1. ADS Activities at Argonne National Laboratory Yousry Gohar Argonne National Laboratory Proton Accelerators for Science and Innovation Workshop FERMILAB, Batavia, Illinois FERMILAB, Batavia, Illinois January 12-14, 2012

2. ADS Activities at Argonne National Laboratory Argonne National Laboratory has three main ADS activities for different missions: I. Develop, design, and construct an experimental neutron source facility consists of electron accelerator driven subcritical system II. Study the physics and develop control methods for future ADS using zero power systems III. Develop ADS concept for disposing of US spent nuclear fuel inventory with minimum extrapolation for the current technologies

3. Experimental Neutron Source Facility Development, Design, and Construction  US Government is supporting the construction of an experimental neutron source facility at Kharkov, Ukraine.  Argonne National Laboratory of USA is collaborating with National Science Center “Kharkov Institute of Physics & Technology” of Ukraine to develop, design, and construct this facility.  The facility consists of an electron accelerator driven subcritical system utilizing low enriched uranium oxide fuel with water coolant and beryllium-carbon reflector.  An electron accelerator is utilized for generating the neutron source driving the subcritical assembly. The accelerator power is 100 KW beam using 100 MeV electrons.  The target material is tungsten or natural uranium cooled with water coolant.

4. Experimental Neutron Source Facility Facility Objectives  Provide capabilities for performing basic and applied research using neutrons  Perform physics and material experiments inside the subcritical assembly and neutron experiments using the radial neutron beam ports of the subcritical assembly  Produce medical isotopes and provide neutron source for performing neutron therapy procedures  Support the Ukraine nuclear power industry by providing the capabilities to train young specialists

5. KIPT Experimental Neutron Source Facility Facility General View

6. KIPT Experimental Neutron Source Facility Overview

7. KIPT Subcritical Assembly Overview

8. General View inside the Subcritical Assembly

9. Target Assembly for generating neutrons  Tungsten and uranium are the target materials for generating neutrons. Water coolant and aluminum alloy structure are used.  The target assembly configurations were developed to accommodate square beam cross sections and hexagonal fuel geometry.  The accelerator power is 100 KW using 100 MeV electrons.  Conservative design rules were used for the target assembly design.

10. Uranium Target Configuration

11. Electron Beam and Target Geometry Parameters Channel Number Tungsten Target Uranium Target Water Channel Thickness mm Target Plate Thickness mm Clad Thickness mm Water Channel Thickness mm Target Plate Thickness mm Clad Thickness mm 01.0 1.0 11.753.00.25x21.753.0 0.7 ×2 21.753.00.25x21.752.5 0.95 ×2 31.753.00.25x21.752.5 41.754.00.25x21.752.5 51.754.00.25x21.753.0 0.7 ×2 61.756.00.25x21.753.0 71.010.00.25x21.754.0 8 1.755.0 9 1.757.0 10 1.7510.0 11 1.014.0 Total12.533.03.519.556.516.9 Beam Power:100 kW Distribution:Uniform Electron Energy:100 MeV Beam Size:64 × 64 mm Target Plate:66 × 66 mm Coolant:Water Pressure:5 atm Inlet Temperature:20.0 C Outlet Temperature:24.1C

12. Power and Temperature Distributions of the Tungsten Target - 1 Power W/cm 3

13. Power and Temperature Distributions of the Tungsten Target - 2 Power W/cm 3 Neutron Source Intensity Tungsten 1.88x1014 n/s Uranium 3.06x1014 n/s

14. WWR-M2 LEU Fuel Design

15. Configuration, Neutron Flux and Energy Deposition for the KIPT ENSF utilizing Tungsten and Uranium Target Driven by 100 kw/100 MeV electron beam Target# of FAsk-eff Flux along the core (n/cm 2 ·s) Flux along the target (n/cm 2 ·s) Energy Deposited in the target (KW) Energy Deposited in the core (KW) Energy Deposited in the reflector (KW) Total Energy deposition (KW) W42 0.97855 (± 0.00012) 1.162e+13 ( ± 0.36 %) 1.353e+13 ( ± 0.33 %) 84.19 ( ± 0.01 %) 134.77 ( ± 0.35 %) 8.10 ( ± 0.22 %) 227.06 U37 0.97547 (± 0.00012) 1.965+13 ( ± 0.26 %) 2.470e+13 ( ± 0.25 %) 88.42 ( ± 0.01 %) 196.89 ( ± 0.35 %) 11.57 ( ± 0.19 %) 296.89

