Technical Report Archive & Image Library (TRAIL) - 105 Matching Results
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- Validation of the Generic TRUEX Model Using Data from TRUEX Demonstrations with Actual High-Level Waste
- The Generic TRUEX Model (GTM) was used to simulate three different counter-current flowsheet tests performed using mixer-settlers that had been carried out prior to 1993 in the Chemical Processing Facility, Tokai-works, of the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. The feed for the PNC runs was the highly active raffinate from reprocessing of spent fuel from fast breeder reactors. The PNC demonstration runs were planned without using the GTM. Results predicted by the GTM and those obtained experimentally by PNC for the three demonstration runs are compared. Effects of stage efficiency, nitrate complexation, temperature, and equipment type are also included.
- VARIANT: VARIational Anisotropic Nodal Transport for Multidimensional Cartesian and Hexagonal Geometry Calculation
- The theoretical basis, implementation information and numerical results are presented for VARIANT (VARIational Anisotropic Neutron Transport), a FORTRAN module of the DIF3D code system at Argonne National Laboratory. VARIANT employs the variational nodal method to solve multigroup steady-state neutron diffusion and transport problems. The variational nodal method is a hybrid finite element method that guarantees nodal balance and permits spatial refinement through the use of hierarchical complete polynomial trial functions. Angular variables are expanded with complete or simplified P₁, P₃ or P₅5 spherical harmonics approximations with full anisotropic scattering capability. Nodal response matrices are obtained, and the within-group equations are solved by red-black or four-color iteration, accelerated by a partitioned matrix algorithm. Fission source and upscatter iterations strategies follow those of DIF3D. Two- and three-dimensional Cartesian and hexagonal geometries are implemented. Forward and adjoint eigenvalue, fixed source, gamma heating, and criticality (concentration) search problems may be performed.
- Weight Losses of Marble and Limestone Briquettes Exposed to Outdoor Environment in the Eastern United States: Results of Exposure 1988-1992
- Monitoring continued on weight changes in marble and limestone briquettes exposed to the outdoor environment at sites in the eastern US. This report presents data for the exposure period 1988 - 1992 and summarizes results for the entire period from 1984. Since 1989, only three exposure sites have remained active, but briquettes from pre-exposed material were added at those sites. A linear relationship was found between cumulative gravimetric losses and exposure period. These losses resulted in an average recession rate of 11 to 21 micrometers/yr for marble and 21 to 45 micrometers/yr for limestone. The recession rates are site-dependent and can be described with respect to rain depth and other atmospheric conditions, as evidenced by the very low rates at the Ohio site on the movable rack, dry regime. Weight monitoring is continuing in a planned 10-year program.
- Well-Point Containment of Impoundment Leakage
- Research was conducted to evaluate the effectiveness of a well-point dewatering system in conjunction with a french drain to intercept waste impoundment leakage while reducing the volume of waste water requiring treatment. A well-point dewatering system composed of 585 production wells was installed around the perimeter of a leaking impoundment that previously used only a french-drain system for leakage control. The placement of the well-point system was designed to intercept and remove the leakage from the groundwater before the contaminant reached the french drain. Groundwater monitoring at this site revealed that after a period of approximately 40 days the well-point dewatering system had stabilized and effectively prevented the further spread of contamination to the french drain.
- Yucca Mountain Project - Argonne National Laboratory Annual Progress Report, FY 1994
- This document reports on the work done by the Nuclear Waste Management Section of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1993-September 1994. Studies have been performed to evaluate the performance of nuclear waste glass and spent fuel samples under unsaturated conditions (low volume water contact) that are likely to exist in the Yucca Mountain environment being considered as a potential site for a high-level waste repository. Tests with simulated waste glasses have been in progress for over eight years and demonstrate that actinides from initially fresh glass surfaces will be released as a result of the spallation of reacted glass layers from the surface, as the small volume of water passes over the waste form.