Lumped-parameter models for transient conduction in nuclear reactor components
Lumped-parameter models are presented for the prediction of transient conduction in cylinders, plane-parallel slabs, tubes and fuel elements under conditions of small-break loss of coolant accidents and planned transients in nuclear reactor systems. The model accounts for heat generation by fission and decay and by gamma absorption and water reaction. The models consist of ordinary differential equations, one each for the solid cylinder, the slab and the tube, and two for fuel pellet and clad in the fuel element. The differential equations are derived from the partial differential equation of energy conservation by volume averaging. The models can be applied to each axial node of a flow passage. The model formulation is particularly suitable for explicit integration over time with high-order integration schemes for ordinary, first-order differential equations.
- Research Organization:
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5461519
- Report Number(s):
- NUREG/CR-1540; BNL-NUREG-51231; ON: TI85015904
- Country of Publication:
- United States
- Language:
- English
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