16. Subcritical Assembly Geometrical Model Beryllium Assemblies Graphite Reflector Horizontal Cross Section ViewVertical Cross Section View

17. Radial and Axial Energy Deposition for Uranium Target with 37 Fuel assemblies and 100KW/100MeV Electrons (KW/cm 3 )

18. Radial and Axial Total Neutron Flux Distributions Using Uranium Target with 100KW/100MeV Electrons (n/cm 2. s)

19. Experimental Neutron Source Facility Summary The experimental neutron source facility has been successfully developed and it is under construction to start April 2014. The experimental neutron source facility has been successfully developed and it is under construction to start April 2014. The facility has a subcritical assembly and it is driven by 100 KW electron accelerator. The electron energy is 100 MeV. The facility has a subcritical assembly and it is driven by 100 KW electron accelerator. The electron energy is 100 MeV. The subcritical assembly uses low enriched uranium fuel, water coolant, beryllium- graphite reflector. The subcritical assembly uses low enriched uranium fuel, water coolant, beryllium- graphite reflector. The design satisfies the facility objectives and it has flexibility for future new functions. The design satisfies the facility objectives and it has flexibility for future new functions.

20. YALINA Facility Collaborative Studies Argonne National Laboratory (ANL) of USA and the Joint Institute for Power and Nuclear Research (JIPNR) SOSNY of Belarus have conducted a joint experimental and analytical ADS research using YALINA-facilities. Argonne National Laboratory (ANL) of USA and the Joint Institute for Power and Nuclear Research (JIPNR) SOSNY of Belarus have conducted a joint experimental and analytical ADS research using YALINA-facilities. ANL coordinated the participation of the ADS international community in the research activity of the YALINA-Booster through the International Atomic Energy Agency (IAEA), ten countries participated. ANL coordinated the participation of the ADS international community in the research activity of the YALINA-Booster through the International Atomic Energy Agency (IAEA), ten countries participated.

21. YALINA-Booster Subcritical Assembly YALINA-Booster assembly front view

22. YALINA Thermal Subcritical Assembly Air Polyethylene Organic Glass Sheet Uranium Graphite Stainless Steel Copper Water

23. ANL–JIPNR YALINA Facility Cooperation Different activities have been completed under the collberation between ANL and JIPNR: Developed detailed material and geometrical specifications of the YALINA-facilities for performing physics analyses. Developed detailed material and geometrical specifications of the YALINA-facilities for performing physics analyses. Developed detailed three dimensional geometrical models for the Monte Carlo and the deterministic analyses. Developed detailed three dimensional geometrical models for the Monte Carlo and the deterministic analyses. Developed new time dependent methods for analyzing the pulsed neutron source experiments. Developed new time dependent methods for analyzing the pulsed neutron source experiments. Utilized the most advanced nuclear data libraries (ENDF/B- VII and JEF3.1) for performing the analyses. Utilized the most advanced nuclear data libraries (ENDF/B- VII and JEF3.1) for performing the analyses. Simulated all the experiments using the most advanced radiation transport computer programs and the analytical results were compared successfully with the experimental measurements. Simulated all the experiments using the most advanced radiation transport computer programs and the analytical results were compared successfully with the experimental measurements.

24. YALINA-Booster Analyses Monte Carlo Analyses Detailed geometrical models were generated for MCNP, MCNPX, MONK analyses. Criticality and neutron source (Cf, D-D, and D-T) analyses were performed using data libraries based ENDF/B-VI.8, ENDF/B-VII.0, and JEF 3.1. YALINA-Booster, and thermal configurations with different number of EK-10 fuel rods were examined. K eff, k s, reaction rate distributions (He-3(n,p), U-235 fission, In-115(n,γ), Mn-55(n,γ), Au-197(n,γ)), spatial neutron flux distributions, neutron, and Kinetic parameters were measured and calculated. Time dependent neutron flux and reaction rates were measured and calculated for D-D and D-T neutron source pulses.

