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1976•Unpublished venueOpen access

Development of a fissile particle for HTGR fuel recycle

F.J. Homan, E.L. Long, T.B. Lindemer, R.L. Beatty, TERRY N. TIEGS

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Abstract

Recycle fissile fuel particles for high-temperature gas-cooled reactors (HTGRs) have been under development since the mid-1960s. Irradiation performance on early UO/sub 2/ and Th/sub 0/./sub 8/U/sub 0/./sub 2/O/sub 2/ kernels is described in this report, and the performance limitations associated with the dense oxide kernels are presented. The development of the new reference fuel kernel, the weak-acid-resin-derived (WAR) UO/sub 2/--UC/sub 2/, is discussed in detail, including an extensive section on the irradiation performance of this fuel in HFIR removable beryllium capsules HRB-7 through -10. The conclusion is reached that the irradiation performance of the WAR fissile fuel kernel is better than that of any coated particle fuel yet tested. Further, the present fissile kernel is adequate for steam cycle HTGRs as well as for many advanced applications such as gas turbine and process heat HTGRs.

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What this paper is about

Recycle fissile fuel particles for high-temperature gas-cooled reactors (HTGRs) have been under development since the mid-1960s. Irradiation performance on early UO/sub 2/ and Th/sub 0/./sub 8/U/sub 0/./sub 2/O/sub 2/ kernels is described in this report, and the performance limitations associated with the dense oxide kernels are presented. The development of the new reference fuel kernel, the weak-acid-resin-derived (WAR) UO/sub 2/--UC/sub 2/, is discussed in detail, including an extensive section on the irradiation performance of this fuel in HFIR removable beryllium capsules HRB-7 through -10. The conclusion is reached that the irradiation performance of the WAR fissile fuel kernel is better than that of any coated particle fuel yet tested. Further, the present fissile kernel is adequate for steam cycle HTGRs as well as for many advanced applications such as gas turbine and process heat HTGRs.

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Available abstract

Recycle fissile fuel particles for high-temperature gas-cooled reactors (HTGRs) have been under development since the mid-1960s. Irradiation performance on early UO/sub 2/ and Th/sub 0/./sub 8/U/sub 0/./sub 2/O/sub 2/ kernels is described in this report, and the performance limitations associated with the dense oxide kernels are presented. The development of the new reference fuel kernel, the weak-acid-resin-derived (WAR) UO/sub 2/--UC/sub 2/, is discussed in detail, including an extensive section on the irradiation performance of this fuel in HFIR removable beryllium capsules HRB-7 through -10. The conclusion is reached that the irradiation performance of the WAR fissile fuel kernel is better than that of any coated particle fuel yet tested. Further, the present fissile kernel is adequate for steam cycle HTGRs as well as for many advanced applications such as gas turbine and process heat HTGRs.

Key concepts: Fissile material, Nuclear engineering, Thorium fuel cycle, Uranium-233, Beryllium, Fuel element failure, Materials science, Nuclear fuel

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