Nuclear Techniques ›› 2015, Vol. 38 ›› Issue (3): 30201-030201.doi: 10.11889/j.0253-3219.2015.hjs.38.030201

• LOW ENERGY ACCELERATOR, RAY AND APPLICATIONS • Previous Articles     Next Articles

Study on improving MCNP computational efficiency of dose rate for a single-rack cobalt irradiation facility

LI Lei LI Xiaoyan HUANG Wei JIANG Shubin WU Xiaoli YANG Guixia   

  1. (Institute of Nuclear Physics and Chemistry, Chinese Academy of Engineering Physics, Mianyang 621900, China)
  • Received:2014-03-10 Revised:2014-07-29 Online:2015-03-10 Published:2015-03-09


Background: Monte Carlo method is regarded as the most accurate method for dose rate calculation at present, whereas its time-consuming defect increases complication for its application in industrial irradiation processing and experiment. Purpose: For a single-rack cobalt irradiation facility with loaded activity of 8.4PBq, a study of optimizing MCNP (Monte Carlo N Particle Transport Code) parameters was done to improve computational efficiency of dose rate. Methods: The effects of five parameters on MCNP computational efficiency, including the thread numbers of parallel computation, tally method, cell size, cutoff energy, and methods dealing with γ-induced electrons were discussed. Results: With certain precision and relative error, the least time-consuming situation was achieved with a set of five parameters, including parallel computation with hyper-thread mode, *F6 tally, cell size of 1cm, γ transport mode and γ-cutoff energy of 100keV. Conclusion: In this work, the cost of time was reduced about 57 times, and the improvement of MCNP computational efficiency was realized.

Key words: Single-rack cobalt irradiation facility, Absorbed dose rate, MCNP (Monte Carlo N Particle Transport Code), Computational efficiency