A LMR Core Thermal-Hydraulics Code Based on the ENERGY Model

  • Published : 1997.10.01

Abstract

A computational method is developed for predicting the steady-state temperature field in an LMR core. Detailed core-wide coolant temperature profiles are efficiently calculated using the simplified energy equation mixing model[1] and the subchannel analysis method. The $\theta$-method is employed for discretizing the energy equations in the axial direction. The interassembly coupling is achieved by interassembly gap flow. Cladding and fuel temperatures are calculated with the one-dimensional conduction model and temperature integrals of conductivities. The accuracy of the method is tested by performing several benchmark calculations for too LMR problems. The results indicate that the accuracy is comparable to the other methods based on ENERGY model. It is also shown that the implicit scheme for the axial discretization is more efficient than the explicit scheme.

Keywords

References

  1. Nucl. Eng. and Des. v.35 A Porous Body Model for Predicting Temperature Distribution in Wire-Wrapped Fuel Rod Assemblies E.U. Khan;W.M. Rohsenow;A.A. Sonein;N.E. Todreas
  2. Nucl. Eng. and Des. v.35 A Porous Body Model for Predicting Assemblies in Combined Forced and Free Convection E.U. Khan;W.M. Rohsenow;A.A.Sonein;N.E. Todreas
  3. COO-2245-20TR, Massachusetts Institutes of Technology, Cambridge Prediction of Coolant Temperature Field in a Breeder Reactor Including Interassembly Heat Transfer B. Chen;N.E. Todreas
  4. PNL-3379, Pacific Northwest Laboratory SUPERENERGY-2 : A Multiassembly, Steady-State Computer Code for LMFBR Core Thermal-Hydraulic Analysis K.L. Basehore;N.E. Todreas
  5. Proc. 7th International Meeting on Nuclear Reactor Thermal Hydraulics, NUREG/CP-0142, Saratoga Springs, New York, September 10-15, 1995 v.3 Assessment of the SE2-ANL Code Using EBR-II Temperature Measurements W.S. Yang;A.M. Yacout
  6. Fast Breeder Reactors A.E. Walter;A.B. Reynolds
  7. Nucl. Eng. and Des. v.22 Turbulent Flow Pressure Drop Model for Fuel Rod Assemblies Utilizing a Helical Wire-Wrap Spacer System E.H. Novenstern
  8. COO-2245-56TR, Massachusetts Institute of Technology Flow Split Model for LMFBR Wire Wrapped Assemblies C. Chiu;W.M. Rohsenow;N.E. Todreas
  9. Nucl. Eng. and Des. v.92 Hydrodynamic Models and Correlations for Bare and Wire-Wrapped Hexagonal Rod Bundles-Bundle Friction Factors, Subchannel Friction Factors and Mixing Parameters S.K. Cheng;N.E. Todreas
  10. Nuclear Technology v.115 Average Irradiation Temperature for the Analysis of In-Pile Intergral Measurements A.M. Yacout;W.S. Yang;G.L. Hofman;Y. Orechwa
  11. 95-83, Electrical Engineering and Science Research Institute Development of a Computer Code for LMR Core Steady-State Thermal-Hydraulics Analysis W.S. Yang(et al.)
  12. Computational Methods in Engineering and Science S. Nakamura
  13. Argonne National Laboratory, personal communication R.B. Vilim