25. YALINA Booster Isometric View of the Monte Carlo Model ModelModel

26. YALINA Booster X-Y Cross Section of the Monte Carlo Model

27. YALINA Booster Y-Z Cross Section of the Monte Carlo Model at X = 0.87

28. YALINA Booster Comparison of the analytical and the experimental results of the configuration with the 90% and the 36% enriched uranium fuels in the fast zone and 1141 EK-10 fuel pins in the thermal zone using Monte Carlo simulations Channel ρ / β eff ($) β eff K eff Exp.  K eff (Exp. – Cal.) MONK MCNPX EC1 -3.3627 ± 0.00770.006950.9772 ± 0.0022-0.0002-0.0017 EC2 -3.4088 ± 0.0069 0.006950.9769 ± 0.0020-0.0005-0.0020 EC3 -3.5198 ± 0.0081 0.006950.9761 ± 0.0022-0.0013-0.0028

29. YALINA Booster Comparison of the analytical and the experimental results of the configuration with the 90% and the 36% enriched uranium fuels in the fast zone and 1141 EK-10 fuel pins in the thermal zone using ERANOS with JEF3.1 nuclear data files simulating a D-D pulsed neutron source measured with He-3 detector

30. YALINA Booster 3 He Detector Response Calculated by MCNP Compared to the Experimental Measurements

31. Total Neutron Flux Map of the YALINA-Booster Configuration with 21% Enriched Uranium Oxide Fuel in the Booster Zone and 14.1 MeV External Neutron Source

32. YALINA Facilities Collaborative Studies Summary ANL and JIPNR have successfully collaborated on studying the physics of accelerator driven systems by performing joint analytical and experimental research programs utilizing YALINA facilities. ANL and JIPNR have successfully collaborated on studying the physics of accelerator driven systems by performing joint analytical and experimental research programs utilizing YALINA facilities. The analytical and the experimental results have been successfully compared. The obtained comparisons are quite satisfactory and valuable results have been obtained for future accelerator driven systems. The analytical and the experimental results have been successfully compared. The obtained comparisons are quite satisfactory and valuable results have been obtained for future accelerator driven systems. New analytical techniques and computational procedures have been successfully developed to analyze accelerator driven systems. New analytical techniques and computational procedures have been successfully developed to analyze accelerator driven systems.

33. Accelerator Driven Systems Concept for Disposing of Spent Nuclear Fuels Objective: Develop a near term approach for disposing of USA spent nuclear fuel inventory using accelerator driven subcritical systems Guidelines: Utilize current technologies with minimum extrapolation,Utilize current technologies with minimum extrapolation, Avoid multi-processing steps of the fuel materials,Avoid multi-processing steps of the fuel materials, Operate the systems at the peak power and produce energy to cover the system cost as much as possible, andOperate the systems at the peak power and produce energy to cover the system cost as much as possible, and Minimize the required number of the accelerator driven systemsMinimize the required number of the accelerator driven systems

34. Current USA Nuclear Energy Production At present, the United States has 104 nuclear reactors generating electricity. At present, the United States has 104 nuclear reactors generating electricity. The produced electricity represents about 20% of the total production and more than 70% of the carbon emission-free electricity. The produced electricity represents about 20% of the total production and more than 70% of the carbon emission-free electricity. These reactors have the highest operating availability of more than 90% of all the present electric power sources; geothermal 75%, coal 73%, wind 27%, and solar 19%. These reactors have the highest operating availability of more than 90% of all the present electric power sources; geothermal 75%, coal 73%, wind 27%, and solar 19%. At the end of the lifetimes of the current operating nuclear power plants, the accumulated spent nuclear fuel inventory is ~120,000 metric tons, mostly U-238. At the end of the lifetimes of the current operating nuclear power plants, the accumulated spent nuclear fuel inventory is ~120,000 metric tons, mostly U-238.

