The Integral Experimental Study On The Fusion Neutronics

Neutron integral experiment is an important method for checking up evaluated neutron nuclear data. It plays significant role not only on the development of nuclear weapons, but also on the design of fusion reactors. The polyethylene is an important neutron shielding material. The nuclear reaction section data of C and H are quite consummate. Therefore the integral experiment on polyethylene sample is usually used to check out neutron transport theory, computational method and the simulative code. It is also an important method to verify the experimental system.In this paper, the experiment method of the leakage spectrum of polyethylene blanket sample based on the plus neutron source of T(d,n)~4He reaction was investigated. Firstly, the model of T(d,n) He reaction neutron was set up using the data of neutron energy spectrum and angular distribution from TARGET code, and the leakage spectrum of polyethylene blanket sample was simulated using MCNP code. The efficiency of detector was also computed using NEFF code. Secondly, a experimental measurement on the leakage spectrum of polyethylene blanket sample using Time-of -flight method (TOF) was carried out in 600 KV T(d,n)~4He reaction pulse neutron generator of CIAE. An experimental leakage spectrum of polyethylene blanket sample was presented. The ratio of the simulated leakage spectrum and the experimental leakage spectrum (C/E ratio) was presented.