The Lead–Bismuth Eutectic (LBE) spallation target has been considered as one of the two alternatives for the spallation target for China Initiative Accelerator-Driven System. This paper reports the preliminary study on physical feasibility of a U-type LBE target with window. The simulation results based on Monte Carlo transport code MCNPX indicate that the spallation neutron yield is about 2.5 per proton. The maximum spallation neutron flux is observed at about 3 cm below the lowest part of the window. When the LBE target is coupled with the reactor, the reactor neutrons from the fission reaction increased the neutron field significantly. The energy deposition of high-energy protons is the main heat source; the spallation neutrons and reactor neutrons contribute only a small fraction. The maximum energy deposition in the LBE is about 590 W/cm3 and that in the target window is about 319 W/cm3. To estimate the lifetime of the target window, we have calculated the radiation damages. The maximum displacement production rate in the target window is about 10 dpa/FPY. The hydrogen and helium production rates generated during normal operation were also evaluated. By analyzing the residual nucleus in the target during the steady operation, we estimated the accumulated quantities of the extreme radioactivity toxicant 210Po in the LBE target loop. The results would be helpful for the evaluation of the target behavior and will be beneficial to the optimization of the target design work of the experimental facilities.
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The authors would like to express their thanks to the colleague in INEST for having provided us with the design scheme of CLEAR-I.
This work is supported by Strategic Priority Research Program of Chinese Academy of Sciences under Grant Number of XDA03030102.
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Zhang, L., Yang, YW. & Gao, YC. Preliminary physics study of the Lead–Bismuth Eutectic spallation target for China Initiative Accelerator-Driven System. NUCL SCI TECH 27, 120 (2016). https://doi.org/10.1007/s41365-016-0114-6
- LBE spallation target
- Target behavior in subcritical reactor
- Neutron flux
- Energy deposition
- Radiation damage
- 210Po accumulated quantities