Core Lifetime and Fuel Utilization in Prismatic VHTR Cores


The Very High Temperature Reactor (VHTR) is a candidate for next generation nuclear plant (NGNP). Accumulated experience with high temperature gas-cooled reactors makes the VHTR the most near-term of all Gen-TV reactors. The VHTR configurations with varying transuranic nuclide (TRU) compositions were analyzed assuming a single-batch core operation. The considered TRU compositions were derived from simulated PWR spent fuel compositions. The 3D models of a prismatic VHTR core were created for use in calculations with the SCALE 5.1 code system. The TRU fuel performance in VHTR prismatic configurations was compared with low enriched uranium (LEU) fueled VHTRs. The analyses showed that TRUs can be effectively employed as VHTR fuel. The TRU-fueled VHTRs exhibited longer core lifetimes and better fuel utilization than the LEU-fueled VHTR.

Meeting Name

International Conference on the Physics of Reactors 2008, PHYSOR 08


Nuclear Engineering and Radiation Science

Document Type

Article - Conference proceedings

Document Version


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© 2008 Curran Associates, All rights reserved.

Publication Date

01 Jan 2008

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