Published July 2008 | Version v1
Report Restricted

Post irradiation analysis of RERTR-7A, 7B and RERTR-8 tests

Creators

  • 1. Argonne National Laboratory, 9700 S. Cass Ave, Argonne, IL 60439 (United States)
  • 2. Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-6188 (United States)

Description

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. (author)

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Part of:
2007 international meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Abstracts and available papers presented at the meeting

Additional details

Identifiers

URL
http://www.rertr.anl.gov/RERTR29/;

Publishing Information

Imprint Title
2007 international meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Abstracts and available papers presented at the meeting
Imprint Pagination
vp.
Journal Page Range
1 p.
Report number
INIS-US--08N0001

Conference

Title
29. international meeting on reduced enrichment for research and test reactors
Acronym
RERTR-2007
Dates
23-27 Sep 2007
Place
Prague (Czech Republic)

INIS

Country of Publication
United States
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
39121047
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; DISPERSIONS; FUEL PLATES; IRRADIATION; NUCLEAR FUELS; PLATES; SILICON; URANIUM 235
Descriptors DEC
ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; ELEMENTS; ENERGY SOURCES; EVEN-ODD NUCLEI; FUEL ELEMENTS; FUELS; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MINUTES LIVING RADIOISOTOPES; NUCLEI; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; SEMIMETALS; SPONTANEOUS FISSION RADIOISOTOPES; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES

Optional Information

Notes
Abstract only