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Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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1

Drinking Water Problems: Radionuclides  

E-Print Network (OSTI)

Radionuclides in drinking water can cause serious health problems for people. This publication explains what the sources of radionuclides in water are, where high levels have been found in Texas, how they affect health and how to treat water to remove them.

Lesikar, Bruce J.; Melton, Rebecca; Hare, Michael; Hopkins, Janie; Dozier, Monty

2006-08-04T23:59:59.000Z

2

Drinking Water Problems: Radionuclides (Spanish)  

E-Print Network (OSTI)

Radionuclides in drinking water can cause serious health problems for people. This publication explains what the sources of radionuclides in water are, where high levels have been found in Texas, how they affect health and how to treat water to remove them.

Lesikar, Bruce J.; Melton, Rebecca; Hare, Michael; Hopkins, Janie; Dozier, Monty

2006-12-21T23:59:59.000Z

3

Radionuclide Sensors for Subsurface Water Monitoring  

SciTech Connect

Contamination of the subsurface by radionuclides is a persistent and vexing problem for the Department of Energy. These radionuclides must be measured in field studies and monitoed in the long term when they cannot be removed. However, no radionuclide sensors existed for groundwater monitoring prior to this team's research under the EMSP program Detection of a and b decays from radionuclides in water is difficult due to their short ranges in condensed media.

Timothy DeVol

2006-06-30T23:59:59.000Z

4

Radionuclide behavior in water saturated porous media: Diffusion and infiltration coupling of thermodynamically and kinetically controlled radionuclide water - mineral interactions  

SciTech Connect

A model is developed describing one dimensional radionuclide transport in porous media coupled with locally reversible radionuclide water-mineral exchange reactions and radioactive decay. Problems are considered in which radionuclide transport by diffusion and infiltration processes occur in cases where radionuclide water-solid interaction are kinetically and thermodynamically controlled. The limits of Sr-90 and Cs-137 migration are calculated over a wide range of the problem variables (infiltration velocity, distribution coefficients, and rate constants of water-mineral radionuclide exchange reactions).

Spasennykh, M.Yu. [Vernadsky Institute of Geochemistry and Analytical Chemistry, Moscow (Russian Federation); Apps, J.A. [Lawrence Berkeley Lab., CA (United States)

1995-05-01T23:59:59.000Z

5

Chancellor Water Colloids: Characterization and Radionuclide Association  

Science Conference Proceedings (OSTI)

Concluding remarks about this paper are: (1) Gravitational settling, zeta potential, and ultrafiltration data indicate the existence of a colloidal phase of both the alpha and beta emitters in the Chancellor water; (2) The low activity combined with high dispersion homogeneity of the Chancellor water indicate that both alpha and beta emitters are not intrinsic colloids; (3) Radionuclides in the Chancellor water, particularly Pu, coexist as dissolved aqueous and sorbed phases - in other words the radionuclides are partitioned between the aqueous phase and the colloidal phase; (4) The presence of Pu as a dissolved species in the aqueous phase, suggests the possibility of Pu in the (V) oxidation state - this conclusion is supported by the similarity of the k{sub d} value of Pu determined in the current study to that determined for Pu(V) sorbed onto smectite colloids, and the similar electrokinetic behavior of the Chancellor water colloids to smectite colloids; (5) About 50% of the Pu(V) is in the aqueous phase and 50% is sorbed on colloids (mass concentration of colloids in the Chancellor water is 0.12 g/L); (6) The k{sub d} of the Pu and the beta emitters (fission products) between aqueous and colloidal phases in the Chancellor water is {approx}8.0 x 10{sup 3} mL/g using two different activity measurement techniques (LSC and alpha spectroscopy); (7) The gravitational settling and size distributions of the association colloids indicate that the properties (at least the physical ones) of the colloids to which the alpha emitters are associated with seem to be different that the properties of the colloids to which the beta emitters are associated with - the beta emitters are associated with very small particles ({approx}50 - 120 nm), while the alpha emitters are associated with relatively larger particles; and (8) The Chancellor water colloids are extremely stable under the natural pH and ionic strength conditions, indicating high potential for transport in the subsurface.

Abdel-Fattah, Amr I. [Los Alamos National Laboratory

2012-06-18T23:59:59.000Z

6

Joint Regulation of Radionuclides at Connecticut Yankee Haddam Neck Plant - Finding Common Ground and Lessons Learned  

Science Conference Proceedings (OSTI)

During the site closure of nuclear facilities where both radionuclides and chemicals are present in environmental media, state and federal regulatory agencies other than the Nuclear Regulatory Commission often have a stake in the regulation of the site closure process. At the Connecticut Yankee Atomic Power Company (CYAPCO) Haddam Neck Plant in Haddam, Connecticut, the site closure process includes both radiological and chemical cleanup which is regulated by two separate divisions within the state and two federal agencies. Each of the regulatory agencies has unique closure criteria which pertain to radionuclides and, consequently, there is overlapping and in some cases disparate regulation of radionuclides. Considerable effort has been expended by CYAPCO to find common ground in meeting the site closure requirements for radionuclides required by each of the agencies. This paper discusses the approaches that have been used by CYAPCO to address radionuclide site closure requirements. Significant lessons learned from these approaches include the demonstration that public health cleanup criteria for most radionuclides of concern at nuclear power generation facilities are protective for chemical toxicity concerns and are protective for ecological receptors and, consequently, performing a baseline ecological risk assessment for radionuclides at power generation facilities is not generally necessary. (authors)

Peters, J.; Glucksberg, N.; Fogg, A. [MACTEC Engineering and Consulting, Inc., Portland, Maine 04112 (United States); Couture, B. [Connecticut Yankee Atomic Power Company, Haddam Neck Plant, Haddam, Connecticut 06424 (United States)

2006-07-01T23:59:59.000Z

7

Ground Water Management Regulations (Louisiana) | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Ground Water Management Regulations (Louisiana) Ground Water Management Regulations (Louisiana) Eligibility Agricultural Construction Developer Fuel Distributor Industrial...

8

Regulations Establishing Water Quality Standards for Surface...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Establishing Water Quality Standards for Surface Water of the State of Arkansas (Arkansas) Regulations Establishing Water Quality Standards for Surface Water of the State of...

9

Inland Wetlands and Water Courses Regulations (Connecticut)  

Energy.gov (U.S. Department of Energy (DOE))

Regulated activities in or near inland wetlands and water courses include the removal or depositing of material, land or water obstruction or alteration, construction, pollution, or water diversion...

10

Radionuclide characterization at US commercial light-water reactors for decommissioning assessment: Distributions, inventories, and waste disposal considerations  

SciTech Connect

A continuing research program, conducted by Pacific Northwest Laboratory for the US Nuclear Regulatory Commission, characterizing radionuclide concentrations associated with US light-water reactors has been conducted for more than a decade. The research initially focused upon sampling and analytical measurements for the purpose of establishing radionuclide distributions and inventories for decommissioning assessment, since very little empirical data existed. The initial phase of the research program examined radionuclide concentrations and distributions external to the reactor vessel at seven US light water reactors. Later stages of the research program have examined the radionuclide distributions in the highly radioactive reactor internals and fuel assembly. Most recently, the research program is determining radionuclide concentrations in these highly radioactive components and comparing empirical results with those derived from the several nonempirical methodologies employed to estimate radionuclide inventories for disposal classification. The results of the research program to date are summarized, and their implications and significance for the decommissioning process are noted.

Abel, K.H.; Robertson, D.E.; Thomas, C.W.

1992-09-01T23:59:59.000Z

11

Produced water radionuclide hazard/risk assessment, Phase 1  

SciTech Connect

Petroleum production may be accompanied by the production of saline water, called produced water.'' Produced water discharged into freshwater streams, estuaries, coastal and outer continental shelf waters can contained enhanced levels of radium isotopes. This document reports on the first phase of a study to estimate the risk to human health and the environment from radium discharged in produced water. The study involved five major steps: (1) evaluate the usefulness of available produced water outfall data for developing estimates of radium environmental concentrations; (2) review the literature on the bioaccumulation of radium by aquatic organism; (3) review the literature on the effects of radiation on aquatic organisms; (4) review the information available concerning the human health risks associated with exposure to Ra-226 and Ra-228 and (5) perform a conservative, screening-level assessment of the health and environmental risks posed by Ra-226 and Ra-228 discharged in produced waters. A screening-level analysis was performed to determine whether radium discharged to coastal Louisiana in produced waters presents potential health or environmental risks requiring further study. This conservative assessment suggested that no detectable impact on populations of fish, molluscs or crustaceans from radium discharged in produced waters is likely. The analysis also suggested that there is a potential for risk were an individual to ingest a large amount of seafood harvested near a produced water discharge point over a lifetime. The number of excess cancers predicted per year under a conservative scenario is comparable to those expected to result from background concentrations of radium.

Hamilton, L.D.; Meinhold, A.F.; Nagy, J.

1991-06-01T23:59:59.000Z

12

Produced water radionuclide hazard/risk assessment, Phase 1  

Science Conference Proceedings (OSTI)

Petroleum production may be accompanied by the production of saline water, called ``produced water.`` Produced water discharged into freshwater streams, estuaries, coastal and outer continental shelf waters can contained enhanced levels of radium isotopes. This document reports on the first phase of a study to estimate the risk to human health and the environment from radium discharged in produced water. The study involved five major steps: (1) evaluate the usefulness of available produced water outfall data for developing estimates of radium environmental concentrations; (2) review the literature on the bioaccumulation of radium by aquatic organism; (3) review the literature on the effects of radiation on aquatic organisms; (4) review the information available concerning the human health risks associated with exposure to Ra-226 and Ra-228 and (5) perform a conservative, screening-level assessment of the health and environmental risks posed by Ra-226 and Ra-228 discharged in produced waters. A screening-level analysis was performed to determine whether radium discharged to coastal Louisiana in produced waters presents potential health or environmental risks requiring further study. This conservative assessment suggested that no detectable impact on populations of fish, molluscs or crustaceans from radium discharged in produced waters is likely. The analysis also suggested that there is a potential for risk were an individual to ingest a large amount of seafood harvested near a produced water discharge point over a lifetime. The number of excess cancers predicted per year under a conservative scenario is comparable to those expected to result from background concentrations of radium.

Hamilton, L.D.; Meinhold, A.F.; Nagy, J.

1991-06-01T23:59:59.000Z

13

Water Pollution Control Permit Regulations (Vermont)  

Energy.gov (U.S. Department of Energy (DOE))

These regulations outline the permits and permitting processes for point discharges to surface waters and outline the monitoring and reporting requirements.

14

An analysis of radionuclide behavior in water pools during accidents at the Annular Core Research Reactor  

SciTech Connect

Physical and chemical phenomena that will affect the behavior of radionuclides released from fuel in the Annular Core Research Reactor during a hypothetical, core disruptive accident are described. The phenomena include boiling of water on heated clad, metal-water reactions, vapor nucleation to form aerosol particles, coagulation of aerosol particles, aerosol deposition within bubbles rising through the shield pool, vapor dissolution in the shield pool, and revaporization of radionuclides from the shield pool. A model of these phenomena is developed and applied to predict the release of radionuclides to the confinement building of the Annular Core Research Reactor. It is found that the shield pool provides overall decontamination factors for particulate of about 2.8 {times} 10{sup 5} and decontamination factors for noble gases of about 2.5--3.7. These results are found to be sensitive to the predicted clad temperature and bubble behavior in the shield pool. Slow revalorization of krypton, xenon and iodine from the shield pool is shown to create a prolonged, low-intensity source term of radioactive material to the confinement atmosphere.

Powers, D.A.

1992-08-01T23:59:59.000Z

15

Regulations Establishing Water Quality Standards for Surface Water of the  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Establishing Water Quality Standards for Surface Water Establishing Water Quality Standards for Surface Water of the State of Arkansas (Arkansas) Regulations Establishing Water Quality Standards for Surface Water of the State of Arkansas (Arkansas) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Water Buying & Making Electricity Home Weatherization Program Info State Arkansas Program Type Environmental Regulations Siting and Permitting

16

Water Quality Regulations (Rhode Island) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Regulations (Rhode Island) Water Quality Regulations (Rhode Island) Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public...

17

Division of Water, Part 675: Great Lakes Water Withdrawal Registration Regulations (New York)  

Energy.gov (U.S. Department of Energy (DOE))

These regulations set forth requirements for the registration of water withdrawals and reporting of water losses from the Great Lakes Basin. The regulations apply to water withdrawals from...

18

Federal Guidance No. 12: External Exposure to Radionuclides in Air, Water, and Soil  

NLE Websites -- All DOE Office Websites (Extended Search)

402-R-93-081 402-R-93-081 FEDERAL GUIDANCE REPORT NO. 12 EXTERNAL EXPOSURE TO RADIONUCLIDES IN AIR, WATER, AND SOIL Keith F. Eckerman and Jeffrey C. Ryman September 1993 ERRATUM p. 218 Table C.2. Scaled External Bremsstrahlung from Electrons for Water For T = 1000.0 and k/T = 0.10, the table entry .0223 should read 1.0223. 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 any of their employees, 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

19

Water-Chemistry Evolution and Modeling of Radionuclide Sorption and Cation Exchange during Inundation of Frenchman Flat Playa  

SciTech Connect

Atmospheric tests and other experiments with nuclear materials were conducted on the Frenchman Flat playa at the Nevada National Security Site, Nye County, Nevada; residual radionuclides are known to exist in Frenchman Flat playa soils. Although the playa is typically dry, extended periods of winter precipitation or large single-event rainstorms can inundate the playa. When Frenchman Flat playa is inundated, residual radionuclides on the typically dry playa surface may become submerged, allowing water-soil interactions that could provide a mechanism for transport of radionuclides away from known areas of contamination. The potential for radionuclide transport by occasional inundation of the Frenchman Flat playa was examined using geographic information systems and satellite imagery to delineate the timing and areal extent of inundation; collecting water samples during inundation and analyzing them for chemical and isotopic content; characterizing suspended/precipitated materials and archived soil samples; modeling water-soil geochemical reactions; and modeling the mobility of select radionuclides under aqueous conditions. The physical transport of radionuclides by water was not evaluated in this study. Frenchman Flat playa was inundated with precipitation during two consecutive winters in 2009-2010 and 2010-2011. Inundation allowed for collection of multiple water samples through time as the areal extent of inundation changed and ultimately receded. During these two winters, precipitation records from a weather station in Frenchman Flat (Well 5b) provided information that was used in combination with geographic information systems, Landsat imagery, and image processing techniques to identify and quantify the areal extent of inundation. After inundation, water on the playa disappeared quickly, for example, between January 25, 2011 and February 10, 2011, a period of 16 days, 92 percent of the areal extent of inundation receded (2,062,800 m2). Water sampling provided valuable information about chemical processes occurring during inundation as the water disappeared. Important observations from water-chemistry analyses included: 1) total dissolved solids (TDS) and chloride ion (Cl-) concentrations were very low (TDS: < 200 mg/L and Cl-: < 3.0 mg/L, respectively) for all water samples regardless of time or areal extent; 2) all dissolved constituents were at concentrations well below what might be expected for evaporating shallow surface waters on a playa, even when 98 to 99 percent of the water had disappeared; 3) the amount of evaporation for the last water samples collected at the end of inundation, estimated with the stable isotopic ratios ?2H or ?18O, was approximately 60 percent; and 4) water samples analyzed by gamma spectroscopy did not show any man-made radioactivity; however, the short scanning time (24 hours) and relative chemical diluteness of the water samples (TDS ranged between 39 and 190 mg/L) may have contributed to none being detected. Additionally, any low-energy beta emitting radionuclides would not have been detected by gamma spectroscopy. From these observations, it was apparent that a significant portion of water on the playa did not evaporate, but rather infiltrated into the subsurface (approximately 40 percent). Consistent with this water chemistry-based conclusion is particle-size analysis of two archived Frenchman Flat playa soils samples, which showed low clay content in the near surface soil that also suggested infiltration. Infiltration of water from the playa during inundation into the subsurface does not necessarily imply that groundwater recharge is occurring, but it does provide a mechanism for moving residual radionuclides downward into the subsurface of Frenchman Flat playa. Water-mineral geochemical reactions were modeled so that changes in the water chemistry could be identified and the extent of reactions quantified. Geochemical modeling showed that evaporation; equilibrium with atmospheric carbon dioxide and calcite; dissolution of sodium chloride, gypsum, and composite volcanic g

Hershey, Ronald; Cablk, Mary; LeFebre, Karen; Fenstermaker, Lynn; Decker, David

2013-08-01T23:59:59.000Z

20

Resource Management Services: Water Regulation, Part 605: Applications...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5: Applications for Diversion or Use of Water for Purposes Other Than Hydro-Electric Power Projects (New York) Resource Management Services: Water Regulation, Part 605:...

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Building Codes and Regulations for Solar Water Heating Systems...  

NLE Websites -- All DOE Office Websites (Extended Search)

Codes and Regulations for Solar Water Heating Systems Building Codes and Regulations for Solar Water Heating Systems June 24, 2012 - 1:50pm Addthis Photo Credit: iStockphoto Photo...

22

Investigation of CTBT OSI Radionuclide Techniques at the DILUTED WATERS Nuclear Test Site  

SciTech Connect

Under the Comprehensive Nuclear-Test-Ban Treaty (CTBT), a verification regime that includes the ability to conduct an On-Site Inspection (OSI) will be established. The Treaty allows for an OSI to include many techniques, including the radionuclide techniques of gamma radiation surveying and spectrometry and environmental sampling and analysis. Such radioactivity detection techniques can provide the “smoking gun” evidence that a nuclear test has occurred through the detection and quantification of indicative recent fission products. An OSI faces restrictions in time and manpower, as dictated by the Treaty; not to mention possible logistics difficulties due to the location and climate of the suspected explosion site. It is thus necessary to have a good understanding of the possible source term an OSI will encounter and the proper techniques that will be necessary for an effective OSI regime. One of the challenges during an OSI is to locate radioactive debris that has escaped an underground nuclear explosion (UNE) and settled on the surface near and downwind of ground zero. To support the understanding and selection of sampling and survey techniques for use in an OSI, we are currently designing an experiment, the Particulate Release Experiment (PRex), to simulate a small-scale vent from an underground nuclear explosion. PRex will occur at the Nevada National Security Site (NNSS). The project is conducted under the National Center for Nuclear Security (NCNS) funded by the National Nuclear Security Agency (NNSA). Prior to the release experiment, scheduled for Spring of 2013, the project scheduled a number of activities at the NNSS to prepare for the release experiment as well as to utilize the nuclear testing past of the NNSS for the development of OSI techniques for CTBT. One such activity—the focus of this report—was a survey and sampling campaign at the site of an old UNE that vented: DILUTED WATERS. Activities at DILUTED WATERS included vehicle-based survey, in situ measurements with high-purity germanium (HPGe) and hand-held LaBr3 systems, soil sampling with a variety of tools, and laboratory gamma spectrometric analysis of those samples. A further benefit of the measurement campaign was to gain familiarity with the many logistical aspects of performing radiological field work at NNSS ahead of the PRex. Many practical lessons concerning the proper methodologies and logistics of using the surveying and sampling equipment were noted. These Lessons Learned are compiled together in Appendix A. The vehicle-based survey was successful in that it found a previously unknown hotspot (determined to be 232Th) while it demonstrated that a better method for keeping a serpentine track without staking was needed. Some of the soil sampling equipment was found to be impractical for the application, though core sampling would not be the correct way to take soil samples for a fresh vent deposit (as opposed to an old site like DILUTED WATERS). Due to the site’s age, 137Cs was the only fission radioisotope identified, though others were searched for. While not enough samples were taken and analyzed to definitively link the 137Cs to DILUTED WATERS as opposed to other NNSS activities, results were consistent with the historical DILUTED WATERS plume. MDAs were compared for soil sampling and in situ measurements.

