TY - GEN
T1 - Resonance calculation code UFOP based on the hyper-fine group neutron resonance calculation method
AU - Qin, Yulong
AU - Wu, Hongchun
AU - Cao, Liangzhi
AU - Liu, Qingjie
PY - 2010
Y1 - 2010
N2 - Resonance self-shielding calculation is very important in reactor physics calculation. Conventional resonance calculation method has some fundamental defects, which hinders its application in some problems. The Hyperfine Energy Group Resonance Calculation Method is studied in this paper and a code named UFOP is developed based on this method. In this method, the resonance energy range is divided into hyperfine energy intervals (tens of thousands) and the collision probabilities are calculated. Then the slowing-down equation is directly solved based on CPM (collision probability method). Some techniques are applied in solving the slowing-down equation for improving computational efficiency and reducing calculation error. A resonance benchmark problem with homogeneous and infinite material is calculated to validate the accuracy of the computation code and the hyper-fine group cross-section library utilized in the code. A PWR fuel cell is also calculated and the results are compared with MCNP. The results show good accuracy of this method and the validity of UFOP code.
AB - Resonance self-shielding calculation is very important in reactor physics calculation. Conventional resonance calculation method has some fundamental defects, which hinders its application in some problems. The Hyperfine Energy Group Resonance Calculation Method is studied in this paper and a code named UFOP is developed based on this method. In this method, the resonance energy range is divided into hyperfine energy intervals (tens of thousands) and the collision probabilities are calculated. Then the slowing-down equation is directly solved based on CPM (collision probability method). Some techniques are applied in solving the slowing-down equation for improving computational efficiency and reducing calculation error. A resonance benchmark problem with homogeneous and infinite material is calculated to validate the accuracy of the computation code and the hyper-fine group cross-section library utilized in the code. A PWR fuel cell is also calculated and the results are compared with MCNP. The results show good accuracy of this method and the validity of UFOP code.
UR - https://www.scopus.com/pages/publications/80053256076
U2 - 10.1115/ICONE18-29491
DO - 10.1115/ICONE18-29491
M3 - 会议稿件
AN - SCOPUS:80053256076
SN - 9780791849309
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - 18th International Conference on Nuclear Engineering, ICONE18
T2 - 18th International Conference on Nuclear Engineering, ICONE18
Y2 - 17 May 2010 through 21 May 2010
ER -