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Morman, J.A.; Froehle, P.H.; Holland, J.W.; Bennett, J.D.
Argonne National Lab., IL (USA)1990
Argonne National Lab., IL (USA)1990
AbstractAbstract
[en] A series of CT codes is under development in the Reactor Analysis and Safety Division of Argonne National Laboratory for use as a post-test examination tool to analyze segments of the final fuel-bundle configuration of TREAT tests. This paper presents the results of CT analysis for fuel assemblies using neutron radiography. Fuel relocation following overpower transients in the TREAT reactor is examined for sections of the assemblies, and results are compared to metallographic sections. Further improvements are expected to increase the use and reliability of CT analysis as a standard post-test examination tool
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Source
1990; 11 p; International topical meeting on fast reactor safety; Snowbird, UT (USA); 12-16 Aug 1990; CONTRACT W-31109-ENG-38; NTIS, PC A03/MF A01 as DE90010087; OSTI; INIS
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Report
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Conference
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AIR COOLED REACTORS, BREEDER REACTORS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FUEL ELEMENTS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HOMOGENEOUS REACTORS, LIQUID METAL COOLED REACTORS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, SAFETY, SOLID HOMOGENEOUS REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS, TOMOGRAPHY
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