Baciak, James E.; Milbrath, Brian D.; Detwiler, Rebecca S.; Kirkham, Randy R.; Keillor, Martin E.; Lepel, Elwood A.; Seifert, Allen; Emer, Dudley; Floyd, Michael

2012-11-01T23:59:59.000Z

23

State Water Permit Regulation (Arkansas) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Permit Regulation (Arkansas) Permit Regulation (Arkansas) State Water Permit Regulation (Arkansas) < Back Eligibility Fuel Distributor Industrial Utility Program Info State Arkansas Program Type Environmental Regulations Siting and Permitting Provider Department of Environmental Quality It is the purpose of this regulation to adopt standards applicable to the storage, discharge, or disposal of any waste which, if unregulated, will cause pollution of waters of the state or result in wastes being placed in a location where it is likely to cause pollution of the waters of the state. These standards are intended to protect public health and the environment, and prevent, control, or abate pollution. The State Water Permit Regulation is implemented to adopt standards applicable to the storage, discharge, or disposal of any waste that, if

24

Radionuclide trap  

DOE Patents (OSTI)

The deposition of radionuclides manganese-54, cobalt-58 and cobalt-60 from liquid sodium coolant is controlled by providing surfaces of nickel or high nickel alloys to extract the radionuclides from the liquid sodium, and by providing surfaces of tungsten, molybdenum or tantalum to prevent or retard radionuclide deposition.

McGuire, Joseph C. (Richland, WA)

1978-01-01T23:59:59.000Z

25

Regulation of Gas, Electric, and Water Companies (Maryland) | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Regulation of Gas, Electric, and Water Companies (Maryland) Regulation of Gas, Electric, and Water Companies (Maryland) Regulation of Gas, Electric, and Water Companies (Maryland) < Back Eligibility Agricultural Commercial Construction Industrial Investor-Owned Utility Local Government Municipal/Public Utility Retail Supplier Rural Electric Cooperative State/Provincial Govt Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Maryland Program Type Safety and Operational Guidelines Siting and Permitting Provider Maryland Public Service Commission The Public Service Commission is responsible for regulating gas, electric, and water companies in the state. This legislation contains provisions for such companies, addressing planning and siting considerations for electric

26

Radionuclides Allyn H. Seymour  

Office of Legacy Management (LM)

Radionuclides Radionuclides Allyn H. Seymour in Air, Water, victor A. Nelson Laboratory of Radiation Ecology, University of and Biota Washington, Seattle, \\'ashington Air, water, and biological samples collected before and after the 1965, 1969, and 1971 underground nuclear detonations at Amchitka Island were analyzed for natural and fallout mdionrrclides b y gamma spectrometry. Selected samples were also analyzed for tritium, " ~ e , and 9 0 ~ r . The objectiues were t o search for and identify radio~tuclides of Amchitka origin in the samples and t o contribute t o the general knowledge of the distribatiotl of radionuclides in the enuironment. The collection of seafoods and the analyses of samples for radionuclides potentially available t o man through the food web were enrphasized, but other

27

Regulation of Dams and Bridges Affecting Navigable Waters (Wisconsin) |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Dams and Bridges Affecting Navigable Waters Dams and Bridges Affecting Navigable Waters (Wisconsin) Regulation of Dams and Bridges Affecting Navigable Waters (Wisconsin) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Water Buying & Making Electricity Home Weatherization Program Info Start Date 2007 State Wisconsin Program Type Siting and Permitting Provider Department of Natural Resources Chapter 31 of the Wisconsin Statutes lays out the regulations relevant to

28

Building Codes and Regulations for Solar Water Heating Systems | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Building Codes and Regulations for Solar Water Heating Systems Building Codes and Regulations for Solar Water Heating Systems Building Codes and Regulations for Solar Water Heating Systems June 24, 2012 - 1:50pm Addthis Photo Credit: iStockphoto Photo Credit: iStockphoto Before installing a solar water heating system, you should investigate local building codes, zoning ordinances, and subdivision covenants, as well as any special regulations pertaining to the site. You will probably need a building permit to install a solar energy system onto an existing building. Not every community or municipality initially welcomes residential renewable energy installations. Although this is often due to ignorance or the comparative novelty of renewable energy systems, you must comply with existing building and permit procedures to install your system.

29

Building Codes and Regulations for Solar Water Heating Systems | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Building Codes and Regulations for Solar Water Heating Systems Building Codes and Regulations for Solar Water Heating Systems Building Codes and Regulations for Solar Water Heating Systems June 24, 2012 - 1:50pm Addthis Photo Credit: iStockphoto Photo Credit: iStockphoto Before installing a solar water heating system, you should investigate local building codes, zoning ordinances, and subdivision covenants, as well as any special regulations pertaining to the site. You will probably need a building permit to install a solar energy system onto an existing building. Not every community or municipality initially welcomes residential renewable energy installations. Although this is often due to ignorance or the comparative novelty of renewable energy systems, you must comply with existing building and permit procedures to install your system.

30

Division of Water, Part 666: Regulation for Administration and Management  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

66: Regulation for Administration and 66: Regulation for Administration and Management of the Wild, Scenic and Recreational Rivers System in New York State Excepting Private Land in the Adirondack Park (New York) Division of Water, Part 666: Regulation for Administration and Management of the Wild, Scenic and Recreational Rivers System in New York State Excepting Private Land in the Adirondack Park (New York) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor Industrial Institutional Investor-Owned Utility Local Government Multi-Family Residential Municipal/Public Utility Nonprofit Rural Electric Cooperative Schools State/Provincial Govt Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water

31

Resource Management Services: Water Regulation, Part 605: Applications for  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5: 5: Applications for Diversion or Use of Water for Purposes Other Than Hydro-Electric Power Projects (New York) Resource Management Services: Water Regulation, Part 605: Applications for Diversion or Use of Water for Purposes Other Than Hydro-Electric Power Projects (New York) < Back Eligibility Agricultural Commercial Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Tribal Government Utility Savings Category Buying & Making Electricity Program Info State New York Program Type Siting and Permitting Provider NY Department of Environmental Conservation These rules apply to all applications for a license or a permit to take, divert, appropriate or otherwise use the waters of the State, except applications for hydro-electric power projects. Applications are reviewed

32

Scientific Analysis Cover Sheet for Radionuclide Screening  

Science Conference Proceedings (OSTI)

The waste forms under consideration for disposal in the proposed repository at Yucca Mountain contain scores of radionuclides (Attachments V and VI). It would be impractical and highly inefficient to model all of these radionuclides in a total system performance assessment (TSPA). Thus, the purpose of this radionuclide screening analysis is to remove from further consideration (screen out) radionuclides that are unlikely to significantly contribute to radiation dose to the public from the proposed nuclear waste repository at Yucca Mountain. The remaining nuclides (those screened in) are recommended for consideration in TSPA modeling for license application. This analysis also covers radionuclides that are not screened in based on dose, but need to be included in TSPA modeling for other reasons. For example, U.S. Environmental Protection Agency (EPA) and U.S. Nuclear Regulatory Commission (NRC) regulations require consideration of the combined activity of Ra-226 and Ra-228 in groundwater (40 CFR 197.30, 10 CFR 63.331). Also, Cm-245, Pu-241, and U-235 decay indirectly to potentially important radionuclides, and are not identified by the screening analysis as important. The radionuclide screening analysis separately considers two different postclosure time periods: the 10,000-y regulatory period for the proposed repository at Yucca Mountain and the period after 10,000 y up to 1 million y after emplacement. The incremental effect of extending the screening for the regulatory period to 20,000 y is also addressed. Four release scenarios are considered: (1) the nominal scenario, which entails long-term degradation of disposal containers and waste forms, (2) a human-intrusion scenario, (3) an intrusive igneous event, and (4) an eruptive igneous event. Because the first three scenarios require groundwater transport, they are called groundwater scenarios below. The screening analysis considers the following waste forms: spent boiling water reactor (BWR) fuel, spent pressurized water reactor (PWR) fuel, U.S. Department of Energy (DOE) spent nuclear fuel (DSNF), and high-level waste (HLW). Average and outlying (high burnup, high initial enrichment, low age, or otherwise exceptional) forms of each waste-form type are considered. This analysis has been prepared in accordance with a technical work plan (BSC 2002c). In a review of Revision 00 of this radionuclide screening analysis, the NRC found that ''processes that affect transport in the biosphere, such as uptake by plants and bioaccumulation are not accounted for'' and that ''the direct exposure pathway is not accounted for'' (Beckman 2001, Section 5.3.2.1). The NRC also found that the solubility and sorption classes were too broadly defined, noting, for example, that Se is in the same solubility and sorptivity groups as Np and U, yet is ''more soluble than Np and U by several orders of magnitude'' (Beckman 2001, Section 5.3.2.1). This revision seeks to build upon the strengths of the earlier screening method while responding to the specific concerns raised by the NRC and other reviewers. In place of simple inhalation and ingestion dose conversion factors, the revised radionuclide screening uses screening factors that also take into account soil accumulation, uptake by plants, exposure to contaminated ground, and other features of the biosphere that were neglected in the previous screening. Whereas the previous screening analysis allowed only two solubility classes (soluble and insoluble), the revised screening introduces an intermediate solubility class to better segregate the radionuclides into transport groups.

G. Ragan

2002-08-09T23:59:59.000Z

33

Resource Management Services: Water Regulation, Part 600: Applications for Licenses and Preliminary Permits Under the Water Power Act (New York)  

Energy.gov (U.S. Department of Energy (DOE))

These regulations provide instructions for applications proposing the construction, repair, or operation of hydropower sources. Applications are reviewed by the Water Power and Control Commission.

34

2008 LANL radionuclide air emissions report  

SciTech Connect

The emissions of radionuclides from Department of Energy Facilities such as Los Alamos National Laboratory (LANL) are regulated by the Amendments to the Clean Air Act of 1990, National Emissions Standards for Hazardous Air Pollutants (40 CFR 61 Subpart H). These regulations established an annual dose limit of 10 mrem to the maximally exposed member of the public attributable to emissions of radionuclides. This document describes the emissions of radionuclides from LANL and the dose calculations resulting from these emissions for calendar year 2008. This report meets the reporting requirements established in the regulations.

Fuehne, David P.

2009-06-01T23:59:59.000Z

35

2010 LANL radionuclide air emissions report /  

SciTech Connect

The emissions of radionuclides from Department of Energy Facilities such as Los Alamos National Laboratory (LANL) are regulated by the Amendments to the Clean Air Act of 1990, National Emissions Standards for Hazardous Air Pollutants (40 CFR 61 Subpart H). These regulations established an annual dose limit of 10 mrem to the maximally exposed member of the public attributable to emissions of radionuclides. This document describes the emissions of radionuclides from LANL and the dose calculations resulting from these emissions for calendar year 2010. This report meets the reporting requirements established in the regulations.

Fuehne, David P.

2011-06-01T23:59:59.000Z

36

Resource Management Services: Water Regulation, Parts 595-599: Hazardous Substances (New York)  

Energy.gov (U.S. Department of Energy (DOE))

These regulations aim to prevent the release of hazardous substances into surface water and groundwater resources. They contain guidance for facilities which store and process hazardous substances,...

37

An Evaluation of the Water Heater Load Potential for Providing Regulation Service  

Science Conference Proceedings (OSTI)

This paper investigates the possibility of providing aggregated regulation services with small loads, such as water heaters or air conditioners. A direct-load control algorithm is presented to aggregate the water heater load for the purpose of regulation. A dual-element electric water heater model is developed, which accounts for both thermal dynamics and users’ water consumptions. A realistic regulation signal was used to evaluate the number of water heaters needed and the operational characteristics of a water heater when providing 2-MW regulation service. Modeling results suggest that approximately 33,333 water heaters are needed to provide a 2-MW regulation service 24 hours a day. However, if water heaters only provide regulation from 6:00 to 24:00, approximately 20,000 will be needed. Because the control algorithm has considered the thermal setting of the water heater, the customer comfort is obstructed little. Therefore, the aggregated regulation service provided by water heater loads can become a major source of revenue for load-service entities when the smart grid enables the direct load control.

Kondoh, Junji; Lu, Ning; Hammerstrom, Donald J.

2011-08-31T23:59:59.000Z

38

Evaluating the Effects of Underground Nuclear Testing Below the Water Table on Groundwater and Radionuclide Migration in the  

E-Print Network (OSTI)

Evaluating the Effects of Underground Nuclear Testing Below the Water Table on Groundwater, using FEHM, evaluate perturbed groundwater behavior associated with underground nuclear tests to an instantaneous pressurization event caused by a nuclear test when different permeability and porosity

39

Natural Radionuclide Activity Concentrations In Spas Of Argentina  

Science Conference Proceedings (OSTI)

Geothermal waters have been used on a large scale for bathing, drinking and medical purposes. These waters can contain natural radionuclides that may increase the exposure to people. In this work the most important natural radionuclide activity concentrations in different thermal spas of Argentina were measured to characterize waters and to evaluate the exposure of workers and members of the public.

Gnoni, G.; Czerniczyniec, M.; Canoba, A.; Palacios, M. [Autoridad Regulatoria Nuclear, Av. Del Libertador 8250, Ciudad de Bs. As. (1429) (Argentina)

2008-08-07T23:59:59.000Z

40

EBS Radionuclide Transport Abstraction  

Science Conference Proceedings (OSTI)

The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in ''Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration'' (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system performance assessment for the license application (TSPA-LA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ). The EBS RT Abstraction conceptual model consists of two main components: a flow model and a transport model. Both models are developed mathematically from first principles in order to show explicitly what assumptions, simplifications, and approximations are incorporated into the models used in the TSPA-LA. The flow model defines the pathways for water flow in the EBS and specifies how the flow rate is computed in each pathway. Input to this model includes the seepage flux into a drift. The seepage flux is potentially split by the drip shield, with some (or all) of the flux being diverted by the drip shield and some passing through breaches in the drip shield that might result from corrosion or seismic damage. The flux through drip shield breaches is potentially split by the waste package, with some (or all) of the flux being diverted by the waste package and some passing through waste package breaches that might result from corrosion or seismic damage. Neither the drip shield nor the waste package survives an igneous intrusion, so the flux splitting submodel is not used in the igneous scenario class. The flow model is validated in an independent model validation technical review. The drip shield and waste package flux splitting algorithms are developed and validated using experimental data. The transport model considers advective transport and diffusive transport from a breached waste package. Advective transport occurs when radionuclides that are dissolved or sorbed onto colloids (or both) are carried from the waste package by the portion of the seepage flux that passes through waste package breaches. Diffusive transport occurs as a result of a gradient in radionuclide concentration and may take place while advective transport is also occurring, as well as when no advective transport is occurring. Diffusive transport is addressed in detail because it is the sole means of transport when there is no flow through a waste package, which may dominate during the regulatory compliance period in the nominal and seismic scenarios. The advective transport rate, when it occurs, is generally greater than the diffusive transport rate. Colloid-facilitated advective and diffusive transport is also modeled and is presented in detail in Appendix B of this report.

J.D. Schreiber

2005-08-25T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Radionuclide deposition control  

DOE Patents (OSTI)

The deposition of radionuclides manganese-54, cobalt-58 and cobalt-60 from liquid sodium coolant is controlled by providing surfaces of nickel or high nickel alloys to extract the radionuclides from the liquid sodium, and by providing surfaces of tungsten, molybdenum or tantalum to prevent or retard radionuclide deposition.

Brehm, William F. (Richland, WA); McGuire, Joseph C. (Richland, WA)

1980-01-01T23:59:59.000Z

42

Collision Regulation Lines in U.S. Waters | Data.gov  

NLE Websites -- All DOE Office Websites (Extended Search)

Collision Regulation Lines in U.S. Waters Energy Data Apps Maps Challenges Resources Blogs Let's Talk Energy Beta You are here Data.gov Communities Energy Data Collision...

43

SELF-REGULATING BOILING-WATER NUCLEAR REACTORS  

DOE Patents (OSTI)

A boiling-water reactor was designed which comprises a pressure vessel containing a mass of water, a reactor core submerged within the water, a reflector tank disposed within the reactor, the reflector tank being open at the top to the interior of the pressure vessel, and a surge tank connected to the reflector tank. In operation the reflector level changes as a function of the pressure witoin the reactor so that the reactivity of the reactor is automatically controlled.

Ransohoff, J.A.; Plawchan, J.D.

1960-08-16T23:59:59.000Z

44

Resource Management Services: Water Regulation, Part 600: Applications...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

provide instructions for applications proposing the construction, repair, or operation of hydropower sources. Applications are reviewed by the Water Power and Control Commission...

45

Application and numerical simulation on water mist cooling for urban environment regulation  

Science Conference Proceedings (OSTI)

The fine water mist is a type of sustainable and environment-friendly cooling technology. This paper concerns the use of water mist flow to improve the quality of urban environment in summer. According to the survey and analysis on the potential for ... Keywords: numerical simulation, regulation of microclimate, spray cooling, two-phase flow

Junfeng Wang; Xincheng Tu; Zhentao Wang; Jiwei Huang

2010-09-01T23:59:59.000Z

46

Division of Water, Parts 670-672: Reservoir Releases Regulations (New York)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

70-672: Reservoir Releases Regulations 70-672: Reservoir Releases Regulations (New York) Division of Water, Parts 670-672: Reservoir Releases Regulations (New York) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Water Buying & Making Electricity Home Weatherization Program Info State New York Program Type Environmental Regulations Provider NY Department of Environmental Conservation Water releases from New York State reservoirs are subject to monitoring and

47

Radionuclides Applied to Tribology  

Science Conference Proceedings (OSTI)

...C.C. Blatchley, Radionuclide Methods, Friction, Lubrication, and Wear Technology, Vol 18, ASM Handbook, ASM International, 1992, p 319â??329...

48

Database of radionuclide measurements in Columbia River water, fish, waterfowl, gamebirds, and shellfish downstream of Hanford`s single-pass production reactors, 1960--1970. Hanford Environmental Dose Reconstruction Project  

Science Conference Proceedings (OSTI)

This report is a result of the Hanford Environmental Dose Reconstruction (HEDR) Project. The goal of the HEDR Project is to estimate the radiation dose that individuals could have received from radionuclide emissions since 1944 at the Hanford Site near Richland, Washington. The HEDR Project is conducted by Battelle, Pacific Northwest Laboratories. The time periods of greatest interest to the HEDR study vary depending on the type of environmental media concerned. Concentrations of radionuclides in Columbia River media from 1960--1970 provide the best historical data for validation of the Columbia River pathway computer models. This report provides the historical radionuclide measurements in Columbia River water (1960--1970), fish (1960--1967), waterfowl (1960--1970), gamebirds (1967--1970), and shellfish (1960--1970). Because of the large size of the databases (845 pages), this report is being published on diskette. A diskette of this report is available from the Technical Steering Panel (c/o K. CharLee, Office of Nuclear Waste Management, Department of Ecology, Technical Support and Publication Information Section, P.O. Box 47651, Olympia, Washington 98504-7651).

Thiede, M.E.; Duncan, J.P.

1994-03-01T23:59:59.000Z

49

Division of Water, Part 673: Dam Safety Regulations (New York) | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3: Dam Safety Regulations (New York) 3: Dam Safety Regulations (New York) Division of Water, Part 673: Dam Safety Regulations (New York) < Back Eligibility Fed. Government Industrial Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative State/Provincial Govt Tribal Government Utility Savings Category Water Buying & Making Electricity Home Weatherization Program Info State New York Program Type Safety and Operational Guidelines Provider NY Department of Environmental Conservation These regulations address dam safety, define dam hazard categories and inspection procedures, and apply to any owner of a dam. Dam owners are required to maintain dams in a safe condition at all times and to comply with Department inquiries for information on the status of a given dam

50

Task 3: PNNL Visit by JAEA Researchers to Participate in TODAM Code Applications to Fukushima Rivers and to Evaluate the Feasibility of Adaptation of FLESCOT Code to Simulate Radionuclide Transport in the Pacific Ocean Coastal Water Around Fukushima  

SciTech Connect

Four JAEA researchers visited PNNL for two weeks in February, 2013 to learn the PNNL-developed, unsteady, one-dimensional, river model, TODAM and the PNNL-developed, time-dependent, three dimensional, coastal water model, FLESCOT. These codes predict sediment and contaminant concentrations by accounting sediment-radionuclide interactions, e.g., adsorption/desorption and transport-deposition-resuspension of sediment-sorbed radionuclides. The objective of the river and coastal water modeling is to simulate • 134Cs and 137Cs migration in Fukushima rivers and the coastal water, and • their accumulation in the river and ocean bed along the Fukushima coast. Forecasting the future cesium behavior in the river and coastal water under various scenarios would enable JAEA to assess the effectiveness of various on-land remediation activities and if required, possible river and coastal water clean-up operations to reduce the contamination of the river and coastal water, agricultural products, fish and other aquatic biota. PNNL presented the following during the JAEA visit to PNNL: • TODAM and FLESCOT’s theories and mathematical formulations • TODAM and FLESCOT model structures • Past TODAM and FLESCOT applications • Demonstrating these two codes' capabilities by applying them to simple hypothetical river and coastal water cases. • Initial application of TODAM to the Ukedo River in Fukushima and JAEA researchers' participation in its modeling. PNNL also presented the relevant topics relevant to Fukushima environmental assessment and remediation, including • PNNL molecular modeling and EMSL computer facilities • Cesium adsorption/desorption characteristics • Experiences of connecting molecular science research results to macro model applications to the environment • EMSL tour • Hanford Site road tour. PNNL and JAEA also developed future course of actions for joint research projects on the Fukushima environmental and remediation assessments.

