Published July 2008 | Version v1
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Post irradiation analysis and performance modeling of dispersion and monolithic U-Mo fuels

  • 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)
  • 3. SSCR RIAR, 433510 Dimitrovgrad, Ulyanovsk Region (Russian Federation)
  • 4. KAERI, 150 Deokjin-dong, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)

Description

We analyzed fission product swelling of post-irradiation U-Mo fuels from the early RERTR tests to the recent RERTR-8 test. We found that the gas bubble swelling of the fuel-swelling model was overestimated. From the recent tests, RERTR-7A and 8, we could also collect a considerable amount of fuel swelling data from monolithic U-Mo fuel plates. The fuel swelling data from the monolithic fuel plates are considered more reliable because the interaction layer growth between the fuel and matrix in dispersion fuel, which obscures fuel swelling, does not exist. The swelling correlation comparison to the Si-added dispersion fuel data and monolithic fuel data suggested that a modification of the existing model was necessary. We also developed an interaction layer growth model for U-Mo/Al dispersion fuel plates with a Si-added matrix. PLATE code calculations with the new PIE data analysis results were performed. The updated versions predict with better accuracies for both monolithic fuel plates and dispersion fuel plates. In this paper, we present the results of fission product swelling characterization. In addition, the interaction layer growth model for U-Mo/Al with a Si-added matrix is presented. (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

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
9 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
39121043
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCURACY; BUBBLES; DATA ANALYSIS; DISPERSION NUCLEAR FUELS; DISPERSIONS; FISSION PRODUCTS; FUEL PLATES; IRRADIATION; LAYERS; PERFORMANCE; SIMULATION; SWELLING; URANIUM-MOLYBDENUM FUELS
Descriptors DEC
ALLOY NUCLEAR FUELS; DEFORMATION; ENERGY SOURCES; FUEL ELEMENTS; FUELS; ISOTOPES; MATERIALS; NUCLEAR FUELS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS

Optional Information

Notes
12 refs, 10 figs