If the load is not relieved as a structure starts to yield, the induced stress is defined as primary stress. If the load relaxes, as a structure begins to yield the induced stress is defined as secondary stress. In design, it is not uncommon to give more weight to primary stresses than to secondary stresses. However, knowing when this is good design practice and when it is not good design practice represents a problem. In particular, the fuel plates in operating reactors contain both primary stresses and secondary stresses, and to properly assess a design there is a need to assign design weights to the stresses. Tests were conducted on reactor fuel plates intended for the advanced neutron source (ANS) to determine the potential of giving different design weights to the primary and secondary stresses. The results of these tests and the conclusion that the stresses should be weighted the same are given in this paper.

1.
ASME Boiler and Pressure Vessel Committee, 1992, “ASME Boiler and Pressure Vessel Code, Section III: Division I,” The American Society of Mechanical Engineers, New York, NY.
2.
Martin, W. R., and Weir, J. R., 1964, “Mechanical Properties of X8001 and 6061 Aluminum Alloys and Aluminum-Base Fuel Dispersion at Elevated Temperatures,” ORNL-3557, Oak Ridge National Laboratory, Oak Ridge, TN.
3.
Swinson, W. F., Battiste, R. L., Luttrell, C. R., and Yahr, G. T., 1993a, “Fuel Plate Stability Experiments and Analysis for the Advanced Neutron Source,” ORNL/TM-12353, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN.
4.
Swinson, W. F., Battiste, R. L., Luttrell, C. R., and Yahr, G. T., 1993b, “Follow-up Fuel Plate Stability Experiments and Analysis for the Advanced Neutron Source,” ORNL/TM-12629, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN.
5.
Swinson, W. F., Luttrell, C. R., and Yahr, G. T., 1994, “An Examination of the Elastic Structural Response of the Advanced Neutron Source Fuel Plates,” ORNL/TM-12712, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN.
6.
Swinson, W. F., Battiste, R. L., and Yahr, G. T., 1995, “Circular Arc Fuel Plates for the Advanced Neutron Source,” ORNL/TM-12977, Lockheed Martin Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN.
7.
West
C. D.
,
1988
, “
Overview of the ANS Project
,”
Trans. American Nuclear Society
, Vol.
57
, pp.
288
289
.
This content is only available via PDF.
You do not currently have access to this content.