Onishi, Yasuo

2013-03-29T23:59:59.000Z

51

Task 3: PNNL Visit by JAEA Researchers to Participate in TODAM Code Applications to Fukushima Rivers and to Evaluate the Feasibility of Adaptation of FLESCOT Code to Simulate Radionuclide Transport in the Pacific Ocean Coastal Water Around Fukushima  

SciTech Connect

Four JAEA researchers visited PNNL for two weeks in February, 2013 to learn the PNNL-developed, unsteady, one-dimensional, river model, TODAM and the PNNL-developed, time-dependent, three dimensional, coastal water model, FLESCOT. These codes predict sediment and contaminant concentrations by accounting sediment-radionuclide interactions, e.g., adsorption/desorption and transport-deposition-resuspension of sediment-sorbed radionuclides. The objective of the river and coastal water modeling is to simulate • 134Cs and 137Cs migration in Fukushima rivers and the coastal water, and • their accumulation in the river and ocean bed along the Fukushima coast. Forecasting the future cesium behavior in the river and coastal water under various scenarios would enable JAEA to assess the effectiveness of various on-land remediation activities and if required, possible river and coastal water clean-up operations to reduce the contamination of the river and coastal water, agricultural products, fish and other aquatic biota. PNNL presented the following during the JAEA visit to PNNL: • TODAM and FLESCOT’s theories and mathematical formulations • TODAM and FLESCOT model structures • Past TODAM and FLESCOT applications • Demonstrating these two codes' capabilities by applying them to simple hypothetical river and coastal water cases. • Initial application of TODAM to the Ukedo River in Fukushima and JAEA researchers' participation in its modeling. PNNL also presented the relevant topics relevant to Fukushima environmental assessment and remediation, including • PNNL molecular modeling and EMSL computer facilities • Cesium adsorption/desorption characteristics • Experiences of connecting molecular science research results to macro model applications to the environment • EMSL tour • Hanford Site road tour. PNNL and JAEA also developed future course of actions for joint research projects on the Fukushima environmental and remediation assessments.

Onishi, Yasuo

2013-03-29T23:59:59.000Z

52

Impacts of operation of CVP regulating reservoirs on water temperature  

DOE Green Energy (OSTI)

The Western Area Power Administration (Western) markets and transmits electric power throughout 15 western states. Western's Sierra Nevada Customer Service Region (Sierra Nevada Region) markets approximately 1,480 megawatts (MW) of firm power (and 100 MW of seasonal peaking capacity) from the Central Valley Project (CVP) and other sources and markets available nonfirm power from the Washoe Project. Western's mission is to sell and deliver electricity generated from CVP powerplants. The hydroelectric facilities of the CVP are operated by the Bureau of Reclamation (Reclamation). Reclamation manages and releases water in accordance with the various acts authorizing specific projects and with enabling legislation. Western's capacity and energy sales must be in conformance with the laws that govern its sale of electrical power. Further, Western's hydropower operations at each facility must comply with minimum and maximum flows and other constraints set by Reclamation, the U.S. Fish and Wildlife Service, or other agencies, acting in accord with law or policy.

Vail, L.W.

1996-06-01T23:59:59.000Z

53

Air Pollution Control Regulations: No. 13- Particulate Emissions from Fossil Fuel Fired Steam or Hot Water Generating Units (Rhode Island)  

Energy.gov (U.S. Department of Energy (DOE))

The purpose of this regulation is to limit emissions of particulate matter from fossil fuel fired and wood-fired steam or hot water generating units.

54

Assessment of hydrologic transport of radionuclides from the Rio Blanco underground nuclear test site, Colorado  

SciTech Connect

DOE is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations used for nuclear testing. Evaluation of radionuclide transport by groundwater is part of preliminary risk analysis. These evaluations allow prioritization of test areas in terms of risk, provide a basis for discussions with regulators and the public about future work, and provide a framework for assessing site characterization data needs. The Rio Blanco site in Colorado was the location of the simultaneous detonation of three 30-kiloton nuclear devices. The devices were located 1780, 1899, and 2039 below ground surface in the Fort Union and Mesaverde formations. Although all the bedrock formations at the site are thought to contain water, those below the Green River Formation (below 1000 in depth) are also gas-bearing, and have very low permeabilities. The transport scenario evaluated was the migration of radionuclides from the blast-created cavity through the Fort Union Formation. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides from the test are contained entirely within the area currently administered by DOE. This modeling was performed to investigate how the uncertainty in various physical parameters affect radionuclide transport at the site, and to serve as a starting point for discussion regarding further investigation; it was not intended to be a definitive simulation of migration pathways or radionuclide concentration values. Given the sparse data, the modeling results may differ significantly from reality. Confidence in transport predictions can be increased by obtaining more site data, including the amount of radionuclides which would have been available for transport (i.e., not trapped in melt glass or vented during gas flow testing), and the hydraulic properties of the formation. 38 refs., 6 figs., 1 tab.

Chapman, J.; Earman, S.; Andricevic, R.

1996-10-01T23:59:59.000Z

55

Selected radionuclides important to low-level radioactive waste management  

Science Conference Proceedings (OSTI)

The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). This report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237.

NONE

1996-11-01T23:59:59.000Z

56

Radionuclide Air Emission Report for 2011  

SciTech Connect

Berkeley Lab operates facilities where radionuclides are produced, handled, stored, and potentially emitted. These facilities are subject to the EPA radioactive air emission regulations in 40 CFR 61, Subpart H. Radionuclides may be emitted from stacks or vents on buildings where radionuclide production or use is authorized or they may be emitted as diffuse sources. In 2011, all Berkeley Lab sources were minor sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.01 mSv/yr]). These minor sources included about 90 stack sources and one source of diffuse emissions. There were no unplanned airborne radionuclide emissions from Berkeley lab operations. Emissions from minor sources (stacks and diffuse emissions) were measured by sampling or monitoring or were calculated based on quantities used, received for use, or produced during the year. Using measured and calculated emissions, and building-specific and common parameters, Laboratory personnel applied the EPA-approved computer codes, CAP88-PC and COMPLY, to calculate the effective dose equivalent to the maximally exposed individual (MEI).

Wahl, Linnea

2012-06-04T23:59:59.000Z

57

Method and apparatus for separating radionuclides from non-radionuclides  

DOE Patents (OSTI)

In an apparatus for separating radionuclides from non-radionuclides in a mixture of nuclear waste, a vessel is provided wherein the mixture is heated to a temperature greater than the temperature of vaporization for the non-radionuclides but less than the temperature of vaporization for the radionuclides. Consequently the non-radionuclides are vaporized while the non-radionuclides remain the solid or liquid state. The non-radionuclide vapors are withdrawn from the vessel and condensed to produce a flow of condensate. When this flow decreases the heat is reduced to prevent temperature spikes which might otherwise vaporize the radionuclides. The vessel is removed and capped with the radioactive components of the apparatus and multiple batches of the radionuclide residue disposed therein. Thus the vessel ultimately provides a burial vehicle for all of the radioactive components of the process.

Harp, Richard J. (18746 Viking Way, Cerritos, CA 90701)

1990-01-01T23:59:59.000Z

58

COST IMPACT OF SAFE DRINKING WATER ACT COMPLIANCE FOR COMMISSION-REGULATED WATER UTILITIES  

E-Print Network (OSTI)

(NRRI) with funding provided by participating member commissions of the National Association of Regulatory Utility Commissioners (NARUC). The views and opinions of the authors do not necessarily state or reflect the views, opinions, or policies of the NRRI, the NARUC, or NARUC member commissions. EXECUTIVE SUMMARY This study was prepared for state public utility commissioners and their staff in response to the growing concern about the effect of the Safe Drinking Water Act (SDWA) on water utilities under their jurisdiction. Compliance with the SDWA is expected to have a significant impact on water utilities and the rates they charge for service. A sensitivity analysis was developed for this report using a hypothetical water company to identify the costs associated with alternative treatment processes. A total of eighteen different treatment processes are considered, from conventional treatment to granular activated carbon (GAC) adsorption and reverse osmosis. Capital costs for these processes range from $100,000 to $3.25 million for a water plant with a designed capacity of one million

Patrick C. Mann; Janice A. Beecher

1989-01-01T23:59:59.000Z

59

Radionuclide Air Emission Report for 2007  

E-Print Network (OSTI)

for Emissions of Radionuclides Other Than Radon FromHazardous Air Pollutants (Radionuclides), Availability ofLBNL to Revise Its Radionuclide NESHAP Monitoring Approach,”

Wahl, Linnea

2008-01-01T23:59:59.000Z

60

Radionuclide Air Emission Report for 2009  

E-Print Network (OSTI)

the public from airborne radionuclide emissions. We requestfor Emissions of Radionuclides Other Than Radon FromFugitive Air Emissions of Radionuclides from Diffuse Sources

Wahl, Linnea

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Radionuclide Air Emission Report for 2011  

E-Print Network (OSTI)

LBNL-470E-20Ì1 Radionuclide Air Emission Report for Preparedfor Emissions of Radionuclides Other Than Radon FromFugitive Air Emissions of Radionuclides from Diffuse Sources

Wahl, Linnea

2012-01-01T23:59:59.000Z

62

Radionuclide Air Emission Report for 2008  

E-Print Network (OSTI)

Fugitive Air Emissions of Radionuclides from Diffuse SourcesHazardous Air Pollutants (Radionuclides), Availability ofLBNL to Revise Its Radionuclide NESHAP Monitoring Approach,”

Wahl, Linnea

2009-01-01T23:59:59.000Z

63

Assessment of hydrologic transport of radionuclides from the Gnome underground nuclear test site, New Mexico  

SciTech Connect

The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary site risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Gnome site in southeastern New Mexico was the location of an underground detonation of a 3.5-kiloton nuclear device in 1961, and a hydrologic tracer test using radionuclides in 1963. The tracer test involved the injection of tritium, {sup 90}Sr, and {sup 137}Cs directly into the Culebra Dolomite, a nine to ten-meter-thick aquifer located approximately 150 in below land surface. The Gnome nuclear test was carried out in the Salado Formation, a thick salt deposit located 200 in below the Culebra. Because salt behaves plastically, the cavity created by the explosion is expected to close, and although there is no evidence that migration has actually occurred, it is assumed that radionuclides from the cavity are released into the overlying Culebra Dolomite during this closure process. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides may be present in concentrations exceeding drinking water regulations outside the drilling exclusion boundary established by DOE. Calculated mean tritium concentrations peak at values exceeding the U.S. Environmental Protection Agency drinking water standard of 20,000 pCi/L at distances of up to almost eight kilometers west of the nuclear test.

Earman, S.; Chapman, J.; Pohlmann, K.; Andricevic, R.

1996-09-01T23:59:59.000Z

64

Diffusion of Radionuclides in Concrete and Soil  

SciTech Connect

One of the methods being considered for safely disposing of Category 3 low-level radioactive wastes is to encase the waste in concrete. Such concrete encasement would contain and isolate the waste packages from the hydrologic environment and would act as an intrusion barrier. Any failure of concrete encasement may result in water intrusion and consequent mobilization of radionuclides from the waste packages. The mobilized radionuclides may escape from the encased concrete by mass flow and/or diffusion and move into the surrounding subsurface environment. Therefore, it is necessary to assess the performance of the concrete encasement structure and the ability of the surrounding soil to retard radionuclide migration. The objective of our study was to measure the diffusivity of Re, Tc and I in concrete containment and the surrounding vadose zone soil. Effects of carbonation, presence of metallic iron, and fracturing of concrete and the varying moisture contents in soil on the diffusivities of Tc and I were evaluated.

Mattigod, Shas V.; Wellman, Dawn M.; Bovaird, Chase C.; Parker, Kent E.; Recknagle, Kurtis P.; Clayton, Libby N.; Wood, Marcus I.

2012-04-25T23:59:59.000Z

65

Idaho radionuclide exposure study: Literature review  

Science Conference Proceedings (OSTI)

Phosphate ores contain elevated levels of natural radioactivity, some of which is released to the environment during processing or use of solid byproducts. The effect of radionuclides from Idaho phosphate processing operations on the local communities has been the subject of much research and study. The literature is reviewed in this report. Two primary radionuclide pathways to the environment have been studied in detail: (1) airborne release of volatile radionuclides, primarily /sup 210/Po, from calciner stacks at the two elemental phosphorus plants; and (2) use of byproduct slag as an aggregate for construction in Soda Springs and Pocatello. Despite the research, there is still no clear understanding of the population dose from radionuclide emissions, effluents, and solid wastes from phosphate processing plants. Two other potential radionuclide pathways to the environment have been identified: radon exhalation from phosphogypsum and ore piles and contamination of surface and ground waters. Recommendations on further study needed to develop a data base for a complete risk assssment are given in the report.

Baker, E.G.; Freeman, H.D.; Hartley, J.N.

1987-10-01T23:59:59.000Z

66

Sediment and radionuclide transport in rivers: radionuclide transport modeling for Cattaraugus and Buttermilk Creeks, New York  

Science Conference Proceedings (OSTI)

SERATRA, a transient, two-dimensional (laterally-averaged) computer model of sediment-contaminant transport in rivers, satisfactorily resolved the distribution of sediment and radionuclide concentrations in the Cattaraugus Creek stream system in New York. By modeling the physical processes of advection, diffusion, erosion, deposition, and bed armoring, SERATRA routed three sediment size fractions, including cohesive soils, to simulate three dynamic flow events. In conjunction with the sediment transport, SERATRA computed radionuclide levels in dissolved, suspended sediment, and bed sediment forms for four radionuclides (/sup 137/Cs, /sup 90/Sr, /sup 239/ /sup 240/Pu, and /sup 3/H). By accounting for time-dependent sediment-radionuclide interaction in the water column and bed, SERATA is a physically explicit model of radionuclide fate and migration. Sediment and radionuclide concentrations calculated by SERATA in the Cattaraugus Creek stream system are in reasonable agreement with measured values. SERATRA is in the field performance phase of an extensive testing program designed to establish the utility of the model as a site assessment tool. The model handles not only radionuclides but other contaminants such as pesticides, heavy metals and other toxic chemicals. Now that the model has been applied to four field sites, including the latest study of the Cattaraugus Creek stream system, it is recommended that a final model be validated through comparison of predicted results with field data from a carefully controlled tracer test at a field site. It is also recommended that a detailed laboratory flume be tested to study cohesive sediment transport, deposition, and erosion characteristics. The lack of current understanding of these characteristics is one of the weakest areas hindering the accurate assessment of the migration of radionuclides sorbed by fine sediments of silt and clay.

Onishi, Y.; Yabusaki, S.B.; Kincaid, C.T.; Skaggs, R.L.; Walters, W.H.

1982-12-01T23:59:59.000Z

67

Radionuclide Ratio Analyst Tool  

E-Print Network (OSTI)

Kendra M. Foltz Biegalski This memo recommends the installation of several upgrades and additions to the Radionuclide Monitoring Software (RMS) into operations at the Center for Monitoring Research (CMR). The software additions and upgrades described herein provide new functionality and improved results to many aspects of radionuclide data analysis. This software was developed under the Technical Verification and Analytical Support (TVAS) program at the CMR. This software has been running on the TVAS development network from 3 months to 2 years. Statement of Objective The objective of this proposal is the implementation of additions and upgrades to the RMS software into CMR operations. The following additional software components are recommended:

unknown authors

2002-01-01T23:59:59.000Z

68

Assessment of hydrologic transport of radionuclides from the Rulison Underground Nuclear Test Site, Colorado  

SciTech Connect

The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Rulison site in west-central Colorado was the location of an underground detonation of a 40-kiloton nuclear device in 1969. The test took place 2,568 m below ground surface in the Mesaverde Formation. Though located below the regional water table, none of the bedrock formations at the site yielded water during hydraulic tests, indicating extremely low permeability conditions. The scenario evaluated was the migration of radionuclides from the blast-created cavity through the Mesaverde Formation. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides from the test are contained entirely within the area currently administered by DOE. The transport calculations are most sensitive to changes in the mean groundwater velocity and the correlation scale of hydraulic conductivity, with transport of strontium and cesium also sensitive to the sorption coefficient.

Earman, S.; Chapman, J.; Andricevic, R.

1996-09-01T23:59:59.000Z

69

Radionuclide Air Emission Report for 2007  

Science Conference Proceedings (OSTI)

Berkeley Lab operates facilities where radionuclides are handled and stored. These facilities are subject to the U.S. Environmental Protection Agency (EPA) radioactive air emission regulations in Code of Federal Regulations (CFR) Title 40, Part 61, Subpart H (EPA 1989). The EPA regulates radionuclide emissions that may be released from stacks or vents on buildings where radionuclide production or use is authorized or that may be emitted as diffuse sources. In 2007, all Berkeley Lab sources were minor stack or building emissions sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.001 mSv/yr]), there were no diffuse emissions, and there were no unplanned emissions. Emissions from minor sources either were measured by sampling or monitoring or were calculated based on quantities received for use or produced during the year. Using measured and calculated emissions, and building-specific and common parameters, Laboratory personnel applied the EPA-approved computer code, CAP88-PC, Version 3.0, to calculate the effective dose equivalent to the maximally exposed individual (MEI). The effective dose equivalent from all sources at Berkeley Lab in 2007 is 1.2 x 10{sup -2} mrem/yr (1.2 x 10{sup -4} mSv/yr) to the MEI, well below the 10 mrem/yr (0.1 mSv/yr) EPA dose standard. The location of the MEI is at the University of California (UC) Lawrence Hall of Science, a public science museum about 1500 ft (460 m) east of Berkeley Lab's Building 56. The estimated collective effective dose equivalent to persons living within 50 mi (80 km) of Berkeley Lab is 3.1 x 10{sup -1} person-rem (3.1 x 10{sup -3} person-Sv) attributable to the Lab's airborne emissions in 2007.

Wahl, Linnea; Wahl, Linnea

2008-06-13T23:59:59.000Z

70

ITER's Tokamak Cooling Water System and the the Use of ASME Codes to Comply with French Regulations of Nuclear Pressure Equipment  

Science Conference Proceedings (OSTI)

During inductive plasma operation of ITER, fusion power will reach 500 MW with an energy multiplication factor of 10. The heat will be transferred by the Tokamak Cooling Water System (TCWS) to the environment using the secondary cooling system. Plasma operations are inherently safe even under the most severe postulated accident condition a large, in-vessel break that results in a loss-of-coolant accident. A functioning cooling water system is not required to ensure safe shutdown. Even though ITER is inherently safe, TCWS equipment (e.g., heat exchangers, piping, pressurizers) are classified as safety important components. This is because the water is predicted to contain low-levels of radionuclides (e.g., activated corrosion products, tritium) with activity levels high enough to require the design of components to be in accordance with French regulations for nuclear pressure equipment, i.e., the French Order dated 12 December 2005 (ESPN). ESPN has extended the practical application of the methodology established by the Pressure Equipment Directive (97/23/EC) to nuclear pressure equipment, under French Decree 99-1046 dated 13 December 1999, and Order dated 21 December 1999 (ESP). ASME codes and supplementary analyses (e.g., Failure Modes and Effects Analysis) will be used to demonstrate that the TCWS equipment meets these essential safety requirements. TCWS is being designed to provide not only cooling, with a capacity of approximately 1 GW energy removal, but also elevated temperature baking of first-wall/blanket, vacuum vessel, and divertor. Additional TCWS functions include chemical control of water, draining and drying for maintenance, and facilitation of leak detection/localization. The TCWS interfaces with the majority of ITER systems, including the secondary cooling system. U.S. ITER is responsible for design, engineering, and procurement of the TCWS with industry support from an Engineering Services Organization (ESO) (AREVA Federal Services, with support from Northrop Grumman, and OneCIS). ITER International Organization (ITER-IO) is responsible for design oversight and equipment installation in Cadarache, France. TCWS equipment will be fabricated using ASME design codes with quality assurance and oversight by an Agreed Notified Body (approved by the French regulator) that will ensure regulatory compliance. This paper describes the TCWS design and how U.S. ITER and fabricators will use ASME codes to comply with EU Directives and French Orders and Decrees.

