Abstract
Reactor safety analyses require high-fidelity numerical solutions of transient neutron transport problems. A predictor–corrector quasi-static (PCQS) method based on the Monte Carlo (MC) simulation is developed and implemented into the Reactor Monte Carlo code (RMC). This method used a hybrid stochastic-deterministic scheme utilizing point kinetic equation formalism to solve transient problems without geometric and energy spectrum approximations and to offer accurate kinetic parameters as well. The PCQS MC method and the RMC code are verified here for the C5G7-TD transient benchmark sub-critical cases. The computational time of this method is only about 1% of that for the quasi-static DMC method. The RMC results agree within about 1% with results of the SUHAM and nTRACER codes for the TD2-1, TD4-4 and TD1-3 cases. The denoising method based on polynomial fittings used here improves the results for these cases.
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