Neutron Sciences 2008 Annual Report - 17.79 MB - Spallation ...
Neutron Sciences 2008 Annual Report - 17.79 MB - Spallation ...
Neutron Sciences 2008 Annual Report - 17.79 MB - Spallation ...
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Technical Parameters–HFIR<br />
Reactor Design Parameters<br />
Core Geometry and Dimensions<br />
Type of core Cylindrical annulus, flux trap<br />
Type of fuel elements Cylindrical annuli (2);<br />
Involute 6061-Al fuel plates<br />
assembled in 6061-Al side plates<br />
Number of plates (inner element) 171<br />
Number of plates (outer element) 369<br />
Fuel plate thickness 0.050 in.<br />
Fuel plate spacing (coolant channel) 0.050 in.<br />
Fuel plate length 24 in.<br />
Length of active fuel 20 in.<br />
Inner fuel element (inside diameter) 5.067 in.<br />
Inner fuel element (outer diameter) 10.590 in.<br />
Outer fuel element (inside diameter) 11.250 in.<br />
Outer fuel element (outer diameter) 17.134 in.<br />
Active fuel volume 50.59 L<br />
Heat transfer surface area 428.8 ft 2<br />
Reactor Core Materials<br />
Fuel U 3 O 8 (93% U 235 ) dispersed in aluminum<br />
Total fuel loading<br />
• Inner fuel element fuel loading<br />
• Outer fuel element fuel loading<br />
Burnable poison (inner element only)<br />
• Inner fuel element poison loading<br />
9.4 kg<br />
2.6 kg<br />
6.8 kg<br />
Reflector Beryllium<br />
Moderator H 2 O<br />
B 4 C dispersed in aluminum<br />
2.8 g<br />
Operating Parameters<br />
Reactor Power<br />
FACTS AND FIGURES <strong>2008</strong> ANNUAL REPORT<br />
Rated power level 85 MW thermal<br />
Average reactor power density 1.64 MW/L<br />
Typical Operating Cycle<br />
Normal operation Steady-state, 85 MW thermal<br />
Length (dependent on core loading) 22–25 days<br />
Maximum Unperturbed Thermal Flux Density in Reflector (Beam Tube Source)<br />
Beginning of cycle 9.35E+14 n/cm 2 s<br />
End of cycle 1.36E+15 n/cm 2 s<br />
Unperturbed Thermal Flux Density at Reflector Outer Diameter<br />
Beginning of cycle 1.19E+14 n/cm 2 s<br />
End of cycle 1.45E+14 n/cm 2 s<br />
Peak Thermal Flux Density<br />
Measured thermal flux in target region 2.5E+15 n/cm 2 s<br />
Reactor Coolant Parameters<br />
Coolant/moderator H 2 O<br />
Inlet temperature 120°<br />
Outlet temperature 156°<br />
Fuel coolant volumetric flow rate 13,000 gal/min<br />
Total coolant volumetric flow rate 16,000 gal/min<br />
Inlet pressure 468 psig<br />
Fuel clad surface temperature 327°<br />
Average heat flux 0.66E+05 Btu/h ft 2<br />
Hot spot heat flux 2.15E+06 Btu/h ft 2<br />
ORNL NEUTRON SCIENCES The Next Generation of Materials Research<br />
91<br />
FACTS AND FIGURES
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