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We propose a technique to effectively sample initial neutron and delayedneutron precursor particles for Monte Carlo (MC) simulations of typicaloff-critical reactor transients. The technique can be seen as an improvement,or alternative, to the existing ones. Similar to some existing techniques, theproposed sampling technique uses the standard MC criticality calculation.However, different from the others, the technique effectively producesuniform-weight particles around user-specified target sizes. The technique isimplemented into the open-source Python-based MC code MC/DC and verifiedagainst an infinite homogeneous 361-group medium problem and the 3D C5G7-TDbenchmark model.

An effective initial particle sampling technique for Monte Carlo reactor transient simulations