References
- 1. IAEA. (2005). Thorium fuel cycle - potential benefi ts and challenges. Vienna: International Atomic Energy Agency. (IAEA-TECDOC-1450).
- 2. Weaver, K. D., & Herring, J. S. (2002). Performance of thorium-based mixed oxide fuels for the consumption of plutonium in current and advanced reactors. In International Congress on Advanced Nuclear Power Plants (ICAPP). ANS Annual Meeting, 9-13 June 2002, Hollywood, Florida, USA.
- 3. Lung, M., & Gremm, O. (1998). Perspectives of the thorium fuel cycle. Nucl. Eng. Des., 180, 133-146.10.1016/S0029-5493(97)00296-3
- 4. Usha, S., Ramanarayanan, R. R., Mohanakrishnan, P., & Kapoor, R. P. (2006). Research reactor KAMINI. Nucl. Eng. Des., 236, 872-880.10.1016/j.nucengdes.2005.09.033
- 5. Kumar, A., Srivenkatesan, R., & Sinha, R. K. (2009). On the physics design of advanced heavy water reactor (AHWR). In International Conference on Opportunities and Challengers for Water Cooled Reactors in the 21st Century, 27-28 October 2009 (pp. 84-85). Vienna: International Atomic Energy Agency. (IAEA-CN-164).
- 6. Maitra, R. (2005) Thorium: Preferred nuclear fuel of the fuel. Sci. Technol., 18, 64-71.
- 7. Sasidharan, K., & Chafale, S. B. (2012). New reactor concepts. BARC Highlights - Reactor Technology and Engineering, from http://barc.gov.in/publications/eb/golden/reactor/toc/chapter9/9.pdf.
- 8. Pelowitz, D. B. (2008). MCNPX2.6.0 user manual. Los Alamos: Los Alamos National Laboratory (LA- -CP-07-1473).
- 9. Thorium high temperature reactor (THTR), from paksnuclearpowerplant.com.
- 10. Fensin, M. L. (2008). Development of the MCNPX depletion capability: A Monte Carlo depletion method that automates the coupling between MCNPX and CINDER90 for high fi delity burn-up calculations. Doctoral dissertation, University of Florida.
- 11. Persson, C. -M. (2005). Reactivity determination and Monte Carlo simulation of the subcritical reactor experiment - “Yalina”. Master of Science Thesis, Department of Nuclear and Reactor, Physics Royal Institute of Technology, Stockholm, from http://neutron. kth.se/publications/library/CalleMSc.pdf.
- 12. Hassanzadeh, M., Feghhi, S. A. H., & Khalafi , H. (2013). Calculation of kinetic parameters in an accelerator driven subcritical TRIGA reactor using MCNIC method. Ann. Nucl. Energy, 59, 188-193.10.1016/j.anucene.2013.03.044
- 13. Westlen, D. (2007). Why faster is better - on minor actinide transmutation in hard neutron spectra. Doctoral dissertation, Division of Reactor Physics, University of Stockholm, from http://neutron.kth.se/publications/PhDtheses.shtml
- 14. Snoj, L., & Ravnik, M. (2006). Calculation of power density with MCNP in TRIGA reactor. In Proceedings of the International Conference on Nuclear Energy for New Europe, 12-15 September 2006 (Paper no. 109, pp. 1-6). Portoroz, Slovenia.
- 15. Shultis, J. K., & Faw, R. E. (2011) An MCNP primer. Department of Mechanical and Nuclear Engineering, Kansas State University, from http://krex.ksu.edu.
- 16. El Bakkari, B., El Bardouni, T., Merroun, O., El Younoussi, Ch., Boulaich, Y., & Chakir, E. (2009). Development of an MCNP-tally based burn-up code and validation through PWR benchmark exercises. Ann. Nucl. Energy, 36, 626-633.10.1016/j.anucene.2008.12.025
- 17. Marin, T. W., Takahashi, K., & Bartels, D. M. (2006). Temperature and density dependence light and heavy water ultraviolet absorption edge. Chem. Phys., 125, 1-11.10.1063/1.233852116999533
- 18. Kazimi, M. S., Czerwinski, K. R., Driscoll, M. J., Hejzlar, P., & Meyer, J. E. (1999). On the use of thorium in light water reactors. Department of Nuclear Engineering, Massachusetts Institute of Technology. (MIT-NFC-TR-016), from http://www.ltbridge.com/ assets/15.pdf.