JMCT Monte Carlo Code with Capability of Integrating Nuclear System Feedback

DOI

10.2991/ammsa-18.2018.10How to use a DOI?

Keywords

monte carlo transport; multi-physics coupled calculation; high fidelity; JMCT; BEAVRS

Abstract

JMCT is a general purpose 3D Mont Carlo (MC) neutron-photon-electron and coupled neutron/photon/electron transport code with a continuous energy and multigroup. The program is developed based on the combinatorial geometry parallel infrastructure JCOGIN and with the most functions of general Monte Carlo particle transport code which include the various variance reduction techniques, Doppler broadening on-the-fly (OTF), uniform tally density (UTD), consistent adjoint driven importance sampling (CADIS), fast criticality search of boron concentration, the domain decomposition (DD), the two level parallel computation of MPI and OpenMP, etc. The geometry zones, materials, tallies, depletion zones, memories and period of random number are enough big for simulation of various extreme complicated problems. Also JMCT is hybrid the discrete ordinate SN program JSNT to generate source biasing factors and weight window parameters. The CAD modeling and visualized output are equipped. JMCT can provide technology support for reactor physics, criticality safe analysis and shielding design. Especially, JMCT is coupled depletion and thermal-hydraulic for simulation of reactor feedback effects, including depletion, thermal feedback. This paper describes the application of the JMCT to the simulation of BEAVRS model. The results are good consistent with MC21, OpenMC and experiment in hot zero power (HZP). Also, we performed the part calculation of hot full power (HFP) in case of 30 axial planes, where the depletion regions exceed 1.528 million and 120 thousand processors to be used in maximum. The capability of high fidelity is shown.

Copyright

© 2018, the Authors. Published by Atlantis Press.

Open Access

This is an open access article distributed under the CC BY-NC license (http://creativecommons.org/licenses/by-nc/4.0/).

Download article (PDF)

TY  - CONF
AU  - Li Deng
AU  - Gang Li
AU  - Baoyin Zhang
AU  - Rui Li
AU  - Dunfu Shi
AU  - Yuangang Fu
AU  - Danhu Shangguan
AU  - Zehua Hu
AU  - Lingyu Zhang
AU  - Liu Peng
PY  - 2018/05
DA  - 2018/05
TI  - JMCT Monte Carlo Code with Capability of Integrating Nuclear System Feedback
BT  - Proceedings of the 2018 2nd International Conference on Applied Mathematics, Modelling and Statistics Application (AMMSA 2018)
PB  - Atlantis Press
SP  - 48
EP  - 54
SN  - 1951-6851
UR  - https://doi.org/10.2991/ammsa-18.2018.10
DO  - 10.2991/ammsa-18.2018.10
ID  - Deng2018/05
ER  -