• Title of article

    Development of a safety analysis code for molten salt reactors Original Research Article

  • Author/Authors

    Dalin Zhang، نويسنده , , Suizheng Qiu، نويسنده , , Guanghui Su، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2009
  • Pages
    8
  • From page
    2778
  • To page
    2785
  • Abstract
    The molten salt reactor (MSR) well suited to fulfill the criteria defined by the Generation IV International Forum (GIF) is presently revisited all around the world because of different attractive features of current renewed relevance. The MSRs are characterized by using the fluid-fuel, so that their technologies are fundamentally different from those used in the conventional solid-fuel reactors. In this work, in particular, the attention is focused on the safety characteristic analysis of the MSRs, in which a point kinetic model considering the flow effects of the fuel salt is established for the MSRs and calculated by developing a microcomputer code coupling with a simplified heat transfer model in the core. The founded models and developed code are applied to analyze the safety characteristics of the molten salt actinide recycler and transmuter system (MOSART) by simulating three types of basic transient conditions including the unprotected loss of flow, unprotected overcooling accident and unprotected transient overpower. Some reasonable results are obtained for the MOSART, which show that the MOSART conceptual design is an inherently stable reactor design. The present study provides some valuable information for the research and design of the new generation MSRs.
  • Journal title
    Nuclear Engineering and Design Eslah
  • Serial Year
    2009
  • Journal title
    Nuclear Engineering and Design Eslah
  • Record number

    895486