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User's manual for RESRAD version 6.

TL;DR: The Residual Radioactivity (RESRAD) code as discussed by the authors has been used to calculate doses and risks from residual radioactive materials and the procedures for applying these models to calculate operational guidelines for soil contamination.
Abstract: This manual provides information on the design and application of the RESidual RADioactivity (RESRAD) code. It describes the basic models and parameters used in the RESRAD code to calculate doses and risks from residual radioactive materials and the procedures for applying these models to calculate operational guidelines for soil contamination. RESRAD has undergone many improvements to make it more realistic in terms of the models used in the code and the parameters used as defaults. Version 6 contains a total of 145 radionuclides (92 principal and 53 associated radionuclides), and the cutoff half-life for associated radionuclides has been reduced to 1 month. Other major improvements to the RESRAD code include its ability to run uncertainty analyses, additional options for graphical and text output, a better dose conversion factor editor, updated databases, a better groundwater transport model for long decay chains, an external ground radiation pathway model, an inhalation area factor model, time-integration of dose and risk, and a better graphical user interface. In addition, RESRAD has been benchmarked against other codes in the environmental assessment and site cleanup arena, and RESRAD models have been verified and validated.

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ANL/EAD-4
User’s Manual for RESRAD Version 6
Environmental Assessment Division
Argonne National Laboratory
Operated by The University of Chicago,
under Contract W-31-109-Eng-38, for the
United States Department of Energy

Argonne National Laboratory
Argonne National Laboratory, with facilities in the states of Illinois and Idaho, is
owned by the United States Government and operated by The University
of Chicago under the provisions of a contract with the Department of Energy.
This technical report is a product of Argonne’s Environmental Assessment
Division (EAD). For information on the division's scientific and engineering
activities, contact:
Director, Environmental Assessment Division
Argonne National Laboratory
Argonne, Illinois 60439-4815
Telephone (630) 252-3107
Publishing support services were provided by Argonne’s Information
and Publishing Division (for more information, see IPD’s home page:
http://www.ipd.anl.gov/).
Disclaimer
This report was prepared as an account of work sponsored by an agency of the
United States Government. Neither the United States Government nor any agency
thereof, nor The University of Chicago, nor any of their employees or officers,
makes any warranty, express or implied, or assumes any legal liability or
responsibility for the accuracy, completeness, or usefulness of any information,
apparatus, product, or process disclosed, or represents that its use would not
infringe privately owned rights. Reference herein to any specific commercial
product, process, or service by trade name, trademark, manufacturer, or otherwise
does not necessarily constitute or imply its endorsement, recommendation, or
favoring by the United States Government or any agency thereof. The views and
opinions of document authors expressed herein do not necessarily state or reflect
those of the United States Government or any agency thereof, Argonne National
Laboratory, or The University of Chicago.
Available electronically at http://www.doe.gov/bridge
Available for a processing fee to U.S. Department of
Energy and its contractors, in paper, from:
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phone: (865) 576-8401
fax: (865) 576-5728
email: reports@adonis.osti.gov

* Wallo and Peterson are affiliated with the Office of Environmental Policy and Assistance and Williams with
the Office of Site Closure, U.S. Department of Energy, Washington, D.C.
ANL/EAD-4
User’s Manual for RESRAD Version 6
by C. Yu, A.J. Zielen, J.-J. Cheng, D.J. LePoire, E. Gnanapragasam, S. Kamboj,
J. Arnish, A. Wallo III,* W.A. Williams,* and H. Peterson*
Environmental Assessment Division
Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439
July 2001
Work sponsored by U.S. Department of Energy, Assistant Secretary for Environment,
Safety and Health, Office of Environmental Policy and Assistance, and Assistant Secretary
for Environmental Management, Office of Site Closure

This report is printed on recycled paper.

