PSI - Issue 60
A. Syed et al. / Procedia Structural Integrity 60 (2024) 195–202 A. Syed/ Structural Integrity Procedia 00 (2023) 000 – 000
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Burst temperature data Correlation
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Burst Pressure (MPa) Fig. 5 : Exponential fitted curve between burst temperature Vs burst pressure of fuel clad at constant heating rate.
Table 2 : Predicted values of burst time and temperature under different internal pressure values Pressure (MPa) Burst temperature ( ˚C) Burst time (s) 0.3 1005 57.44 0.8 931 52.13 2 831 44.26 5 654 33.81 10 585 29.35
6. Conclusions In this work, finite element simulations has been carried out to evaluate the critical damage parameter that can predict the burst of the fuel clad under different operating conditions using Rice and Tracey’s model. Following conclusions can be drawn from the study. The burst behaviour of the clad tubes depends on the material damage parameter rather than an empirical correlation between the burst stress and temperature. Critical material damage parameter can predict the burst time of the clad tubes under any operating conditions by taking into account the stress triaxiality and incremental creep strain developed during ballooning of the clad tubes. Value of the critical material damage parameter is found to be 0.12. Burst temperature decreases exponentially with increase in internal pressure. The burst temperature of the fuel clad reduces from 101 5 ˚C at 0.3 MPa to 585 ˚C at 10 MPa internal pressure. Beremin, F.M., 1981. Three-dimensional constitutive relations and ductile fracture. Nemat-Nasser S. (Eds). North-Holland Publication, Amsterdam, 185-205. Chapman, R.H., Crowley, J.L., Longest, A.W., Hofman, G.H, 1979. Zirconium cladding deformation in a steam environment with transient heating. 4th International Conference on Zirconium in the Nuclear Industry 681, 393-408. Chung, H.M., Garde, A.M., Kassner, T.F., Lowe Jr,. A.L., Parry, G.W, 1977. Deformation and Rupture Behavior of Zircaloy Cladding under Simulated Loss of coolant Accident Conditions. 3rd International Conference on Zirconium in the Nuclear Industry 633, 82-97. Erbacher, F., Neitzel, H.J., Wiehr, K, 1979. Studies on Zircaloy Fuel Clad Ballooning in a Loss of coolant Accident results of Burst Tests with Indirectly Heated Fuel Rod Simulators. 4th International Conference on Zirconium in the Nuclear Industry 681, 429-426. References
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