Berry, Jan [ORNL; Ferrada, Juan J [ORNL; Curd, Warren [ITER Organization, Saint Paul Lez Durance, France; Dell Orco, Dr. Giovanni [ITER Organization, Saint Paul Lez Durance, France; Barabash, Vladimir [ITER Organization, Saint Paul Lez Durance, France; Kim, Seokho H [ORNL

2011-01-01T23:59:59.000Z

71

Radionuclide transport in the Yenisei River  

E-Print Network (OSTI)

Data characterizing the pollution of the Yenisei River (water and bottom sediment) by radionuclide resulting from the use of the river water for cooling industrial reactors in the Mining-Chemical Complex are presented. Studies have been made of the contamination of the river during the period when reactors with direct flow cooling were used and after these were shut down. Distinctive features of the migration of radionuclide in the Yenisei are noted, in particular, their distribution between the solid and liquid phases. The amounts of 137Cs, 65Zn, 60Co, 54Mn, and 152Eu in the channel are determined from the effluent discharge site to Dudinka port. The rate of continuous self removal of 137Cs is estimated to be 0.19 1/year, corresponding to a half purification time of 3.6 years for a 600 km long segment of the river bed.

S. M. Vakulovsky; E. G. Tertyshnik; A. I. Kabanov

2012-11-15T23:59:59.000Z

72

Radionuclides in United States commercial nuclear power reactors  

SciTech Connect

In the next ten to twenty years, many of the commercial nuclear power reactors in the United States will be reaching their projected lifetime of forty years. As these power plants are decommissioned, it seems prudent to consider the recycling of structural materials such as stainless steel. Some of these materials and components have become radioactive through either nuclear activation of the elements within the components or surface contamination with radioactivity form the operational activities. In order to understand the problems associated with recycling stainless steel from decommissioned nuclear power reactors, it is necessary to have information on the radionuclides expected on or in the contaminated materials. A study has been conducted of radionuclide contamination information that is available for commercial nuclear power reactors in the United States. There are two types of nuclear power reactors in commercial use in the United States, pressurized water reactors (PWRs) and boiling water reactors (BWRs). Before presenting radionuclide activities information, a brief discussion is given on the major components and operational differences for the PWRs and BWRs. Radionuclide contamination information is presented from 11 PWRs and over 8 BWRs. These data include both the radionuclides within the circulating reactor coolant water as well as radionuclide contamination on and within component parts.

Bechtold, T.E. [ed.] [Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States); Dyer, N.C. [Oregon Graduate Inst. of Science and Technology, Beaverton, OR (United States)

1994-01-01T23:59:59.000Z

73

Radionuclide Air Emission Report for 2008  

SciTech Connect

Berkeley Lab operates facilities where radionuclides are handled and stored. These facilities are subject to the U.S. Environmental Protection Agency (EPA) radioactive air emission regulations in Code of Federal Regulations (CFR) Title 40, Part 61, Subpart H (EPA 1989). Radionuclides may be emitted from stacks or vents on buildings where radionuclide production or use is authorized or they may be emitted as diffuse sources. In 2008, all Berkeley Lab sources were minor sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.001 mSv/yr]). These minor sources include more than 100 stack sources and one source of diffuse emissions. There were no unplanned emissions from the Berkeley Lab site. Emissions from minor sources (stacks and diffuse emissions) either were measured by sampling or monitoring or were calculated based on quantities used, received for use, or produced during the year. Using measured and calculated emissions, and building-specific and common parameters, Laboratory personnel applied the EPA-approved computer code, CAP88-PC, to calculate the effective dose equivalent to the maximally exposed individual (MEI). The effective dose equivalent from all sources at Berkeley Lab in 2008 is 5.2 x 10{sup -3} mrem/yr (5.2 x 10{sup -5} mSv/yr) to the MEI, well below the 10 mrem/yr (0.1 mSv/yr) dose standard. The location of the MEI is at the University of California (UC) Lawrence Hall of Science, a public science museum about 1500 ft (460 m) east of Berkeley Lab's Building 56. The estimated collective effective dose equivalent to persons living within 50 mi (80 km) of Berkeley Lab is 1.1 x 10{sup -1} person-rem (1.1 x 10{sup -3} person-Sv) attributable to the Lab's airborne emissions in 2008.

Wahl, Linnea

2009-05-21T23:59:59.000Z

74

Identification of radionuclides of concern in Hanford Site environmental cleanup  

Science Conference Proceedings (OSTI)

The purpose of this document is to consider which radionuclides should be included in conducting environmental surveys relative to site remediation at Hanford. During the operation of the Hanford site, the fission product radionuclides and a large number of activation products including the transuranic radionuclides were formed. The reactor operations and subsequent chemical processing and metallurgical operations resulted in the environmental release of gaseous and liquid effluents containing some radionuclides; however, the majority of the radionuclides were stored in waste tanks or disposed to trenches and cribs. Since some contamination of both soils and subsurface waters occurred, one must decide which radionuclides still remain in sufficient amounts to be of concern at the time when site remediation is to be complete. Many of the radionuclides which have constituted the principal hazard during site operation have half-lives on the order of a year or less; therefore, they will have decayed to insignificant amounts by the year 2030, a possible date for completion of the remediation process.

Perkins, R.W.; Jenquin, U.P.

1994-08-01T23:59:59.000Z

75

Uranium-series radionuclide records of paleoceanographic and sedimentary changes in the Arctic Ocean  

E-Print Network (OSTI)

The radionuclides ²³¹Pa and ²³?Th, produced in the water column and removed from the ocean by particle scavenging and burial in sediments, offer a means for paleoceanographers to examine past dynamics of both water column ...

Hoffmann, Sharon Susanna

2009-01-01T23:59:59.000Z

76

MOIRA-PLUS: A decision support system for the management of complex fresh water ecosystems contaminated by radionuclides and heavy metals  

Science Conference Proceedings (OSTI)

The accidental release of radioactive substances into the environment leads to the necessity of applying suitable countermeasures for the restoration of the polluted environment. However, despite their obvious benefits, such interventions may result ... Keywords: Countermeasures, Decision systems, Fresh water ecosystems, MOIRA DSS, Modelling, Multi-attribute analysis

Luigi Monte; John E. Brittain; Eduardo Gallego; Lars Håkanson; Dmitry Hofman; Antonio Jiménez

2009-05-01T23:59:59.000Z

77

Deriving cleanup guidelines for radionuclides at Brookhaven National Laboratory  

Science Conference Proceedings (OSTI)

Past activities at Brookhaven National Laboratory (BNL) resulted in soil and groundwater contamination. As a result, BNL was designated a Superfund site under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). BNL`s Office of Environmental Restoration (OER) is overseeing environmental restoration activities at the Laboratory. With the exception of radium, there are no regulations or guidelines to establish cleanup guidelines for radionuclides in soils at BNL. BNL must derive radionuclide soil cleanup guidelines for a number of Operable Units (OUs) and Areas of Concern (AOCs). These guidelines are required by DOE under a proposed regulation for radiation protection of public health and the environment as well as to satisfy the requirements of CERCLA. The objective of this report is to propose a standard approach to deriving risk-based cleanup guidelines for radionuclides in soil at BNL. Implementation of the approach is briefly discussed.

Meinhold, A.F.; Morris, S.C.; Dionne, B.; Moskowitz, P.D.

1997-01-01T23:59:59.000Z

78

Tracing Noble Gas Radionuclides in the Environment  

E-Print Network (OSTI)

Trace analysis of radionuclides is an essential and versatile tool in modern science and technology. Due to their ideal geophysical and geochemical properties, long-lived noble gas radionuclides, in particular, 39Ar (t1/2 = 269 yr), 81Kr (t1/2 = 2.3x10^5 yr) and 85Kr (t1/2 = 10.8 yr), have long been recognized to have a wide range of important applications in Earth sciences. In recent years, significant progress has been made in the development of practical analytical methods, and has led to applications of these isotopes in the hydrosphere (tracing the flow of groundwater and ocean water). In this article, we introduce the applications of these isotopes and review three leading analytical methods: Low-Level Counting (LLC), Accelerator Mass Spectrometry (AMS) and Atom Trap Trace Analysis (ATTA).

P. Collon; W. Kutschera; Z. -T. Lu

2004-02-11T23:59:59.000Z

79

Passive containment cooling system with drywell pressure regulation for boiling water reactor  

DOE Patents (OSTI)

A boiling water reactor is described having a regulating valve for placing the wetwell in flow communication with an intake duct of the passive containment cooling system. This subsystem can be adjusted to maintain the drywell pressure at (or slightly below or above) wetwell pressure after the initial reactor blowdown transient is over. This addition to the PCCS design has the benefit of eliminating or minimizing steam leakage from the drywell to the wetwell in the longer-term post-LOCA time period and also minimizes the temperature difference between drywell and wetwell. This in turn reduces the rate of long-term pressure buildup of the containment, thereby extending the time to reach the design pressure limit. 4 figures.

Hill, P.R.

1994-12-27T23:59:59.000Z

80

Passive containment cooling system with drywell pressure regulation for boiling water reactor  

DOE Patents (OSTI)

A boiling water reactor having a regulating valve for placing the wetwell in flow communication with an intake duct of the passive containment cooling system. This subsystem can be adjusted to maintain the drywell pressure at (or slightly below or above) wetwell pressure after the initial reactor blowdown transient is over. This addition to the PCCS design has the benefit of eliminating or minimizing steam leakage from the drywell to the wetwell in the longer-term post-LOCA time period and also minimizes the temperature difference between drywell and wetwell. This in turn reduces the rate of long-term pressure buildup of the containment, thereby extending the time to reach the design pressure limit.

Hill, Paul R. (Tucson, AZ)

1994-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

FINAL REPORT SELECTION OF RADIONUCLIDES FOR  

E-Print Network (OSTI)

FINAL REPORT SELECTION OF RADIONUCLIDES FOR INCLUSION IN DOSE RECONSTRUCTIONS AT IDAHO NATIONAL Author: David C. Kocher SENES Oak Ridge, Inc. July 2005 #12;Selection of Radionuclides July 2005..................................................................................2 3.0 Selection of Radionuclides by Screening

82

Targeted radionuclide therapy  

Science Conference Proceedings (OSTI)

Targeted radionuclide therapy (TRT) seeks molecular and functional targets within patient tumor sites. A number of agents have been constructed and labeled with beta, alpha, and Auger emitters. Radionuclide carriers spanning a broad range of sizes; e.g., antibodies, liposomes, and constructs such as nanoparticles have been used in these studies. Uptake, in percent-injected dose per gram of malignant tissue, is used to evaluate the specificity of the targeting vehicle. Lymphoma (B-cell) has been the primary clinical application. Extension to solid tumors will require raising the macroscopic absorbed dose by several-fold over values found in present technology. Methods that may effect such changes include multistep targeting, simultaneous chemotherapy, and external sequestration of the agent. Toxicity has primarily involved red marrow so that marrow replacement can also be used to enhance future TRT treatments. Correlation of toxicities and treatment efficiency has been limited by relatively poor absorbed dose estimates partly because of using standard (phantom) organ sizes. These associations will be improved in the future by obtaining patient-specific organ size and activity data with hybrid SPECT/CT and PET/CT scanners.

Williams, Lawrence E.; DeNardo, Gerald L.; Meredith, Ruby F. [Radiology Division, City of Hope National Medical Center, Duarte, California 91010 (United States); Internal Medicine, University of California Davis Medical Center, 1508 Alhambra Boulevard, Suite 3100, Sacramento, California 95816 (United States); Department of Radiation Oncology, Wallace Tumor Institute WTI No. 117, University of Alabama at Birmingham, Birmingham, Alabama 35294 (United States)

2008-07-15T23:59:59.000Z

83

Radionuclide Air Emission Report for 2009  

SciTech Connect

Berkeley Lab operates facilities where radionuclides are handled and stored. These facilities are subject to the EPA radioactive air emission regulations in 40CFR61, Subpart H (EPA 1989). Radionuclides may be emitted from stacks or vents on buildings where radionuclide production or use is authorized or they may be emitted as diffuse sources. In 2009, all Berkeley Lab sources were minor sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.001 mSv/yr]). These minor sources included more than 100 stack sources and one source of diffuse emissions. There were no unplanned emissions from the Berkeley Lab site. Emissions from minor sources (stacks and diffuse emissions) either were measured by sampling or monitoring or were calculated based on quantities used, received for use, or produced during the year. Using measured and calculated emissions, and building-specific and common parameters, Laboratory personnel applied the EPA-approved computer code, CAP88-PC, to calculate the effective dose equivalent to the maximally exposed individual (MEI). The effective dose equivalent from all sources at Berkeley Lab in 2009 is 7.0 x 10{sup -3} mrem/yr (7.0 x 10{sup -5} mSv/yr) to the MEI, well below the 10 mrem/yr (0.1 mSv/yr) dose standard. The location of the MEI is at the University of California (UC) Lawrence Hall of Science, a public science museum about 1500 ft (460 m) east of Berkeley Lab's Building 56. The estimated collective effective dose equivalent to persons living within 50 mi (80 km) of Berkeley Lab is 1.5 x 10{sup -1} person-rem (1.5 x 10{sup -3} person-Sv) attributable to the Lab's airborne emissions in 2009.

Wahl, Linnea

2010-06-01T23:59:59.000Z

84

U.S. DOE 2004 LANL Radionuclide Air Emissions  

SciTech Connect

Amendments to the Clean Air Act, which added radionuclides to the National Emissions Standards for Hazardous Air Pollutants (NESHAP), went into effect in 1990. Specifically, a subpart (H) of 40 CFR 61 established an annual limit on the impact to the public attributable to emissions of radionuclides from U.S. Department of Energy facilities, such as the Los Alamos National Laboratory (LANL). As part of the new NESHAP regulations, LANL must submit an annual report to the U.S. Environmental Protection Agency headquarters and the regional office in Dallas by June 30. This report includes results of monitoring at LANL and the dose calculations for the calendar year 2004.

K.W. Jacobson

2005-08-12T23:59:59.000Z

85

Bioremediation of Metals and Radionuclides: What It Is and How It Works (2nd Edition)  

E-Print Network (OSTI)

63 ACRONYMS Radionuclides . . . . . . .5 The Focus on Radionuclides andand Radionuclides . . . . . . . . . . . . . . 56 Feature:

Palmisano, Anna; Hazen, Terry

2003-01-01T23:59:59.000Z

86

MICROBIAL TRANSFORMATIONS OF RADIONUCLIDES AND ENVIRONMENTAL RESTORATION THROUGH BIOREMEDIATION.  

Science Conference Proceedings (OSTI)

Treatment of waste streams containing radionuclides, the remediation of contaminated materials, soils, and water, and the safe and economical disposal of radionuclides and toxic metals containing wastes is a major concern. Radionuclides may exist in various oxidation states and may be present as oxide, coprecipitates, inorganic, and organic complexes depending on the process and waste stream. Unlike organic contaminants, the metals cannot be destroyed, but must either be converted to a stable form or removed. Microorganisms present in the natural environment play a major role in the mobilization and immobilization of radionuclides and toxic metals by direct enzymatic or indirect non-enzymatic actions and could affect the chemical nature of the radionuclides by altering the speciation, solubility and sorption properties and thus could increase or decrease the concentrations of radionuclides in solution. Fundamental understanding of the mechanisms of microbiological transformations of various chemical forms of uranium present in wastes and contaminated soils and water has led to the development of novel bioremediation processes. One process uses anaerobic bacteria to stabilize the radionuclides by reductive precipitation from higher to lower oxidation state with a concurrent reduction in volume due to the dissolution and removal of nontoxic elements from the waste matrix. In an another process, uranium and other toxic metals are removed from contaminated surfaces, soils, and wastes by extracting with the chelating agent citric acid. Uranium is recovered from the citric acid extract after biodegradation followed by photodegradation in a concentrated form as UO{sub 3} {center_dot} 2H{sub 2}O for recycling or appropriate disposal. These processes use all naturally occurring materials, common soil bacteria, naturally occurring organic compound citric acid and sunlight.

FRANCIS, A.J.

2006-09-29T23:59:59.000Z

87

Radionuclide Retention in Concrete Wasteforms  

Science Conference Proceedings (OSTI)

Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how wasteform performance is affected by the full range of environmental conditions within the disposal facility; the process of wasteform aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of wasteform aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the wasteforms come in contact with groundwater. The information present in the report provides data that (1) measures the effect of concrete wasteform properties likely to influence radionuclide migration; and (2) quantifies the rate of carbonation of concrete materials in a simulated vadose zone repository.

Bovaird, Chase C.; Jansik, Danielle P.; Wellman, Dawn M.; Wood, Marcus I.

2011-09-30T23:59:59.000Z

88

Temperature Effect on the Sorption of Radionuclides by Freshwater Algae  

SciTech Connect

The heavy waters of the reactor effluent streams within the Savannah River Plant area transport very low concentrations of fission and activation products through miles of natural streambeds and swamps to the Savannah River. This study emphasizes the effects of environmental factors on the sorption of radionuclides by representative species.

Harvey, R.S.

2003-01-06T23:59:59.000Z

89

MIGRATION OF RADIONUCLIDES THROUGH SORBING MEDIA ANALYTICAL SOLUTION - I  

E-Print Network (OSTI)

centration Phenomenon of Radionuclide Chain Migra- tion", B5only MIGRA'riON OF RADIONUCLIDES THROUGH SORBING MEDIATransport Equation for Radionuclide in Porous Media General

Harada, M.

2013-01-01T23:59:59.000Z

90

MIGRATION OF RADIONUCLIDES THROUGH SORBING MEDIA ANALYTICAL SOLUTIONS--II  

E-Print Network (OSTI)

for the Transport of Radionuclides and Their Decay ProductsVolume II MIGRATION OF RADIONUCLIDES THROUGH iORBING MEDIAAl. M. Albert, "Radionuclide Migration with Multidimensional

Pigford, T.H.

2010-01-01T23:59:59.000Z

91

Radionuclide Retention in Concrete Wasteforms  

SciTech Connect

Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how wasteform performance is affected by the full range of environmental conditions within the disposal facility; the process of wasteform aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of wasteform aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the wasteforms come in contact with groundwater. Data collected throughout the course of this work will be used to quantify the efficacy of concrete wasteforms, similar to those used in the disposal of LLW and MLLW, for the immobilization of key radionuclides (i.e., uranium, technetium, and iodine). Data collected will also be used to quantify the physical and chemical properties of the concrete affecting radionuclide retention.

Wellman, Dawn M.; Jansik, Danielle P.; Golovich, Elizabeth C.; Cordova, Elsa A.

2012-09-24T23:59:59.000Z

92

Radionuclide detection devices and associated methods  

Science Conference Proceedings (OSTI)

Radionuclide detection devices comprise a fluid cell comprising a flow channel for a fluid stream. A radionuclide collector is positioned within the flow channel and configured to concentrate one or more radionuclides from the fluid stream onto at least a portion of the radionuclide collector. A scintillator for generating scintillation pulses responsive to an occurrence of a decay event is positioned proximate at least a portion of the radionuclide collector and adjacent to a detection system for detecting the scintillation pulses. Methods of selectively detecting a radionuclide are also provided.

Mann, Nicholas R. (Rigby, ID); Lister, Tedd E. (Idaho Falls, ID); Tranter, Troy J. (Idaho Falls, ID)

2011-03-08T23:59:59.000Z

93

Solid Radwaste Radionuclide Measurements  

Science Conference Proceedings (OSTI)

Methods employed at U.S. nuclear power plants to assay low level solid radwaste were reviewed to identify those aspects of the assay process that have substantial improvement potential and to develop recommendations on programs to develop more effective methods. Discussions were held on practices at 41 nuclear stations and in-depth reviews were performed at 14 sites. Recommendations for future efforts are provided, particularly with reference to demonstrating adherence to proposed regulations.

1982-11-01T23:59:59.000Z

94

National Emission Standards for Hazardous Air Pollutants—Calendar Year 2010 INL Report for Radionuclides (2011)  

SciTech Connect

This report documents the calendar Year 2010 radionuclide air emissions and resulting effective dose equivalent to the maximally exposed individual member of the public from operations at the Department of Energy's Idaho National Laboratory Site. This report was prepared in accordance with the Code of Federal Regulations, Title 40, 'Protection of the Environment,' Part 61, 'National Emission Standards for Hazardous Air Pollutants,' Subpart H, 'National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.'

