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November 9–12, 2025
Washington, DC|Washington Hilton
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NNSA awards BWXT $1.5B defense fuels contract
The Department of Energy’s National Nuclear Security Administration has awarded BWX Technologies a contract valued at $1.5 billion to build a Domestic Uranium Enrichment Centrifuge Experiment (DUECE) pilot plant in Tennessee in support of the administration’s efforts to build out a domestic supply of unobligated enriched uranium for defense-related nuclear fuel.
Hoai Nam Tran, Yasuyoshi Kato
Nuclear Science and Engineering | Volume 159 | Number 1 | May 2008 | Pages 83-93
Technical Paper | doi.org/10.13182/NSE159-83
Articles are hosted by Taylor and Francis Online.
A new 237Np burning strategy in a supercritical CO2-cooled fast reactor core has been proposed: consuming 237Np as fuel and burnable poison to attain zero burnup reactivity loss. Addition of 237Np at content of 6.5 wt% in fuel engenders nearly zero burnup reactivity loss of 0.02% k/k during 10 yr. The burning rate of 237Np in the core is ~69 kg/yr, which is equivalent to the quantity produced in a year from about 20 light water reactors of equivalent electrical output. The zero burnup reactivity loss enables reduction of the control rod number to half that of a typical sodium-cooled mixed-oxide fuel MONJU core without added 237Np and no need for rod operation with fuel burning to compensate for the burnup reactivity loss. Void reactivity is 0.72% k/kk', which is three-fourths that of a typical Na-cooled core, although 237Np is added and the active core length is elongated to 1.2 m. The power density is reduced to ~20% of that in a Na-cooled core. The hot-spot temperature of cladding is below its maximum permissible temperature of 700°C.