Research ArticleOpen AccessGoogle Scholar indexed
Numerical Analysis for Transients in External Source Driven Reactors
Nuclear Engineering Institute, National Commission for Nuclear Energy, Rio de Janeiro, Brazil
Nuclear Engineering Program, COPPE, Federal University of Rio de Janeiro/UFRJ, Rio de Janeiro, Brazil
Nuclear Engineering Institute, National Commission for Nuclear Energy, Rio de Janeiro, Brazil
- 1 Nuclear Engineering Institute, National Commission for Nuclear Energy, Rio de Janeiro, Brazil
- 2 Nuclear Engineering Program, COPPE, Federal University of Rio de Janeiro/UFRJ, Rio de Janeiro, Brazil
- 3 Nuclear Engineering Institute, National Commission for Nuclear Energy, Rio de Janeiro, Brazil
World Journal of Nuclear Science and Technology·Volume 07 (2017)·Pages 103–120·Published 3 April 2017·DOI10.4236/wjnst.2017.72009
Copy link · social · email
Abstract
The main purpose of this paper is to perform a numerical analysis of the Neutron Spatial Kinetic Equations, subject to transients of the External Neutron Source, by applying the Implicit Euler Method as well as the Runge-Kutta Method in order to check which methods are best applicable in transients caused by External Neutron Source. For this purpose, a one-dimensional ADS reactor with a constant external source was simulated based on the geometry of ANL-BSS-6 reactor for benchmark effects.
KeywordsADSTransientsSpatial Kinetics
- Salvatores, M., et al. (1997) Long-Lived Radioactive Waste Transmutation and the Role of Accelerator Driven (Hybrid) Systems. Nuclear Instruments and Methods, 414, 5.
- Lomonaco, G., Frasciello, O., Osipenko, M., Ricco, G. and Ripani, M. (2014) An Intrinsically Safe Facility for Forefront Research and Training on Nuclear Technologies—Burnup and Transmutation. The European Physical Journal Plus, 129, 74. https://doi.org/10.1140/epjp/i2014-14074-6
- Rubbia, C., et al. (1995) Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier. CERN Report, Genebra.
- Yasin, Z. and Shahzad, M.I. (2010) From Conventional Nuclear Power Reactors to Accelerator-Driven Systems. Annals of Nuclear Energy, 37, 87-92.
- Organization for Economic Co-Operation and Development and Nuclear Energy Agency (2002) Accelerator-Driven Systems (ADS) and Fast Reactors (FR) in Advanced Nuclear Fuel Cycles: A Comparative Study. Technical Report, Paris.
- Nakamura, S. (1977) Computational Methods in Engineering and Science. Wiley and Sons, New York.
- Alvim, A.C.M. (2007) Métodos Numéricos Em Engenharia Nuclear. Certa Ltd., Curitiba.
- Stacey, W.M. (1969) Space-Time Nuclear Reactor Kinetics. Academic Press, New York.
- Kaps, P. and Rentrop, P. (1979) Generalized Runge-Kutta Methods of Order Four with Stepsize Control for Stiff Ordinary Differential Equations. Numerische Mathematik, 33, 55-68. https://doi.org/10.1007/BF01396495
- Press, H.W., Teukolsky, S.A., Vetterling, W.T., et al. (1992) Numerical Recipes in Fortran. 2nd Edition, Cambridge University Press, London.
- Aviles, B.N. (1993) Development of a Variable Time-Step Transient NEM Code: SPANDEX. Transactions of the American Nuclear Society Journal, 68, 425-427.
- Shampine, L.F. (1982) Implementation of Rosenbrock Methods. ACM Transactions on Mathematical Software, 8, 94. https://doi.org/10.1145/355993.355994
- Nagaya, Y. and Kobayashi, K. (1995) Solution do 1D Multi-Group Time-Dependent Diffusion Equations Using the Coupled Reactors Theory. Annals Nuclear Energy, 22, 421-440.
- Argonne Code Center (1977) Benchmark Problem Book. Argonne National Laboratory, Chicago.
- Figueira, A.J., Alvim, A.C.M. and da Silva, F.C. (2016) Non Symmetric Alternating Direction Explicit Method Applied to the Calculation of ADS Transients, Annals of Nuclear Energy, 90, 459-467.