A Preliminary Radiological Risk Assessment Model for Disposition of Remote-Handled Transuranic Wastes at Los Alamos National Laboratory Area G

摘要

The U.S. Department of Energy operates a low-level radioactive waste disposal site at Material Disposal Area G in Los Alamos, N.M. Area G has been the primary LLW disposal site for Los Alamos National Laboratory (LANL) since the 1960s. In addition to LLW, Area G is host to a variety of other wastes, the disposition of which must be determined before closure of the site. A probabilistic radiological risk assessment (RRA) for Area G is used in order to support decision-making regarding some wastes that are not addressed in the extant Area G Performance Assessment (PA) and Composite Analysis (CA).Between 1979 and 1987, 33 special shafts were bored into the Bandelier Tuff at Area G. This volcanic tuff is present across Pajarito Plateau on the eastern slopes of the Jemez Mountains and varies widely in its consistency, from weakly indurated non-welded layers to welded layers that uphold the mesa cliffs of the plateau. These mesas are home to LANL, Area G, and the town-sites of Los Alamos and White Rock, with residences about 1,400 meters from Area G. The 33 shafts were lined with steel casing and contain remote-handled transuranic wastes (TRU) resulting from experiments and analysis performed in special glove boxes at the Chemistry and Metallurgy Research facility at LANL. Some of these wastes originated as used nuclear fuel.The purpose of the Area G RRA is to evaluate the potential future risk to humans and the environment from the remote-handled TRU in the 33 shafts in the context of the risk associated with the surrounding wastes at Area G. The analysis is responsive to expectations outlined in DOE Order 458.1, Radiation Protection of the Public and the Environment, and is informed by the manual and guidance accompanying DOE Order 435.1, Radioactive Waste Management. Because the waste meets the definition of TRU, the regulatory context necessarily takes into consideration the regulation governing the disposal of TRU from the U.S. Environmental Protection Agency: 40 CFR 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-level and Transuranic Radioactive Wastes.Given the broader regulatory context for the RRA, the analysis is subject to different assumptions from those made in the existing DOE Order 435.1 PA and CA, such as allowing for future occupation of the site. The analysis begins with a comprehensive evaluation of features, events, processes, and exposure scenarios (FEPS) for Area G and the wastes it contains. These FEPSs are screened to eliminate from further consideration those of extremely low probability and/or consequence, and a conceptual site model (CSM) is subsequently developed. The scope and structure of the Area G RRA model is informed by this CSM, and the Area G RRA model is developed using the GoldSim systems analysis modeling platform.This paper presents the initial version of a defensible, transparent, and reasonably realistic model, which is based on the state of knowledge of the wastes, the site, and the FEPSs that govern contaminant transport from wastes into the environment and subsequent exposures to humans and other biota. Probabilistic model input distributions represent uncertainties inherent in the real and modeled systems. The results of the Area G RRA model inform decisions regarding the disposition of the remote-handled TRU in the 33 shafts.