iii
CONTENTS
PREFACE .............................................................. xi
ACKNOWLEDGMENTS .................................................. xv
DOE FOREWORD ....................................................... xvii
NOTATION ............................................................. xxi
ABSTRACT............................................................. 1-1
1 INTRODUCTION ..................................................... 1-3
2 PATHWAY ANALYSIS ................................................ 2-1
2.1 Source Terms .................................................... 2-2
2.1.1 Geometry of the Contaminated Zone ............................ 2-2
2.1.2 Time Dependence ........................................... 2-3
2.1.3 Redistribution .............................................. 2-3
2.2 Pathways ........................................................ 2-3
2.2.1 Pathway Identification ....................................... 2-3
2.2.2 External Radiation Pathways .................................. 2-6
2.2.3 Inhalation Pathways ......................................... 2-6
2.2.4 Ingestion Pathways .......................................... 2-7
2.2.4.1 Food Pathways ...................................... 2-7
2.2.4.2 Water Pathway Segments .............................. 2-9
2.2.4.3 Drinking Water Pathway .............................. 2-12
2.2.4.4 Soil Ingestion Pathway................................ 2-12
2.3 Dose Conversion Factors ........................................... 2-12
2.3.1 Ingestion and Inhalation ...................................... 2-13
2.3.2 External Radiation .......................................... 2-15
2.4 Exposure Scenarios................................................ 2-16
2.4.1 Resident Farmer Scenario ..................................... 2-16
2.4.2 Suburban Resident, Industrial Worker, and Recreationist Scenarios .... 2-20
3 GUIDELINES FOR RADIONUCLIDE CONCENTRATIONS IN SOIL .......... 3-1
3.1 Radiological Release Criteria ........................................ 3-1
3.2 Dose/Source Concentration Ratios for Uniform Contamination ............. 3-11
3.2.1 Dose Conversion Factors ..................................... 3-14
3.2.2 Environmental Transport Factors ............................... 3-15
3.2.3 Source Factors .............................................. 3-16
3.3 Guidelines for Inhomogeneous Contamination .......................... 3-16

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Cites background or methods from "User's manual for RESRAD version 6...."

  • ...These recommended values have been incorporated into many predictive food chain models (e.g. Brown and Simmonds, 1995; Müller and Pr€ohl, 1993; USNRC, 1977; Yu et al., 2001)....

    [...]

  • ...In this paper, we assess our ability to extrapolate radioecological data of relevance towildlife radiological assessments considering these recent advances and future potential....

    [...]

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TL;DR: Toxicity characteristic leaching procedure (TCLP) (EPA Method 1311) was used to assess the leaching behavior of Ra-226 in the impoundment sludge and its implications for waste management strategies for this low-level radioactive solid waste.
Abstract: Natural gas extraction from Marcellus Shale generates large quantities of flowback water that contain high levels of salinity, heavy metals, and naturally occurring radioactive material (NORM). This water is typically stored in centralized storage impoundments or tanks prior to reuse, treatment or disposal. The fate of Ra-226, which is the dominant NORM component in flowback water, in three centralized storage impoundments in southwestern Pennsylvania was investigated during a 2.5-year period. Field sampling revealed that Ra-226 concentration in these storage facilities depends on the management strategy but is generally increasing during the reuse of flowback water for hydraulic fracturing. In addition, Ra-226 is enriched in the bottom solids (e.g., impoundment sludge), where it increased from less than 10 pCi/g for fresh sludge to several hundred pCi/g for aged sludge. A combination of sequential extraction procedure (SEP) and chemical composition analysis of impoundment sludge revealed that Barite is t...

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TL;DR: The results indicate that, under current water resource exploitation programs, reuse or disposal of the treatment wastes from large scale urban water treatment plants in Australia do not pose a significant radiological risk.