Mark Verdoorn; Tom Haney

2011-06-01T23:59:59.000Z

95

Radionuclide air emissions report for the Hanford Site, calendar year 1992  

SciTech Connect

This report documents radionuclide air emissions from the Hanford Site in 1992 and the resulting effective dose equivalent to an member of the public. The report has been prepared and will be submitted in accordance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, ``National Emissions Standards for Hazardous Air Pollutants,`` Subpart H, ``National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.``

Diediker, L.P.; Johnson, A.R. [Westinghouse Hanford Co., Richland, WA (United States); Rhoads, K.; Klages, D.L.; Soldat, J.K. [Pacific Northwest Lab., Richland, WA (United States); Rokkan, D.J. [Science Applications International Corp., Richland, WA (United States)

1993-06-01T23:59:59.000Z

96

Radionuclide air emissions report for the Hanford site, Calendar year 1994  

Science Conference Proceedings (OSTI)

This report documents radionuclide air emissions from the Hanford Site in 1994, and the resulting effective dose equivalent to the maximally exposed member of the public, referred to as the ``MEI.`` The report has been prepared and will be submitted in accordance with reporting requirements in the Code of Federal Regulations, title 40, Protection of the Environment, Part 61, ``National Emissions Standards for Hazardous Air Pollutants,`` Subpart H, ``National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.``

Gleckler, B.P.; Diediker, L.P. [Westinghouse Hanford Co., Richland, WA (United States); Jette, S.J.; Rhoads, K.; Soldat, S.K. [Pacific Northwest Lab., Richland, WA (United States)

1995-06-01T23:59:59.000Z

97

Radionuclide labeled lymphocytes for therapeutic use  

DOE Patents (OSTI)

Lymphocytes labelled with ..beta..-emitting radionuclides are therapeutically useful, particularly for lymphoid ablation. They are prepared by incubation of the lymphocytes with the selected radionuclide-oxine complex.

Srivastava, S.C.; Fawwaz, R.A.; Richards, P.

1983-05-03T23:59:59.000Z

98

Radionuclide labeled lymphocytes for therapeutic use  

DOE Patents (OSTI)

Lymphocytes labelled with .beta.-emitting radionuclides are therapeutically useful, particularly for lymphoid ablation. They are prepared by incubation of the lymphocytes with the selected radionuclide-oxine complex.

Srivastava, Suresh C. (Setauket, NY); Fawwaz, Rashid A. (Pelham, NY); Richards, Powell (Bayport, NY)

1985-01-01T23:59:59.000Z

99

Water Permits (Louisiana)  

Energy.gov (U.S. Department of Energy (DOE))

The Water Permits Division authorizes permits administered under the Water Quality Regulations. Louisiana's Water Quality Regulations require permits for the discharge of pollutants from any point...

100

NIST Radionuclide Half-Life Measurements (HTML)  

Science Conference Proceedings (OSTI)

... Radionuclide, Number of Sources, Number of Half Lives Followed, Half Life *, Statistical Standard Uncertainty, Other Standard Uncertainty, References ...

2010-10-05T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Rules and Regulations Pertaining to a User Fee System for Point Source Dischargers that Discharge Pollutants into the Waters of the State (Rhode Island)  

Energy.gov (U.S. Department of Energy (DOE))

These regulations establish a user fee system for point source dischargers that discharge pollutants into the surface waters of the State. The funds from such fees are used by the Department of...

102

GUIDANCE ON IMPLEMENTING RADIONUCLIDE NESHAPS  

E-Print Network (OSTI)

- Radionuclide Emissions Other than Radon from DOE Facilities . . . . . . . . . . . . . . . . 13 2.2.2 Subpart I - NRC Licensed and Non-DOE Federal Facilities . . . . . . . . . . . . . . . . . . 14 2.3 NESHAPS Subpart I . . . . 44 3.2 Other NRC Licensees - 40 CFR 61 Subpart I . . . . . . 44 3.3 DOE Facilities

103

Effects of evaporative cooling on the regulation of body water and ...  

Science Conference Proceedings (OSTI)

building, causing air to be drawn through the cooling pads. The study was conducted during two ...... of gut water in living ruminants. Aust J Agric Res 15:

104

Hydrogeological influences on radionuclide migration from the major radioactive waste burial sites at Chernobyl (A review)  

Science Conference Proceedings (OSTI)

This paper summarizes the recent hydrogeological investigations of several research organizations on waste confinement at the major radioactive waste (RW) burial sites immediately adjacent to the Chernobyl Nuclear Power Plant (Ch. NPP). Hydrogeological conditions and radiologic ground-water contamination levels are described. Ongoing ground-water monitoring practices are evaluated. The chemical and physical characteristics of the radionuclides within the burial sites are considered. Ground water and radionuclide transport modeling studies related to problems of the RW disposal sites are also reviewed. Current concerns on future impacts of the RW burial sites on the hydrological environment and water resources of the Ch.NPP area are discussed.

Dgepo, S.P.; Skalsky, A.S.; Bugai, D.A.; Marchuk, V.V. [Inst. of Geological Sciences, Kiev (Ukraine); Waters, R.D. [Sandia National Labs., Albuquerque, NM (United States)

1994-03-01T23:59:59.000Z

105

EVALUATION OF RADIONUCLIDE ACCUMULATION IN SOIL DUE TO LONG-TERM IRRIGATION  

Science Conference Proceedings (OSTI)

Radionuclide accumulation in soil due to long-term irrigation is an important part of the model for predicting radiation dose in a long period of time. The model usually assumes an equilibrium condition in soil with a constant irrigation rate, so that radionuclide concentration in soil does not change with time and can be analytically solved. This method is currently being used for the dose assessment in the Yucca Mountain project, which requires evaluating radiation dose for a period of 10,000 years. There are several issues associated with the method: (1) time required for the equilibrium condition, (2) validity of constant irrigation rate, (3) agricultural land use for a long period of time, and (4) variation of a radionuclide concentration in water. These issues are evaluated using a numerical method with a simple model built in the GoldSim software. Some key radionuclides, Tc-99, Np-237, Pu-239, and Am-241 are selected as representative radionuclides. The results indicate that the equilibrium model is acceptable except for a radionuclide that requires long time to accumulate in soil and that its concentration in water changes dramatically with time (i.e. a sharp peak). Then the calculated dose for that radionuclide could be overestimated using the current equilibrium method.

De Wesley Wu

2006-04-16T23:59:59.000Z

106

Characterization of radionuclide-chelating agent complexes found in low-level radioactive decontamination waste. Literature review  

SciTech Connect

The US Nuclear Regulatory Commission is responsible for regulating the safe land disposal of low-level radioactive wastes that may contain organic chelating agents. Such agents include ethylenediaminetetraacetic acid (EDTA), diethylenetriaminepentaacetic acid (DTPA), picolinic acid, oxalic acid, and citric acid, and can form radionuclide-chelate complexes that may enhance the migration of radionuclides from disposal sites. Data from the available literature indicate that chelates can leach from solidified decontamination wastes in moderate concentration (1--100 ppm) and can potentially complex certain radionuclides in the leachates. In general it appears that both EDTA and DTPA have the potential to mobilize radionuclides from waste disposal sites because such chelates can leach in moderate concentration, form strong radionuclide-chelate complexes, and can be recalcitrant to biodegradation. It also appears that oxalic acid and citric acid will not greatly enhance the mobility of radionuclides from waste disposal sites because these chelates do not appear to leach in high concentration, tend to form relatively weak radionuclide-chelate complexes, and can be readily biodegraded. In the case of picolinic acid, insufficient data are available on adsorption, complexation of key radionuclides (such as the actinides), and biodegradation to make definitive predictions, although the available data indicate that picolinic acid can chelate certain radionuclides in the leachates.

Serne, R.J.; Felmy, A.R.; Cantrell, K.J.; Krupka, K.M.; Campbell, J.A.; Bolton, H. Jr.; Fredrickson, J.K. [Pacific Northwest National Lab., Richland, WA (United States)

1996-03-01T23:59:59.000Z

107

Natural chelates for radionuclide decorporation  

DOE Patents (OSTI)

This invention relates to the method and resulting chelates of desorbing a radionuclide selected from thorium, uranium, and plutonium containing cultures in a bioavailable form involving pseudomonas or other microorganisms. A preferred microorganism is Pseudomonas aeruginosa which forms multiple chelates with thorium in the range of molecular weight 1000 to 1000 and also forms chelates with uranium of molecular weight in the area of 100 to 1000 and 1000 to 2000.

Premuzic, E.T.

1983-08-25T23:59:59.000Z

108

Water  

NLE Websites -- All DOE Office Websites (Extended Search)

Laws Envirosearch Institutional Controls NEPA Activities RCRA RQ*Calculator Water HSS Logo Water Laws Overview of water-related legislation affecting DOE sites Clean...

109

Radionuclide behavior in the environment  

Science Conference Proceedings (OSTI)

The purpose of this report is to document the results of the following task: Review for quality and consistency the available data on measurements of initial ground contamination of Chernobyl radionuclides in various parts of Norway and subsequent concentrations of these radionuclides in various environmental media as functions of time. Utilize the data obtained to verify the existing models, or to improve them, for describing radionuclide behavior in the environment. Some of the processes standard were: migration into soil; weathering; resuspension; food-chain contamination; and loss or reconcentration by run-off. The task performed within this contract has been to use post-Chernobyl data from Norway to verify or find areas for possible improvement in the chronic exposure pathway models utilized in MACCS. Work has consisted mainly of collecting and evaluating post-Chernobyl information from Norway or other countries when relevant; but has also included experimental work performed specifically for the current task. In most connections the data available show the models and data in MACCS to be appropriate. A few areas where the data indicate that the MACCS approach is faulty or inadequate are, however, pointed out in the report. These should be examined carefully, and appropriate modifications should eventually be made. 14 refs., 12 figs., 22 tabs.

Tveten, U. (Institutt for Energiteknikk, Kjeller (Norway))

1991-09-01T23:59:59.000Z

110

Bioremediation of metals and radionuclides: What it is and How it Works  

E-Print Network (OSTI)

Restoration Objectives. The Focus on Radionuclides andAFFECTING METALS AND RADIONUCLIDES THE BIOREMEDIATION OFOF METALS RADIONUCLIDES Scope of Problem . . . . . . . . .

McCullough, J.; Hazen, Terry; Benson, Sally

1999-01-01T23:59:59.000Z

111

Washing of Cloth Contaminated with Radionuclides Using A Detergent-Free Laundry System  

SciTech Connect

In this study, we describe a new laundry system to wash clothes, including those contaminated with radionuclides, without using detergent. The main part of this system is electrolytic cell that consists of a cathode with a special coating of nickel, an anode of nickel, and a cation exchange membrane between the two electrodes. The electrolyte is supplied to the anode and the tap-water to the cathode. When an electricity of 5 volts and 25 amperes is applied to the electrodes, the processed water is produced from the cathode. This processed water containing no detergent was investigated experimentally with regard to its decontamination efficiency of radionuclides and detergency of soil as compared to the conventional washing using detergent. It was found that the processed water from this system has an ability to simultaneously remove radionuclides and soil from the cloth with good efficiency.

Yim, S. P.; Ahn, B. G.; Lee, H. J.; Shon, J. S.; Chung, H.; Kim, K. J.; Kim, H. J.; Park, J. H.; Lee, W. S.

2003-02-25T23:59:59.000Z

112

Methods of separating short half-life radionuclides from a mixture of radionuclides  

DOE Patents (OSTI)

The present invention is a method of obtaining a radionuclide product selected from the group consisting of {sup 223}Ra and {sup 225}Ac, from a radionuclide ``cow`` of {sup 227}Ac or {sup 229}Th respectively. The method comprises the steps of (a) permitting ingrowth of at least one radionuclide daughter from said radionuclide ``cow`` forming an ingrown mixture; (b) insuring that the ingrown mixture is a nitric acid ingrown mixture; (c) passing the nitric acid ingrown mixture through a first nitrate form ion exchange column which permits separating the ``cow`` from at least one radionuclide daughter; (d) insuring that the at least one radionuclide daughter contains the radionuclide product; (e) passing the at least one radionuclide daughter through a second ion exchange column and separating the at least one radionuclide daughter from the radionuclide product and (f) recycling the at least one radionuclide daughter by adding it to the ``cow``. In one embodiment the radionuclide ``cow`` is the {sup 227}Ac, the at least one daughter radionuclide is a {sup 227}Th and the product radionuclide is the {sup 223}Ra and the first nitrate form ion exchange column passes the {sup 227}Ac and retains the {sup 227}Th. In another embodiment the radionuclide ``cow`` is the {sup 229}Th, the at least one daughter radionuclide is a {sup 225}Ra and said product radionuclide is the {sup 225}Ac and the {sup 225}Ac and nitrate form ion exchange column retains the {sup 229}Th and passes the {sup 225}Ra/Ac. 8 figs.

Bray, L.A.; Ryan, J.L.

1998-09-15T23:59:59.000Z

113

Methods of separating short half-life radionuclides from a mixture of radionuclides  

DOE Patents (OSTI)

The present invention is a method of obtaining a radionuclide product selected from the group consisting of .sup.223 Ra and .sup.225 Ac, from a radionuclide "cow" of .sup.227 Ac or .sup.229 Th respectively. The method comprises the steps of a) permitting ingrowth of at least one radionuclide daughter from said radionuclide "cow" forming an ingrown mixture; b) insuring that the ingrown mixture is a nitric acid ingrown mixture; c) passing the nitric acid ingrown mixture through a first nitrate form ion exchange column which permits separating the "cow" from at least one radionuclide daughter; d) insuring that the at least one radionuclide daughter contains the radionuclide product; e) passing the at least one radionuclide daughter through a second ion exchange column and separating the at least one radionuclide daughter from the radionuclide product and f) recycling the at least one radionuclide daughter by adding it to the "cow". In one embodiment the radionuclide "cow" is the .sup.227 Ac, the at least one daughter radionuclide is a .sup.227 Th and the product radionuclide is the .sup.223 Ra and the first nitrate form ion exchange column passes the .sup.227 Ac and retains the .sup.227 Th. In another embodiment the radionuclide "cow"is the .sup.229 Th, the at least one daughter radionuclide is a .sup.225 Ra and said product radionuclide is the .sup.225 Ac and the .sup.225 Ac and nitrate form ion exchange column retains the .sup.229 Th and passes the .sup.225 Ra/Ac.

Bray, Lane A. (Richland, WA); Ryan, Jack L. (West Richland, WA)

1998-01-01T23:59:59.000Z

114

Measurement of radionuclides in waste packages  

DOE Patents (OSTI)

A method is described for non-destructively assaying the radionuclide content of solid waste in a sealed container by analysis of the waste's gamma-ray spectrum and neutron emissions. Some radionuclides are measured by characteristic photopeaks in the gamma-ray spectrum; transuranic nuclides are measured by neutron emission rate; other radionuclides are measured by correlation with those already measured.

Brodzinski, R.L.; Perkins, R.W.; Rieck, H.G.; Wogman, N.A.

1984-09-12T23:59:59.000Z

115

Colloid labelled with radionuclide and method  

DOE Patents (OSTI)

This report discusses a ferric hydroxide colloid having an alpha- emitting radionuclide essentially on the outer surfaces and a method of forming same. The method includes oxidizing a ferrous hydroxide to ferric hydroxide in the presence of a preselected radionuclide to form a colloid having the radionuclide on the outer surface thereof, and thereafter washing the colloid, and suspending the washed colloid in a suitable solution. The labeled colloid is useful in cancer therapy and for the treatment of inflamed joints. 3 tabs.

Atcher, R.W.; Hines, J.J.

1989-05-30T23:59:59.000Z

116

Method of making colloid labeled with radionuclide  

DOE Patents (OSTI)

A ferric hydroxide colloid having an alpha-emitting radionuclide essentially on the outer surfaces and a method of forming same. The method includes oxidizing a ferrous hydroxide to ferric hydroxide in the presence of a preselected radionuclide to form a colloid having the radionuclide on the outer surface thereof, and thereafter washing the colloid, and suspending the washed colloid in a suitable solution. The labelled colloid is useful in cancer therapy and for the treatment of inflamed joints.

Atcher, Robert W. (Chicago, IL); Hines, John J. (Glen Ellyn, IL)

1991-01-01T23:59:59.000Z

117

Colloid labelled with radionuclide and method  

DOE Patents (OSTI)

A ferric hydroxide colloid having an alpha-emitting radionuclide essentially on the outer surfaces and a method of forming same. The method includes oxidizing a ferrous hydroxide to ferric hydroxide in the presence of a preselected radionuclide to form a colloid having the radionuclide on the outer surface thereof, and thereafter washing the colloid, and suspending the washed colloid in a suitable solution. The labelled colloid is useful in cancer therapy and for the treatment of inflamed joints.

Atcher, Robert W. (Chicago, IL); Hines, John J. (GlenEllyn, IL)

1990-01-01T23:59:59.000Z

118

Measurement of radionuclides in waste packages  

DOE Patents (OSTI)

A method is described for non-destructively assaying the radionuclide content of solid waste in a sealed container by analysis of the waste's gamma-ray spectrum and neutron emissions. Some radionuclides are measured by characteristic photopeaks in the gamma-ray spectrum; transuranic nuclides are measured by neutron emission rate; other radionuclides are measured by correlation with those already measured.

Brodzinski, Ronald L. (Richland, WA); Perkins, Richard W. (Richland, WA); Rieck, Henry G. (Richland, WA); Wogman, Ned A. (Richland, WA)

1986-01-01T23:59:59.000Z

119

Colloid labelled with radionuclide and method  

DOE Patents (OSTI)

A ferric hydroxide colloid having an alpha-emitting radionuclide essentially on the outer surfaces and a method of forming same. The method includes oxidizing a ferrous hydroxide to ferric hydroxide in the presence of a preselected radionuclide to form a colloid having the radionuclide on the outer surface thereof, and thereafter washing the colloid, and suspending the washed colloid in a suitable solution. The labelled colloid is useful in cancer therapy and for the treatment of inflamed joints. No Drawings

Atcher, R.W.; Hines, J.J.

1990-11-13T23:59:59.000Z

120

NIST Radionuclide Half-Life Measurements  

Science Conference Proceedings (OSTI)

... The half lives of many radionuclides have been measured in the Radioactivity Group of NIST. The table below, based on "New and revised half-life ...

2011-12-09T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Ion binding compounds, radionuclide complexes, methods of making radionuclide complexes, methods of extracting radionuclides, and methods of delivering radionuclides to target locations  

DOE Patents (OSTI)

The invention pertains to compounds for binding lanthanide ions and actinide ions. The invention further pertains to compounds for binding radionuclides, and to methods of making radionuclide complexes. Also, the invention pertains to methods of extracting radionuclides. Additionally, the invention pertains to methods of delivering radionuclides to target locations. In one aspect, the invention includes a compound comprising: a) a calix[n]arene group, wherein n is an integer greater than 3, the calix[n]arene group comprising an upper rim and a lower rim; b) at least one ionizable group attached to the lower rim; and c) an ion selected from the group consisting of lanthanide and actinide elements bound to the ionizable group. In another aspect, the invention includes a method of extracting a radionuclide, comprising: a) providing a sample comprising a radionuclide; b) providing a calix[n]arene compound in contact with the sample, wherein n is an integer greater than 3; and c) extracting radionuclide from the sample into the calix[n]arene compound. In yet another aspect, the invention includes a method of delivering a radionuclide to a target location, comprising: a) providing a calix[n]arene compound, wherein n is an integer greater than 3, the calix[n]arene compound comprising at least one ionizable group; b) providing a radionuclide bound to the calix[n]arene compound; and c) providing an antibody attached to the calix[n]arene compound, the antibody being specific for a material found at the target location.

