The dimensions and the large amount of shielding required for Global Nuclear Energy Partnership (GNEP) facilities, advanced radiation shielding, and dose computation techniques are beyond today’s capabilities and will certainly be required. With the Generation IV Nuclear Energy System Initiative, it will become increasingly important to be able to accurately model advanced Boiling Water Reactor and Pressurized Water Reactor 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).
The MAVRIC sequence is being 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 effectiveness of the code systems. The ability to calculate doses in deep-penetration problems will also be evaluated.
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.
Available at: http://digitalscholarship.unlv.edu/hrc_trp_reactor/25