References
- 1. Lee, E. K., Shin, H. C., Bae, S. M., & Lee, Y. K. (2005). New dynamic method to measure rod worths in zero power physics test at PWR startup. Ann. Nucl. Energy, 32, 1457-1475.
- 2. Shimazu, Y., Okazaki, K., & Tsuji, M. (2006). Feasibility study for evaluation of control rod worth in pressurized water reactors using neutron count rate during a control rod drop testing. Nucl. Sci. Technol., 43, 919-923.
- 3. Kalcheva, S., & Koonen, E. (2009). Improved Monte Carlo-Perturbation method for estimation of control rod worths in a research reactor. Ann. Nucl. Energy, 36, 344-349.
- 4. Varvayanni, M., Savva, P., & Catsaros, N. (2009). Control rod worth calculations using deterministic and stochastic methods. Ann. Nucl. Energy, 36, 1718-1725.
- 5. Petit, O., Hugot, F. -X., Lee, Y. -K., Jouanne, C., & Maz-zolo, A. (2008). TRIPOLI-4 Version 4 User Guide. (CEA–R-6169). Code Available from OECD/NEA Data Bank.
- 6. Greene, N. M., Petrie, L. M., & Westfall, R. M. (2000). NITAWL-II: scale system module for performing resonance shielding and working library production. (NUREG/CR-0200). Revision 6, V. 2, Section F2. (ORNL/NUREG/ CSD-2/V2/R6).
- 7. Greene, N. M., & Petrie, L. M. (2000). XSDRNPM: a one-dimensional discrete-ordinates code for transport analysis. Oak Ridge National Laboratory. (NUREG/ CR-0200). Revision 6, V. 2, Section F3. (ORNL/NUREG/ CSD-2/V2/R6).
- 8. Fowler, T. B., Vondy, D. R., & Guningham, G. W. (1971). Nuclear reactor core analysis code: CITATION. Oak Ridge National Laboratory. (ORNL-TM-2496). Rev. 2.
- 9. Savva, P., Varvayanni, M., & Catsaros, N. (2011). Dependence of control rod worth on fuel burnup. Nucl. Eng. Des., 241, 492-497.
- 10. Fadaei, A. H., & Setayeshi, S. (2009). Control rod worth calculation for VVER-1000 nuclear reactor using WIMS and CITATION codes. Prog. Nucl. Energy, 51, 184-191.
- 11. Winfrith. (1982). LWR-WIMS, a computer code for light water reactor calculations. AEE, UK. AEEW-R 1498.
- 12. D'Auria, F., Fischer, K., Mavko, B., & Sartmandjiev, A. (2001). Validation of accident and safety analysis methodology. Vienna: IAEA. (CRP/J.020.03).
- 13. Internationa Atomic Energy Agency. (2008). Best estimate safety analysis for nuclear power plants: uncertainty evaluation. Vienna: IAEA. (Safety Series Report No. 52).
- 14. Marleau, G., Hébert, A., & Roy, R. (2011). A user guide for DRAGON Version 4. Institut de génie nucléaire, Dé-partement de génie mécanique, École Polytechnique de Montréal. (Report IGE-294).
- 15. Popov, A. V., & Olekhnovitch, A. (2012). Adapting the feed-back model to dynamic core heterogeneity. Ann. Nucl. Energy, 48, 134-137.
- 16. Popov, A. V., Olekhnovitch, A., & Fassi Fehri, M. (2012). LBLOCA in CANDU-NG cooled by light water. Ann. Nucl. Energy, 45, 161-165.
- 17. Sekki, D., Hébert, A., & Chambon, R. (2011). A user guide for DONJON Version 4. Institut de génie nucléaire, Département de génie mécanique, École Polytechnique de Montréal. (Report IGE-300).
- 18. AEOI. (2006). Album of neutron and physical characteristics of the initial fuel inventory. Refers to Organization of operation on BNPP-1.
- 19. AEOI. (2007). Final safety analysis report, Chapter 4, REACTOR. Atomic Energy Organization of Iran.