Diffusion of uranium in H-451 graphite at 900 to 1400/sup 0/C

Technical Report · Tue Mar 01 04:00:00 EST 1983

DOI:https://doi.org/10.2172/6403945· OSTI ID:6403945

Tallent, O K; Wichner, R P; Towns, R L

In this study, the diffusion of uranium (as a stand-in for plutonium) was investigated under conditions approximating those of the primary coolant loop in a High Temperature Gas-Cooled Reactor (HTGR). Profiles were obtained for uranium penetration in H-451 graphite (from the Great Lakes Carbon Company) at temperatures ranging from 900 to 1400/sup 0/C. Diffusion coefficients are established for UO/sub 2/ and UC/sub 2/.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6403945
• Report Number(s): ORNL/TM-8205; ON: DE83009879
• Country of Publication: United States
• Language: English

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