Numerical solution of diffusion equation to study fast neutrons flux distribution for variant radii of nuclear fuel pin and moderator regions

References

1 Rafiei Karahroudi, M; Mousavi Shirazi, S. A.: Study of power distribution in the CZP, HFP and normal operation states of VVER-1000 (Bushehr) nuclear reactor core by coupling nuclear codes. Annals of Nuclear Energy75 (2015) 3810.1016/j.anucene.2014.07.038Suche in Google Scholar

2 Mousavi Shirazi, S. A; Shafeie Lilehkouhi, M. S.: The assessment of radioisotopes and radiomedicines in the MNSR reactor of Isfahan and obtaining the burnup by applying the obtained information. Proc. Conf. Asia-Pacific Power and Energy Engineering (APPEEC), Shanghai, March 27–29, 2012, p. 110.1109/APPEEC.2012.6307050Suche in Google Scholar

3 Rafiei Karahroudi, M; Mousavi Shirazi, S. A.; Sepanloo, K.: Optimization of designing the core fuel loading pattern in a VVER-1000 nuclear power reactor using the genetic algorithm. Annals of Nuclear Energy57 (2013) 14210.1016/j.anucene.2013.01.051Suche in Google Scholar

4 Rafiei Karahroudi, M; Mousavi Shirazi, S. A.: Obtaining the neutronic and thermal hydraulic parameters of the VVER-1000 Bushehr nuclear reactor core by coupling nuclear codes. Kerntechnik79 (2014) 52810.3139/124.110440Suche in Google Scholar

5 Fowler, T. B.: CITALDI-PC README File, List Directed Input, 1996Suche in Google Scholar

6 Fowler, T; Vondy, D; Cunningham, G.: Nuclear Reactor Core Analysis Code: CITATION. ORNL-TM-2496, Rev.2, with Supplements 1, 2, and 3, 1971. p. 55Suche in Google Scholar

7 Mousavi Shirazi, S. A.: The simulation of a model by SIMULINK of MATLAB for determining the best ranges for velocity and delay time of control rod movement in LWR reactors. Progress in Nuclear Energy54 (2012) 6410.1016/j.pnucene.2011.08.005Suche in Google Scholar

8 Mousavi Shirazi, S. A.; Rastayesh, S.: The comparative investigation and calculation of thermo-neutronic parameters on two gens II and III nuclear reactors with same powers. World Academy of Science, Engineering and Technology (WASET)49 (2011) 105Suche in Google Scholar

9 Todreas, N. E.; Kazimi, M. S.: Nuclear Systems I Thermal Hydraulic Fundamentals, Hemisphere Publishing Corporation, New York, 1990Suche in Google Scholar

10 Nakamura, S.: Applied Numerical Methods with Software, Prentice-Hall International, USA, 1991Suche in Google Scholar

11 Lamarsh, J. R.: Introduction to nuclear engineering, Addison Wesley Publishing Company, Boston, 1983Suche in Google Scholar

12 Mousavi Shirazi, S. A.; Sardari, D.: Design and Simulation of a New Model for Treatment by Neutron Therapy. Science and Technology of Nuclear Installations2012 (2012) 110.1155/2012/213640Suche in Google Scholar

13 Final Safety Analysis Report (FSAR), NPP “Bushehr”. Ministry of Russian Federation of Atomic Energy, Federal State of Unitary Enterprise “Research, design, engineering and survey institute” (ATOMENERGOPROEKT), Moscow, 2003. Chap. 4, p. 4Suche in Google Scholar

14 Mousavi Shirazi, S. A.; Taheri, A.: A NEW METHOD FOR NEUTRON CAPTURE THERAPY (NCT) AND RELATED SIMULATION BY MCNP4C CODE. Proc. Conf. Neutron and X-Ray Scattering in Advancing Materials Research, American Institute of Physics (AIP), Kuala Lumpur, June–July 29–01, 2009, p. 77.10.1063/1.3295614Suche in Google Scholar

15 Douglas Faires, J; Burden, R.: Numerical Methods, Cole Publishing Company, Wisconsin, 1998Suche in Google Scholar

16 Dusinberre, G. M.: Heat Transfer Calculating by Finite Difference, International Textbook Company, Scranton, Pennsylvania, 1961Suche in Google Scholar

17 Kubicek, M; Hlavacek, V.: Numerical Solution of Nonlinear Boundary Value Problems with Applications, Prentice-Hall, 1983Suche in Google Scholar