Monte Carlo methods are used to compute fluxes or dose rates over large areas using mesh tallies. For problems that demand that the uncertainty in each mesh cell be less than some set maximum, computation time is controlled by the cell with the largest uncertainty. This issue becomes quite troublesome in deep-penetration problems, and advanced variance reduction techniques are required to obtain reasonable uncertainties over large areas.
In this project the MAVRIC sequence will be evaluated along with the Monte Carlo engine Monaco to investigate its effectiveness and usefulness in facility shielding and dose rate analyses. A previously MCNP-evaluated cask array from the Yucca Mountain Project’s proposed aging pad and/or buffer area design will be utilized for evaluation and benchmarking purposes. In addition, dose mapping will be performed inside the surface facilities utilizing a transportation cask to evaluate the codes’ effectiveness and also ability to calculate deep-penetration problems. Because of the dimensions and the large amount of shielding required for GNEP facilities, advanced variance reduction techniques beyond today’s capabilities will certainly be required. Thus this evaluation will benefit the GNEP program. In addition, with the Generation IV Nuclear Energy System Initiative, it will become increasingly important to be able to accurately model advanced BWR and PWR facilities and to calculate dose rates at all locations within a containment (e.g., resulting from radiations from the reactor as well as the from the primary coolant loop) and adjoining structures (e.g., from the spent fuel pool).
Monte Carlo method; Nuclear reactors; Radiation — Dosage; Radiation dosimetry; Shielding (Radiation); Statistics
Nuclear | Nuclear Engineering | Oil, Gas, and Energy | Statistical Methodology | Statistical Models
Monaco/MAVRIC Evaluation for Facility Shielding and Dose Rate Analysis: To Support the Global Nuclear Energy Partnership.
Available at: http://digitalscholarship.unlv.edu/hrc_trp_reactor/24