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A method for determining allowable residual contamination levels of radionuclide mixtures in soil

Description: An important consideration in the disposal of radioactive wastes, and consequently in the preparation of plans for remedial actions at contaminated sites, is the amount of radioactive contamination that may be allowed to remain at any particular waste site. The allowable residual contamination level (ARCL) is dependent on the radiation dose limit imposed, the physical and environmental characteristics of the waste site, and the time at which exposure to the wastes is assumed to occur. The steps in generating an ARCL are generally as follows: (1) develop plausible, credible site-specific exposure scenario; (2) calculate maximum annual radiation doses to an individual for each radionuclide based on the existing physical characteristics of the waste site and the site-specific exposure scenario; (3) calculate the ARCL for the dose limit desired, including all radionuclides present, uncorrected for site cleanup or barrier considerations; and (4) apply any corrections for proposed cleanup activity or addition of barriers to waste migration or uptake to obtain the ARCL applicable to the proposed action. Use of this method allows appropriate application of resources to achieve uniform compliance with a single regulatory standard, i.e., a radiation dose rate limit. Application and modification of the ARCL method requires appropriate models of the environmental transport and fate of radionuclides. Example calculations are given for several specific waste forms and waste site types in order to demonstrate the technique and generate comparisons with other approaches.
Date: May 1, 1982
Creator: Napier, B.A.
Partner: UNT Libraries Government Documents Department

Standardized input for Hanford environmental impact statements

Description: Models and computer programs for simulating the environmental behavior of radionuclides in the environment and the resulting radiation dose to humans have been developed over the years by the Environmental Analysis Section staff, Ecological Sciences Department at the Pacific Northwest Laboratory (PNL). Methodologies have evolved for calculating raidation doses from many exposure pathways for any type of release mechanism. Depending on the situation or process being simulated, different sets of computer programs, assumptions, and modeling techniques must be used. This report is a compilation of recommended computer programs and necessary input information for use in calculating doses to members of the general public for environmental impact statements prepared for DOE activities to be conducted on or near the Hanford Reservation.
Date: May 1, 1981
Creator: Napier, B.A.
Partner: UNT Libraries Government Documents Department

Allowable residual contamination levels for decommissioning the 115-F and 117-F facilities at the Hanford Site

Description: This report contains the results of a study sponsored by UNC Nuclear Industries to determine Allowable Residual Contamination Levels (ARCL) for the 115-F and 117-F facilities at the Hanford Site. The purpose of this study is to provide data useful to UNC engineers in conducting safety and cost comparisons for decommissioning alternatives. The ARCL results are based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for three specific modes of future use of the land and facilities. These modes of use are restricted, controlled, and unrestricted. Information on restricted and controlled use is provided to permit a full consideration of decommissioning alternatives. Procedures are presented for modifying the ARCL values to accommodate changes in the radionuclide mixture or concentrations and to determine instrument responses for various mixtures of radionuclides. Finally, a comparison is made between existing decommissioning guidance and the ARCL values calculated for unrestricted release of the 115-F and 117-F facilities. The comparison shows a good agreement.
Date: July 1, 1983
Creator: Kennedy, W.E. Jr. & Napier, B.A.
Partner: UNT Libraries Government Documents Department

Selection of dominant radionuclides for Phase 1 of the Hanford Environmental Dose Reconstruction Project

Description: The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of emissions from nuclear operations at Hanford since their inception in 1944. A vital step in the estimation of radiation doses is the determination of the source term,'' that is, the quantities of radionuclides that were released to the environment from the various Hanford operations. Hanford operations have at various times involved hundreds of different radionuclides, some in relatively large quantities. Those radionuclides present in the largest quantities, although significant from an operational handling point of view, may not necessarily have been those of greatest concern for offsite radiation dose. This report documents the selection of the dominant radionuclides (those that may have resulted in the largest portion of the received doses) in the source term for Phase 1 of the HEDR Project, that is, for atmospheric releases from 1944 through 1947 and for surface water releases from 1964 through 1966. 15 refs., 3 figs., 10 tabs.
Date: July 1, 1991
Creator: Napier, B.A.
Partner: UNT Libraries Government Documents Department

Allowable residual-contamination levels for decommissioning facilities in the 100 areas of the Hanford Site

