Measurement of leakage neutron spectra with D-T neutrons and evaluated nuclear data

Rui Han,Zhiqiang Chen,Yangbo Nie,Hui Sun,Xin Zhang,Suyalatu Zhang,Fudong Shi,Guoyu Tian,Bingyan Liu,Z Ge,Y Chen,N Shu,H Zhang,W Wang

doi:10.1051/epjconf/202023918009

Abstract

Benchmarking of evaluated neutron nuclear data libraries was performed for ∼14.8 MeV neutrons on the several targets, such as gallium, graphite, silicon carbide, uranium and tungsten samples. The experiments were performed at China Institute of Atomic Energy (CIAE). The neutron leakage spectra from the samples were measured at 60◦ and 120◦ by a TOF technique with a BC501A scintillation detector. The measured spectra are rather well reproduced by MCNP-4C simulations with the CENDL3.1, JENDL-4.0 and the new release ENDF/B-VIII.0, JEFF-3.3 evaluated nuclear data libraries and so on. There have some difference between experiments and simulations for the elastic and inelastic contributions in the partial energy range. And the discrepancies of the neutron leakage spectra in the MCNP simulations originate simply from the differences in the spectra distributions of the neutron reaction channels in the evaluated nuclear data libraries.

Highlights

The experimental studies of fast neutron scattering are important for design of nuclear reactors [1, 2] and accelerator driven subcritical systems (ADS) [3, 4]
They play a crucial role for verification of the evaluated nuclear data libraries, especially some elements that are of interest in ADS, fission and fusion reactor technologies, such as spallation target material, structural material, fission fuel and so on
The results show that the experimental neutron leakage spectra are well reproduced by the four evaluated nuclear data libraries, except below 3 MeV enrgy range with the ENDF/B-VIII.0 and JEFF-3.3 libraries

Summary

Introduction

The experimental studies of fast neutron scattering are important for design of nuclear reactors [1, 2] and accelerator driven subcritical systems (ADS) [3, 4] They play a crucial role for verification of the evaluated nuclear data libraries, especially some elements that are of interest in ADS, fission and fusion reactor technologies, such as spallation target material (gallium and tungsten), structural material (graphite and silicon carbide), fission fuel (uranium) and so on. For these nuclear engineering design, precise and reliable nuclear data, and detailed study of the neutronics are required.

Measurements and simulations

Gallium

Graphite

Silicon carbide

Uranium

Summary