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Sodium Cooled Fast Reactor for TRU Recycling. Douglas Fynan, Nathan Mar, David Sirajuddin University of Michigan, Department of Nuclear Engineering and Radiological Sciences 2007. I. Purpose

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Sodium Cooled Fast Reactor for TRU Recycling

Douglas Fynan, Nathan Mar, David Sirajuddin

University of Michigan, Department of Nuclear Engineering and Radiological Sciences 2007

I. Purpose

Stockpiles of plutonium and minor actinides exist in large quantities from nuclear weapons programs, civilian reprocessing programs, and in spent nuclear fuel from light water reactors. Most of this material is destined for geological disposal and poses long term radiological risks. The purpose of the SFR is to transmute plutonium and minor actinides in a proliferation resistant closed fuel cycle while expanding electricity generation, consistent with the goals of GNEP, AFCI, and GEN IV.

IV. Fuel Selection

The SFR core is capable of burning a variety of driver fuel compositions. Four driver fuel types were modeled in the core based on available feedstocks from stockpiles.

Driver Fuel Selections:

  • Weapons Grade Plutonium (WGPu) (94% Pu-239, 6% Pu-240)

  • Reactor Grade Plutonium (RGPu) (60% Pu-239,21% 240 Pu, 14% Pu-241)

  • Recycled Light Water Spent Fuel (RCLW) (51% Pu-239, 24% Pu-240,

    14% Pu-241, 6% Am-241, 4% Np-237)

  • Minor Actinide Enriched (MAE) (29% Pu-239, 13% Pu-240, 28% Am-241, 19% Np237)

    To optimize transmutation of Pu and MAs, thorium was chosen over natural

    uranium as the host fuel to prevent breeding of Pu during the cycle. However, a thorium

    host fuel breeds fissile U-233 over 95% enrichment. The proliferation limit for U-233

    enrichment is 12%. A 75% Th – 25% U host fuel is required to denature U-233 below the

    12% treaty limit at end of cycle.

VI. Burnable Poisons

Burnable poisons were considered as a possible method of reducing the reactivity swing. However, burnable poisons increased the reactivity swing. Criticality was only possible with an increased proportion of driver fuel with respect to the host fuel.

VII. Safety Analysis

Preliminary analyses was performed to ascertain the potential safety performance.

Doppler, volumetric thermal expansion, and void coefficients of reactivity were calculated

to illustrate the inherent safety mechanisms of the SFR design. The positive void

coefficient signifies overmoderated reactor operation; however, this positive coefficient is

offset by both the Doppler coefficient, and the largely negative expansion coefficient of

the fuel allowing for safe operation.

The SFR design comprises a passive safety system with layered heat removal pathways.

The reactor’s response to an accident is immediate scram, followed by heat removal

Through the reactor coolant system, and the power cycle heat exchangers. An,

emergency low-capacity heat removal is also provided in the event of normal power loss.

Finally, the SFR design allows for heat removal through natural circulation in the case of

total power failure. Void coefficients were further examined in the inner, middle, and outer

regions of the core to assess the sensitivity of void formation to reactivity in particular


II. Core Specifications

The reference core is a PRISM Moderate Burner design with the following characteristics:

- 840 MWt power rating

- 310 day cycle length assuming 85% capacity factor

- 46 cm active core height

- 4 m core diameter

- Variable driver fuel composition

VII. Thermal Hydraulics

REBUS-3 calculates power density for five axial regions representing the active core height and five radial regions. The radial power distribution is relatively flat and the axial power distribution is a chopped cosine curve.

Pressure drops across a fuel assembly due to friction and gravity were calculated. Pressure drop due to form loss was estimated from values from references.

Linear power, fuel centerline temperature, and clad temperature were calculated using thermodynamic properties of liquid sodium and the fuel pin materials. Coolant flow rate was estimated from references.

VIII. Economics

The core was found to produce power at nearly double the projected estimate GNEP for generation IV reactors. This was primarily a factor of the high capital cost of constructing a fast reactor, combined with the relatively high cost of reprocessing and market thorium prices. The increased cost of the cores incorporating minor actinide driver fuels reflects the greater cost of fabrication for minor actinide fuels.

V. Core Height

The effects of core height on transmutation and reactivity swing were analyzed. Increasing

active core height softened the neutron spectrum and thereby decreased transmutation

capabilities. The reactivity swing also decreased with core height. Smaller core heights

increased neutron leakage and possessed passive safety advantages.

III. Computational Methods

- REBUS-3 fuel cycle code for equilibrium cycle analysis

- MC2 for lattice physics calculations

We would like to thank to

Professor John C. Lee and

Nick Touran