Daniel Wojtaszek 3rd Technical Workshop on Fuel Cycle Simulation

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Presentation transcript:

Fuel Cycle Systems Scenario Analysis: Recycling LWR Plutonium in Thorium Fuelled PT-HWRs Daniel Wojtaszek 3rd Technical Workshop on Fuel Cycle Simulation For best results, please send the large top image to the back layer. Choose “Arrange” then select “Send to Back”. July 11, 2018 UNRESTRICTED

Presentation Outline Objective Pressure Tube Heavy Water Reactor (PT-HWR) Thorium-Plutonium Fuel Concepts Two Stage Fuel Cycle Scenario Implementation Results Conclusion Discussion

Objective To compare the impact of multiple Pu+Th fuel concepts on electricity production in a fuel cycle scenario. Pu from LWR UOX spent fuel -> Pu+Th PT-HWR fuel.

Pressure Tube Heavy Water Reactor Heavy water moderated and cooled. High neutron economy. Current PT-HWRs are fuelled with natural uranium (NU). Online refuelling. Fuel is in the form of cylindrical fuel bundles. (~0.5 m long, ~0.1 m diameter).

Thorium-Plutonium Fuel Concepts Low-PU+Th 3.5% Pu. BU ~23.6 MWd/kg. Core Mass ~60 MTHE. ~550 MWe. Hi-Pu+Th 4.5% Pu. BU ~36.4 MWd/kg. ~492 MWe. Central Graphite Rod To reduce CVR. Depletion Calculations WIMS-AECL. RFSP.

Two Stage Fuel Cycle Scenario Fuel Feed Material Nuclear Fuel Nuclear Power Plant Back-end Storage Separations Pu To ST-2 Sep-A UOX Separation LEU O2 Stage 1 (ST-1) RU NU LWR FP,MA UOX fuel. 4.1% Enriched. 47 MWd/kg. DU Pu to Pu+Th fabrication (FIFO). RU, FPs, and MAs to long-term storage. 1 UOX separations plant. ~3,000 MTHE/year. 25 year lifetime. Begins operating 24 years. into the scenario. Spent UOX fuel. 5 years cooling (minimum). FIFO transfer to separations. 100 LWRs (740 MWe each). 40 year lifetime. All begin operation 1 year into the scenario. Pu From ST-1 Stage 2 (ST-2) Pu + Th O2 Th PT-HWR 1 (Pu,Th)O2 fabrication plant. Sufficient throughput to fuel the entire fleet. 25 year lifetime. Begins operating 1 month after start of separations plant. Interim Storage Fleet size depends on fuel availability. 30 year lifetime. Deployment begins 1 month after start of (Pu,Th)O2 fabrication plant. Rate of deployment depends on fuel fabrication throughput. Long-term Storage

Implementation Scenario implemented using Cyclus fuel cycle simulator. Composition of Pu+Th fuel adjusted by Cycamore fuel fabrication plant based on a starting composition. Size of the PT-HWR fleet was calculated using trial and error simulation runs. Warning! Adjusted composition does not take into account any delay in loading fuel into the reactor. Required calculating the deployment schedule offline based on a guess of the maximum fleet size, and its required fuel fabrication throughput. Th Mine Pu+Th Fabrication Pu+Th Storage PT-HWRs Pu from St. 1

Results 100 LWRs 1080 TWd 34 PT-HWRs 183 TWd 26 PT-HWRs 156 TWd

Results

Results Not FIFO here

Conclusions PT-HWRs are a viable existing technology for utilizing thorium-based fuels with plutonium from LWR spent UOX fuel. The higher-burnup fuel can result in more power generation than that of the low-burnup fuel.

Discussion Calculation of plutonium fraction in fuel taking into account post-fabrication decay. Finding the PT-HWR deployment schedules required repeated complete simulation runs. Improving the ability to couple simulation code with an external facility deployment code. Option of halting or backtracking a simulation when there is insufficient fuel.