SHI Tai, HU Wen-jun, ZHANG Dong-hui. Research and Development of Hypothetical Core Disruptive Accident Code in Fast Breeder Reactor[J]. Atomic Energy Science and Technology, 2015, 49(zengkan1): 132-136. DOI: 10.7538/yzk.2015.49.S0.0132
Citation: SHI Tai, HU Wen-jun, ZHANG Dong-hui. Research and Development of Hypothetical Core Disruptive Accident Code in Fast Breeder Reactor[J]. Atomic Energy Science and Technology, 2015, 49(zengkan1): 132-136. DOI: 10.7538/yzk.2015.49.S0.0132

Research and Development of Hypothetical Core Disruptive Accident Code in Fast Breeder Reactor

  • The liquid metal fast breeder reactor (FBR) is one of the generation Ⅳ nuclear powers, and it is necessary to analyze core disruptive accident of FBR so that the system can contain the radioactive material. The modified Bethe-Tait model is the general method of core disruptive accident analysis. In order to analyze the hypothetical core disruptive accident of FBR, based on the Bethe-Tait model, the core power distribution of FBR was added to the procedure. Compared with the French EPIXCOPOS code results, it is shown that the procedure can analyze core disruptive accident of FBR.
  • loading

Catalog

    Turn off MathJax
    Article Contents

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return