Description: This report contains the results of a study sponsored by UNC Nuclear Industries to determine Allowable Residual Contamination Levels (ARCL) for five generic categories of facilities in the 100 Areas of the Hanford Site. The purpose of this study is to provide ARCL data useful to UNC engineers in conducting safety and cost comparisons for decommissioning alternatives. The ARCL results are based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for three specific modes of future use of the land and facilities. These modes of use are restricted, controlled, and unrestricted. The information on ARCL values for restricted and controlled use provided by this report is intended to permit a full consideration of decommissioning alternatives. ARCL results are presented both for surface contamination remaining in facilities (in dpm/100 cm/sup 2/), and for unconfined surface and confined subsurface soil conditions (in pCi/g). Two confined soil conditions are considered: contamination at depths between 1 and 4 m, and contamination at depths greater than or equal to 5 m. A set of worksheets are presented in an appendix for modifying the ARCL values to accommodate changes in the radionuclide mixture or concentrations, to consider the impacts of radioactive decay, and to predict instrument responses. Finally, a comparison is made between the unrestricted release ARCL values for the 100 Area facilities and existing decommissioning and land disposal regulations. For surface contamination, the comparison shows good agreement. For soil contamination, the comparison shows good agreement if reasonable modification factors are applied to account for the differences in modeling soil contamination and licensed low-level waste.
Date: July 1, 1983
Creator: Kennedy, W.E. Jr. & Napier, B.A.
Partner: UNT Libraries Government Documents Department

Computational model design specification for Phase 1 of the Hanford Environmental Dose Reconstruction Project

Description: The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of emission from nuclear operations at Hanford since their inception in 1944. The purpose of this report is to outline the basic algorithm and necessary computer calculations to be used to calculate radiation doses specific and hypothetical individuals in the vicinity of Hanford. The system design requirements, those things that must be accomplished, are defined. The system design specifications, the techniques by which those requirements are met, are outlined. Included are the basic equations, logic diagrams, and preliminary definition of the nature of each input distribution. 4 refs., 10 figs., 9 tabs.
Date: July 1, 1991
Creator: Napier, B.A.
Partner: UNT Libraries Government Documents Department

Determination of radionuclides and pathways contributing to dose in 1945

Description: A series of scoping calculations has been undertaken to evaluate the absolute and relative contributions of different radionuclides and exposure pathways to doses that may have been received by individuals living in the vicinity of the Hanford Site. This scoping calculation (Calculation 003) examined the contributions of numerous radionuclides to dose via environmental exposures and accumulation in foods. This study builds on the work initiated in the first scoping study of iodine in cow's milk (calculation 001). Addressed in this calculation were the contributions to organ and effective dose of infants and adults from (1) air submersion and groundshine external dose, (2) inhalation, (3) ingestion of soil by humans, (4) ingestion of leafy vegetables, (5) ingestion of other vegetables and fruits, (6) ingestion of meat, (7) ingestion of eggs, and (8) ingestion of cows' milk from Feeding Regime 1, as described in Calculation 001.
Date: December 1, 1992
Creator: Napier, B.A.
Partner: UNT Libraries Government Documents Department

Determination of radionuclides and pathways contributing to cumulative dose

Description: A series of scoping calculations has been undertaken to evaluate the absolute and relative contributions of different radionuclides and exposure pathways to doses that may have been received by individuals living in the vicinity of the Hanford Site. This scoping calculation (Calculation 004) examined the contributions of numerous radionuclides to cumulative dose via environmental exposures and accumulation in foods. Addressed in this calculation were the contributions to organ and effective dose of infants and adults from (1) air submersion and groundshine external dose, (2) inhalation, (3) ingestion of soil by humans, (4) ingestion of leafy vegetables, (5) ingestion of other vegetables and fruits, (6) ingestion of meat, (7) ingestion of eggs, and (8) ingestion of cows' milk from Feeding Regime 1, as described in calculation 002. This calculation specifically addresses cumulative radiation doses to infants and adults resulting from releases occurring over the period 1945 through 1972.
Date: December 1, 1992
Creator: Napier, B.A.
Partner: UNT Libraries Government Documents Department

Hanford Dose Overview Program. Comparison of AIRDOS-EPA and Hanford site dose codes

