U.S. DEPARTMENT OF ENERGY. Defense Nuclear Nonproliferation FOREIGN RESEARCH REACTOR FUEL PROGRAM

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1 FOREIGN RESEARCH REACTOR FUEL PROGRAM 1

2 M 3 Nuclear Material Removal Programs Remove or dispose of excess weapon-usable nuclear materials located at civilian sites worldwide U.S.-Origin Nuclear Material Removal Program : Remove or dispose of U.S.-origin HEU and LEU from TRIGA and MTR research reactors worldwide. Russian-Origin Nuclear Remove Program: Remove or dispose of Russian-origin nuclear material from research reactors worldwide. Gap Removal: Remove or dispose of vulnerable high risk nuclear materials that are not covered under the Russian-origin and U.S.-origin nuclear material removal programs. U.S. Origin Shipment from South Africa Gap Shipment from Chile 2

3 M 3 Nuclear Material Removal Accomplishments Status: Removed or confirmed the disposition of over 6,000 kilograms of HEU and plutonium Russian-origin: 2,171 kilograms removed/downblended US-origin: 1,309 kilograms removed/downblended Gap-material: 2,251 kilograms removed/downblended Poland Shipment 2010 Enough material for 240 nuclear weapons All HEU has been removed from 30 countries and Taiwan Vietnam Shipment 2013 Serbia Shipment

4 U.S.-Origin Nuclear Removal Objective Goal: Remove or dispose of excess weapon-usable U.S.-origin nuclear materials located at civilian sites worldwide: Reduce and, to the extent possible, eliminate the use of HEU from civilian nuclear applications Disposition LEU spent fuel as an incentive for foreign reactor operators to convert from HEU to LEU fuel Allow time for countries with spent fuel (both HEU and LEU) containing uranium enriched in the United States to resolve their own disposition These efforts result in permanent threat reduction because each kilogram of this dangerous material that is secured and disposed of removes it from possible diversion for malevolent purposes. 4

5 U.S.-Origin Removal Accomplishments Approximately 60 shipments completed 50 via Ocean to East Coast 9,563 spent fuel assemblies, from 32 countries 10 cross-country shipments completed including one west coast shipment 233 casks/7,995 assemblies to SRS 21 casks/1,503 rods to INL 25 casks/65 assemblies to Y-12 5

6 EM Partnership with M3 EM supports the U.S. non-proliferation and highly enriched uranium (HEU) minimization policies led by DOE-NNSA, Office of Materials Management and Minimization (M3) Support M3 efforts to secure and consolidate HEU and plutonium materials to prevent them from falling into the hands of terrorists Disposition of nuclear materials in a manner that renders these nuclear materials non-proliferable EM continues to receive, safely store and securely manage spent nuclear fuel (SNF) via M3 s Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Acceptance Program from research reactors with 41 participating countries All SNF received is consolidated at the Savannah River Site (SRS) and Idaho National Laboratory (INL) o Aluminum clad fuel is stored at SRS o Non-aluminum clad fuel is stored at INL Note: SRS and INL also receive SNF from US domestic research reactors (DRR EM also supports M3 efforts to eliminate other excess high-risk nuclear materials through receipt, storage and disposition of separated plutonium and non U.S.-origin HEU 6

7 SRS Nuclear Materials Management Process FRR & DRR SNF Gap SNF L Basin Aluminum Clad SNF Defense Waste Processing Facility H Canyon / HB-Line Canada Liquid Target Material Excess Pu Consolidation High Activity Liquid Waste Gap Pu K Area Storage Non-MOXable Pu (AFS-2) MOXable Pu WIPP Non MOXable Pu & Transuranic Waste WIPP 7

8 Savannah River Site, South Carolina All SNF in wet storage (L-Basin) Implementing Augmented Monitoring & Condition Assessment Program in addition to existing maintenance activities Continue to receive FRR (until 2019) and DRR Aluminum-clad SNF only Includes High Flux Isotope Reactor (HFIR) Fuel temporarily suspended due to storage capacity Wet storage at L- Basin HFIR Fuel (Office of Science) 8

9 Spent Fuel Processing in H-Canyon Per 2013 Amended Record of Decision, continuing processing of aluminum-clad SNF - Frees up storage capacity in L-Basin to support FRR and DRR receipts - Non-proliferation benefits by converting separated HEU to low enriched uranium (LEU) for use in commercial reactors - Expected to produce up to 40 MT of LEU 9

10 INTEC SNF Facilities Fort St. Vrain, Colorado 10

11 Idaho National Laboratory, Idaho (cont) Continue to receive FRR (until 2019) and DRR Non-aluminum clad fuel (primarily TRIGA fuel) Currently all shipments into Idaho are suspended until treatment of remaining sodium bearing liquid waste is completed (missed Settlement Agreement milestone) Cask Pad 11

12 End of US-Origin Removal Program In accordance with the program authorization, the program will terminate in 2019: Stop irradiation by 12 May 2016 All shipments completed by 12 May 2019 DOE does not plan to extend the program If you are interested in participating in the program, please contact DOE Jeff Galan, Program Manager Off: (803) Mob: (240)

13 THANK YOU FOR YOUR ATTENTION 13