You are being redirected because this document is part of your ASTM Compass® subscription.
    This document is part of your ASTM Compass® subscription.


    Initial Results of Swelling and Irradiation Creep Interaction Testing

    Published: 0

      Format Pages Price  
    PDF (268K) 27 $25   ADD TO CART
    Complete Source PDF (19M) 1219 $77   ADD TO CART


    An EBR-II irradiation test, designated as WSA-60, was established to provide swelling and irradiation creep interaction data when these two effects interact simultaneously in opposition. This type of behavior occurs under irradiation in cylindrical tubing containing an internal heat source and external heat sink. The WSA-60 test consists of encapsulated fuel pins wherein the capsules comprise the test samples.

    Slit tube data have been obtained on two 20% cold-worked AISI 316 stainless steel capsules irradiated to a peak fluence level of 2.2 × 1022 n/cm2 (E>0.1 MeV). The capsules were irradiated to approximately the same fluence level and had similar temperature profiles. The slit tube data from the two capsules were observed to be self-consistent. Since the data are limited to low fluence levels where swelling is negligible the material behavior is dominated by irradiation creep effects.

    An assessment of the slit tube data was made by comparing the data with performance calculations using an irradiation creep equation formulated from pressurized tube data. The results show significant differences between the slit tube data and the calculations. A 34% reduction in irradiation creep was necessary to obtain consistency between the data and calculations. This difference is attributed to the following: 1. Differences in material compositions between the slit tube and pressurized tube specimens. 2. The analytical methods used in irradiation creep equation development.


    radiation, stainless steels, neutron irradiation, residual stress, creep properties, creep rate, stress relaxation, swelling, deformation

    Author Information:

    Foster, JP

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP34338S