Chen, Xiaoyuan (Syracuse, NY); Wai, Chien M. (Moscow, ID); Fisher, Darrell R. (Richland, WA)

2000-01-01T23:59:59.000Z

122

Position Paper on Practicable Performance Criteria for the Removal Efficiency of Volatile Radionuclides  

SciTech Connect

As a result of fuel reprocessing, volatile radionuclides may be released from the facility stack if no processes are put in place to remove them. The radionuclides that are of concern in this document are 3H, 14C, 85Kr, and 129I. The question we attempted to answer is how efficient must this removal process be for each of these radionuclides? To answer this question, we examined the three regulations that may impact the degree to which these radionuclides must be reduced before process gases can be released from the facility. These regulations are 40 CFR 61 (EPA 2010a), 40 CFR 190(EPA 2010b), and 10 CFR 20 (NRC 2012). These regulations apply to the total radionuclide release and to a particular organ - the thyroid. Because these doses can be divided amongst all the radionuclides in different ways and even within the four radionuclides in question, we provided several cases. We first looked at the inventories for these radionuclides for three fuel types (PWR UOX, PWR MOX, and AHTGR), several burn-up values, and time out of reactor extending to 200 y. We calculated doses to the maximum exposed individual (MEI) with the EPA code CAP-88 (Rosnick 1992). Finally, we looked at two dose cases. Allocating all of the allowable dose to be used by the volatile radionuclides is one case, but, perhaps, unrealistic. In lieu of this, we arbitrarily selected a value of 10% of the allowable dose to be assigned to the volatile radionuclides. We calculated the required decontamination factors (DFs) for both of these cases, including the case for the thyroid dose for which 14C and 129I were the main contributors. With respect to 129I doses, we found that the highest dose was calculated with iodine as a fine particulate. The dose scaled as the fraction of the total 129I that was particulate. Therefore, we assumed for all of our calculations that 100% of the 129I was particulate and allow the user of the results given here to scale our calculated doses to their needs.

R. T. Jubin; N. Soelberg; D. M. Strachan

2012-03-01T23:59:59.000Z

123

Comparison of Different Internal Dosimetry Systems for Selected Radionuclides Important to Nuclear Power Production  

Science Conference Proceedings (OSTI)

This report compares three different radiation dosimetry systems currently applied by various U.S. Federal agencies and dose estimates based on these three dosimetry systems for a set of radionuclides often identified in power reactor effluents. These dosimetry systems were developed and applied by the International Commission on Radiological Protection at different times over the past six decades. Two primary modes of intake of radionuclides are addressed: ingestion in drinking water and inhalation. Estimated doses to individual organs and to the whole body based on each dosimetry system are compared for each of four age groups: infant, child, teenager, and adult. Substantial differences between dosimetry systems in estimated dose per unit intake are found for some individual radionuclides, but differences in estimated dose per unit intake generally are modest for mixtures of radionuclides typically found in nuclear power plant effluents.

Leggett, Richard Wayne [ORNL; Eckerman, Keith F [ORNL; Manger, Ryan P [ORNL

2013-08-01T23:59:59.000Z

124

Situ formation of apatite for sequestering radionuclides and heavy metals  

DOE Patents (OSTI)

Methods for in situ formation in soil of a permeable reactive barrier or zone comprising a phosphate precipitate, such as apatite or hydroxyapatite, which is capable of selectively trapping and removing radionuclides and heavy metal contaminants from the soil, while allowing water or other compounds to pass through. A preparation of a phosphate reagent and a chelated calcium reagent is mixed aboveground and injected into the soil. Subsequently, the chelated calcium reagent biodegrades and slowly releases free calcium. The free calcium reacts with the phosphate reagent to form a phosphate precipitate. Under the proper chemical conditions, apatite or hydroxyapatite can form. Radionuclide and heavy metal contaminants, including lead, strontium, lanthanides, and uranium are then selectively sequestered by sorbing them onto the phosphate precipitate. A reducing agent can be added for reduction and selective sequestration of technetium or selenium contaminants.

Moore, Robert C. (Edgewood, NM)

2003-07-15T23:59:59.000Z

125

Division of Water, Part 675: Great Lakes Water Withdrawal Registration...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

75: Great Lakes Water Withdrawal Registration Regulations (New York) Division of Water, Part 675: Great Lakes Water Withdrawal Registration Regulations (New York) Eligibility...

126

CRITICAL RADIONUCLIDE AND PATHWAY ANALYSIS FOR THE SAVANNAH RIVER SITE  

SciTech Connect

This report is an update to the analysis, Assessment of SRS Radiological Liquid and Airborne Contaminants and Pathways, that was performed in 1997. An electronic version of this large original report is included in the attached CD to this report. During the operational history (1954 to the present) of the Savannah River Site (SRS), many different radionuclides have been released to the environment from the various production facilities. However, as will be shown by this updated radiological critical contaminant/critical pathway analysis, only a small number of the released radionuclides have been significant contributors to potential doses and risks to offsite people. The analysis covers radiological releases to the atmosphere and to surface waters, the principal media that carry contaminants offsite. These releases potentially result in exposure to offsite people. The groundwater monitoring performed at the site shows that an estimated 5 to 10% of SRS has been contaminated by radionuclides, no evidence exists from the extensive monitoring performed that groundwater contaminated with these constituents has migrated off the site (SRS 2011). Therefore, with the notable exception of radiological source terms originating from shallow surface water migration into site streams, onsite groundwater was not considered as a potential exposure pathway to offsite people. In addition, in response to the Department of Energy's (DOE) Order 435.1, several Performance Assessments (WSRC 2008; LWO 2009; SRR 2010; SRR 2011) and a Comprehensive SRS Composite Analysis (SRNO 2010) have recently been completed at SRS. The critical radionuclides and pathways identified in these extensive reports are discussed and, where applicable, included in this analysis.

Jannik, T.

2011-08-30T23:59:59.000Z

127

Colloid-facilitated radionuclide transport in fractured porous rock  

E-Print Network (OSTI)

Numerical methods have been applied for the prediction of colloid-facilitated radionuclide transport through water-saturated fractured porous rock. The presence of colloids may enhance the transport of radionuclides in groundwater by reducing retardation effects. The colloids existing in the groundwater act as carriers, adsorbing radionuclides on their large surface area and moving faster than the average water velocity. With colloids present, the system consists of three phases, i. e., an aqueous phase, a carrier phase, and a stationary solid phase. In the basic model, one-dimensional advection in a single planar fracture of infinite extent is coupled with diffusion in the rock matrix perpendicular to the fracture. In this study, a full-equilibrium model was developed to describe the transport and fate of the radionuclides in the fracture. Sorption onto rock matrix, fracture surface and sorption into mobile and immobile colloids are included. The effect of colloidal particle size was also considered. Mass partition mechanisms between the colloids and solid matrix and between colloid and contaminant are represented by local equilibrium. In the three-phase i.e., retardation coefficient, hydrodynamic dispersion system, the coefficient, and fracture width are modified to include the equilibrium distribution coefficient of contaminant with a carrier. In the three phase model, much smaller retardation and hydrodynamic dispersion coefficients are obtained and the effect of fracture width is larger. With the additional consideration of colloidal particle sizes, these effects become ever larger. Numerical solutions for the model were obtained using a fully implicit finite difference scheme. A significant sensitivity to model parameters was discovered, and in particular, the equilibrium distribution coefficients between a contaminant and the carrier were found to be the most important factors.

Baek, Inseok

1994-01-01T23:59:59.000Z

128

Environmental regulation of carbon isotope composition and crassulacean acid metabolism in three plant communities along a water availability gradient  

E-Print Network (OSTI)

communities along a water availability gradient M. Fernandawith decreasing water availability. Overall, variation inrelated to water and light availability and CAM appeared to

2010-01-01T23:59:59.000Z

129

Radionuclide Migation Project 1984 progress report  

SciTech Connect

The report discusses the hydrogeologic settings and histories of studies associated with the Cheshire (U20n), Cambric (U5e), Nash (UE2ce), Bilby (U3cn), Bourbon (U7n), and Faultless (UC1) Events. Radionuclide and some chemical data are presented for water samples from cavity or chimney wells associated with the Cheshire, Cambric, and Bilby Events, and from satellite wells at the Cambric, Nash, Bibly, Bourbon, and Faultless Event sites. The report also gives the results of studies of specific sampling or analytical methodologies. These studies demonstrated that the apparent migration of /sup 155/Eu is an artfact of spectrometric misidentification of gamma- and x-ray peaks from other constituents. A potential problem with atmospheric contamination of samples collected with evacuated thief samples was also identified. Ultrafiltration techniques were applied to some of the Cheshire cavity samples collected, and preliminary results suggest that substantial amounts of activity may be associated with colloidal particles in the size range of 0.006 to 0.45 ..mu..m. A study has begun of the recharge of effluent water from RNM-2S (Cambric satellite well) into the desert floor as a result of nine years of continuous pumping. This report gives the initial results of unsaturated zone studies showing the propagation of moisture and tritium fronts through the shallow soil. Geochemical modeling of the behavior of ruthenium and technetium was carried out, with particular emphasis on the identification of ionic species that would be potentially mobile under NTS ground-water conditions. The report compares the results with observations of ruthenium migration to the Cambric satellite well.

Buddemeier, R.W.; Isherwood, D. (comps.)

1985-04-01T23:59:59.000Z

130

Transverse section radionuclide scanning system  

DOE Patents (OSTI)

This invention provides a transverse section radionuclide scanning system for high-sensitivity quantification of brain radioactivity in cross-section picture format in order to permit accurate assessment of regional brain function localized in three-dimensions. High sensitivity crucially depends on overcoming the heretofore known raster type scanning, which requires back and forth detector movement involving dead-time or partial enclosure of the scan field. Accordingly, this invention provides a detector array having no back and forth movement by interlaced detectors that enclose the scan field and rotate as an integral unit around one axis of rotation in a slip ring that continuously transmits the detector data by means of laser emitting diodes, with the advantages that increased amounts of data can be continuously collected, processed and displayed with increased sensitivity according to a suitable computer program.

Kuhl, David E. (Rosemont, PA); Edwards, Roy Q. (Plymouth Township, PA)

1976-01-01T23:59:59.000Z

131

Developments in Bioremediation of Soils and Sediments Polluted with Metals and Radionuclides: 2. Field Research on Bioremediation of Metals and Radionuclides  

E-Print Network (OSTI)

of metals and radionuclides shows great promise but it willand Sediments Polluted with Metals and Radionuclides 2.Bioremediation of Metals and Radionuclides Terry C. Hazen 1

Hazen, Terry C.

2010-01-01T23:59:59.000Z

132

U.S. Department of Energy Report, 2005 LANL Radionuclide Air Emissions  

SciTech Connect

Amendments to the Clean Air Act, which added radionuclides to the National Emissions Standards for Hazardous Air Pollutants (NESHAP), went into effect in 1990. Specifically, a subpart (H) of 40 CFR 61 established an annual limit on the impact to the public attributable to emissions of radionuclides from U.S. Department of Energy facilities, such as the Los Alamos National Laboratory (LANL). As part of the new NESHAP regulations, LANL must submit an annual report to the U.S. Environmental Protection Agency headquarters and the regional office in Dallas by June 30. This report includes results of monitoring at LANL and the dose calculations for the calendar year 2006.

Keith W. Jacobson, David P. Fuehne

2006-09-01T23:59:59.000Z

133

National Emission Standards for Hazardous Air Pollutants—Calendar Year 2011 INL Report for Radionuclides (2012)  

SciTech Connect

This report documents the calendar year 2011 radionuclide air emissions and resulting effective dose equivalent to the maximally exposed individual member of the public from operations at the Department of Energy's Idaho National Laboratory Site. This report was prepared in accordance with the Code of Federal Regulations, Title 40, 'Protection of the Environment,' Part 61, 'National Emission Standards for Hazardous Air Pollutants,' Subpart H, 'National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.' The effective dose equivalent to the maximally exposed individual member of the public was 4.58E-02 mrem per year, 0.46 percent of the 10 mrem standard.

Mark Verdoorn; Tom Haney

2012-06-01T23:59:59.000Z

134

Radionuclide air emission report for the Hanford Site Calendar Year 1993  

SciTech Connect

This report documents radionuclide air emissions from the Hanford Site in 1993 and the resulting effective dose equivalent to any member of the public. The report has been prepared and will be submitted in accordance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, {open_quotes}National Emissions Standards for Hazardous Air Pollutants,{close_quotes} Subpart H, {open_quotes}National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.{close_quotes}

Diediker, L.P.; Curn, B.L. [Westinghouse Hanford Co., Richland, WA (United States); Rhoads, K.; Damberg, E.G.; Soldat, J.K.; Jette, S.J. [Pacific Northwest Lab., Richland, WA (United States)

1994-08-01T23:59:59.000Z

135

Unclassified Source Term and Radionuclide Data for Corrective Action Unit 98: Frenchman Flat Nevada Test Site, Nevada, Rev. No.: 0  

Science Conference Proceedings (OSTI)

Frenchman Flat is one of several areas of the Nevada Test Site (NTS) used for underground nuclear testing (Figure 1-1). These nuclear tests resulted in groundwater contamination in the vicinity of the underground test areas. As a result, the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is currently conducting a corrective action investigation (CAI) of the Frenchman Flat underground test areas. Since 1996, the Nevada Division of Environmental Protection (NDEP) has regulated NNSA/NSO corrective actions through the ''Federal Facility Agreement and Consent Order'' ([FFACO], 1996). Appendix VI of the FFACO agreement, ''Corrective Action Strategy'', was revised on December 7, 2000, and describes the processes that will be used to complete corrective actions, including those in the Underground Test Area (UGTA) Project. The individual locations covered by the agreement are known as corrective action sites (CASs), which are grouped into corrective action units (CAUs). The UGTA CASs are grouped geographically into five CAUs: Frenchman Flat, Central Pahute Mesa, Western Pahute Mesa, Yucca Flat/Climax Mine, and Rainier Mesa/Shoshone Mountain (Figure 1-1). These CAUs have distinctly different contaminant source, geologic, and hydrogeologic characteristics related to their location (FFACO, 1996). The Frenchman Flat CAU consists of 10 CASs located in the northern part of Area 5 and the southern part of Area 11 (Figure 1-1). This report documents the evaluation of the information and data available on the unclassified source term and radionuclide contamination for Frenchman Flat, CAU 98. The methodology used to estimate hydrologic source terms (HSTs) for the Frenchman Flat CAU is also documented. The HST of an underground nuclear test is the portion of the total inventory of radionuclides that is released over time into the groundwater following the test. The total residual inventory of radionuclides associated with one or more tests is known as the radiologic source term (RST). The RST is comprised of radionuclides in water, glass, or other phases or mineralogic forms. This evaluation was conducted in support of the development of a CAU contaminant transport model for the Frenchman Flat CAU.

Farnham, Irene

2005-09-01T23:59:59.000Z

136

Marine plankton as an indicator of low-level radionuclide contamination in the Southern Ocean  

SciTech Connect

We have initiated an investigation of the utility of marine plankton as bioconcentrating samplers of low-level marine radioactivity in the southern hemisphere. A literature review shows that both freshwater and marine plankton have trace element and radionuclide concentration factors (relative to water) of up to 10/sup 4/. In the years 1956-1958, considerable work was done on the accumulation and distribution of a variety of fission and activation products produced by the nuclear tests in the Marshall Islands. Since then, studies have largely been confined to a few selected radionuclides, and by far most of this work has been done in the northern hemisphere. We participated in Operation Deepfreeze 1981, collecting 32 plankton samples from the U.S. Coast Guard Cutter Glacier on its Antarctic cruise, while Battelle Pacific Northwest Laboratories concurrently sampled air, water, rain and fallout. We were able to measure concentrations of the naturally occurring radionuclides /sup 7/Be, /sup 40/K and the U and th series, and we believe that we have detected low levels of /sup 144/Ce and /sup 95/Nb in seven samples ranging as far south as 68/sup 0/. There is a definite association between the radionuclide content of plankton and air filters, suggesting that aerosol resuspension of marine radioactivity may be occurring. Biological identification of the plankton suggests a possible correlation between radionuclide concentration and foraminifera content of the samples. 38 references, 7 figures, 3 tables.

Marsh, K.V.; Buddemeier, R.W.

1984-07-01T23:59:59.000Z

137

LBL-34868 UC-800 EOS7R: Radionuclide Transport for TOUGH2  

E-Print Network (OSTI)

EOS7R provides radionuclide transport capability for TOUGH2. EOS7R extends the EOS7 module (water, brine, and optional air) to model water, brine, parent component, daughter component, and optional air and heat. The radionuclide components follow a first-order decay law, and may adsorb onto the solid grains. Volatilization of the decaying components is modeled by Henry's Law. The decaying components are normally referred to as radionuclides, but they may in fact be any trace components that decay, adsorb, and volatilize. The decay process need not be radioactive decay, but could be any process that follows a first-order decay law, such as biodegradation. EOS7R includes molecular diffusion for all components in gaseous and aqueous phases using a simplified binary diffusion model. When EOS7R is used with standard TOUGH2, transport occurs by advection and molecular diffusion in all phases. When EOS7R is coupled with the dispersion module T2DM, one obtains T2DMR, the radionuclide transport version of T2DM. T2DMR models advection, diffusion, and hydrodynamic dispersion in rectangular two-dimensional regions. Modeling of radionuclide transport requires input parameters specifying the half-life for first-order decay, distribution coefficients for each rock

Curtis M. Oldenburg; Karsten Pruess

1995-01-01T23:59:59.000Z

138

The role of organic complexants and microparticulates in the facilitated transport of radionuclides  

SciTech Connect

This progress report describes the results of ongoing radiological and geochemical investigations of the mechanisms of radionuclide transport in groundwater at two low-level waste (LLW) disposal sites within the waste management area of the Chalk River Laboratories (CRL), Ontario, Canada. These sites, the Chemical Pit liquid disposal facility and the Waste Management Area C solid LLW disposal site, have provided valuable 30- to 40-year-old field locations for characterizing the migration of radionuclides and evaluating a number of recent site performance objectives for LLW disposal facilities. This information will aid the NRC and other federal, state, and local regulators, as well as LLW disposal site developers and waste generators, in maximizing the effectiveness of existing or projected LLW disposal facilities for isolating radionuclides from the general public and thereby improving the health and safety aspects of LLW disposal.

Schilk, A.J.; Robertson, D.E.; Abel, K.H.; Thomas, C.W. [and others

1996-12-01T23:59:59.000Z

139

Assessment of atmospherically-released radionuclides using the computerized radiological risk investigation system  

SciTech Connect

For radionuclides, the standards are in terms of an annual dose, and the regulations require assurance that no member of the general public receives a dose in excess of that standard. Thus, spatial variations in the population around an emission source must be considered. Furthermore, for most chemical pollutants the standards are written in terms of an air concentration while for radionuclides other pathways of exposure, e.g., uptake of the airborne emissions by terrestrial food chains must also be considered. The remainder of this paper discusses the computer codes that make up the CRRIS and how they are used to perform an assessment of the health impacts on man of radionuclides released to the atmosphere.

Nelson, C.B.; Sjoreen, A.L.; Miller, C.W.; Baes, C.F. III

1986-01-01T23:59:59.000Z

140

Pacific Northwest National Laboratory Facility Radionuclide Emission Points and Sampling Systems  

Science Conference Proceedings (OSTI)

Battelle—Pacific Northwest Division operates numerous research and development laboratories in Richland, Washington, including those associated with the Pacific Northwest National Laboratory (PNNL) on the Department of Energy’s Hanford Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all effluent release points that have the potential for radionuclide emissions. Potential emissions are assessed annually. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission point system performance, operation, and design information. A description of the buildings, exhaust points, control technologies, and sample extraction details is provided for each registered or deregistered facility emission point. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided.

Barfuss, Brad C.; Barnett, J. M.; Ballinger, Marcel Y.

2009-04-08T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Waste/Rock Interactions Technology Program: the status of radionuclide sorption-desorption studies performed by the WRIT program  

SciTech Connect

The most credible means for radionuclides disposed as solid wastes in deep-geologic repositories to reach the biosphere is through dissolution of the solid waste and subsequent radionuclide transport by circulating ground water. Thus safety assessment activities must consider the physicochemical interactions between radionculides present in ground water with package components, rocks and sediments since these processes can significantly delay or constrain the mass transport of radionuclides in comparison to ground-water movement. This paper focuses on interactions between dissolved radiouclides in ground water and rocks and sediments away from the near-field repository. The primary mechanism discussed is adsorption-desorption, which has been studied using two approaches. Empirical studies of adsorption-desorption rely on distribution coefficient measurements while mechanism studies strive to identify, differentiate and quantify the processes that control nuclide retardation.

Serne, R.J.; Relyea, J.F.

