Neutronic Analysis of Generic Heavy Water Research Reactor Core Parameters to Use Standard Hydride Fuel
Affiliation(s)
. Department of Engineering, Islamic Azad University, Aliabad Katoul Branch, Aliabad Katoul, Golestan, Iran.
. Department of Engineering, Islamic Azad University, Aliabad Katoul Branch, Aliabad Katoul, Golestan, Iran.
ABSTRACT
This research presents neutronic calculations for heavy water research reactor core substituting hydride fuel for uranium dioxide fuel. The aim of this research is feasibility analysis of reactor utilization with its original design using a new proposed fuel and changing the coolant and moderator circuit to light water. The required group constants for the CITATION code will be calculated using WIMSD-4 code. Neutronic calculations such as multiplication factors, radial and axial power peaking factor and fuel burn-up calculations are carried out by the CITATION code.
This research presents neutronic calculations for heavy water research reactor core substituting hydride fuel for uranium dioxide fuel. The aim of this research is feasibility analysis of reactor utilization with its original design using a new proposed fuel and changing the coolant and moderator circuit to light water. The required group constants for the CITATION code will be calculated using WIMSD-4 code. Neutronic calculations such as multiplication factors, radial and axial power peaking factor and fuel burn-up calculations are carried out by the CITATION code.
Cite this paper
nullS. Tashakor, F. Javidkia and M. Hashemi-Tilehnoee, "Neutronic Analysis of Generic Heavy Water Research Reactor Core Parameters to Use Standard Hydride Fuel," World Journal of Nuclear Science and Technology, Vol. 1 No. 2, 2011, pp. 46-49. doi: 10.4236/wjnst.2011.12008.
nullS. Tashakor, F. Javidkia and M. Hashemi-Tilehnoee, "Neutronic Analysis of Generic Heavy Water Research Reactor Core Parameters to Use Standard Hydride Fuel," World Journal of Nuclear Science and Technology, Vol. 1 No. 2, 2011, pp. 46-49. doi: 10.4236/wjnst.2011.12008.
References
[1] D. Olander, E. Greenspan, H. D. Garkisch and P. Bojan, “Uranium-Zirconium Hydride Fuel Properties,” Nuclear Engineering and Design, Vol. 239, No. 8, 2009, pp. 1406-1424. doi:10.1016/j.nucengdes.2009.04.001 [2] E. Greenspana, M. Fratoni, F. Ganda, F. Ginex, D. Olander, N. Todreas, P. Diller, P. Ferroni, J. Malen, A. Romano, C. Shuffler, J. Trant, B. Petrovic and H. Garkisch, “Hydride fuel for LWRs-Project Overview,” Nuclear Engineering and Design, Vol. 239, No. 8, 2009, pp. 1374-1405. doi:10.1016/j.nucengdes.2008.11.023 [3] A. Romano, C. A. Shuffler, H. D. Garkisch, D. R. Olander and N. E. Todreas, “Fuel Performance Analysis for PWR Cores,” Nuclear Engineering and Design, Vol. 239, No. 8, 2009, pp. 1481-1488. doi:10.1016/j.nucengdes.2008.11.022 [4] F. Ganda and E. Greenspan, “Neutronic analysis of Hydride Fueled PWR Cores,” Nuclear Engineering and Design, Vol. 239, No. 8, 2009, pp. 1425-1441. doi:10.1016/j.nucengdes.2008.12.027 [5] F. Faghihi, E. Ramezani, F. Yousefpour and S. M. Mirvakili, “Level-1 Probability Safety Assessment of the Iranian Heavy Water Reactor Using SAPHIRE Software,” Reliability Engineering and System Safety, Vol. 93, No. 10, 2008, pp. 1377-1409. doi:10.1016/j.ress.2007.10.002 [6] M. Hashemi-Tilehnoee, A. Pazirandeh and S. Tashakor, “HAZOP-Study on Heavy Water Research Reactor Primary Cooling System,” Annals of Nuclear Energy, Vol. 37, No. 3, 2010, pp. 428-433. doi:10.1016/j.anucene.2009.12.006 [7] S. Q. B. Leite, “An Assessment of WIMS Method for Computing Collision Probabilities in One-Dimensional Annular Systems,” Progress in Nuclear Energy, Vol. 36, No. 4, 2000, pp. 367-378. doi:10.1016/S0149-1970(00)00015-9 [8] Oak Ridge National Laboratory, “CITATION-LDI2 code,” Oak Ridge, 1972. [9] Oak Ridge Department of Energy (DOE) Fundamentals Handbook, “Nuclear Physics and Reactor Theory”, Vol. 1-2, 1993. [10] D. G. Cacuci, “Handbook of Nuclear Engineering,” Springer Science Publications, Berlin, 2010. doi:10.1007/978-0-387-98149-9
[1] D. Olander, E. Greenspan, H. D. Garkisch and P. Bojan, “Uranium-Zirconium Hydride Fuel Properties,” Nuclear Engineering and Design, Vol. 239, No. 8, 2009, pp. 1406-1424. doi:10.1016/j.nucengdes.2009.04.001 [2] E. Greenspana, M. Fratoni, F. Ganda, F. Ginex, D. Olander, N. Todreas, P. Diller, P. Ferroni, J. Malen, A. Romano, C. Shuffler, J. Trant, B. Petrovic and H. Garkisch, “Hydride fuel for LWRs-Project Overview,” Nuclear Engineering and Design, Vol. 239, No. 8, 2009, pp. 1374-1405. doi:10.1016/j.nucengdes.2008.11.023 [3] A. Romano, C. A. Shuffler, H. D. Garkisch, D. R. Olander and N. E. Todreas, “Fuel Performance Analysis for PWR Cores,” Nuclear Engineering and Design, Vol. 239, No. 8, 2009, pp. 1481-1488. doi:10.1016/j.nucengdes.2008.11.022 [4] F. Ganda and E. Greenspan, “Neutronic analysis of Hydride Fueled PWR Cores,” Nuclear Engineering and Design, Vol. 239, No. 8, 2009, pp. 1425-1441. doi:10.1016/j.nucengdes.2008.12.027 [5] F. Faghihi, E. Ramezani, F. Yousefpour and S. M. Mirvakili, “Level-1 Probability Safety Assessment of the Iranian Heavy Water Reactor Using SAPHIRE Software,” Reliability Engineering and System Safety, Vol. 93, No. 10, 2008, pp. 1377-1409. doi:10.1016/j.ress.2007.10.002 [6] M. Hashemi-Tilehnoee, A. Pazirandeh and S. Tashakor, “HAZOP-Study on Heavy Water Research Reactor Primary Cooling System,” Annals of Nuclear Energy, Vol. 37, No. 3, 2010, pp. 428-433. doi:10.1016/j.anucene.2009.12.006 [7] S. Q. B. Leite, “An Assessment of WIMS Method for Computing Collision Probabilities in One-Dimensional Annular Systems,” Progress in Nuclear Energy, Vol. 36, No. 4, 2000, pp. 367-378. doi:10.1016/S0149-1970(00)00015-9 [8] Oak Ridge National Laboratory, “CITATION-LDI2 code,” Oak Ridge, 1972. [9] Oak Ridge Department of Energy (DOE) Fundamentals Handbook, “Nuclear Physics and Reactor Theory”, Vol. 1-2, 1993. [10] D. G. Cacuci, “Handbook of Nuclear Engineering,” Springer Science Publications, Berlin, 2010. doi:10.1007/978-0-387-98149-9