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Fractional calculus with applications for nuclear reactors dynamics / Santanu Saha Ray, Department of Mathematics, National Institute of Technology Rourkela, Orissa, India.

By: Saha Ray, Santanu [author.]Material type: TextTextPublisher: Boca Raton, Florida : CRC Press, [2016]Copyright date: ©2016Description: 1 online resourceContent type: text Media type: computer Carrier type: online resourceISBN: 9780429075834Subject(s): Fractional calculusDDC classification: 515.83 LOC classification: QA314 | .S24 2016Online resources: Click here to view.
Contents:
1. Mathematical methods in nuclear reactor physics -- 2. Neutron diffusion equation model in dynamical systems -- 3. Fractional order neutron point kinetic model -- 4. Numerical solution for deterministic classical and fractional order neutron point kinetic model -- 5. Classical and fractional order stochastic neutron point kinetic model -- 6. Solution for nonlinear classical and fractional order neutron point kinetic model with Newtonian temperature feedback reactivity -- 7. Numerical simulation using Haar Wavelet Operational method for neutron point kinetic equation involving imposed reactivity function -- 8. Numerical solution using two-dimensional Haar Wavelet collocation method for stationary neutron transport equation in homogeneous isotropic medium.
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Central University Of Rajasthan
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1. Mathematical methods in nuclear reactor physics -- 2. Neutron diffusion equation model in dynamical systems -- 3. Fractional order neutron point kinetic model -- 4. Numerical solution for deterministic classical and fractional order neutron point kinetic model -- 5. Classical and fractional order stochastic neutron point kinetic model -- 6. Solution for nonlinear classical and fractional order neutron point kinetic model with Newtonian temperature feedback reactivity -- 7. Numerical simulation using Haar Wavelet Operational method for neutron point kinetic equation involving imposed reactivity function -- 8. Numerical solution using two-dimensional Haar Wavelet collocation method for stationary neutron transport equation in homogeneous isotropic medium.

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