Spark Plasma Sintering (SPS) Update for the Fuel Conversion Effort at the Transient Reactor Test Facility
Over the lifetime of the Transient Reactor Test Facility (TREAT) reactor from 1959 to 1994, a series of historical tests disclosed certain material specific requisites for irradiation testing variables resulted in negligible structural damage after exposure to the reactor and multiple experiments. Comparable fuel design, material testing, and qualifications needs to occur for the high-enriched uranium (HEU) to low enriched uranium (LEU) fuel conversion (<20% U235) of TREAT. This includes, retaining a uniform precipitate dispersion of fueled UO2 micron-size particles throughout a graphite-moderating matrix, where high-density graphite is in direct contact with the fuel and acts as a moderator. On that note, the design of future LEU reactor TREAT fuel core will consider the relative sizing and spacing of fuel as well as the retention of graphite in accordance with the expected thermal, neutron, and energy portfolio for future conversion. In light of the above, LEU conversion fuel blocks currently being manufactured must undergo critical materials testing, irradiation, and examination to determine effects on the manufactured replacement fuel blocks at the millimeter to sub-micron size scale. Herein, we will report and update the community on value-added studies focusing on spark plasma sintering as an alternative technique to fabricate high density graphite dispersion fuel.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA)
- DOE Contract Number:
- DE-AC07-05ID14517
- OSTI ID:
- 1632863
- Report Number(s):
- INL/CON-17-43418-Rev000
- Resource Relation:
- Conference: TREAT Annual Progress Meeting, Idaho Falls, 10/16/2017 - 10/19/2017
- Country of Publication:
- United States
- Language:
- English
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