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Fluor to serve as EPC contractor for Centrus’s Piketon plant expansion
The HALEU cascade at the American Centrifuge Plant in Piketon, Ohio. (Photo: Centrus Energy)
American Centrifuge Operating, a subsidiary of Centrus Energy Corp., has formed a multiyear strategic collaboration with Fluor Corporation in which Fluor will serve as the engineering, procurement, and construction (EPC) contractor for Centrus’s expansion of its uranium enrichment facility in Piketon, Ohio. Fluor will lead the engineering and design aspects of the American Centrifuge Plant’s expansion, manage the supply chain and procurement of key materials and services, oversee construction at the site, and support the commissioning of new capacity.
Kazuhiro Sawa, Tsutomu Tobita
Nuclear Technology | Volume 142 | Number 3 | June 2003 | Pages 250-259
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT03-A3387
Articles are hosted by Taylor and Francis Online.
In current high-temperature gas-cooled reactors (HTGRs), Tri-isotropic (TRISO)-coated fuel particles are employed as fuel. In safety design of the HTGR fuels, it is important to retain fission products within particles so that their release to primary coolant does not exceed an acceptable level. From this point of view, the basic design criteria for the fuel are to minimize the failure fraction of as-fabricated fuel coating layers and to prevent significant additional fuel failures during operation. The maximum burnup of the first-loading fuel of the High Temperature Engineering Test Reactor (HTTR) is limited to 3.6%FIMA (% fission per initial metallic atom) to certify its integrity during the operation. In order to investigate fuel behavior under extended burnup condition, irradiation tests were performed. The irradiation was carried out as HRB-22 and 91F-1A capsule irradiation tests. The fuel for the irradiation tests was called extended burnup fuel, whose target burnup and fast neutron fluence were higher than those of the first-loading fuel of the HTTR. In order to keep fuel integrity up to over 5%FIMA, the thickness of buffer and SiC layers of fuel particle were increased. The fuel compacts were irradiated in the HRB-22 and the 91F-1A capsules at the High Flux Isotope Reactor of Oak Ridge National Laboratory and at the Japan Materials Testing Reactor of the Japan Atomic Energy Research Institute, respectively. The comparison of measured and calculated release rate-to-birth rate ratios showed that there were additional failures in both irradiation tests. A pressure vessel failure model analysis showed that no tensile stresses acted on the SiC layers even at the end of irradiation and no pressure vessel failure occurred in the intact particles even in a particle with thin buffer layer with failed OPyC layer. The presumed failure mechanisms are additional through-coatings failure of as-fabricated SiC-failed particles or an excessive increase of internal pressure by the accelerated irradiation. Further study is needed to clarify the failure mechanism.