Test Design Description and Postirradiation Examination of the HT9 Advanced Driver Fuel Test (X430)

Technical Report · Tue Mar 01 04:00:00 EST 1994

DOI:https://doi.org/10.2172/10199805· OSTI ID:10199805

Hayes, S L; Crawford, D C; Pahl, R G

The HT9 Advanced Driver Fuel Test, subassembly X430 (later reconstituted into X430A and X4308), was initiated to obtain fuel performance data for a fuel element design similar to that envisioned for a PRISM-type advanced liquid metal reactor. HT9 cladding of 0.290-in. diameter and 13.5- in. long fuel slugs of 0.225-in. diameter were employed. Irradiation in EBR-II was performed to peak burnups of 12.0 at.% for U-10Zr, 11.9 at.% for U-19Pu-10Zr, and 6.6 at.% for both U-22Pu-10Zr and U-26Pu-10Zr fueled elements. This report contains the X430 test design description and the results of the postirradiation examinations performed to date; a calculated thermal history for the test is also included. Measurements of axial fuel swelling, cladding diametral strain, and fission gas release indicate that the performance of these larger-diameter, higher-Pu fuel elements is consistent with previous data for smaller-diameter, lower-Pu fuel, such as subassembly X425.

• Research Organization: Argonne National Lab., Idaho Falls, ID (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10199805
• Report Number(s): ANL-IFR--225; ON: TI94020637
• Country of Publication: United States
• Language: English

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