irradiated materials in 1h or 1d bins, depending on cooling period unit Start-up inventory !? More sophisticated approach could reduce inventory further

8 Recycling Introduces Problems –Produces high level waste (HLW) for most materials –Increases activity and decay heat –Mandates remote handling (costly) in target fab –Requires radioactive storage system –Adds cost and complexity to target assembly/fabrication facility

9 Several Factors May Prematurely Terminate Recycling Process Requiring Fresh Hohlraum Wall Materials Waste disposal rating * of hohlraum debris violates Class C low level waste requirement Recycling dose * exceeds hands-on or remote handling limits Accident dose at site boundary exceeds 1 rem following accidents in chamber and/or in Target Fab Transmutation level in hohlraum debris reaches limit set by target designers to minimize beam losses to hohlraum walls. Alternative option is to separate transmutations on-line and address feasibility and economic issues Decay heat of radioactive hohlraum materials raises frozen DT temp above 1.8 K before target injection. Mogahed’s preliminary analysis showed insignificant change in temperature for LLNL target design meaning foams provide good thermal shield for capsule _____________ * Most restrictive factors in descending order

10 Potential Design Solutions for Materials with Recycling Problems I- Filter out transmutations on-line  Cup(s) of HLW Lowest LLW inventory Recycle for plant life (47 y) No cooling period II- Limit exposure time (or end recycling process) and call for fresh materials  No transmutations removal system (unpractical) No HLW Exclude Gd Larger LLW inventory than Option-I No cooling period Recycle for < 47 y III- Store materials for < 2 y of cooling period before fabrication  No transmutations removal system (unpractical) No HLW Exclude Gd Lower LLW inventory than Option-II Recycle for plant life (47 y)

11 No Major Change in Material’s WDR after One Shot Hohlraum Wall MaterialsWDREOL Inventory m 3 Tons Gold/Gadolinium (ref.) 2 x Gold Tungsten 2 x Lead 2 x Mercury 5 x Tantalum Lead/Tantalum/Cesium 1 x Mercury/Tungsten/Cesium 2 x Lead/Hafnium 8 x Hafnium 3 x Solid Kr Solid Xe 2 x Without recycling, all materials qualify as Class C (or A) LLW after one shot

12 Limit Exposure Time or Cooling Period to Control WDR WDR reported at 100 y after exposure using Fetter’s limits, except for Xe (NRC) Recommendations: –Gd generates HLW after 2.5 s (10 pulses)  Do not recycle Gd unless on-line clean-up system removes all Tb –W, Ta and Xe are Class C EOL even with no cooling period or clean-up system –For other materials : Limit exposure time to years for no cooling period, or Extend cooling period to days and recycle for 47 y of operation

13 On-line removal of transmutation products prolongs exposure time and shortens cooling period further but generates cup(s) of HLW Use of Cooling Period to Control WDR is Preferred to Lower EOL Inventory Maximum Total Exposure Inventory Time EOL (m 3 ) Au5.9 y0.1 W47 y0.01 Pb6 y0.1 Hg6 y0.1 Ta47 y0.01 Pb/Ta/Cs9.5 y0.06 Hg/W/Cs19 y0.04 Pb/Hf6.4 y0.09 Hf35 y0.02 Solid Kr0.7 y0.8 Solid Xe47 y0.01 _____________ * No cooling period. No transmutations removal Minimum Total Cooling Inventory Period EOL (m 3 ) Au8.2 d0.03 W00.01 Pb13 d0.06 Hg5 d0.03 Ta00.01 Pb/Ta/Cs7.5 d0.04 Hg/W/Cs3 d0.02 Pb/Hf11.5 d0.06 Hf0.6 d0.02 Solid Kr250 d0.8 Solid Xe00.01 _____________ # 47 y of operation. No transmutations removal

14 All Materials Must Meet Recycling Dose Limits Hands-on limit *# : without ALARA principle 10  Sv/h with ALARA principle 1  Sv/h Conservative Remote handling limit *## 10 mSv/h Advanced Remote Handling Limit Sv/h (recommended for ARIES) ____________________________________ * Ref: D. Petti et al., “Safety Analysis of Initiating Events”, ARIES E-meeting, Oct 17, Same as Japanese and European limits # Based on 20 mSv annual limit for 2000 h/y worker ## Based on arbitrary factor of 1000 above HO limit + For fission waste, per N. Taylor. On-going EU recycling study will develop RH limit for fusion waste

