MONTE CARLO SIMULATION OF THE NEUTRON AND GAMMA TRANSPORT EQUATIONS ON COMPUTERS WITH ARITHMETIC ACCELERATORS
I. V. Semenov, A. G. Mal'kin, A. S. Rybkin
VANT. Ser.: Mat. Mod. Fiz. Proc 2014. Вып.3. С. 59-70.
The paper presents results of the development of SMK-U code complex for solving the time-independent neutron and gamma transport equation with the use of arithmetic accelerators. The main algorithmic modifications, as compared to SMK code, are described. Numerical investigations of the speedup have been performed for a number of nuclear power engineering problems. Keywords: arithmetic accelerator, graphical processor, Monte Carlo method, parallelization in events, fuel element, fuel assembly, WWER-1000.
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