Description: Radiation dose commitments for persons in the Hanford environs calculated using AIRDOS-EPA were compared with those calculated using a suite of Hanford codes: FOOD, PABLM, DACRIN, and KRONIC. Dose commitments to the population and to the maximally exposed individual (MI) based on annual releases of eight radionuclides from the N-Reactor, were calculated by these codes. Dose commitments from each pathway to the total body, lung, thyroid, and lower large intestine (LLI) are given for the population and MI, respectively. 11 refs., 25 tabs.
Date: November 1, 1985
Creator: Aaberg, R.L. & Napier, B.A.
Partner: UNT Libraries Government Documents Department

Developing isotopic functions

Description: Isotopic functions, or ratios of two isotopic variables, are used to verify Pu and U measurements of spent fuels in reprocessing plants. Systematic methods have been developed for forming and evaluating isotopic functions. This paper describes the method used at Battelle to form and evaluate isotopic functions. The data base at Battelle contains measurements and calculations for the fuel from 35 reactors. (DLC)
Date: June 1, 1978
Creator: Napier, B.A. & Timmerman, C.L.
Partner: UNT Libraries Government Documents Department

Selected isotopic functions: a description and demonstration of their uses

Description: Eleven selected isotopic functions useful in the safeguards verification of input accountability measurements at a reprocessing facility are described. Tables provide summaries of how various factors affect the selected isotopic functions for pressurized water reactors (PWR) and for boiling water reactors (BWR). The eleven isotopic functions shown are pairings of various combination variables of uranium and plutonium isotopics and totals. A description and explanation of these variables and functions are provided. Also included in this report is a demonstration of the verification process utilizing isotopic safeguards techniques. The example used is the verification (or nonverification) of various Pu/U measurements. The technique demonstrates both the internal consistency check and the external data source verification which uses a similar reference data source.
Date: October 1, 1978
Creator: Timmerman, C.L.; Selby, G.P. & Napier, B.A.
Partner: UNT Libraries Government Documents Department

PABLM: a computer program to calculate accumulated radiation doses from radionuclides in the environment

Description: A computer program, PABLM, was written to facilitate the calculation of internal radiation doses to man from radionuclides in food products and external radiation doses from radionuclides in the environment. This report contains details of mathematical models used and calculational procedures required to run the computer program. Radiation doses from radionuclides in the environment may be calculated from deposition on the soil or plants during an atmospheric or liquid release, or from exposure to residual radionuclides in the environment after the releases have ended. Radioactive decay is considered during the release of radionuclides, after they are deposited on the plants or ground, and during holdup of food after harvest. The radiation dose models consider several exposure pathways. Doses may be calculated for either a maximum-exposed individual or for a population group. The doses calculated are accumulated doses from continuous chronic exposure. A first-year committed dose is calculated as well as an integrated dose for a selected number of years. The equations for calculating internal radiation doses are derived from those given by the International Commission on Radiological Protection (ICRP) for body burdens and MPC's of each radionuclide. The radiation doses from external exposure to contaminated water and soil are calculated using the basic assumption that the contaminated medium is large enough to be considered an infinite volume or plane relative to the range of the emitted radiations. The equations for calculations of the radiation dose from external exposure to shoreline sediments include a correction for the finite width of the contaminated beach.
Date: March 1, 1980
Creator: Napier, B.A.; Kennedy, W.E. Jr. & Soldat, J.K.
Partner: UNT Libraries Government Documents Department

Onsite disposal of commercial radioactive waste: the onsite/MAXI1 computer program

Description: The objective of this study was to modify an existing environmental pathways-to-humans model and accompanying computer program (MAXI1) for use by NRC staff for assessing potential radiological impacts resulting from the onsite burial of low-level radioactive wastes. As part of this effort, specific human-intrusion scenarios were developed to consider various routes of potential exposure, which included direct external exposure, inhalation, and ingestion of contaminated foodstuffs and drinking water. A computer software package, entitled ONSITE/MAXI1, was developed to project potential exposures based on these scenarios.
Date: June 1, 1985
Creator: Kennedy, W.E. Jr.; Peloquin, R.A. & Napier, B.A.
Partner: UNT Libraries Government Documents Department

Allowable Residual Contamination Levels in soil for decommissioning the Shippingport Atomic Power Station site

