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An experimental investigation of the interaction of primary and secondary stresses in fuel plates

TLDR
In this paper, 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.
Abstract
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 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.

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References
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ReportDOI

Fuel plate stability experiments and analysis for the Advanced Neutron Source

TL;DR: The planned Advanced Neutron Source (ANS) as mentioned in this paper will use closely spaced arrays of involute-shaped fuel plates that will be cooled by water flowing through the channels between the plates, and there is concern that at certain coolant flow velocities, adjacent plates may deflect and touch, with resulting failure of the plates.
ReportDOI

Follow-up fuel plate stability experiments and analyses for the Advanced Neutron Source

TL;DR: In this paper, two sets of tests were performed on the upper and lower fuel plates for the structural response of the fuel plates to the required high coolant flow velocities.
ReportDOI

Mechanical properties of x8001 and 6061 aluminum alloys and aluminum-base fuel dispersion at elevated temperatures

W.R. Martin, +1 more
TL;DR: In this article, the mechanical properties of two aluminum alloys and a fuel dispersion have been investigated for the purpose of selecting a cladding material and supplying data for design evaluation of the Advanced Test Reactor fuel plates.
Journal Article

Overview of the ANS project

TL;DR: In this paper, the authors present the current cooling system design as a direct result of guidance received from the Probabilistic Risk Assessment (PRA) for the Advanced Neutron Source (ANS) project.
Journal ArticleDOI

An experimental investigation of the structural response of reactor fuel plates

TL;DR: In this article, an experimental-analytical solution to this problem for design purposes has been developed and is presented and is used in the design of a nuclear power plant with a single-input single-output (SISO) system.
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