EVALUATION OF IRRADIATED EXPERIMENTAL OMR FUEL ELEMENTS--1

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As part of a program to develop an economical fuel cycle for an Organic Moderated Reactor (OMR), experimental fuel elements are being irradiated in the Organic Moderated Reactor Experiment (OMRE). The first two experimental fuel elements have been removed from the OMRE, examined, and evaluated. These extended-surface, platetype fuel elements had finned aluminum cladding, metallurgically bonded to flat uranium alloy fuel plates. A 0.0005 in. nickel layer was used to prevent interdiffusion between the aluminum and uranium. The fuel core alloys irradiated were U--5.5% Mo and U--3.5% Mo--0.5% Si. These two experimental elements were removed from the reactor after one ... continued below

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Pages: 49

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Walter, J.H.; Garrett, E.E. & Davis, J.M. April 1, 1960.

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Description

As part of a program to develop an economical fuel cycle for an Organic Moderated Reactor (OMR), experimental fuel elements are being irradiated in the Organic Moderated Reactor Experiment (OMRE). The first two experimental fuel elements have been removed from the OMRE, examined, and evaluated. These extended-surface, platetype fuel elements had finned aluminum cladding, metallurgically bonded to flat uranium alloy fuel plates. A 0.0005 in. nickel layer was used to prevent interdiffusion between the aluminum and uranium. The fuel core alloys irradiated were U--5.5% Mo and U--3.5% Mo--0.5% Si. These two experimental elements were removed from the reactor after one of the elements released fission products, and cladding temperatures increased on both fuel elements. The maximum measured cladding temperature was 780 deg F. The maximum fuel burnup was later determined to be 0.25 at.% U. Hot-cell examination revealed that the coolant inlet ends of the fuel elements had filtered particulate matter out of the coolant, which blocked the ends of the coolant channels. Restriction of the coolant flow through the elements caused partial melting of the cladding in one fuel element and a blister on one of the fuel plates from the other fuel element. Dimensions were taken on three of the fuel plates. Metallographic sections from the blistered fuel plates were examined, and burnup profiles were determined for the three plates measured. The fuel had good dimensional stability, which is significant, since the melted cladding and the core microstructure evidenced temperatures substantially above the maximurn temperatures recorded by thermocouples. Nothing was observed that would indicate the fuel elements would not have functioned properly in the same coolant if the coolant were free of particulate matter of sizes that could be trapped. (auth)

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Pages: 49

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  • Other Information: Orig. Receipt Date: 31-DEC-60

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  • Report No.: NAA-SR-4670
  • Grant Number: AT-11-1-GEN-8
  • DOI: 10.2172/4160581 | External Link
  • Office of Scientific & Technical Information Report Number: 4160581
  • Archival Resource Key: ark:/67531/metadc870811

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Office of Scientific & Technical Information Technical Reports

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  • April 1, 1960

Added to The UNT Digital Library

  • Sept. 16, 2016, 12:32 a.m.

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  • Dec. 5, 2016, 3:18 p.m.

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Walter, J.H.; Garrett, E.E. & Davis, J.M. EVALUATION OF IRRADIATED EXPERIMENTAL OMR FUEL ELEMENTS--1, report, April 1, 1960; Canoga Park, California. (digital.library.unt.edu/ark:/67531/metadc870811/: accessed November 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.