Description: As part of decommissioning the Shippingport Atomic Power Station, a fundamental concern is the determination of Allowable Residual Contamination Levels (ARCL) for radionuclides in the soil at the site. The ARCL method described in this report is based on a scenario/exposure-pathway analysis and compliance with an annual dose limit for unrestricted use of the land after decommissioning. In addition to naturally occurring radionuclides and fallout from weapons testing, soil contamination could potentially come from five other sources. These include operation of the Shippingport Station as a pressurized water reactor, operations of the Shippingport Station as a light-water breeder, operation of the nearby Beaver Valley reactors, releases during decommissioning, and operation of other nearby industries, including the Bruce-Mansfield coal-fired power plants. ARCL values are presented for 29 individual radionculides and a worksheet is provided so that ARCL values can be determined for any mixture of the individual radionuclides for any annual dose limit selected. In addition, a worksheet is provided for calculating present time soil concentration value that will decay to the ARCL values after any selected period of time, such as would occur during a period of restricted access. The ARCL results are presented for both unconfined (surface) and confined (subsurface) soil contamination. The ARCL method and results described in this report provide a flexible means of determining unrestricted-use site release conditions after decommissioning the Shippingport Atomic Power Station.
Date: September 1, 1983
Creator: Kennedy, W.E. Jr.; Napier, B.A. & Soldat, J.K.
Partner: UNT Libraries Government Documents Department

DITTY - a computer program for calculating population dose integrated over ten thousand years

Description: The computer program DITTY (Dose Integrated Over Ten Thousand Years) was developed to determine the collective dose from long term nuclear waste disposal sites resulting from the ground-water pathways. DITTY estimates the time integral of collective dose over a ten-thousand-year period for time-variant radionuclide releases to surface waters, wells, or the atmosphere. This document includes the following information on DITTY: a description of the mathematical models, program designs, data file requirements, input preparation, output interpretations, sample problems, and program-generated diagnostic messages.
Date: March 1, 1986
Creator: Napier, B.A.; Peloquin, R.A. & Strenge, D.L.
Partner: UNT Libraries Government Documents Department

Hanford Dose Overview Program: standardized methods and data for Hanford environmental dose calculations. Rev. 1

Description: This document serves as a guide to Hanford contractors for obtaining or performing Hanford-related environmental dose calculations. Because environmental dose estimation techniques are state-of-the-art and are continually evolving, the data and standard methods presented herein will require periodic revision. This document is scheduled to be updated annually, but actual changes to the program will be made more frequently if required. For this reason, PNL's Occupational and Environmental Protection Department should be contacted before any Hanford-related environmental dose calculation is performed. This revision of the Hanford Dose Overview Program Report primarily reflects changes made to the data and models used in calculating atmospheric dispersion of airborne effluents at Hanford. The modified data and models are described in detail. In addition, discussions of dose calculation methods and the review of calculation results have been expanded to provide more explicit guidance to the Hanford contractors. 19 references, 30 tables.
Date: May 1, 1984
Creator: McCormack, W.D.; Ramsdell, J.V. & Napier, B.A.
Partner: UNT Libraries Government Documents Department

Scoping calculation for components of the cow-milk dose pathway for evaluating the dose contribution from iodine-131

Description: A series of scoping calculations have been undertaken to evaluate The absolute and relative contribution of different exposure pathways to doses that may have been received by individuals living in the vicinity of the Hanford site. This scoping calculation (Calculation 001) examined the contributions of the various exposure pathways associated with environmental transport and accumulation of iodine-131 in the pasture-cow-milk pathway. Addressed in this calculation were the contributions to thyroid dose of infants and adult from (1) the ingestion by dairy cattle of various feedstuffs (pasturage, silage, alfalfa hay, and grass hay) in four different feeding regimes; (2) ingestion of soil by dairy cattle; (3) ingestion of stared feed on which airborne iodine-131 had been deposited; and (4) inhalation of airborne iodine-131 by dairy cows.
Date: December 1, 1992
Creator: Ikenberry, T.A. & Napier, B.A.
Partner: UNT Libraries Government Documents Department

Determination of radionuclides and pathways contributing to dose in 1945. Hanford Environmental Dose Reconstruction Project: Dose code recovery activities, Calculation 003