35. US Spent Nuclear Fuels Inventory At present, ~60,000 metric tons of spent nuclear fuels are stored. At present, ~60,000 metric tons of spent nuclear fuels are stored. The current accumulation rate is ~2000 metric tons per year. The current accumulation rate is ~2000 metric tons per year. By the year 2015, the expected inventory is ~70,000 metric tons. By the year 2015, the expected inventory is ~70,000 metric tons. The 70,000 metric tons after 25 years of cooling time consists of: The 70,000 metric tons after 25 years of cooling time consists of: o ~96% enriched uranium – can be recycled for use in future nuclear power plants o ~3% fission products – short lived isotopes can be stored for ~300 years to reduce their radiotoxicity by decay to that of the natural uranium ore o ~1% transuranics - ~700 metric tons (DOE/EIS-0250 Report) − Plutonium is ~585 metric tons – a fraction can be used with the minor actinides in ADS and the balance as MOX fuel for thermal and fast power reactors − Minor actinides can be utilized in ADS,~115 metric tons (Np, AM, Cm)

36. Accelerator Driven System for Disposing of Spent Nuclear Fuels

37. Accelerator Driven Systems Parameters for Disposing of Spent Nuclear Fuels The system power is 3 GW th, which can produce ~ 1 GW e similar to a nuclear power plant. The system power is 3 GW th, which can produce ~ 1 GW e similar to a nuclear power plant. The effective neutron multiplication factor of the subcritical is 0.98. The effective neutron multiplication factor of the subcritical is 0.98. The required proton beam power for this system is ~25 MW. The required proton beam power for this system is ~25 MW. Lead bismuth eutectic or liquid lead is the fuel carrier (molten salt is backup option) with transuranics without uranium. Lead bismuth eutectic or liquid lead is the fuel carrier (molten salt is backup option) with transuranics without uranium. Low plutonium concentration is used with the minor actinides to achieve the required effective neutron multiplication factor. Low plutonium concentration is used with the minor actinides to achieve the required effective neutron multiplication factor. The physics analyses show the required plutonium concentration in the transuranic is ~30%. The physics analyses show the required plutonium concentration in the transuranic is ~30%. For the 70,000 tons of spent nuclear fuels by 2015, the total minor actinides inventory is ~115 tons. Four accelerator driven systems can consume 150 tons (115 tons MA +35 tons Pu) for disposing of the US spent nuclear fuel inventory. For the 70,000 tons of spent nuclear fuels by 2015, the total minor actinides inventory is ~115 tons. Four accelerator driven systems can consume 150 tons (115 tons MA +35 tons Pu) for disposing of the US spent nuclear fuel inventory.

38. System Characteristics Liquid metal targets are selected to simplify the target design, to enhance the target performance including its lifetime, and to relax some of the reliability requirements for the accelerator. Liquid metal targets are selected to simplify the target design, to enhance the target performance including its lifetime, and to relax some of the reliability requirements for the accelerator. Lead-bismuth eutectic and liquid lead are the main target candidates for this application. Lead-bismuth eutectic and liquid lead are the main target candidates for this application. Subcritical assemblies with solid fuel materials are considered to utilize the gained experience from the fission power reactors. Such choice requires the development of new fuel designs, multi reprocessing steps, and additional fuel reprocessing plants. These characteristics require more R&D, time&cost, and time to dispose of the spent nuclear fuels. Subcritical assemblies with solid fuel materials are considered to utilize the gained experience from the fission power reactors. Such choice requires the development of new fuel designs, multi reprocessing steps, and additional fuel reprocessing plants. These characteristics require more R&D, time&cost, and time to dispose of the spent nuclear fuels. Mobile fuel forms with transuranic materials and without uranium are considered to avoid the issues of the solid fuel forms and to achieve the objective of eliminating the transuranics and most of the long-lived fission products of the spent nuclear fuels. Mobile fuel forms with transuranic materials and without uranium are considered to avoid the issues of the solid fuel forms and to achieve the objective of eliminating the transuranics and most of the long-lived fission products of the spent nuclear fuels.

