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Some aspects of low-level radioactive-waste disposal in the US

Description: This report summarizes the NRC supported Shallow Land Burial research program at Brookhaven National Laboraotry and its relationship to the proposed revised ruling on disposal of low level radioactive waste, 10 CFR Part 61. Section of the proposed regulation, which establish the new low level waste classification system and the performance objective placed on waste form, are described briefly. The report also summarizes the preliminary results obtained from the EPA program in which low level wa… more
Date: January 1, 1982
Creator: Schweitzer, D.G. & Davis, R.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Low-level-waste-form criteria

Description: Efforts in five areas are reported: technical considerations for a high-integrity container for resin wastes; permissible radionuclide loadings for organic ion exchange resin wastes; technical factors affecting low-level waste form acceptance requirements of the proposed 10 CFR 61 and draft BTP; modeling of groundwater transport; and analysis of soils from low-level waste disposal sites (Barnwell, Hanford, and Sheffield). (DLC)
Date: January 1, 1982
Creator: Barletta, R.E. & Davis, R.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Source terms for analysis of accidents at a high level waste repository

Description: This paper describes an approach to identifying source terms from possible accidents during the preclosure phase of a high-level nuclear waste repository. A review of the literature on repository safety analyses indicated that source term estimation is in a preliminary stage, largely based on judgement-based scoping analyses. The approach developed here was to partition the accident space into domains defined by certain threshold values of temperature and impact energy density which may arise i… more
Date: January 1, 1989
Creator: Mubayi, V.; Davis, R.E. & Youngblood, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Wet and dry cycle leaching: aspects of releases in the unsaturated zone

Description: The NRC criteria of containment and controlled release for a HLW repository have in the past been addressed by leaching and radionuclide release experiments that correspond to repository flooding or temporally independent saturation. Both high-level waste repository and low-level waste burial sites can be expected to experience unsaturated conditions, as determined by the nature, frequency, and length of the wetting fronts. An important aspect of radionuclide release in the unsaturated zone is … more
Date: January 1, 1983
Creator: Dayal, R.; Davis, R.E. & Schweitzer, D.G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Impact of Zr metal and coking reactions on the ex-vessel source term predictions of CORCON/VANESA

Description: During a core meltdown accident in a LWR, molten core materials (corium) could leave the reactor vessel and interact with concrete. In this paper, the impact of the zirconium content of the corium pool and the coking reaction on the release of fission products are quantified using CORCON/Mod2 and VANESA computer codes. Detailed calculations show that the total aerosol generation is proportional to the zirconium content of the corium pool. Among the twelve fission product groups treated by the V… more
Date: January 1, 1987
Creator: Lee, M.; Davis, R.E. & Khatib-Rahbar, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Impact of Zr metal and coking reactions on the fission product aerosol release during MCCI (Molten Core Concrete Interactions)

Description: During a core meltdown accident in a light water reactor, molten core materials (corium) could leave the reactor vessel and interact with concrete. In this paper, the impact of the zirconium content of the corium pool and the coking reaction on the release of fission products during Molten Core Concrete Interactions (MCCI) are quantified using CORCON/MOD2 and VANESA computer codes. Detailed calculations show that the total aerosol generation is proportional to the zirconium content of the coriu… more
Date: January 1, 1987
Creator: Lee, M.; Davis, R.E. & Khatib-Rahbar, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Biodegradation testing of bitumen

Description: An estimate of the rate of biodegradation of bituminous material is necessary to predict the long-term stability of low- and intermediate-level waste solidified using bitumen. Data from a series of scoping experiments have been analyzed to determine the rate of degradation of blown bitumen samples under a variety of conditions. Among the variables investigated were the effect of soil type, moisture, sample surface area and microbial strain. The rate of degradation was measured by monitoring met… more
Date: January 1, 1986
Creator: Barletta, R.E.; Bowerman, B.S.; Davis, R.E. & Shea, C.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Leach behavior and mechanical-integrity studies of irradiated Epicor-II waste products

