Measurement And Simulation Study Of Leakage Spectra By Time-of-flight Method With Iron Slab

The integral experimental study on the fusion neutron,as a means of testing and evaluating the quality of neutron database data,is of great significance.A large number of integral experiments have been carried out in the major international databases and played an important part in updating the databases whereas the domestic relevant experiments is insufficient.Iron is a so important structural material of nuclear device that the accuracy of fast neutron cross section data is of great significance to the design of new nuclear device.In this paper,research in D-T fusion neutron integral experimental tests and simulation have been found by taking iron slab as the sample which in the purpose of integral examination of neutron database.The main approach of the research and results is introduced below.Research in the methods of experiment and data processing and related theory about the integral neutron experiments have been found on the neutron database integral benchmark experimental facility in China Institute of Atomic Energy.By taking the method of time-of-flight,the measurement of the neutron leakage spectra from iron slab samples of different thickness at 60°and 120°was completed.And the neutron leakage spectra were dealt with data acquisition system,considering the n-? discrimination of original data,background subtraction,reconstruction and normalization.The model of D-T fast neutron source,experimental geometry arrangement and material was established.According to the ENDF/B-VII.1,CENDL-3.1 and JENDL-4.0 libraries,the neutron spectra leaking from 60°and 120° iron slab sample in the D-T fusion neutron source was simulating by Monte Carlo method.Comparison between the time-of-flight of simulation and experiments in four energy area,the results come to the ratio of calculation and experiments(C/E)and primarily accomplish the integral examination in the test of iron database in the three libraries.The main obtained conclusion are summarized as follows:(1)in the elastic scattering energy region about 12MeV-16 MeV,the data in ENDF/B-VII.1 was higher in contrast to the JENDL-4.0 and more reliable in CENDL-3.1;(2)in the inelastic scattering energy of discrete energy-level region about 8.5MeV-12 MeV,the data in ENDF/B-VII.1 was lower in contrast to the JENDL-4.0 and more reliable in CENDL-3.1,(3)in the inelastic scattering energy of continuous energy-level region about 3.0MeV-8.5MeV,the data quality of three libraries was better;(4)in the(n,2n)region about 0.8MeV-3.0MeV,the data in ENDF/B-VII.1 and CENDL-3.1 was quite higher,and more reliable in JENDL-4.0.