Paper Profile


Comparison of Different Strategies for Global Tallying in Monte Carlo Criticality Calculation


Documents: Full paper available in Conference Proceedings.
 
Date: Tuesday October 20
Time:16:15 - 16:40
 
Session:2C3: Monte Carlo III
 
Authors: Danhua Shangguan (Institute of Applied Physics and Computational Mathematics, China)
BaoYin Zhang (Institute of Applied Physics and Computational Mathematics, China)
Gang Li (Institute of Applied Physics and Computational Mathematics, China)
Li Deng (Institute of Applied Physics and Computational Mathematics, China)
Yan Ma (Institute of Applied Physics and Computational Mathematics, China)
Yuanguang Fu (CAEP Software Center for High Performance Numerical Simulation, China)
Rui Li (CAEP Software Center for High Performance Numerical Simulation, China)
Xiaoli Hu (CAEP Software Center for High Performance Numerical Simulation, China)
Abstract:

We propose the uniform tally density algorithm and the uniform track number density algorithm for biasing the fission secondary neutron number in active cycles of the Monte Carlo criticality calculation when the target is seeking high performance of some global tally and compare these strategies with the original uniform fission site algorithm. Using the global volume averaged cell flux tally and the global energy deposition tally of the pin-by-pin model of Dayawan nuclear reactor as examples, the efficiencies of these strategies are compared carefully. All the strategies are realized in a recently developed parallel Monte Carlo particle transport code JMCT.

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