Accession Number:

AD0606696

Title:

IN-DEPTH EMBRITTLEMENT TO A SIMULATED PRESSURE VESSEL WALL OF A302-B STEEL,

Descriptive Note:

Corporate Author:

NAVAL RESEARCH LAB WASHINGTON D C

Personal Author(s):

Report Date:

1964-09-04

Pagination or Media Count:

22.0

Abstract:

Because of the self shielding and attenuation properties of the vessel material, a nuclear reactor pressure vessel will have a neutron flux and spectrum variation across its thickness. As a result of this variation, a pressure vessel should show various degrees of neutron-induced embrittlement throughout its thickness, and thatit is postulated that the embrittlement will be greatest at the inner wall and least at the outer wall. This phenomenon has been investigated by the irradiation of a large block of A302-B steel at the core face of a pool reactor in a position simulating the location of an actual pressure vessel. The steel block, 6 in. thick, was made to accommodate five equally spaced assemblies of Charpy V-notch specimens which, in turn, represented the vessel material at comparable positions. The notch ductility test results of the irradiated specimens demonstrate a significant degree of embrittlement as well as a significant decrease in the degree of embrittlement through the simulated pressure vessel wall. However, the observed decrease is small when related to the respective variation in neutron dosage. A correlation of the notch ductility data developed in this study to that between test reactor experiments and in-service power reactor conditions is indicated. Author

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Distribution Statement:

APPROVED FOR PUBLIC RELEASE