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Investigations of fuel cladding chemical interaction in irradiated LMFBR type oxide fuel pins

Abstract

Understanding and controlling the chemical attack of fuel pin cladding by fuel and fission products are major objectives of the U.S. LMFBR Mixed Oxide Irradiation Testing Program. Fuel-cladding chemical interaction (FCCI) has been recognized as an important factor in the ability to achieve goal peak burnups of 8% (80.MWd/kg) in FFTF and in excess of 10% (100.MWd/kg) in the LMFBR demonstration reactors while maintaining coolant bulk outlet temperatures up to {approx}60 deg. C (1100 deg. F). In this paper we review pertinent parts of the irradiation program and describe recent observation of FCCI in the fuel pins of this program. One goal of the FCCI investigations is to obtain a sufficiently quantitative understanding of FCCI such that correlations can be developed relating loss of effective cladding thickness to irradiation and fuel pin fabrication parameters. Wastage correlations being developed using different approaches are discussed. Much of the early data on FCCI obtained in the U.S. Mixed Oxide Fuel Program came from capsule tests irradiated in both fast and thermal flux facilities. The fast flux irradiated encapsulated fuel pins continue to provide valuable data and insight into FCCI. Currently, however, bare pins with prototypic fuels and cladding irradiated in the fast flux  More>>
Authors:
Roake, W E; [1]  Adamson, M G; [2]  Hilbert, R F; Langer, S
  1. Westinghouse-Hanford Co., Richland, WA (United States)
  2. General Electric Company, Vallecitos Nuclear Center, Pleasanton, CA (United States)
Publication Date:
Apr 01, 1977
Product Type:
Conference
Report Number:
IWGFR-16
Reference Number:
EDB-01:020728
Resource Relation:
Conference: IAEA-IWGFR technical committee meeting on fuel and cladding interaction, Tokyo (Japan), 21-25 Feb 1977; Other Information: 28 refs, 22 figs, 8 tabs; PBD: Apr 1977; Related Information: In: Technical committee meeting on fuel and cladding interaction. Summary report, 208 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BURNUP; EBR-2 REACTOR; ENCAPSULATION; EXPERIMENTAL CHANNELS; FUEL PINS; FUEL-CLADDING INTERACTIONS; GETR REACTOR; NEUTRON FLUX; PERFORMANCE TESTING; POST-IRRADIATION EXAMINATION
OSTI ID:
20137475
Research Organizations:
International Atomic Energy Agency, International Working Group on Fast Reactors, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA0100201006570
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 137-158
Announcement Date:

Citation Formats

Roake, W E, Adamson, M G, Hilbert, R F, and Langer, S. Investigations of fuel cladding chemical interaction in irradiated LMFBR type oxide fuel pins. IAEA: N. p., 1977. Web.
Roake, W E, Adamson, M G, Hilbert, R F, & Langer, S. Investigations of fuel cladding chemical interaction in irradiated LMFBR type oxide fuel pins. IAEA.
Roake, W E, Adamson, M G, Hilbert, R F, and Langer, S. 1977. "Investigations of fuel cladding chemical interaction in irradiated LMFBR type oxide fuel pins." IAEA.
@misc{etde_20137475,
title = {Investigations of fuel cladding chemical interaction in irradiated LMFBR type oxide fuel pins}
author = {Roake, W E, Adamson, M G, Hilbert, R F, and Langer, S}
abstractNote = {Understanding and controlling the chemical attack of fuel pin cladding by fuel and fission products are major objectives of the U.S. LMFBR Mixed Oxide Irradiation Testing Program. Fuel-cladding chemical interaction (FCCI) has been recognized as an important factor in the ability to achieve goal peak burnups of 8% (80.MWd/kg) in FFTF and in excess of 10% (100.MWd/kg) in the LMFBR demonstration reactors while maintaining coolant bulk outlet temperatures up to {approx}60 deg. C (1100 deg. F). In this paper we review pertinent parts of the irradiation program and describe recent observation of FCCI in the fuel pins of this program. One goal of the FCCI investigations is to obtain a sufficiently quantitative understanding of FCCI such that correlations can be developed relating loss of effective cladding thickness to irradiation and fuel pin fabrication parameters. Wastage correlations being developed using different approaches are discussed. Much of the early data on FCCI obtained in the U.S. Mixed Oxide Fuel Program came from capsule tests irradiated in both fast and thermal flux facilities. The fast flux irradiated encapsulated fuel pins continue to provide valuable data and insight into FCCI. Currently, however, bare pins with prototypic fuels and cladding irradiated in the fast flux Experimental Breeder Reactor-II (EBR-II) as multiple pin assemblies under prototypic powers, temperatures and thermal gradients are providing growing quantities of data on FCCI characteristics and cladding thickness losses from FCCI. A few special encapsulated fuel pin tests are being conducted in the General Electric Test Reactor (GETR) and EBR-II, but these are aimed at providing specific information under irradiation conditions not achievable in the fast flux bare pin assemblies or because EBR-II Operation or Safety requirements dictate that the pins be encapsulated. The discussion in this paper is limited to fast flux irradiation test results from encapsulated pins and multiple pin subassemblies in EBR-II and selected encapsulated tests irradiated in GETR. Other comparative tests in thermal reactors indicate that fast flux and thermal flux results are similar. An adequate understanding of FCCI requires integration of in reactor tests and out-of-reactor applied and fundamental studies. To this end a Fuel Cladding Chemical Interaction Program has been established involving several ERDA laboratories and contractors. Other papers to be presented at this international meeting will describe: FCCI work being carried on out-of-reactor but simulating reactor irradiation conditions; studies using all available data sources aimed at illuminating the mechanism and developing models for FCCI; in-reactor and out-of-reactor tests using various techniques and materials whose objectives are to prevent serious FCCI or to mitigate its effect on fuel pin behavior; and the application of FCCI data to lifetime estimates and design criteria.}
place = {IAEA}
year = {1977}
month = {Apr}
}