Radiation Damage Investigation on Certain Alternative Fluids in a Hybrid System by Using MCNPX Monte Carlo Radiation Transport Code

• Authors: M. Günay
• Languages of publication: EN

Abstracts

EN

In this study, the effect of the radiation damage of spent fuel-grade plutonium content was investigated in the structural material of a designed fusion-fission hybrid reactor system. In this study, the molten salt-heavy metal mixtures 99-95% Li_{20}Sn_{80}-1-5% SFG-Pu, 99-95% Li_{20}Sn_{80}-1-5% SFG-PuF_{4}, and 99-95% Li_{20}Sn_{80}-1-5% SFG-PuO_{2} were used as fluids. The fluids were used in the liquid first-wall, blanket and shield zones of the designed hybrid reactor system. Four centimeter thick 9Cr2WVTa ferritic steel was used as the structural material. Proton, deuterium, tritium, He-3 and He-4 gas production rates are the parameters of radiation damage. In this study, damage to the total structural material and each 1.0 cm thickness thereof was measured as a function of radiation energy, using the selected fluid rates, for 30 full power years (FPYs). Three-dimensional analyses were performed using the most recent MCNPX-2.7.0 Monte Carlo radiation transport code and the ENDF/B-VII.0 nuclear data library.

Keywords

EN

28.52.-s; 28.52.Av

Discipline

• 28.52.-s: Fusion reactors(see also 52.55.-s Magnetic confinement and equilibrium, 52.57.-z Laser inertial confinement, and 52.58.-c Other confinement methods in physics of plasmas; 89.30.Jj Nuclear fusion power in energy resources)
• 28.52.Av: Theory, design, and computerized simulation

• Journal: Acta Physica Polonica A
• Year: 2015
• Volume: 128
• Issue: 2B
• Pages: B-113-B-117

Dates

published

2015-8

Contributors

author

M. Günay

• İnönü University, Science and Art Faculty, Physics Department, Malatya, Turkey

References

• [1] S. Şahın, M. Übeyli, Energy Conv. Manag. 46, 3185 (2005), doi: 10.1016/j.enconman.2005.03.007
• [2] H.M. Şahın, Ann. Nucl. Energy 34, 861 (2007), doi: 10.1016/j.anucene.2007.04.011
• [3] B. Şarer, M. Günay, M.E. Korkmaz, A. Hançerlioğulları, Fusion Sci. Technol. 52, 107 (2007)
• [4] M. Günay, B. Şarer, Y. Çelik, Ann. Nucl. Energy 38, 2757 (2011), doi: 10.1016/j.anucene.2011.08.007
• [5] IAEA, International Atomic Energy Agency, IAEA-TECDOC-1349, 2003
• [6] M. Piera, A. Lafuente, A. Abánades, J. M. Martinez-Valet, Energy Conv. Manag. 51, 1758 (2010), doi: 10.1016/j.enconman.2010.01.025
• [7] A. Ying, K. Gulec, N. Morley, S. Smolentsev, M.Youssef, T. Sketchley, M. Abdou, B. Nelson, P. Fogarty, S. Zinkle, R. Moir, T. Rognlien, M. Resnink, D. Sze, H. Khater, J. Santarius, APEX Interim Report, Ch. 5: Thick Liquid Blanket Concept, 1999
• [8] B. Şarer, A. Aydın, M. Günay, M.E. Korkmaz, E. Tel, Ann. Nucl. Energy 36, 417 (2009), doi: 10.1016/j.anucene.2008.11.025
• [9] M. Günay, Ann. Nucl. Energy 53, 59 (2013), doi: 10.1016/j.anucene.2012.06.038
• [10] M.B. Chadwick, P. Oblozinsky, M. Herman, N.M. Greene, R.D. McKnight, D.L. Smith, P.G.Young, R.E. MacFarlane, G.M. Hale, S.C. Frankle, A.C. Kahler, T. Kawano, R.C. Little, D.G. Madland, P. Moller, R.D. Mosteller, P.R. Page, P. Talou, H. Trellue, M.C. White, W.B. Wilson, R. Arcilla, C.L. Dunford, S.F. Mughabghab, B. Pritychenko, D. Rochman, A.A. Sonzogni, C.R. Lubitz, T.H. Trumbull, J.P. Weinman, D.A. Brown, D.E. Cullen, D.P. Heinrichs, D.P. McNabb, H. Derrien, M.E. Dunn, N.M. Larson, L.C. Leal, A.D. Carlson, R.C. Block, J.B. Briggs, E.T. Cheng, H.C. Huria, M.L. Zerkle, K.S. Kozier, A. Courcelle, V. Pronyaev, S.C. Van der Marck, Nuclear Data Sheets 107, 2931 (2006), doi: 10.1016/j.nds.2006.11.001
• [11] D.B. Pelowitz, MCNPX User's Manual, Version 2.7.0, LA-CP-11-00438, 2011
• [12] R.W. Moir, R.L. Bieri, X.M. Chen, T.J. Dolan, M.A. Hoffman, P.A. House, R.L. Leber, J.D. Lee, Y.T. Lee, J.C. Liu, G.R. Longhurst, W.R. Meier, P.F. Peterson, R.W. Petzoldt, V.E. Schrock, M.T. Tobin, W.H. Williams, Fusion Sci. Technol. 25, 5 (1994)

Identifiers

DOI

10.12693/APhysPolA.128.B-113