YUAN Long-jun, CHEN Yi-xue, HAN Jing-ru. Fast Neutron Fluence Calculation Benchmark Analysis Based on 3D MC S N Bidirectional Coupling Method[J]. Atomic Energy Science and Technology, 2014, 48(3): 407-411. DOI: 10.7538/yzk.2014.48.03.0407
Citation: YUAN Long-jun, CHEN Yi-xue, HAN Jing-ru. Fast Neutron Fluence Calculation Benchmark Analysis Based on 3D MC S N Bidirectional Coupling Method[J]. Atomic Energy Science and Technology, 2014, 48(3): 407-411. DOI: 10.7538/yzk.2014.48.03.0407

Fast Neutron Fluence Calculation Benchmark Analysis Based on 3D MC S N Bidirectional Coupling Method

  • The Monte Carlo (MC)-discrete ordinates (SN) bidirectional coupling method is an efficient approach to solve shielding calculation of the large complex nuclear facility. The test calculation was taken by the application of the MC-SN bidirectional coupling method on the shielding calculation of the large PWR nuclear facility. Based on the characteristics of NUREG/CR-6115 PWR benchmark model issued by the NRC, 3D Monte Carlo code was employed to accurately simulate the structure from the core to the thermal shield and the dedicated model of the calculation parts locating in the pressure vessel, while the TORT was used for the calculation from the thermal shield to the second down-comer region. The transform between particle probability distribution of MC and angular flux density of SN was realized by the interface program to achieve the coupling calculation. The calculation results were compared with MCNP and DORT solutions of benchmark report and satisfactory agreements were obtained. The preliminary validity of feasibility by using the method to solve shielding problem of a large complex nuclear device was proved.
  • loading

Catalog

    Turn off MathJax
    Article Contents

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return