Journal of Nuclear Science and Technology
Online ISSN : 1881-1248
Print ISSN : 0022-3131
Self-Limiting Power Excursion Characteristics of Light Water Reactor, (IV)
Measurement of Fuel-Cladding Strain
Kiyokazu INAGAKIHidemasa KATO
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1972 Volume 9 Issue 10 Pages 584-591

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Abstract

A strain gage was used for the measurement of fuel cladding strain generated during pulse operation tests on the Hitachi Training Reactor. In the analysis of the measured strain, two kinds of correction were called for: (1) the radiation effect on the strain gage and lead wires, and (2) the temperature effect due to the lag of the gage filament temperature behind the true fuel cladding temperature. The experimental axial strain after the two corrections were applied was 781×10-6cm/cm for the hottest fuel rod in the pulse operation test with an inserted reactivity of 1.20%Δk/k. This maximum strain corresponded to 2, 169kg/cm2 of thermal stress and 111cal/cm2•sec of heat flux. These results were obtained under the condition of maximum temperature in the fuel center of 1, 200°C and a fuel cladding temperature of 140°C. When the axial strain was calculated with consideration given to the gap or contact conductance between the fuel and its cladding, a reasonable agreement was obtained between the calculation and the experimental results.

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