FUELING RPS WITH MEDIUM AND MEDIUM HEAVY METAL ISOTOPES FROM FRESH SPENT NUCLEAR FUEL OF LWR

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  • Zhou Yangping
    Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University
  • Gu Zhengwei
    Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University
  • Li Zhengcao
    State Key Laboratory of New Ceramics and Fine Processing, Key Laboratory of Advanced Materials (MOE), School of Materials Science and Engineering, Tsinghua University
  • Shi Lei
    Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University
  • Dong Yujie
    Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University
  • Zhang Zuoyi
    Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University

抄録

All energy systems, including nuclear energy systems, are facing the challenge for economy and environment protection which are now closely related. In order to improve the economy of nuclear energy and reduce the amount of nuclear waste, here we propose a scheme to use a group of medium and medium heavy metal isotopes from fresh spent nuclear fuel as the fuel of Radioisotope Power Systems (RPS) based on the design of Multi-Mission Radioisotope Thermoelectric Generator (MMRTG) by Department of Energy, USA. The composite isotopes from fission products of light-water reactor are chosen to fuel the Spent Nuclear Fuel-Multi-Mission Radioisotope Power Systems (SNF-MMRPS) regarding the balance of Decay Heat Density (DHD), technique feasibility and economy for mass production and waste reduction. Several concept designs are introduced to provide power and/or heat in different hash environments (e.g. space and remote area). We also discussed the advantages, disadvantages and present challenges of the SNF-MMRPS.

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