skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Post irradiation analysis and performance modeling of dispersion and monolithic U-Mo fuels.

Abstract

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.

Authors:
; ; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
971160
Report Number(s):
ANL/NE/CP-60276
TRN: US1001045
DOE Contract Number:
DE-AC02-06CH11357
Resource Type:
Conference
Resource Relation:
Conference: 2007 RERTR International Meeting; Sep. 23, 2007 - Sep. 27, 2007; Prague, Czech Republic
Country of Publication:
United States
Language:
ENGLISH
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; BUBBLES; DATA ANALYSIS; FISSION PRODUCTS; FUEL PLATES; IRRADIATION; MODIFICATIONS; PERFORMANCE; PLATES; SIMULATION; SWELLING

Citation Formats

Kim, Y. S., Hofman, G. L., Medvedev, P.G., Shevlyakov, G.V., Robinson, A.B., Ryu, H.J., Nuclear Engineering Division, INL, SSCR RIAR, and KAERI. Post irradiation analysis and performance modeling of dispersion and monolithic U-Mo fuels.. United States: N. p., 2007. Web.
Kim, Y. S., Hofman, G. L., Medvedev, P.G., Shevlyakov, G.V., Robinson, A.B., Ryu, H.J., Nuclear Engineering Division, INL, SSCR RIAR, & KAERI. Post irradiation analysis and performance modeling of dispersion and monolithic U-Mo fuels.. United States.
Kim, Y. S., Hofman, G. L., Medvedev, P.G., Shevlyakov, G.V., Robinson, A.B., Ryu, H.J., Nuclear Engineering Division, INL, SSCR RIAR, and KAERI. Mon . "Post irradiation analysis and performance modeling of dispersion and monolithic U-Mo fuels.". United States. doi:.
@article{osti_971160,
title = {Post irradiation analysis and performance modeling of dispersion and monolithic U-Mo fuels.},
author = {Kim, Y. S. and Hofman, G. L. and Medvedev, P.G. and Shevlyakov, G.V. and Robinson, A.B. and Ryu, H.J. and Nuclear Engineering Division and INL and SSCR RIAR and KAERI},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 2007},
month = {Mon Jan 01 00:00:00 EST 2007}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share:
  • 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 monolithicmore » 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)« less
  • The evaluation and prediction of integrated fuel performance is a critical component of the Reduced Enrichment for Research and Test Reactors (RERTR) program. The PLATE code is the primary tool being developed and used to perform these functions. The code is being modified to incorporate the most recent fuel/matrix interaction correlations as they become available for both aluminum and aluminum/silicon matrices. The code is also being adapted to treat cylindrical and square pin geometries to enhance the validation database by including the results gathered from various international partners. Additional modeling work has been initiated to evaluate the thermal and mechanicalmore » performance requirements unique to monolithic fuels during irradiation.« less
  • No abstract prepared.
  • No abstract prepared.