1982-04-01T23:59:59.000Z

142

DETERMINATION OF THE DISTRIBUTION AND INVENTORY OF RADIONUCLIDES WITHIN A SAVANNAH RIVER SITE WATERWAY  

Science Conference Proceedings (OSTI)

An investigation was conducted to evaluate the radionuclide inventory within the Lower Three Runs (LTR) Integrator Operable Unit (IOU) at the U.S. Department of Energy’s (DOE’s) Savannah River Site (SRS). The scope of this effort included the analysis of previously existing sampling and analysis data as well as additional streambed and floodplain sampling and analysis data acquired to delineate horizontal and vertical distributions of the radionuclide as part of the ongoing SRS environmental restoration program, and specifically for the LTR IOU program. While cesium-137 (Cs-137) is the most significant and abundant radionuclide associated with the LTR IOU it is not the only radionuclide, hence the scope included evaluating all radionuclides present and includes an evaluation of inventory uncertainty for use in sensitivity and uncertainty analyses. The scope involved evaluation of the radionuclide inventory in the P-Reactor and RReactor cooling water effluent canal systems, PAR Pond (including Pond C) and the floodplain and stream sediment sections of LTR between the PAR Pond Dam and the Savannah River. The approach taken was to examine all of the available Sediment and Sediment/Soil analysis data available along the P- and R-Reactor cooling water re-circulation canal system, the ponds situated along those canal reaches and along the length of LTR below Par Pond dam. By breaking the IOU into a series of sub-components and sub-sections, the mass of contaminated material was estimated and a representative central concentration of each radionuclide was computed for each compartment. The radionuclide inventory associated with each sub-compartment was then aggregated to determine the total radionuclide inventory that represented the full LTR IOU. Of special interest was the inventory of Cs-137 due to its role in contributing to the potential dose to an offsite member of the public. The overall LTR IOU inventory of Cs-137 was determined to be 75.5 Ci, which is similar to two earlier estimates. This investigation provides an independent, ground-up estimate of Cs-137 inventory in LTR IOU utilizing the most recent field data.

Hiergesell, R.; Phifer, M.

2012-11-09T23:59:59.000Z

143

Radionuclide Air Emissions Report for the Hanford Site Calendar Year 1999  

SciTech Connect

This report documents radionuclide air emissions from the US. Department of Energy (DOE) Hanford Site in 1999 and the resulting effective dose equivalent to the maximally exposed individual (MEI) member of the public. The report has been prepared in accordance with the Code of Federal Regulations (CFR). Title 40, Protection of the Environment, Part 61. National Emission Standards for Hazardous Air Pollutants, Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities'', and with the Washington Administrative Code (WAC) Chapter 246-247. Radiation Protection-Air Emissions. The federal regulations in Subpart H of 40 CFR 61 require the measurement and reporting of radionuclides emitted from US. Department of Energy (DOE) facilities and the resulting offsite dose from those emissions. A standard of 10 mrem/yr effective dose equivalent (EDE) is imposed on them. The EDE to the MEI due to routine emissions in 1999 from Hanford Site point sources was 0.029 mrem (2.9 E-04 mSv), which is less than 0.3 percent of the federal standard. WAC 246-247 requires the reporting of radionuclide emissions from all Hanford Site sources, during routine as well as nonroutine operations. The state has adopted the 40 CFR 61 standard of 10 mrem/yr EDE into their regulations. The state further requires that the EDE to the MEI be calculated not only from point source emissions but also from diffuse and fugitive sources of emissions. The EDE from diffuse and fugitive emissions at the Hanford Site in 1999 was 0.039 mrem (3.9 E-04 mSv) EDE. The total dose from point sources and from diffuse and fugitive sources of radionuclide emissions during all operating conditions in 1999 was 0.068 mrem (6.8 E-04 mSv) EDE, which is less than 0.7 percent of the state standard.

ROKKAN, D.J.

2000-06-01T23:59:59.000Z

144

Biological treatment of concentrated hazardous, toxic, and radionuclide mixed wastes without dilution  

E-Print Network (OSTI)

Hazardous, Toxic, and Radionuclide Mixed Wastes Without1997). Less volatile radionuclides are collected with 3 ofmeet the permissible radionuclide concentration and were not

Stringfellow, William T.; Komada, Tatsuyuki; Chang, Li-Yang

2004-01-01T23:59:59.000Z

145

Modeling studies of mountain-scale radionuclide transport in the unsaturated zone at Yucca Mountain, Nevada  

E-Print Network (OSTI)

Wu, and G.S. Bodvarsson, Radionuclide Transport Models Underdaughters of certain radionuclides. Increasing infiltrationOF MOUNTAIN-SCALE RADIONUCLIDE TRANSPORT IN THE UNSATURATED

Moridis, George J.; Seol, Yongkoo; Wu, Yu-Shu

2003-01-01T23:59:59.000Z

146

EFFECT OF SOURCE BOUNDARY CONDITIONS IN PREDICTING THE MIGRATION OF RADIONUCLIDES THROUGH GEOLOGIC MEDIA  

E-Print Network (OSTI)

concentra· tions of radionuclides undergoing hydrogeologicRelease of Decaying Radionuclides Through Sorbing Media,"of the Tnms- port of a Radionuclide Chain Through a Sorbing

Harada, M.

2013-01-01T23:59:59.000Z

147

Preparation of Radiopharmaceuticals Labeled with Metal Radionuclides  

Science Conference Proceedings (OSTI)

The overall goal of this project was to develop methods for the production of metal-based radionuclides, to develop metal-based radiopharmaceuticals and in a limited number of cases, to translate these agents to the clinical situation. Initial work concentrated on the application of the radionuclides of Cu, Cu-60, Cu-61 and Cu-64, as well as application of Ga-68 radiopharmaceuticals. Initially Cu-64 was produced at the Missouri University Research Reactor and experiments carried out at Washington University. A limited number of studies were carried out utilizing Cu-62, a generator produced radionuclide produced by Mallinckrodt Inc. (now Covidien). In these studies, copper-62-labeled pyruvaldehyde Bis(N{sup 4}-methylthiosemicarbazonato)-copper(II) was studied as an agent for cerebral myocardial perfusion. A remote system for the production of this radiopharmaceutical was developed and a limited number of patient studies carried out with this agent. Various other copper radiopharmaceuticals were investigated, these included copper labeled blood imaging agents as well as Cu-64 labeled antibodies. Cu-64 labeled antibodies targeting colon cancer were translated to the human situation. Cu-64 was also used to label peptides (Cu-64 octriatide) and this is one of the first applications of a peptide radiolabeled with a positron emitting metal radionuclide. Investigations were then pursued on the preparation of the copper radionuclides on a small biomedical cyclotron. A system for the production of high specific activity Cu-64 was developed and initially the Cu-64 was utilized to study the hypoxic imaging agent Cu-64 ATSM. Utilizing the same target system, other positron emitting metal radionuclides were produced, these were Y-86 and Ga-66. Radiopharmaceuticals were labeled utilizing both of these radionuclides. Many studies were carried out in animal models on the uptake of Cu-ATSM in hypoxic tissue. The hypothesis is that Cu-ATSM retention in vivo is dependent upon the oxygen retention of the tissue and the significantly greater retention amounting in hypoxic tissue. This hypothesis was confirmed in a series of animal studies. Cu-64 can be used both as an imaging radionuclide and a therapeutic radionuclide. The therapeutic efficacy of Cu-64 ATSM was proven in hamsters bearing the CW39 human colorectal tumors. The administration of Cu-64 ATSM significantly increased the survival time of tumor-bearing animals with no acute toxicity. This copper agent therefore shows promise for radiotherapy. The flow tracer Cu-64 PTSM also demonstrates therapeutic potential by inhibiting cancer cells implanted in animal models. Again, this inhibition occurred at doses which showed no sign of toxicity to the animals. Cu-ATSM was translated to humans, under other support a series of tumors were investigated; these included head and neck cancer, non-small cell lung cancer, cervical cancer and renal cancer. Another radionuclide that was investigated was titanium 45. This radionuclide was successfully produced by radiation of a scandium foil with 15 MeV protons. The titanium 45 was processed and separated from residual scandium by high exchange chomotrophy. Titanium titanocene has been utilized as a therapeutic agent; this compound was prepared and studied in vitro and in vivo. Another project was the preparation of cyclodextrin dimers as a new pre-targeting approach for tumor uptake. Beta-cyclodextradin and two other dimers were synthesized. These dimers were studied for the in vivo application. Work continued on the application of the radionuclide already discussed. Technetium 94m, a positron emitting radionuclide of the widely used 99m Tc nuclide was also prepared. This allows the quantification of the uptake of technetium radiopharmaceuticals. In collaboration with Professor David Piwnica-Worms, technetium 94m, sestamibi was studied in animal models and in a limited number of human subjects.

Welch, M.J.

2012-02-16T23:59:59.000Z

148

Effects of radionuclide decay on waste glass behavior: A critical review  

Science Conference Proceedings (OSTI)

This paper is an extension of a chapter in an earlier report [1] that provides an updated review on the status of radiation damage problems in nuclear waste glasses. This report will focus on radiation effects on vitrified borosilicate nuclear waste glasses under conditions expected in the proposed Yucca mountain repository. Radiation effects on high-level waste glasses and their surrounding repository environment are important considerations for radionuclide immobilization because of the potential to alter the glass stability and thereby influence the radionuclide retentive properties of this waste form. The influence of radionuclide decay on vitrified nuclear waste may be manifested by several changes, including volume, stored energy, structure, microstructure, mechanical properties, and phase separation. Radiation may also affect the composition of aqueous fluids and atmospheric gases in relatively close proximity to the waste form. What is important to the radionuclide retentive properties of the repository is how these radiation effects collectively or individually influence the durability and radionuclide release from the glass in the event of liquid water contact.

Wronkiewicz, D.J.

1993-12-01T23:59:59.000Z

149

Targets and methods for target preparation for radionuclide production  

DOE Patents (OSTI)

The invention relates to nuclear technology, and to irradiation targets and their preparation. One embodiment of the present invention includes a method for preparation of a target containing intermetallic composition of antimony Ti--Sb, Al--Sb, Cu--Sb, or Ni--Sb in order to produce radionuclides (e.g., tin-117 m) with a beam of accelerated particles. The intermetallic compounds of antimony can be welded by means of diffusion welding to a copper backing cooled during irradiation on the beam of accelerated particles. Another target can be encapsulated into a shell made of metallic niobium, stainless steel, nickel or titanium cooled outside by water during irradiation. Titanium shell can be plated outside by nickel to avoid interaction with the cooling water.

Zhuikov, Boris L; Konyakhin, Nicolai A; Kokhanyuk, Vladimir M; Srivastava, Suresh C

2012-10-16T23:59:59.000Z

150

Radionuclide Retention in Concrete Wasteforms - FY13  

SciTech Connect

Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how wasteform performance is affected by the full range of environmental conditions within the disposal facility; the process of wasteform aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of wasteform aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the wasteforms come in contact with groundwater. Data collected throughout the course of this work will be used to quantify the efficacy of concrete wasteforms, similar to those used in the disposal of low-level waste and mixed low-level waste, for the immobilization of key radionuclides (i.e., uranium, technetium, and iodine). Data collected will also be used to quantify the physical and chemical properties of the concrete affecting radionuclide retention.

Snyder, Michelle MV; Golovich, Elizabeth C.; Wellman, Dawn M.; Crum, Jarrod V.; Lapierre, Robert; Dage, Denomy C.; Parker, Kent E.; Cordova, Elsa A.

2013-10-15T23:59:59.000Z

151

Radionuclide Retention in Concrete Waste Forms  

Science Conference Proceedings (OSTI)

Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how waste form performance is affected by the full range of environmental conditions within the disposal facility; the process of waste form aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of waste form aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the waste forms come in contact with groundwater. The information presented in the report provides data that 1) quantify radionuclide retention within concrete waste form materials similar to those used to encapsulate waste in the Low-Level Waste Burial Grounds (LLBG); 2) measure the effect of concrete waste form properties likely to influence radionuclide migration; and 3) quantify the stability of uranium-bearing solid phases of limited solubility in concrete.

Mattigod, Shas V.; Bovaird, Chase C.; Wellman, Dawn M.; Wood, Marcus I.

2010-09-30T23:59:59.000Z

152

1999 INEEL National Emission Standards for Hazardous Air Pollutants - Radionuclides  

Science Conference Proceedings (OSTI)

Under Section 61.94 of Title 40, Code of Federal Regulations (CFR), Part 61, Subpart H, ''National Emission Standards for Emission of Radionuclides Other Than Radon From Department of Energy Facilities,'' each Department of Energy (DOE) facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at the Idaho National Engineering and Environmental Laboratory (INEEL) for calendar year (CY) 1999. The Idaho Operations Office of the DOE is the primary contract concerning compliance with the National Emission Standards for Hazardous Air Pollutants (NESHAPs) at the INEEL. For CY 1999, airborne radionuclide emissions from the INEEL operations were calculated to result in a maximum individual dose to a member of the public of 7.92E-03 mrem (7.92E-08 Sievert). This effective dose equivalent (EDE) is well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year).

J. W. Tkachyk

2000-06-01T23:59:59.000Z

153

1998 INEEL National Emission Standard for Hazardous Air Pollutants - Radionuclides  

Science Conference Proceedings (OSTI)

Under Section 61.94 of Title 40, Code of Federal Regulations (CFR), Part 61, Subpart H, ''National Emission Standards for Emission of Radionuclides Other Than Radon From Department of Energy Facilities,'' each Department of Energy (DOE) facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at the Idaho National Engineering and Environmental Laboratory (INEEL) for calendar year (CY) 1998. The Idaho Operations Office of the DOE is the primary contract concerning compliance with the National Emission Standards for Hazardous Air Pollutants (NESHAPs) at the INEEL. For CY 1998, airborne radionuclide emissions from the INEEL operations were calculated to result in a maximum individual dose to a member of the public of 7.92E-03 mrem (7.92E-08 Sievert). This effective dose equivalent (EDE) is well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year).

J. W. Tkachyk

1999-06-01T23:59:59.000Z

154

Laboratory studies of radionuclide migration in tuff  

SciTech Connect

The movement of selected radionuclides has been observed in crushed tuff, intact tuff, and fractured tuff columns. Retardation factors and dispersivities were determined from the elution profiles. Retardation factors have been compared with those predicted on the basis of batch sorption studies. This comparison forms a basis for either validating distribution coefficients or providing evidence of speciation, including colloid formation. Dispersivities measured as a function of velocity provide a means of determining the effect of sorption kinetics or mass transfer on radionuclide migration. Dispersion is also being studied in the context of scaling symmetry to develop a basis for extrapolating from the laboratory scale to the field. 21 refs., 6 figs., 2 tabs.

Rundberg, R.S.; Mitchell, A.J.; Ott, M.A.; Thompson, J.L.; Triay, I.R.

1989-10-01T23:59:59.000Z

155

Radionuclide Behavior and Geochemistry in Boom Clay after ...  

Science Conference Proceedings (OSTI)

Radioactive Demonstrations of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes · Radionuclide Behavior and Geochemistry in Boom  ...

156

Radionuclide release calculations for selected severe accident scenarios  

Science Conference Proceedings (OSTI)

This report provides the results of source term calculations that were performed in support of the NUREG-1150 study. Severe Accident Risks: An Assessment for Five US Nuclear Power Plants.'' This is the sixth volume of a series of reports. It supplements results presented in the earlier volumes. Analyses were performed for three of the NUREG-1150 plants: Peach Bottom, a Mark I, boiling water reactor; Surry, a subatmospheric containment, pressurized water reactor; and Sequoyah, an ice condenser containment, pressurized water reactor. Complete source term results are presented for the following sequences: short term station blackout with failure of the ADS system in the Peach Bottom plant; station blackout with a pump seal LOCA for the Surry plant; station blackout with a pump seal LOCA in the Sequoyah plant; and a very small break with loss of ECC and spray recirculation in the Sequoyah plant. In addition, some partial analyses were performed which did not require running all of the modules of the Source Term Code Package. A series of MARCH3 analyses were performed for the Surry and Sequoyah plants to evaluate the effects of alternative emergency operating procedures involving primary and secondary depressurization on the progress of the accident. Only thermal-hydraulic results are provided for these analyses. In addition, three accident sequences were analyzed for the Surry plant for accident-induced failure of steam generator tubes. In these analyses, only the transport of radionuclides within the primary system and failed steam generator were examined. The release of radionuclides to the environment is presented for the phase of the accident preceding vessel meltthrough. 17 refs., 176 figs., 113 tabs.

Denning, R.S.; Leonard, M.T.; Cybulskis, P.; Lee, K.W.; Kelly, R.F.; Jordan, H.; Schumacher, P.M.; Curtis, L.A. (Battelle Columbus Div., OH (USA))

1990-08-01T23:59:59.000Z

157

The Molecular Basis for Water Taste in Drosophila  

E-Print Network (OSTI)

and the regulation of water intake are essential for animalsimportance in regulating water intake. Although taste cells

Cameron, Peter

2010-01-01T23:59:59.000Z

158

A groundwater flow and transport model of long-term radionuclide migration in central Frenchman flat, Nevada test site  

Science Conference Proceedings (OSTI)

A set of groundwater flow and transport models were created for the Central Testing Area of Frenchman Flat at the former Nevada Test Site to investigate the long-term consequences of a radionuclide migration experiment that was done between 1975 and 1990. In this experiment, radionuclide migration was induced from a small nuclear test conducted below the water table by pumping a well 91 m away. After radionuclides arrived at the pumping well, the contaminated effluent was discharged to an unlined ditch leading to a playa where it was expected to evaporate. However, recent data from a well near the ditch and results from detailed models of the experiment by LLNL personnel have convincingly demonstrated that radionuclides from the ditch eventually reached the water table some 220 m below land surface. The models presented in this paper combine aspects of these detailed models with concepts of basin-scale flow to estimate the likely extent of contamination resulting from this experiment over the next 1,000 years. The models demonstrate that because regulatory limits for radionuclide concentrations are exceeded only by tritium and the half-life of tritium is relatively short (12.3 years), the maximum extent of contaminated groundwater has or will soon be reached, after which time the contaminated plume will begin to shrink because of radioactive decay. The models also show that past and future groundwater pumping from water supply wells within Frenchman Flat basin will have negligible effects on the extent of the plume.

Kwicklis, Edward Michael [Los Alamos National Laboratory; Becker, Naomi M [Los Alamos National Laboratory; Ruskauff, Gregory [NAVARRO-INTERA, LLC.; De Novio, Nicole [GOLDER AND ASSOC.; Wilborn, Bill [US DOE NNSA NSO

2010-11-10T23:59:59.000Z

159

Improving Targeted Radionuclide Therapy Using Nuclear Nanotechnology  

E-Print Network (OSTI)

The objectives of this thesis are to produce radioactive antibody-conjugated gold nanoparticles to improve the efficacy of targeted radionuclide therapy for the treatment of cancer, and to demonstrate that this product can be produced at Texas A&M University. We have proposed a method for determining the distribution of radioactive nuclei per nanoparticle, which is critical for determining radiotherapeutic efficacy. Using the distribution of radioactive nuclei per nanoparticle, we have produced methods for calculating the radiative dose to tissue using nano-improved targeted radionuclide therapy, but more importantly we propose procedures to experimentally determine the efficacy of targeted radionuclide therapy improved by application of radioactive nanomaterials in combination with immunotherapy, nanomaterial cytotoxicity, and other cancer therapies such as chemotherapy. These methods can also be used to determine the efficacy of combinatory treatments as a function of time. Characterization of the antibody-nanoparticle attachment is critical; we have demonstrated successful antibody-nanoparticle conjugation using atomic force microscopy, dynamic light scattering, and agarose gel electrophoresis, providing more conclusive evidence of successful conjugation compared to flow cytometry. We provide a mathematical derivation from basic electron-transport principles which demonstrates the theoretical dosimetric advantages of applying radioactive nanomaterials to targeted radionuclide therapy. The general formulae can be applied to any tumor size, any radionuclide, and any pharmacokinetic nanoparticle distribution throughout the body, ultimately allowing a quick method of approximating the necessary activation time and treatment dosage parameters for a specific patient without burdensome Monte Carlo computational simulations. We further demonstrated that nano-TRT dosage to tumors should be considered as a function of radial position rather than average, as the dose across the tumor may be noticeably non-uniform causing some portions of the tumor to receive (potentially) significantly less dose than average.

