A Neutronics and Burnup Analysis of the Accelerator-Driven Transmutation System with Cross Section Libraries

摘要

The difference of the neutronics and burnup characteristics of the Accelerator-Driven System (ADS) caused by the different nuclear data libraries, JENDL-3.2, ENDF/B-VI and JEF-2.2, was analyzed. It is important to know the current accuracy of the cross section data of the Minor Actinides (Np, Am, Cm) to improve the reliability of the analysis and to guarantee the subcriticality of the fuel region of ADS. The analysis was performed with benchmark problems of the OECD/NEA ADS transmuter. An ATRAS code system and a MVp code were used for the analysis. Group cross section sets were newly created from JENDL-3.2, ENDF/B-VI and JEF-2.2, respectively. To make the difference of the MA cross section data clearly, the group cross sections generated from JENDL-3.2 were used for cooling and structural nuclides of ENDF/B-VI and JEF-2.2. From the results of the analysis, JENDL-3.2 and JEF-2.2 gives close k-effective values and similar trends of burnup reactivity swing. However, ENDF/B-VI gives different k-effective values and burnup changes from other two libraries.