LYU Niu, XIA Zhao-dong, ZHU Qing-fu. Calculation Study of Criticality Safety for Tianwan Nuclear Power Plant Spent Fuel Dry Storage[J]. Atomic Energy Science and Technology, 2017, 51(8): 1442-1446. DOI: 10.7538/yzk.2017.51.08.1442
Citation: LYU Niu, XIA Zhao-dong, ZHU Qing-fu. Calculation Study of Criticality Safety for Tianwan Nuclear Power Plant Spent Fuel Dry Storage[J]. Atomic Energy Science and Technology, 2017, 51(8): 1442-1446. DOI: 10.7538/yzk.2017.51.08.1442

Calculation Study of Criticality Safety for Tianwan Nuclear Power Plant Spent Fuel Dry Storage

  • Exampled by the dry storage container CASTOR 1000/19 loading Tianwan Nuclear Power Plant hexagonal spent fuel assembly, the criticality safety of dry storage of hexagonal spent fuel assembly was studied. Based on fresh fuel assumption, the keff of the CASTOR 1000/19 loading hexagonal spent fuel assembly fully was calculated at different conditions by using the MONK9A code. The results show that keff is far less than the critical safety limit under normal condition, i.e. it is safe. When the 235U enrichment is greater than 3.15%, the system has critical safety risk at accident conditions. And the loading capacity had to be reduced to ensure the criticality safety. Considering burnup credit (BUC), a reference loading curve was proposed based on the same calculation model, which could ensure criticality safety. The availability of the storage container increases by adopting BUC. The achievements could be reference for spent fuel dry storage scheme in Tianwan Nuclear Power Plant.
  • loading

Catalog

    Turn off MathJax
    Article Contents

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return