Conversion of U-238 and Th-232 Using a Fusion Neutron Source

作者: Xianjun Zheng , Baiquan Deng , Wei Ou , Fujun Gou

DOI: 10.4236/WJNST.2014.44028

关键词: FusionNeutronFission productsBerylliumNuclear engineeringNuclear powerNuclear physicsEnergy conversion efficiencyNuclear transmutationPhysicsBlanket

摘要: This article proposes a general framework for the conversion of U-238 and Th-232 utilizing fusion-produced neutrons. recognizes that emerging fusion technologies may not produce sufficient net energy output to justify stand-alone applications, yet be commercially viable breeder transmutation or hybrid fusion-fission reactor concepts proposed herein dispose nuclear wastes long life high radioactive fission products remaining in shutdown power plants. Results show this could achievable within decade, given an appropriate source. However, if 20% beryllium nuclei density is added convertor blanket, efficiency process can significantly increased. Also, neutron spectrum resulting from dense D-D plasma core much softer than D-T source, hence probability (n, p) α) backward decay reaction paths will smaller elevated.

参考文章(4)
B.Q. Deng, Z.X. Li, C.Y. Li, K.M. Feng, Tritium well depth, tritium well time and sponge mechanism for reducing tritium retention Nuclear Fusion. ,vol. 51, pp. 073041- ,(2011) , 10.1088/0029-5515/51/7/073041
Bai-Quan Deng, J.P. Allain, Zheng-Ming Luo, Li-Lin Peng, Jian-Cheng Yan, Near-surface bipartition model for the study of material response of plasma-facing surfaces exposed to energetic charged particles Nuclear Instruments & Methods in Physics Research Section B-beam Interactions With Materials and Atoms. ,vol. 259, pp. 847- 852 ,(2007) , 10.1016/J.NIMB.2007.03.013
Baiquan Deng, Zaixin Li, Jinhua Huang, Tao Yuan, Computer Simulation of Tritium Inventory and Leakage of the Fusion Experimental Reactor FEB-E Fusion Science and Technology. ,vol. 46, pp. 548- 560 ,(2004) , 10.13182/FST04-A590