Chai Xiaoming, Tu Xiaolan, Guo Fengchen, et al. Development and preliminary V&V for advanced neutron transport lattice code KYLIN-2[J]. High Power Laser and Particle Beams, 2017, 29: 016016. doi: 10.11884/HPLPB201729.160306
Citation:
Chai Xiaoming, Tu Xiaolan, Guo Fengchen, et al. Development and preliminary V&V for advanced neutron transport lattice code KYLIN-2[J]. High Power Laser and Particle Beams, 2017, 29: 016016. doi: 10.11884/HPLPB201729.160306
Chai Xiaoming, Tu Xiaolan, Guo Fengchen, et al. Development and preliminary V&V for advanced neutron transport lattice code KYLIN-2[J]. High Power Laser and Particle Beams, 2017, 29: 016016. doi: 10.11884/HPLPB201729.160306
Citation:
Chai Xiaoming, Tu Xiaolan, Guo Fengchen, et al. Development and preliminary V&V for advanced neutron transport lattice code KYLIN-2[J]. High Power Laser and Particle Beams, 2017, 29: 016016. doi: 10.11884/HPLPB201729.160306
In order to simulate the complex structure fuel assembly, Nuclear Power Institute of China(NPIC) has developed an advanced neutron transport lattice code, named KYLIN-2. The subgroup method is adopted in KYLIN-2 to treat resonance problems. And method of characteristics(MOC) is used to solve neutron transport equation and generalized coarse mesh finite difference(GCMFD) method is used to accelerate the calculation. In order to solve the depletion equation, CRAM method and PPC method are used. The graphical input and display interface are developed to make sure the KYLIN-2 code can be used easily by engineers. The numerical results show that the KYLIN-2 can calculate the PWR assembly accurately.