EPJ Web Conf.
Volume 153, 2017ICRS-13 & RPSD-2016, 13th International Conference on Radiation Shielding & 19th Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society - 2016
|Number of page(s)||6|
|Section||6. Calculation Methods Monte Carlo & Deterministic|
|Published online||25 September 2017|
JMCT Monte Carlo Simulation Analysis of BEAVRS and SG-III Shielding
1 Institute of Applied Physics and Computational Mathematics (IAPCM), Beijing, China
2 CAEP Software Centre for High Performance Numerical Simulation(CAEP-SCNS), Beijing, China
* Corresponding author: firstname.lastname@example.org
Published online: 25 September 2017
JMCT is a general purpose Mont Carlo neutron-photon-electron or coupled neutron/photon/electron transport code with a continuous energy and multigroup. The code has almost all functions of a general Monte Carlo code which include the various variance reduction techniques, the multi-level parallel computation of MPI and OpenMP, the domain decomposition and on-fly Doppler broadening, etc. Especially, JMCT supports the depletion calculation with TTA and CRAM methods. The input uses the CAD modelling and the calculated results use the visual output. The geometry zones, materials, tallies, depletion zones, memories and the period of random number are enough big for suit of various problems. This paper describes the application of the JMCT Monte Carlo code to the simulation of BEAVRS and SG-III shielding model. For BEAVRS model, the JMCT results of HZP status are almost the same with MC21, OpenMC and experiment. Also, we performed the coupled calculation of neutron transport and depletion in full power. The results of ten depletion steps are obtained, where the depletion regions exceed 1.5 million and 120 thousand processors to be used. Due to no coupled with thermal hydraulics, the result is only for reference. Finally, we performed the detail modelling for Chinese SG-III laser facility, where the anomalistic geometry bodies exceed 10 thousands. The flux distribution of the radiation shielding is obtain based on the mesh tally in case of Deuterium-Tritium fusion reaction. The high fidelity of JMCT has been shown.
© The Authors, published by EDP Sciences, 2017
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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