Fynan, Mar, Sirajuddin Sodium-Cooled Fast Reactor First Preliminary Report: Fuel Composition Analysis.

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Presentation transcript:

Fynan, Mar, Sirajuddin Sodium-Cooled Fast Reactor First Preliminary Report: Fuel Composition Analysis

Fynan, Mar, Sirajuddin Base Core Driver Fuel: Weapons Grade Plutonium Host Fuel: Natural Uranium

Fynan, Mar, Sirajuddin Comparison to Reference Core

Fynan, Mar, Sirajuddin TRU Transmutation Optimization Two approaches: Host Fuel Modification Thorium Host Fuel Enriched Uranium Host Fuel (Reactor Grade) Introduction of Burnable Poisons

Fynan, Mar, Sirajuddin Host Fuel Modification Natural thorium host fuel transmutes over double that of the natural uranium host fuel Enriched Uranium unsuitable as a host fuel

Fynan, Mar, Sirajuddin Burnable Poisons Poison impact on transmutation potential relatively low, and insensitive to poison positioning

Fynan, Mar, Sirajuddin Reactor Grade Plutonium Driver Fuel Loss of transmutation efficiency with introduction of BP

Fynan, Mar, Sirajuddin Recycled LWR Spent Fuel Driver Lower reactivity swing than WGPu driver fuel core

Fynan, Mar, Sirajuddin Power Density Comparisons

Fynan, Mar, Sirajuddin Power Density Comparisons Uranium host fuel yielded highest power density ( W/cc) Average difference between max power between uranium host and thorium host W/cc Compositions with WGPu driver gave highest power densities BP introduction did not detriment power out significantly W/cc difference on average Maximum power density independent of BP positioning

Fynan, Mar, Sirajuddin Power Distribution Analysis: Axial

Fynan, Mar, Sirajuddin Power Distribution Analysis: Axial Cosine shape, with maximum at center of fuel pin Power fluctuations are small between: Differenet BP positioning Uranium and thorium fuel compositions

Fynan, Mar, Sirajuddin Power Distribution Analysis: Radial

Fynan, Mar, Sirajuddin Power Distribution Analysis: Radial Power peaks at center of core Decrease occurs due to configuration of low and high energy drivers Power increases near outer core due to increased flux from reflectors

Fynan, Mar, Sirajuddin Future Prospects

Fynan, Mar, Sirajuddin References [1] N.J. Nicholas, K.L. Coop and R.J. Estep, Capability and Limitation Study of DDT Passive-Active Neutron Waste Assay Instrument (Los Alamos: Los Alamos National Laboratory, LA MS, 1992). [2] Plutonium Fuel: An Assesment (Paris:OECD/NEA,1989) [3] Hill RN, Wade DC, Liaw JR, and Fujita EK, Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle. Nuclear Science and Engineering: 121, (1995) [4] H. Conde, Introduction to ADS for Waste Incineration and Energy Production.(Uppsala University, SE Uppsala, Sweden) Rebus3 for multi-group diffusion analysis Argonne National Laboratory MC2 for lattice physics calculations Argonne National Laborator