The development of magnetic configurations to confine the stability fluid plasmas for fusion energy is a challenge that is a mixture of basic fusion engineering and invention. In order to keep the fusion reactions in the plasma to be continuing in the fusion reactors, the speed of tritium breeding (TBR) should be kept above a certain value. At the Apex fusion reactor, a fast flowing thin liquid wall has replaced the solid first wall concept of the traditional reactors. Behind the fast flowing thin liquid wall, a slower and thicker second liquid wall (coat) is present. Monte Carlo Random method (MCRS) is the general name for the solution of experimental and statistical problems with a random approach. This method is dependent upon the theory of probability. In the present work, Mhd impacts are investigated quite unimportant for Flibe salt solutions. In this study, the fissile fuel production calculations are done for a neutron wall load of 10 MW/m2 fissile fuel production rates of 238U(n, γ)239Pu and 232Th(n,γ)233U increases almost linearly with increased heavy metal content.
References
[1]
Hançerliogullari, A. (2006) Monte Carlo Simulation Method and MCNP Code System. Kastamonu Education Journal, 14, 545-556.
[2]
Sobol Ilya, M. (1994) A Primer for the Monte Carlo Method. CRC Press, London.
[3]
Rod Blais, J.A. and Zhang, Z. (2011) Exploring Pseudo and Chaotic Random Monte Carlo Simulations. Computer & Geosciences, 37, 928-934. http://dx.doi.org/10.1016/j.cageo.2011.01.009
[4]
Behnia, S., Akhavan, A., Akhshani, A. and Samsudin, A. (2011) A Novel Dynamic Model of Pseudo Random Number Generator. Journal of Computational and Applied Mathematics, 235, 3455-3463.
http://dx.doi.org/10.1016/j.cam.2011.02.006
[5]
Binder, K. (1997) Applications of Monte Carlo Methods to Statistical Physics. Reports on Progress in Physics, 60, 487-559
[6]
Carter Jr., E.F. (1999) Random Walks, Markov Chains and the Monte Carlo Method, Monte Carlo Integration. Taygeta Scientific Inc. https://www.taygeta.com/rwalks/node5.html
[7]
Pevey, R.E. (1998) Monte Carlo Course Notes. Department of Nuclear Engineering, the University of Tennessee, Knoxville. Spring Semester. http://web.utk.edu/~rpevey/
[8]
Foster, D. and Artur, G. (1982) Average Neutronic Properties of “Prompt” Fission Poducts. Los Alamos National Laboraty Report la-9168-ms, February.
[9]
Johston, R.A. (1963) General Monte Carlo Neutronics Code. Lams-2856, Los Alamos.
[10]
Briesmeister, J. (1993) RSIC Computer Code Collection MCNP 4a, Monte Carlo N-Particle Transport Code System. Los Alamos National Laboratory, New Mexico.
[11]
Hançerliogullari, A. (2011) Determining of Energy Multiplication in the Apex Hybrid Reactor by Using ThF4 and UF4 Heavy Metals Salts. International Journal of Energy Research, 36, 1375-1382.
[12]
Abdou, M.A. (1999) Exploring Novel High Power Density Concepts for Attractive Fusion System. Fusion Engineering & Design, 4, 67-145.
[13]
Moir, R.W. (1997) Liquid First Walls for Magnetic Fusion Energy Configurations. Nuclear Fusion, 37, 557.
http://dx.doi.org/10.1088/0029-5515/37/4/I13
[14]
Abdou, M.A. and The Apex Team (1999) Exploring Novel High Power Density Concepts for Attractive Fusion Systems. Fusion Engineering and Design, 45, 145-167. http://dx.doi.org/10.1016/S0920-3796(99)00018-6
[15]
Abdou, M.A., Ying, A. and Morley, N. and The Apex Team (2001) On the Exploration of Innovative Concepts for Fusion Chamber Technology. Fusion Engineering and Design, 54, 181-247.
http://dx.doi.org/10.1016/S0920-3796(00)00433-6
[16]
Sarer, B., Hançerliogullari, A. and Savruk, N. (2005) A Design for Apex Hybrid Reactor Model by Using Monte Carlo Method. G.U. Journal of Science, 18, 17-25.
[17]
Sahin, H.M. (2007) Monte Carlo Calculation of Radiation Damage in First Wall of an Experimental Hybrid Reactor. Annals of Nuclear Energy, 34, 861-870.
[18]
Doucet, A., Johansen, M.A. and Tadic, B.V. (2010) On Solving Integral Equations Using Markov Chain Monte Carlo Methods. Applied Mathematics and Computation, 216, 2869-2880. http://dx.doi.org/10.1016/j.amc.2010.03.138
[19]
Beyli, M.U. and Acir, A. (2007) Utilization of Thorium in a High Power Density Hybrid Reactor with ?nnovative Coolants. Energy Conversion and Management, 48, 576-582. http://dx.doi.org/10.1016/j.enconman.2006.06.007
[20]
Maziar, N., Matthew, C.W. and Needs, J.R. (2003) Quantum Monte Carlo Studies of Density Functional Theory. Mathematics and Computers in Simulation, 62, 463-470.
[21]
Mahdavi, M. and Asadi, E. (2013) Estimates of Tritium Produced Ratio in the Blancet of Fusion Reactors. Open Journal of Microphysics, 3, 8-11. http://dx.doi.org/10.4236/ojm.2013.31002
[22]
Hançerliogullari, A. (2014) Thermodynamics Properties of Molten Salt Technology Assessment for New Generation Fusion Reactors. Journal of Fusion Energy, 33, 5.
