Reactor dosimetry applications using a parallel 3-D radiation transport code

A computer-implemented method for simulating a three dimensional radiation field distribution of neutron and gamma radiation in a nuclear reactor to calculate ex-vessel dosimetry responses, the nuclear reactor comprising a reactor vessel and a reactor core, said method comprising:

• generating a geometrical model of the reactor core;
• generating a material distribution of the reactor core;
• calculating the neutron and gamma radiation using a radiation transport methodology, the transport methodology comprising:
• calculating a distribution of particles throughout a phase space by generating a solution of the Linearized Boltzmann Equation (LBE) which includes solving discrete ordinates method (SN) equations;
• generating a solution to the SN equations on 3-D Cartesian or cylindrical geometries using domain decomposition algorithm methodology, the algorithm methodology comprising:
• partitioning angular and spatial domains of the phase space into subsets;
• allocating independently the subsets to a plurality of processors;
• and
• processing the subsets on the plurality of processors.