锆评价核数据的聚变中子学积分实验研究

中子学积分实验是检验评价核数据可靠性的重要手段和研究方法。锆的热中子吸收截面低，熔点高、耐腐蚀性能好，被广泛用作核反应堆燃料包壳和堆芯结构材料，其评价中子核数据的准确性直接影响着中子学计算、核装置设计与安全及核理论计算结果的质量。最新版本不同评价库的锆数据之间，以及与实验数据之间仍存在着较大分歧。当前关于锆评价核数据的积分实验非常稀少，因此开展锆的中子学积分实验对检验和改进现有评价数据、提高数据质量具有十分重要的意义。本项目计划在中国原子能科学研究院D-T中子源积分实验装置上，利用一种新型中子探测器EJ-299-33A测量锆平板样品不同方向泄漏的中子谱。同时，利用MCNP程序结合不同评价中子数据库，计算得到相同实验条件的中子谱。通过比较分析实验泄漏中子谱与计算结果，对锆评价中子核数据进行中子学基准检验研究。

Neutronics integral experiment has been a powerful tool and method for examining the reliability of evaluated nuclear data. Zirconium is widely used as nuclear reactor fuel cladding and other structure materials, because of its high melting point, strong corrosion resistance, low neutron absorption cross section. The accuracy of zirconium evaluated neutron nuclear data directly affect the results of reactor neutronics calculation, nuclear facility design and nuclear theoretical calculations. The most recently evaluated nuclear data and the available experimental data still show large discrepancies. At present, the integral experiments of zirconium evaluated neutron data are very scarce worldwide. However, it have very important meaning to perform the zirconium neutronics integral experiments for testing and improving of present evaluated data, and increasing the quality of nuclear data. In this proposal, leakage neutron spectra at different emission angles from zirconium slab sample are measured with a new type of neutron detector EJ-299-33A at the D-T neutron source integral experimental facility of China Institute of Atomic Energy. Also, the calculations of leakage neutron spectra are performed by using the MCNP code and the evaluated nuclear data from different libraries following the same experimental conditions. Neutronics benchmark validations of zirconium evaluated neutron data will be studied by the comparisons between experimental leakage neutron spectra with calculated ones.