Yuhan Fan , Rui Yan , Guifeng Zhu , Liang Chen , Naiwen Zhang , Yang Zou
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引用次数: 0
Abstract
Micro reactor is an ideal choice for future deep space exploration mission due to their advantage of stability, long life and minisize. In this study, a Megawatt Gas-Cooled Reactor concept design using Prismatic CERMET(PC-MGCR) is proposed. It aims to support 1MWe power for both electric thrusters and detection equipment operation in 10 years. The helium-xenon binary gas is simultaneously used for reactor coolant and working medium of the Brayton cycle to simplify the system. The influence of core parameters of fuel pin, core size, radial reflector on reactor miniaturization and neutron economy is investigated by Monte Carlo code OpenMC. The difference of Spectral Shift Absorbers(SSAs), control drum(CD) and control rod(CR) on typical accident critical safety is analyzed. An applicable control rod layout scheme with maximum shutdown depth is determined based on control rod interference and flux distribution. The control rod and the control drum represent a similar variation on the effective multiplication factor, with the maximum differential worth appearing at 60˚ and 17.5 cm, respectively. The core can tolerate the failure of 6 control drums and 1 control rod or all control drums in the dropping accident, which reveals high security. The reactor core optimization result based on miniaturization and falling accident critical safety objectives are further obtained. The parameters of the optimized core are evaluated quantitatively from various aspects. The result shows that PC-MGCR has an extremely hard neutron spectrum and a negative fuel temperature coefficient of −0.258pcm/K with a sensitive control and inherent safety. The power and flux distribution of the active core in different states are obtained. Core power distribution is increasingly flat due to unevenly depletion. The comparison results with existing schemes demonstrates the PC-MGCR exists visible advantages in increasing the fuel inventory, the miniaturization, burnup depth and high-temperature operation. Relevant design and analysis results can provide the reference for the subsequent PC-MGCR.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.