39. System Characteristics (continued) The mobile fuel form has a closed material cycle, which is highly proliferation resistance. The liquid carrier has the fission products mixed with the transuranics all the time. The mobile fuel form has a closed material cycle, which is highly proliferation resistance. The liquid carrier has the fission products mixed with the transuranics all the time. A significant fraction of the long-lived fission products are transmuted during the power generation process. A significant fraction of the long-lived fission products are transmuted during the power generation process. The continuous feed of the transuranics during the operation reduces significantly the produced radioactive waste and the needed capacity for a long-term geological storage. The continuous feed of the transuranics during the operation reduces significantly the produced radioactive waste and the needed capacity for a long-term geological storage. The successful operation of fission reactors with lead bismuth eutectic coolant, spallation targets, and different lead-bismuth eutectic and liquid lead loops in Russia, Europe, India, Japan, Korea, and USA provides the technical experiences to proceed with such material. The successful operation of fission reactors with lead bismuth eutectic coolant, spallation targets, and different lead-bismuth eutectic and liquid lead loops in Russia, Europe, India, Japan, Korea, and USA provides the technical experiences to proceed with such material.

40. Beam Power Requirements as a Function of the Proton Energy with Lead Bismuth Target for 3 GW th System 0.95 K eff 0.98 K eff

41. Subcritical Assembly Concept Characteristics Mobile fuel forms: Mobile fuel forms:  Eliminate the minor actinides without the need for extra fuel processing steps.  Relax some of the reliability requirements for the accelerators,  Remove fission gases during operation,  Reduce the required R&D, the deployment time, and the total cost.  Fast system, which provides neutronics advantages relative to thermal systems: – Efficient neutron utilization, – Good neutron economy in the presence of fission products, – Lower probabilities for generating higher actinides.  Achieve the proposed objective and permit controlling the output power without changing the proton beam power

42. Subcritical Configuration with Mobile Fuel Target Proton beam power25 MW Proton energy1 GeV Target materialLead Bismuth Eutectic Proton beam radius19.5 cm Target length70 cm Target radius including I/O manifolds 35 cm Subcritical Outer radius~150 cm Height~300 cm Fuel carrier/coolantLead Bismuth Eutectic Actinides oxide concentration5.0, 7.0, or 10.0% Plutonium concentration in the actinides for the above three actinides concentrations35.7, 27.2, or 20.0%

43. K eff and ADS power from 25MW/1GeV proton beam and 7% actinides concentration in the lead bismuth eutectic as a function of the plutonium concentration

44. k eff at each fuel burnup time step for the ADS system with 5%(35.7% Pu), 7%(27.2% Pu)or 10%(20% Pu) actinides concentration in the lead bismuth eutectic

45. Actinides, plutonium, and minor actinides annual transmutation rates for the ADS system (3MW th ) with 5%(35.7% Pu), 7%(27.2 Pu)% or 10%(20% Pu) actinides concentration in the lead bismuth eutectic

46. Long lived fission products transmutation during the first 10 years of ADS operation with 7% actinides (27.2% Pu) in the lead bismuth eutectic

47. Summary Accelerator driven systems can be utilized to dispose of the USA spent nuclear fuel inventory. These systems have unique attractive features: Utilize limited resources to complete the mission Utilize limited resources to complete the mission Require limited extrapolation of the current technologies Require limited extrapolation of the current technologies Need short term R&D programs Need short term R&D programs Can be deployed in the near term Can be deployed in the near term Extend the uranium resource for energy production Extend the uranium resource for energy production Enhance the proliferation resistance of the nuclear materials Enhance the proliferation resistance of the nuclear materials Reduce the generated radioactive waste by avoiding multi- processing steps Reduce the generated radioactive waste by avoiding multi- processing steps Compute with the other disposition options Compute with the other disposition options

48. Acknowledgements This work is supported by the U.S. Department of Energy, Office of Global Nuclear Material Threat Reduction (NA213), National Nuclear Security Administration and Argonne National Laboratory Directed Research and Development funds.

49. Fuel compositions for 10 years of operation of the fission blanket with 7% actinides and 27.2% plutonium concentration