Description: A series of scoping calculations has been undertaken to evaluate the absolute and relative contributions of different radionuclides and exposure pathways to doses that may have been received by individuals living in the vicinity of the Hanford Site. This scoping calculation (Calculation 003) examined the contributions of numerous radionuclides to dose via environmental exposures and accumulation in foods. This study builds on the work initiated in the first scoping study of iodine in cow`s milk (calculation 001). Addressed in this calculation were the contributions to organ and effective dose of infants and adults from (1) air submersion and groundshine external dose, (2) inhalation, (3) ingestion of soil by humans, (4) ingestion of leafy vegetables, (5) ingestion of other vegetables and fruits, (6) ingestion of meat, (7) ingestion of eggs, and (8) ingestion of cows` milk from Feeding Regime 1, as described in Calculation 001.
Date: December 1, 1992
Creator: Napier, B. A.
Partner: UNT Libraries Government Documents Department

Determination of radionuclides and pathways contributing to cumulative dose. Hanford Environmental Dose Reconstruction Project: Dose code recovery activities, Calculation 004

Description: A series of scoping calculations has been undertaken to evaluate the absolute and relative contributions of different radionuclides and exposure pathways to doses that may have been received by individuals living in the vicinity of the Hanford Site. This scoping calculation (Calculation 004) examined the contributions of numerous radionuclides to cumulative dose via environmental exposures and accumulation in foods. Addressed in this calculation were the contributions to organ and effective dose of infants and adults from (1) air submersion and groundshine external dose, (2) inhalation, (3) ingestion of soil by humans, (4) ingestion of leafy vegetables, (5) ingestion of other vegetables and fruits, (6) ingestion of meat, (7) ingestion of eggs, and (8) ingestion of cows` milk from Feeding Regime 1, as described in calculation 002. This calculation specifically addresses cumulative radiation doses to infants and adults resulting from releases occurring over the period 1945 through 1972.
Date: December 1, 1992
Creator: Napier, B. A.
Partner: UNT Libraries Government Documents Department

Assessment of effectiveness of geologic isolation systems: a short description of the AEGIS approach

Description: To meet licensing criteria and protection standards for HLW disposal, research programs are in progress to determine acceptable waste forms, canisters, backfill materials for the repository, and geological formations. Methods must be developed to evaluate the effectiveness of the total system. To meet this need, methods are being developed to assess the long-term effectiveness of isolating nuclear wastes in geologic formations. This work was started in 1976 in the Waste Isolation Safety Assessment Program (WISAP) and continues in the Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) Program. The evaluation of this long-term effectiveness involves a number of distinct steps. AEGIS currently has the methods for performing these evaluation steps. These methods are continuously being improved to meet the inreasing level of sophistication which will be required. AEGIS develops a conceptual description of the geologic systems and uses computer models to simulate the existing ground-water pathways. AEGIS also uses a team of consulting experts, with the assistance of a computer model of the geologic processes, to develop and evaluate plausible release scenarios. Then other AEGIS computer models are used to simulate the transport of radionuclides to the surface and the resultant radiation doses to individuals and populations. (DLC)
Date: September 1, 1980
Creator: Silviera, D.J.; Harwell, M.A.; Napier, B.A.; Zellmer, J.T. & Benson, G.L.
Partner: UNT Libraries Government Documents Department

Assessment of effectiveness of geologic isolation systems. ARRRG and FOOD: computer programs for calculating radiation dose to man from radionuclides in the environment

Description: The computer programs ARRRG and FOOD were written to facilitate the calculation of internal radiation doses to man from the radionuclides in the environment and external radiation doses from radionuclides in the environment. Using ARRRG, radiation doses to man may be calculated for radionuclides released to bodies of water from which people might obtain fish, other aquatic foods, or drinking water, and in which they might fish, swim or boat. With the FOOD program, radiation doses to man may be calculated from deposition on farm or garden soil and crops during either an atmospheric or water release of radionuclides. Deposition may be either directly from the air or from irrigation water. Fifteen crop or animal product pathways may be chosen. ARRAG and FOOD doses may be calculated for either a maximum-exposed individual or for a population group. Doses calculated are a one-year dose and a committed dose from one year of exposure. The exposure is usually considered as chronic; however, equations are included to calculate dose and dose commitment from acute (one-time) exposure. The equations for calculating internal dose and dose commitment are derived from those given by the International Commission on Radiological Protection (ICRP) for body burdens and Maximum Permissible Concentration (MPC) of each radionuclide. The radiation doses from external exposure to contaminated farm fields or shorelines are calculated assuming an infinite flat plane source of radionuclides. A factor of two is included for surface roughness. A modifying factor to compensate for finite extent is included in the shoreline calculations.
Date: June 1, 1980
Creator: Napier, B.A.; Roswell, R.L.; Kennedy, W.E. Jr. & Strenge, D.L.
Partner: UNT Libraries Government Documents Department

