Abstract:
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.
下载:
