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Radioisotope Power System Facility shielding analysis

Description: A series of calculations for the Radioisotope Power System Facility have been performed. These analyses have determined the shielding required for storage, testing, and transport of /sup 238/Pu heat source modules using the Monte Carlo code MCNP3B. The source terms and the assumptions used have been verified by comparison of calculated dose rates with measured ones. This paper describes the methodology used for shielding designs and the utilization of available variance reduction techniques to … more
Date: January 1, 1989
Creator: Lu, A.H. & Morford, R.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Development of an adjoint sensitivity method for site characterization, uncertainty analysis, and code calibration/validation

Description: The adjoint method is applied to groundwater flow-mass transport coupled equations in variably saturated media. The sensitivity coefficients derived by this method can be calculated by a single execution for each performance measure regardless of the number of parameters in question. The method provides an efficient and effective way to rank the importance of the parameters, so that data collection can be guided in support of site characterization programs. The developed code will facilitate th… more
Date: September 1, 1991
Creator: Lu, A.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Finite-element model evaluation of barrier configurations to reduce infiltration into waste-disposal structures: preliminary results and design considerations

Description: Barriers to reduce infiltration into waste burial disposal structures (trenches, pits, etc.) may be required to provide adequate waste confinement. The preliminary engineering design of these barriers should consider interrelated barrier performance factors. This paper summarizes preliminary computer simulation activities to further engineering barrier design efforts. Several barrier configurations were conceived and evaluated. Models were simulated for each barrier configuration using a finite… more
Date: September 1, 1982
Creator: Lu, A.H.; Phillips, S.J. & Adams, M.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Interpretation and modeling of a subsurface injection test, 200 East Area, Hanford, Washington

Description: A tracer experiment was conducted in 1980 and 1981 in the unsaturated zone in the southeast portion of the Hanford 200 East Area near the Plutonium-Uranium Extraction (PUREX) facility. The field design consisted of a central injection well with 32 monitoring wells within an 8-m radius. Water containing radioactive and other tracers was injected weekly during the experiment. The unique features of the experiment were the documented control of the inputs, the experiment`s three-dimensional nature… more
Date: November 1, 1994
Creator: Smoot, J.L. & Lu, A.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Contaminant transport in unconfined aquifer, input to low-level tank waste interim performance assessment

Description: This report describes briefly the Hanford sitewide groundwater model and its application to the Low-Level Tank Waste Disposal (LLTWD) interim Performance Assessment (PA). The Well Intercept Factor (WIF) or dilution factor from a given areal flux entering the aquifer released from the LLTWD site are calculated for base case and various sensitivity cases. In conjunction with the calculation for released fluxes through vadose zone transport,the dose at the compliance point can be obtained by a sim… more
Date: August 14, 1996
Creator: Lu, A.H., Westinghouse Hanford
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Performance assessment for the disposal of low-level waste in the 200 West Area Burial Grounds

Description: This document reports the findings of a performance assessment (PA) analysis for the disposal of solid low-level radioactive waste (LLW) in the 200 West Area Low-Level Waste Burial Grounds (LLBG) in the northwest corner of the 200 West Area of the Hanford Site. This PA analysis is required by US Department of Energy (DOE) Order 5820.2A (DOE 1988a) to demonstrate that a given disposal practice is in compliance with a set of performance objectives quantified in the order. These performance object… more
Date: June 1, 1995
Creator: Wood, M. I.; Khaleel, R.; Rittmann, P. D.; Lu, A. H.; Finfrock, S. H.; DeLorenzo, T. H. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Re-evaluation of a subsurface injection experiment for testing flow and transport models

Description: The current preferred method for disposal of low-level radioactive waste (LLW) at the Hanford Site is to vitrify the wastes so they can be stored in a near-surface, shallow-land burial facility (Shord 1995). Pacific Northwest Laboratory (PNL) managed the PNL Vitrification Technology Development (PVTD) Project to assist Westinghouse Hanford Company (WHC) in designing and assessing the performance of a disposal facility for the vitrified LLW. Vadose zone flow and transport models are recognized a… more
Date: December 1, 1995
Creator: Fayer, M. J.; Lewis, R. E.; Engelman, R. E.; Pearson, A. L.; Murray, C. J.; Smoot, J. L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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