Post irradiation analysis of RERTR-7A, 7B and RERTR-8 tests
- Argonne National Laboratory, 9700 S. Cass Ave, Argonne, IL 60439 (United States)
- Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-6188 (United States)
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 {approx}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. (author)
- Research Organization:
- Argonne National Laboratory, Nuclear Engineering Division, RERTR Department, Argonne, IL (United States); Czech Technical University, Prague (Czech Republic)
- OSTI ID:
- 21113509
- Report Number(s):
- INIS-US-08N0001; TRN: US08N0031121047
- Resource Relation:
- Conference: RERTR-2007: 29. international meeting on reduced enrichment for research and test reactors, Prague (Czech Republic), 23-27 Sep 2007; Other Information: Country of input: International Atomic Energy Agency (IAEA); Abstract only; Related Information: In: 2007 international meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Abstracts and available papers presented at the meeting, vp.
- Country of Publication:
- United States
- Language:
- English
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