1D/2D benchmark experiments of aluminum alloy irradiated by 14 MeV neutrons for ICF facilities

• Published in: Fusion engineering and design Vol. 189; p. 113467
• Main Authors: Li, Yu, Chen, Zhilin, Lai, Caifeng, Cheng, Shenghan, Yang, Yang, Peng, Taiping
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01.04.2023
• Subjects: 14 MeV neutron; Aluminum alloy; Benchmark experiment; Dose rate; Neutron activation; Benchmark experiment; Neutron activation; Dose rate; 14 MeV neutron; Aluminum alloy
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2023.113467

•1D/2D benchmark experiments on 5083 aluminum alloy were carried out with DT neutron sources at INPC.•The air kerma rates outside the assemblies after irradiation and activities of activation foils were measured.•Calculated results using the R2S method based on transport code JMCT with FENDL-3.1d and inventory code FISPACT with EAF-2007 were compared with the measured ones.•Simulations show good agreement with measurements within ±20%. Aluminum alloy (5083) is one of the most important structural materials used in laser-driven Inertial Confinement Fusion (ICF) facilities, which will be exposed to high-yield 14 MeV neutrons and highly activated after the DT explosion. Reliable estimation of shutdown dose rate levels is of great importance for machine operation planning and to ensure the safety of people entering into target bay. Both 1D and 2D benchmark experiments were performed on a DT neutron accelerator at the Institute of Nuclear Physics and Chemistry (INPC) to validate the calculation codes and cross section libraries (JMCT with FENDL-3.1d and FISPACT with EAF-2007) used in the simulations of neutron transport and activation for aluminum alloy 5083. The total neutron yield was about 6 × 1014 in the experiments. Both radioactivity of foils placed inside the assembly and air kerma rate at given positions out of the assembly have been measured in 1D/2D experiments. Monte-Carlo code JMCT with FENDL-3.1d was used in both neutron and gamma-ray transport, and the inventory code FISPACT with EAF-2007 was used to calculate neutron activation. Results show that the relative error for air kerma rate in simulations and experiments is less than 20%, and radioisotopes give different contribution ratios on dose levels for 1D/2D experimental assemblies after DT neutron irradiation, especially for 24Na, 27Mg and 56Mn at the time within 16 h after neutron irradiated. Besides, simulations of radioactivity give good agreement with experimental results obtained for radioisotopes 24Na, 196Au, 57Ni and 58Co in both 1D and 2D experiments, and the relative error is less than ±16%.