1. T. Bahadir and S. Ö. Lindahl. Studsvik’s next generation nodal code SIMULATE-5. m. Nucl. Soc. - 4th Top. Meet. Adv. Nucl. Fuel Manag. 2009, ANFM IV, vol. 2, no. Anfm, pp. 992-1003, 2009.
2. An analysis of condensation errors in multi-group cross-section generation for fine-mesh neutron transport calculations;Boyd;Ann. Nucl. Energy,2018
3. Burnup dependent Monte Carlo neutron physics calculations of IAEA MTR benchmark;Chaudri;Prog. Nucl. Energy,2015
4. Impact of inflow transport approximation on light water reactor analysis;Choi;J. Comput. Phys.,2015
5. Gelbard EM. Application of spherical harmonics method to reactor problems. Bettis Atomic Power Laboratory, West Mifflin, PA, Technical Report No. WAPD-BT-20, 1960.