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01 Jan 2003
TL;DR: In this paper, the authors provided a complete description of calculations and their results estimating potential annual doses, normalized to a unit concentration, to an individual following the clearance of specific materials.
Abstract: NUREG-1640 iii ABSTRACT This report provides a complete description of calculations and their results estimating potential annual doses, normalized to a unit concentration, to an individual following the clearance of specific materials. These materials are scrap iron and steel, copper, aluminum, and concrete rubble from licensed nuclear facilities. Clearance means the removal of radiological controls by the licensing authority. The estimated potential doses are calculated probabilistically to account for a large number of possible variations in each of the 86 scenarios. These scenarios encompass the full range of realistic situations likely to yield the greatest normalized doses. Each scenario was analyzed with the 115 radionuclides considered most likely to be associated with materials from licensed nuclear facilities. The design basis of the analyses is to realistically model current processes, to identify critical groups on a nuclide-by-nuclide basis, and to enable the conversion of a dose criterion to a concentration. Material for recycle or disposal was evaluated using material flow models and dose assessment models. Both models are based on probabilistic methods. This resulted in distributions of nuclide-by-nuclide normalized doses from one year of exposure per massor surface-based concentrations. The means and the 5th, 50th, 90th, and 95th percentiles are reported. These percentiles can be used to generically evaluate the likelihood that the derived mean concentration would correspond to a particular dose criterion. Additionally, they can be used to quantify the confidence that a safety goal is not exceeded.

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References
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Journal ArticleDOI
TL;DR: In this paper, a power function relating soil moisture and hydraulic conductivity is used to derive a formula for the wetting front suction required by the Green-Ampt equation.
Abstract: The soil moisture characteristic may be modeled as a power curve combined with a short parabolic section near saturation to represent gradual air entry. This two-part function—together with a power function relating soil moisture and hydraulic conductivity—is used to derive a formula for the wetting front suction required by the Green-Ampt equation. Representative parameters for the moisture characteristic, the wetting front suction, and the sorptivity, a parameter in the infiltration equation derived by Philip (1957), are computed by using the desorption data of Holtan et al. (1968). Average values of the parameters, and associated standard deviations, are calculated for 11 soil textural classes. The results of this study indicate that the exponent of the moisture characteristic power curve can be predicted reasonably well from soil texture and that gradual air entry may have a considerable effect on a soil's wetting front suction.

2,273 citations

Journal ArticleDOI
TL;DR: In this paper, a model to predict annual-average, order-of-magnitude leaching constants for solutes in agricultural soils is given, specific by geographic location and solute, are for use in exposure, dose, or risk assessment models to account for removal from the root zone via leaching in a manner analogous to radiological decay.
Abstract: A model to predict annual-average, order-of-magnitude leaching constants for solutes in agricultural soils is given. The leaching constants, specific by geographic location and solute, are for use in exposure, dose, or risk assessment models to account for removal from the root zone via leaching in a manner analogous to radiological decay. The model presented here relates annual-average water infiltration (Vw) with soil bulk density (ϱ) and porosity (θ) and the distribution coefficient (Kd) for the solute. Annual infiltration is determined from site-specific estimates of total precipitation (P), irrigation (I), and evapotranspiration (E). A review, discussion, and determination of generic default model input parameters is included. The parameters ϱ and θ vary within a factor of three, and are lognormally distributed with estimated geometric mean values of 1.35 g cm⁻³ and 0.48 cm³ cm⁻³, respectively. Geographic distributions of U.S. county-averaged P, I, and E were determined from historical weather station records, the 1974 Agricultural Census, and an evapotranspiration model, respectively. Variability in site-specific annual-average estimates of these parameters is expected to be within a factor of three, also. The most variable and unpredictable parameter is Kd, which may range from one to many orders of magnitude, depending on solute and soil characteristics, including pH. Estimated distributions of Kd for 27 elements in soils 4.5 ≤ pH ≤ 9.0, and correlations between Kd and pH for Cu, Zn, Cd, and Pb are also included. Finally, eight comparisons of model predictions with leaching constants, determined directly from observed data, are made for Pu, Sr, and Tc. In all comparisons, except one study of Pu, the model predicted leaching constants within an order of magnitude of observed values. For Pu the model underpredicted, and for Sr and Tc the model overpredicted leaching rates.

131 citations

Journal ArticleDOI
TL;DR: In this paper, the air in a room was cleaned, and then airborne particulate matter was collected for various subsequent time intervals simultaneously in the room and outdoors nearby by pumping air through filters; the filters were analyzed by X-ray excitation for elements known to be primarily of outdoor origin (Fe, Zn, Pb, Br, Ca).

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This manual provides information on the design and application of the RESidual RADioactivity ( RESRAD ) code.