Parameters used in the environmental pathways and radiological dose modules of the Phase I air pathway code

Description: This report is a description of work performed for the Hanford Environmental Dose Reconstruction (HEDR) Project. The HEDR Project was established to estimate radiation doses to individuals resulting from releases of radionuclides from the Hanford Site since 1944, when facilities there first began operating. An independent Technical Steering Panel directs the project, which is conducted by Battelle staff from the Pacific Northwest Laboratory. The objective of Phase 1 of the HEDR Project was to demonstrate through calculation that adequate models and support data existed or could be developed to allow estimation of realistic doses to individuals from historical Hanford Site radionuclide releases. The HEDR Phase 1 computer code was used to model the transport of iodine-131 released to the atmosphere from the Hanford Site facilities, through environmental pathways to points of human exposure. Output from the code was preliminary estimates of doses received by members of the public living in the vicinity of the Hanford Site. Later project work continues to build upon Phase 1 progress in order to refine dose estimates.
Date: May 1, 1992
Creator: Shindle, S.F.; Ikenberry, T.A. & Napier, B.A.
Partner: UNT Libraries Government Documents Department

Determination of the temporal resolution required for the HEDR dose code

Description: A series of scoping calculations has been undertaken to evaluate the radiation doses that may have-been received by individuals living in the vicinity of the Hanford site. This scoping calculation (Calculation 008) examined the potential for changes in the uncertainty distributions of potential doses from releases in the year 1945 as a function of temporal resolution of the intermediate data storage. This study builds on the work initiated in the fifth scoping calculation, which addressed the uncertainty of the dose estimates at a point; the sixth calculation, which extrapolated the doses throughout the atmospheric transport domain; and the seventh, which evaluated the spatial scales across the domain. A projection of dose to representative individuals throughout the proposed HEDR atmospheric transport domain was prepared on the basis of the HEDR source term. Addressed in this calculation were the contributions to iodine-131 thyroid dose of infants from (1) air submersion and groundshine external dose, (2) inhalation, (3) ingestion of soil by humans, (4) ingestion of leafy vegetables, (5) ingestion of other vegetables and fruits, (6) ingestion of meat, (7) ingestion of eggs, and ingestion of cow's milk.
Date: December 1, 1992
Creator: Napier, B.A. & Simpson, J.C.
Partner: UNT Libraries Government Documents Department

Determination of the feasibility of reducing the spatial domain of the HEDR dose code

Description: A series of scoping calculations has been undertaken to evaluate the doses that may have been received by individuals living in the vicinity of the Hanford site. The primary impetus for this scoping calculation was to determine if large areas of the Hanford Environmental Dose Reconstruction (HEDR) Project atmospheric domain could be excluded from detailed calculation because the atmospheric transport of radionuclides from Hanford resulted in no (or negligible) deposition in those areas. The secondary impetus was to investigate whether an intermediate screen could be developed to reduce the data storage requirements by taking advantage of locations with periods of effectively zero'' deposition. This scoping calculation (Calculation 006) examined the spatial distribution of potential doses resulting from releases in the year 1945. This study builds on the work initiated in the first scoping study, of iodine in cow's milk, and the third scoping study, which added additional pathways. Addressed in this calculation were the contributions to thyroid dose of infants from (1) air submersion and groundshine external dose, (2) inhalation, (3) ingestion of soil by humans, (4) ingestion of leafy vegetables, (5) ingestion of other vegetables and fruits, and (6) ingestion of meat, (7) ingestion of eggs, and (8) ingestion of cow's milk from Feeding Regime 1 as described in scoping calculation 001.
Date: December 1, 1992
Creator: Napier, B.A. & Snyder, S.F.
Partner: UNT Libraries Government Documents Department