Description: The leachability of Cs and Sr from cement solidified ion exchange media claimed to be representative of the Epicor-II prefilters (D-mix) is presented. The Cs and Sr release is significantly lower than that typically observed for organic ion exchange resin/cement composites. The effect of radiation up to a total dose of 10/sup 7/ Gy upon the leachability and mechanical integrity (as measured by MCC-11) of D-mix/cement composites has been investigated. No deleterious effects were found. 6 figures. more
Date: January 1, 1982
Creator: Barletta, R. E.; Swyler, K. J.; Chan, S. F. & Davis, R. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Risk comparisons based on representative source terms with the NUREG-1150 results

Description: Standardized source terms, based on a specified release of fission products during potential accidents at commercial light water nuclear reactors, have been used for a long time for regulatory purposes. The siting of nuclear power plants, for example, which is governed by Part 100 of the Code of Federal Regulations Title 10, has utilized the source term recommended in TID-14844 supplemented by Regulatory Guides 1.3 and 1.4 and the Standard Review Plan. With the introduction of probabilistic ris… more
Date: December 1, 1993
Creator: Mubayi, V.; Davis, R. E. & Hanson, A. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Calculations in support of a potential definition of large release

Description: The Nuclear Regulatory Commission has stated a hierarchy of safety goals with the qualitative safety goals as Level I of the hierarchy, backed up by the quantitative health objectives as Level II and the large release guideline as Level III. The large release guideline has been stated in qualitative terms as a magnitude of release of the core inventory whose frequency should not exceed 10{sup -6} per reactor year. However, the Commission did not provide a quantitative specification of a large r… more
Date: May 1, 1994
Creator: Hanson, A. L.; Davis, R. E. & Mubayi, V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Source Term Development for Tritium at the Sheffield Disposal Site

Description: The Sheffield low-level radioactive waste disposal site, which ceased operation in 1978, has been the focus of modeling efforts by the NRC for the purpose of predicting long-term site behavior. To provide the NRC with the information required for its modeling effort, a study to define the source term for tritium in eight trenches at the Sheffield site has been undertaken. Tritium is of special interest since significant concentrations of the isotope have been found in groundwater samples taken … more
Date: 1984~
Creator: MacKenzie, D. R.; Barletta, R. E.; Smalley, J. F.; Kempf, C. R. & Davis, R. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reassessment of selected factors affecting siting of Nuclear Power Plants

Description: Brookhaven National Laboratory has performed a series of probabilistic consequence assessment calculations for nuclear reactor siting. This study takes into account recent insights into severe accident source terms and examines consequences in a risk based format consistent with the quantitative health objectives (QHOs) of the NRC`s Safety Goal Policy. Simplified severe accident source terms developed in this study are based on the risk insights of NUREG-1150. The results of the study indicate … more
Date: February 1997
Creator: Davis, R. E.; Hanson, A. L.; Mubayi, V. & Nourbakhsh, H. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A safety and regulatory assessment of generic BWR and PWR permanently shutdown nuclear power plants

Description: The long-term availability of less expensive power and the increasing plant modification and maintenance costs have caused some utilities to re-examine the economics of nuclear power. As a result, several utilities have opted to permanently shutdown their plants. Each licensee of these permanently shutdown (PSD) plants has submitted plant-specific exemption requests for those regulations that they believe are no longer applicable to their facility. This report presents a regulatory assessment f… more
Date: August 1997
Creator: Travis, R. J.; Davis, R. E.; Grove, E. J. & Azarm, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Assessment of the use of H{sub 2}, CH{sub 4}, NH{sub 3} and CO{sub 2} as NTP propellants. Revision

Description: In this paper the effect of changing from the traditional NTP coolant, hydrogen, to several alternative coolant is studied. Hydrogen is generally chosen as an NTP coolant, since its use maximizes the specific impulse for a given operating temperature. However, there are situations in which it may not be available as optional. The alternative coolant which were considered are ammonia, urethane, carbon dioxide and carbon monoxide. A particle bed reactor (PBR) generating 200 MW and coolant by hydr… more
Date: October 1, 1991
Creator: Selcow, E. C.; Davis, R. E.; Perkins, K. R.; Ludewig, H. & Cerbone, R. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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