Verification of the direct transport code SHARK with the JRR-3M macro benchmark

The Combined Fission Matrix (CFM) method entails the instantaneous estimation of the entire system's fission matrix by amalgamating fission matrices from a pre-existing database. This approach allows for the rapid and accurate determination of the effective multiplication factor (keff) and the distribution of fission rates across the reactor system. This work applies the CFM method to the Japan Research Reactor-3 (JRR-3M), a water-cooled plate-type reactor. The CFM method demonstrates a high level of agreement with Monte Carlo (MC) simulation results, completing calculations within a minute. In the two cases of 'All Absorbers In' and 'All Absorbers Out', this method achieved a low root-mean-square (RMS) error of only 0.4% and 1% , respectively, with keff-error of 44 pcm and 24 pcm .

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Verification of the direct transport code SHARK with the JRR-3M macro benchmark

Cited by 4 publications

References 11 publications

An efficient parallel algorithm of variational nodal method for heterogeneous neutron transport problems

An efficient parallel algorithm of variational nodal method for heterogeneous neutron transport problems

Validation of whole core transport code SHARK with HPR1000 experiment

Application of Combined Fission Matrix to Plate-type Research Reactor

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