TY - JOUR
T1 - 快堆程序SARAX中不可分辨共振区有效自屏截面计算方法研究
AU - Wei, Linfang
AU - Wu, Hongchun
AU - Zheng, Youqi
AU - Du, Xianan
AU - Yuan, Xianbao
N1 - Publisher Copyright:
© 2018, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.
PY - 2018/12/20
Y1 - 2018/12/20
N2 - In fast reactors, the neutron flux level in Unresolved Resonance Region (URR) of 238U is relatively high, and the accuracy of cross-section in corresponding energy regions makes direct influence on the fast reactor spectrum and homogenized cross-section calculation. Aiming at effective self-shielding cross-section calculation in URR of 238U, this paper improves the spectrum calculation code TULIP in SARAX. TULIP uses background cross-section interpolation in URR, but the accuracy of interpolation significantly affects the final results. Considering that the content ratio of 238U in fast reactor assemblies is large and the background cross-section of 238U is small, this paper analyzes the requirements of cross-section interpolation for 238U in URR, and verifies the effectiveness of improving calculation accuracy with denser background cross-section interpolation points by comparing the reaction rate before and after making denser interpolation points of 238U. Then, the accuracy of SARAX code at high temperatures is improved.
AB - In fast reactors, the neutron flux level in Unresolved Resonance Region (URR) of 238U is relatively high, and the accuracy of cross-section in corresponding energy regions makes direct influence on the fast reactor spectrum and homogenized cross-section calculation. Aiming at effective self-shielding cross-section calculation in URR of 238U, this paper improves the spectrum calculation code TULIP in SARAX. TULIP uses background cross-section interpolation in URR, but the accuracy of interpolation significantly affects the final results. Considering that the content ratio of 238U in fast reactor assemblies is large and the background cross-section of 238U is small, this paper analyzes the requirements of cross-section interpolation for 238U in URR, and verifies the effectiveness of improving calculation accuracy with denser background cross-section interpolation points by comparing the reaction rate before and after making denser interpolation points of 238U. Then, the accuracy of SARAX code at high temperatures is improved.
KW - Background cross-section interpolation
KW - Effective self-shielding cross-section
KW - SARAX
KW - Unresolved resonance
UR - https://www.scopus.com/pages/publications/85062967260
U2 - 10.13832/j.jnpe.2018.S2.0038
DO - 10.13832/j.jnpe.2018.S2.0038
M3 - 文章
AN - SCOPUS:85062967260
SN - 0258-0926
VL - 39
SP - 38
EP - 42
JO - Hedongli Gongcheng/Nuclear Power Engineering
JF - Hedongli Gongcheng/Nuclear Power Engineering
ER -