October 1, 2013
Conference Paper

IMPLEMENTING PRIMARY CREEP CALCULATIONS DURING STRESS CHANGES AND REVERSALS IN THE FUEL PERFORMANCE CODE FRAPCON-3

Abstract

Recently, the creep models in FRAPCON-3.4 were used to model the creep tests performed in IFA-699 up through cycle 4. IFA-699 is an instrumented test rig in the Halden Boiling Water Reactor that is being used to perform in-reactor creep experiments under changing stress conditions. The cladding creep tests in IFA-699 were on four fresh fuel segments with Zircaloy-4, E110, M-MDA, and M5™ cladding. These fuel segments were loaded in a test rig and placed in a PWR loop and operated under PWR conditions. Each of the test fuel rods were connected to gas lines in order to apply tensile and compressive stresses to the cladding. Diameters of the cladding were measured by diameter gages at several intervals to measure the creep behavior of the cladding as a function of time. The creep tests were performed at a temperature of around 360°C and fast neutron flux of 1.8 to 2.4×1017 n/m²-s (depends on specimen location). During the four cycles of operation, hoop stresses of -75, -50, +30, and +110 MPa were applied to the specimens. In addition to providing assessment of the FRAPCON-3.4 creep modeling, the creep model comparisons were also used to provide insight into the nature of primary creep following stress changes, whether creep behavior is symmetric under tensile and compressive loading, and the effect of fast fluence on creep rate. It was determined that creep strain should be calculated as a function of effective stress rather than hoop stress. This accounts for the observed difference between creep under compressive and tensile stress for the same hoop stress. It was also determined that the primary creep changes in proportion to the change in stress following stress change or stress reversal. Finally, it was observed that the irradiation creep rate decreases somewhat with increasing fluence. The creep model in FRAPCON-3.4 has already been developed to be a function of effective stress and includes a term that decreases the irradiation creep rate with increasing fluence. A new mathematical formulation has been developed that is suitable for a fuel performance code to calculate the primary creep strain under conditions of changing stress and stress reversal. The creep model in FRAPCON-3.4 and the formulation for calculating primary creep under changing stress conditions will be described in this paper. Comparisons to data will also be provided.

Revised: January 7, 2019 | Published: October 1, 2013

Citation

Geelhood K.J. 2013. IMPLEMENTING PRIMARY CREEP CALCULATIONS DURING STRESS CHANGES AND REVERSALS IN THE FUEL PERFORMANCE CODE FRAPCON-3. In Proceedings of the LWR Fuel Performance Meeting / TopFuel 2013, September 15-19, 2013, Charlotte, North Carolina, 1, 188-194. La Grange Park, Illinois:American Nuclear Society. PNNL-SA-96962.