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**,
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.
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Contact: 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
The 2016 International RERTR Meeting (RERTR-2016) will take place in Belgium.
Stay tuned for further details.
The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
For more information visit RERTR-2015.