15 Recycling Dose Only Pb can meet HO limit (1  Sv/h) with long cooling period (~2 y) All materials meet advanced RH limit ( 3000 Sv/h) with <18 d cooling period On-line removal of transmutation products shortens cooling period

16 Recommended Cooling Period to Meet Both WDR and Dose Requirements # Cooling Period Cooling Period Recommended for WDR < 1 for Dose < 3000 Sv/h Cooling Period Au/Gd> 2 y9.5 dNA * Au8.2 d12.2 d12.2 d W06.2 d6.2 d Pb13 d< 1 d13 d Hg5 d < 1 d5 d Ta01 d1 d Pb/Ta/Cs7.5 d17.2 d17.2 d Hg/W/Cs3 d17.5 d17.5 d Pb/Hf11.5 d < 1 d11.5 d Hf0.6 d1.5 d1.5 d Solid Kr250 d4.5 d250 d Solid Xe06.5 d6.5 d _____________ # 47 y of operation. No transmutation removal * Insignificant inventory reduction for cooling period exceeding 2 y. On-line removal of transmutation products shortens cooling period further and may allow recycling of Gd

17 WDR * Dose # Au/Gd (50:50) 158 Tb 196 Au Au 192n Ir, 194 Hg 196 Au W 186m Re, 178n Hf 184 Re Pb 208 Bi, 202 Pb 203 Pb, 202 Tl Hg 192n Ir, 194 Hg 202 Tl, 196 Au, 203 Hg Ta 178n Hf 182 Ta, 179n Hf Pb/Ta/Cs (45:20:35) 208 Bi, 202 Pb 132 Cs Hg/W/Cs (45:20:35) 192n Ir, 194 Hg 132 Cs, 203 Pb, 202 Tl Pb/Hf (70:30) 208 Bi, 202 Pb 175 Hf Hf 178n Hf **175 Hf, 179n Hf **, 179 Lu Kr 81 Kr (gas) 84 Rb, 82 Br Xe 129 I, 135 Cs, 137 Cs 134 Cs, 132 Cs, 127 Xe (gas) In some cases, same elements contribute to both WDR and dose Efficient on-line clean-up system could remove almost all radioisotopes _______________ * 47 y of operation with no cooling period. No transmutation removal # Contributors at recommended cooling period for dose. 47 y of operation. No transmutation removal ** Difficult to separate Main Contributors to WDR and Dose

18 Disposal of Radioactive Kr & Xe Gases (valid also for chamber buffer gases) Filter out solid transmutation products using cold traps, per Sze (UCSD) Use laser-based isotope separation system for gases and solids, per Waganer (Boeing) [ Ref: Prometheus Report, DOE/ER-54101, P (1992)] Store gases in glass spheres, per Nikroo (GA): –Heat up glass shells –Fill out shells with gases –Cool down to trap gases inside shells –Store for future use or dispose in repositories Store Kr in hydrides, per Malang (FZK): –Heat up hydrides –Allow Kr to permeate through hydrides –Cool down hydrides –Store for future use or dispose in repositories

19 Conclusions Hohlraum walls represent small waste stream for IFE (< 1% of total nuclear island waste)  recycling is not a must unless materials have cost/resources problems One-shot use of hohlraum generates 43 m 3 of very low waste (Class A) Recycling introduces activation problems, adds complexity, and mandates remote handling (costly) in target Fab WDR and recycling dose are most restrictive factors in recycling process Three potential solutions could solve recycling problems: efficient transmutation removal system, limited exposure time, and controlled cooling period Highly efficient on-line clean-up system removes most transmutation products and allow recycling of all materials In absence of efficient system, exclude Gd for generating HLW after 10 pulses and use other materials with 2-8% penalty in driver’s cost and small hit in cost of electricity (< 5%) Attractive scheme would combine efficient clean-up system and controlled cooling period. Additional cost and complexity should be addresses. Clean-up system will filter out cup(s) of HLW that could be burned in special modules to avoid deep geological burial*and meet ARIES Class C-only waste requirement ________________ * L. El-Guebaly, “Need for Special Burning Modules in Fusion Devices to Transmute Fusion High Level Waste”, To be published in April 2002.