Abstracts and Available Papers Presented at the Meeting
Post Irradiation Analysis of RERTR-7A, 7B, and RERTR-8 Tests
G.L. Hofman, Yeon Soo Kim, A.B. Robinson*, G.V. Shevlyakov**,
Argonne National Laboratory, 9700 S. Cass Ave, Argonne, IL 60439, USA
* Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-6188
** Assigned to RERTR program from RIAR
Addition of 2 wt% or more of silicon in the Al matrix for U-Mo/Al dispersion fuel has proved to be effective in reducing interaction layer growth from the RERTR-7A test to a burnup of ~100 at% U-235 (LEU equivalent). The recent RERTR-8 test also showed the consistent results. In this paper, we present the post irradiation analysis results of these tests. A considerable number of monolithic fuel plates were irradiated in the RERTR-7A and RERTR-8 tests. The post irradiation results of these plates are also included. The RERTR-7B test was a lower burnup test with similar power to the RERTR-7A. In this test, dispersion fuel plates with U-7Mo-1Ti and U- 7Mo-2Zr in Al-5Si were irradiated. The post irradiation results of these plates are also covered.
Abstract in PDF format
- Post Irradiation
Analysis of RERTR-7A, 7B, and RERTR-8 Tests, G.L.
Hofman et al.
[PDF, 16KB, 1 pages]
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Dr. Jordi Roglans-Ribas
Technical Director, RERTR Department
Nuclear Engineering Division – 362
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439
Fax: +1 630-252-5161