Evans, Jordan Andrew

2013-05-01T23:59:59.000Z

160

2006 LANL Radionuclide Air Emissions Report  

SciTech Connect

This report describes the impacts from emissions of radionuclides at Los Alamos National Laboratory (LANL) for calendar year 2006. This report fulfills the requirements established by the Radionuclide National Emissions Standards for Hazardous Air Pollutants (Rad-NESHAP). This report is prepared by LANL's Rad-NESHAP compliance team, part of the Environmental Protection Division. The information in this report is required under the Clean Air Act and is being reported to the U.S. Environmental Protection Agency (EPA). The highest effective dose equivalent (EDE) to an off-site member of the public was calculated using procedures specified by the EPA and described in this report. LANL's EDE was 0.47 mrem for 2006. The annual limit established by the EPA is 10 mrem per year. During calendar year 2006, LANL continuously monitored radionuclide emissions at 28 release points, or stacks. The Laboratory estimates emissions from an additional 58 release points using radionuclide usage source terms. Also, LANL uses a network of air samplers around the Laboratory perimeter to monitor ambient airborne levels of radionuclides. To provide data for dispersion modeling and dose assessment, LANL maintains and operates meteorological monitoring systems. From these measurement systems, a comprehensive evaluation is conducted to calculate the EDE for the Laboratory. The EDE is evaluated as any member of the public at any off-site location where there is a residence, school, business, or office. In 2006, this location was the Los Alamos Airport Terminal. The majority of this dose is due to ambient air sampling of plutonium emitted from 2006 clean-up activities at an environmental restoration site (73-002-99; ash pile). Doses reported to the EPA for the past 10 years are shown in Table E1.

David P. Fuehne

2007-06-30T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Radionuclide Interaction and Transport in Representative Geologic Media |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Radionuclide Interaction and Transport in Representative Geologic Radionuclide Interaction and Transport in Representative Geologic Media Radionuclide Interaction and Transport in Representative Geologic Media The report presents information related to the development of a fundamental understanding of disposal-system performance in a range of environments for potential wastes that could arise from future nuclear fuel cycle alternatives. It addresses selected aspects of the development of computational modeling capability for the performance of storage and disposal options. Topics include radionuclide interaction with geomedia, colloid-facilitated radionuclide transport (Pu colloids), interaction between iodide (accumulate in the interlayer regions of clay minerals) and a suite of clay minerals, adsorption of uranium onto granite and bentonite,

162

Colloid-Facilitated Transport of Radionuclides through the Vadose Zone  

SciTech Connect

The main purpose of this project was to advance the basic scientific understanding of colloid and colloid-facilitated Cs transport of radionuclides in the vadose zone. We focused our research on the hydrological and geochemical conditions beneath the leaking waste tanks at the USDOE Hanford reservation. Specific objectives were (1) to determine the lability and thermodynamic stability of colloidal materials, which form after reacting Hanford sediments with simulated Hanford Tank Waste, (2) to characterize the interactions between colloidal particles and contaminants, i.e., Cs and Eu, (3) to determine the potential of Hanford sediments for \\textit{in situ} mobilization of colloids, (4) to evaluate colloid-facilitated radionuclide transport through sediments under unsaturated flow, (5) to implement colloid-facilitated contaminant transport mechanisms into a transport model, and (6) to improve conceptual characterization of colloid-contaminant-soil interactions and colloid-facili\\-tated transport for clean-up procedures and long-term risk assessment. We have previously shown that upon contact with simulated waste tank solutions, Hanford sediments change their mineralogical composition. Certain minerals, i.e., quartz, smectite, and kaolinite, are partially dissolved, and new mineral phases, i.e., the feldspathoids cancrinite and sodalite, are formed. We have characterized these mineral transformations and clarified the mineral transformation pathways. The new minerals were mainly in the colloidal size fraction (diameter less than 2 mum), had a negative surface charge, and were microporous, meaning they contained small pores. When Cs was present during the formation of the minerals, contaminants, like Cs, could be trapped inside the mineral structure. Transport experiments under water saturated and unsaturated conditions showed that the colloids were mobile in Hanford sediments. As the water saturation of the sediments decreased, the amount of colloids transported also decreased. The colloids had the ability to enhance the migration of the radionuclide Cs; however, Cs initially sorbed to colloids was desorbed during transport through uncontaminated Hanford sediments. The finding that Cs was stripped off the colloids during the transport through uncontaminated sediments implies that colloids will likely not be an effective carrier for Cs, unless the Cs is incorporated into the mineral structure of the colloids such that the radionuclide cannot desorb from the colloids. Nevertheless, it appears that the amount of Cs that can be transported by mobile colloids beneath Hanford waste tanks is limited. Colloids will not be able to move the bulk mass of Cs through the vadose zone at Hanford. Colloid stability studies indicate that Hanford sediment form stable colloidal suspensions when suspended in Hanford sediment pore waters. Colloid stability was assessed by determination of the critical coagulation concentration, i.e., the chemical electrolyte concentration at which colloidal suspensions flocculate and settle out (become unstable). Although in the stable mode, Hanford colloids will settle out of solution after extended periods of time (months to years). Given the low recharge rates at Hanford range, which from near 0 to more than 100 mm/year, and the long travel times for rainwater to reach the groundwater of more than 40 years, it appears that colloidal transport is unlikely to occur if colloids are initially to be suspended close to the soil surface by infiltrating rainwater. However, if preferential flow or transient flow occurs, then colloidal transport may become more important. The results of this project have also led to improvements of our fundamental understanding of colloid transport and mobilization under unsaturated flow conditions in porous media. We have found that colloid attachment to the liquid-gas interface is not that relevant and that colloids rather attached near the triple phase interface where air, water, and solid phases meet. We have also found that capillary forces are the most dominant forces governing

Markus Flury; James B. Harsh; John F. McCarthy; Peter C. Lichtner; John M. Zachara

2006-11-21T23:59:59.000Z

163

Colloid-Facilitated Transport of Radionuclides through the Vadose Zone  

Science Conference Proceedings (OSTI)

The main purpose of this project was to advance the basic scientific understanding of colloid and colloid-facilitated Cs transport of radionuclides in the vadose zone. We focused our research on the hydrological and geochemical conditions beneath the leaking waste tanks at the USDOE Hanford reservation. Specific objectives were (1) to determine the lability and thermodynamic stability of colloidal materials, which form after reacting Hanford sediments with simulated Hanford Tank Waste, (2) to characterize the interactions between colloidal particles and contaminants, i.e., Cs and Eu, (3) to determine the potential of Hanford sediments for \\textit{in situ} mobilization of colloids, (4) to evaluate colloid-facilitated radionuclide transport through sediments under unsaturated flow, (5) to implement colloid-facilitated contaminant transport mechanisms into a transport model, and (6) to improve conceptual characterization of colloid-contaminant-soil interactions and colloid-facili\\-tated transport for clean-up procedures and long-term risk assessment. We have previously shown that upon contact with simulated waste tank solutions, Hanford sediments change their mineralogical composition. Certain minerals, i.e., quartz, smectite, and kaolinite, are partially dissolved, and new mineral phases, i.e., the feldspathoids cancrinite and sodalite, are formed. We have characterized these mineral transformations and clarified the mineral transformation pathways. The new minerals were mainly in the colloidal size fraction (diameter less than 2 mum), had a negative surface charge, and were microporous, meaning they contained small pores. When Cs was present during the formation of the minerals, contaminants, like Cs, could be trapped inside the mineral structure. Transport experiments under water saturated and unsaturated conditions showed that the colloids were mobile in Hanford sediments. As the water saturation of the sediments decreased, the amount of colloids transported also decreased. The colloids had the ability to enhance the migration of the radionuclide Cs; however, Cs initially sorbed to colloids was desorbed during transport through uncontaminated Hanford sediments. The finding that Cs was stripped off the colloids during the transport through uncontaminated sediments implies that colloids will likely not be an effective carrier for Cs, unless the Cs is incorporated into the mineral structure of the colloids such that the radionuclide cannot desorb from the colloids. Nevertheless, it appears that the amount of Cs that can be transported by mobile colloids beneath Hanford waste tanks is limited. Colloids will not be able to move the bulk mass of Cs through the vadose zone at Hanford. Colloid stability studies indicate that Hanford sediment form stable colloidal suspensions when suspended in Hanford sediment pore waters. Colloid stability was assessed by determination of the critical coagulation concentration, i.e., the chemical electrolyte concentration at which colloidal suspensions flocculate and settle out (become unstable). Although in the stable mode, Hanford colloids will settle out of solution after extended periods of time (months to years). Given the low recharge rates at Hanford range, which from near 0 to more than 100 mm/year, and the long travel times for rainwater to reach the groundwater of more than 40 years, it appears that colloidal transport is unlikely to occur if colloids are initially to be suspended close to the soil surface by infiltrating rainwater. However, if preferential flow or transient flow occurs, then colloidal transport may become more important. The results of this project have also led to improvements of our fundamental understanding of colloid transport and mobilization under unsaturated flow conditions in porous media. We have found that colloid attachment to the liquid-gas interface is not that relevant and that colloids rather attached near the triple phase interface where air, water, and solid phases meet. We have also found that capillary forces are the most dominant forces governing

Markus Flury; James B. Harsh; John F. McCarthy; Peter C. Lichtner; John M. Zachara

2006-11-21T23:59:59.000Z

164

SALTSTONE AND RADIONUCLIDE INTERACTIONS: RADIONUCLIDE SORPTION AND DESORPTION, AND SALTSTONE REDUCTION CAPACITY  

SciTech Connect

The overall objective of this study was to measure a number of key input parameters quantifying geochemical processes in the subsurface environment of the Savannah River Site's (SRS's) Saltstone Facility. For the first time, sorption (K{sub d}) values of numerous radionuclides were measured with Saltstone and Vault 2 concrete. Particular attention was directed at understanding how Tc adsorbs and desorbs from these cementitious materials with the intent to demonstrate that desorption occurs at a much slower rate than adsorption, thus permitting the use of kinetic terms instead of (or along with) the steady state K{sub d} term. Another very important parameter measured was the reduction capacity of these materials. This parameter is used to estimate the duration that the Saltstone facility remains in a reduced chemical state, a condition that maintains several otherwise mobile radionuclides in an immobile form. Key findings of this study follow. K{sub d} values for Am, Cd, Ce, Co, Cs, Hg, I, Np, Pa, Pu, Se, Sn, Tc, U, and Y for Saltstone and Vault 2 concrete were measured under oxidized and reduced conditions. Precipitation of several of the higher valence state radionuclides was observed. There was little evidence that the Vault 2 and Saltstone K{sub d} values differed from previous SRS K{sub d} values measured with reducing grout (Kaplan and Coates 2007). These values also supported a previous finding that K{sub d} values of slag-containing cementitious materials, tend to be greater for cations and about the same for anions, than regular cementitious materials without slag. Based on these new findings, it was suggested that all previous reducing concrete K{sub d} values be used in future PAs, except Np(V) and Pu(IV) K{sub d} values, which should be increased, and I values, which should be slightly decreased in all three stages of concrete aging. The reduction capacity of Saltstone, consisting of 23 wt-% blast furnace slag, was 821.8 microequivalents per gram ({micro}eq/g). This value was approximately the same value as the one measured for 100% blast furnace slag. The cause for this approximately four-fold greater reduction capacity than anticipated is not known, but may be the result of the higher pH of Saltstone (pH {approx}11) compared to blast furnace slag (pH {approx}8), the presence of reducing minerals in the fly ash used to make the Saltstone, or to the Saltstone possibly having semi-conductor properties. These reduction capacity values will result in a near four-fold increase in the estimated duration that the Saltstone facility will remain in a reduced chemical state. The implication of this result is that oxidation-state-sensitive contaminants, such as Pu, Np, and Tc, will remain for a longer duration in a much less mobile form than previously believed. The reduction capacity of vault concrete, which consisted of 10 wt-% blast furnace slag, was 240 {micro}eq/g. Essentially all Am, Cd, Ce, Co, Cs, Hg, Sr, and Y was (ad)sorbed within four hours, whereas <3% of the adsorbed metals desorbed from these solids after 90 hours of continuous leaching. In particular, desorption of Tc (under oxidizing conditions) was >10{sup 3} fold slower than (ad)sorption (under reducing conditions). An important implication of this finding is that if groundwater by-passes or short-circuits the reduction capacity of the Saltstone by flowing along a crack, the ability of the oxygenated water to promote Tc desorption is appreciably less than that predicted based on the K{sub d} value. Relatively low Tc K{sub d} values, 6 to 91 mL/g, were measured in these studies indicating that little if any of the Tc(VII) introduced into the Saltstone or Vault 2 concrete suspensions was reduced to Tc(IV). Such a reduction results in apparent K{sub d} values on the order of 10{sup 4} mL/g. As such, these Tc sorption/desorption experiments need additional investigation to fully represent Saltstone environmental conditions. It is important to understand the limits of these data. They do not provide insight into how radionuclides cured and immobilize

Kaplan, D; Kimberly Roberts, K; Steven Serkiz, S; Matthew Siegfried, M

2008-10-30T23:59:59.000Z

165

SALTSTONE AND RADIONUCLIDE INTERACTIONS: RADIONUCLIDE SORPTION AND DESORPTION, AND SALTSTONE REDUCTION CAPACITY  

Science Conference Proceedings (OSTI)

The overall objective of this study was to measure a number of key input parameters quantifying geochemical processes in the subsurface environment of the Savannah River Site's (SRS's) Saltstone Facility. For the first time, sorption (K{sub d}) values of numerous radionuclides were measured with Saltstone and Vault 2 concrete. Particular attention was directed at understanding how Tc adsorbs and desorbs from these cementitious materials with the intent to demonstrate that desorption occurs at a much slower rate than adsorption, thus permitting the use of kinetic terms instead of (or along with) the steady state K{sub d} term. Another very important parameter measured was the reduction capacity of these materials. This parameter is used to estimate the duration that the Saltstone facility remains in a reduced chemical state, a condition that maintains several otherwise mobile radionuclides in an immobile form. Key findings of this study follow. K{sub d} values for Am, Cd, Ce, Co, Cs, Hg, I, Np, Pa, Pu, Se, Sn, Tc, U, and Y for Saltstone and Vault 2 concrete were measured under oxidized and reduced conditions. Precipitation of several of the higher valence state radionuclides was observed. There was little evidence that the Vault 2 and Saltstone K{sub d} values differed from previous SRS K{sub d} values measured with reducing grout (Kaplan and Coates 2007). These values also supported a previous finding that K{sub d} values of slag-containing cementitious materials, tend to be greater for cations and about the same for anions, than regular cementitious materials without slag. Based on these new findings, it was suggested that all previous reducing concrete K{sub d} values be used in future PAs, except Np(V) and Pu(IV) K{sub d} values, which should be increased, and I values, which should be slightly decreased in all three stages of concrete aging. The reduction capacity of Saltstone, consisting of 23 wt-% blast furnace slag, was 821.8 microequivalents per gram ({micro}eq/g). This value was approximately the same value as the one measured for 100% blast furnace slag. The cause for this approximately four-fold greater reduction capacity than anticipated is not known, but may be the result of the higher pH of Saltstone (pH {approx}11) compared to blast furnace slag (pH {approx}8), the presence of reducing minerals in the fly ash used to make the Saltstone, or to the Saltstone possibly having semi-conductor properties. These reduction capacity values will result in a near four-fold increase in the estimated duration that the Saltstone facility will remain in a reduced chemical state. The implication of this result is that oxidation-state-sensitive contaminants, such as Pu, Np, and Tc, will remain for a longer duration in a much less mobile form than previously believed. The reduction capacity of vault concrete, which consisted of 10 wt-% blast furnace slag, was 240 {micro}eq/g. Essentially all Am, Cd, Ce, Co, Cs, Hg, Sr, and Y was (ad)sorbed within four hours, whereas 10{sup 3} fold slower than (ad)sorption (under reducing conditions). An important implication of this finding is that if groundwater by-passes or short-circuits the reduction capacity of the Saltstone by flowing along a crack, the ability of the oxygenated water to promote Tc desorption is appreciably less than that predicted based on the K{sub d} value. Relatively low Tc K{sub d} values, 6 to 91 mL/g, were measured in these studies indicating that little if any of the Tc(VII) introduced into the Saltstone or Vault 2 concrete suspensions was reduced to Tc(IV). Such a reduction results in apparent K{sub d} values on the order of 10{sup 4} mL/g. As such, these Tc sorption/desorption experiments need additional investigation to fully represent Saltstone environmental conditions. It is important to understand the limits of these data. They do not provide insight into how radionuclides cured and immobilize

Kaplan, D; Kimberly Roberts, K; Steven Serkiz, S; Matthew Siegfried, M

2008-10-30T23:59:59.000Z

166

Study for radionuclide transfer ratio of aerosols generated during heat cutting  

SciTech Connect

The metallic elements with a low melting point and high vapor pressure seemed to transfer in aerosols selectively at dismantling reactor internals using heat cutting. Therefore, the arc melting tests of neutron irradiated zirconium alloy were conducted to investigate the radionuclide transfer behavior of aerosols generated during the heat cutting of activated metals. The arc melting test was conducted using a tungsten inert gas welding machine in an inert gas or air atmosphere. The radioactive aerosols were collected by filter and charcoal filter. The test sample was obtained from Zry-2 fuel cladding irradiated in a Japanese boiling water reactor for five fuel cycles. The activity analysis, chemical composition measurement and scanning electron microscope observation of aerosols were carried out. Some radionuclides were enriched in the aerosols generated in an inert gas atmosphere and the radionuclide transfer ratio did not change remarkably by the presence of air. The transfer ratio of Sb-125 was almost the same as that of Co-60. It was expected that Sb-125 was enriched from other elements since Sb is an element with a low melting point and high vapor pressure compared with the base metal (Zr). In the viewpoint of the environmental impact assessment, it became clear that the influence if Sb-125 is comparable to Co-60. The transfer ratio of Mn-54 was one order higher compared with other radionuclides. The results were discussed on the basis of thermal properties and oxide formation energy of the metallic elements. (authors)

Iguchi, Yukihiro; Baba, Tsutomu; Kawakami, Hiroto [Japan Nuclear Energy Safety Organization - JNES (Japan); Kitahara, Takashi; Watanabe, Atsushi [Hitachi, Ltd. (Japan); Kodama, Mitsuhiro [Nippon Nuclear Fuel Development Co., Ltd. (Japan)

2007-07-01T23:59:59.000Z

167

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

Science Conference Proceedings (OSTI)

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.

Napier, B.A.

1991-07-01T23:59:59.000Z

168

ORIGINAL ARTICLE Radionuclide Concentrations in Benthic Invertebrates  

Office of Legacy Management (LM)

Environ Monit Assess (2007) 128:329-341 Environ Monit Assess (2007) 128:329-341 DO1 10.1007/~10661-006-93 I 6 4 ORIGINAL ARTICLE - Radionuclide Concentrations in Benthic Invertebrates from Amchitka and Kiska Islands in the Aleutian Chain, Alaska Joanna Burger Michael Gochfeld Stephen C. Jewett Received: 8 March 2006 /Accepted: 8 May 2006 1 Published online: 21 October 2006 0 Springer Science + Business Media B.V. 2006 Abstract Concentrations of 13 radionuclides 1291, 60co, 1 5 2 ~ ~ , 9 0 s r , 9 9 ~ ~ , 2 4 1 ~ ~ , 238pu, 239249pu, 2 3 4 ~ , 2 3 5 ~ , 236U, 2 3 8 ~ were examined in seven species of invertebrates from Amchitka and Kiska Islands, in the Aleutian Chain of Alaska, using gamma spectroscopy, inductively coupled plasma mass spectroscopy, and alpha spectroscopy. Amchitka Island was the site of three underground nuclear test

169

Sequim Site Radionuclide Air Emissions Report for Calendar Year 2012  

SciTech Connect

This report is prepared to document compliance with the Code of Federal Regulations (CFR), Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (NESHAP), Subpart H, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities and ashington Administrative Code (WAC) Chapter 246-247, Radiation Protection Air Emissions. This report meets the calendar year 2012 Sequim Site annual reporting requirement for its operations as a privately-owned facility as well as its federally-contracted status that began in October 2012. Compliance is indicated by comparing the estimated dose to the maximally exposed individual (MEI) with the 10 mrem/yr Environmental Protection Agency (EPA) standard. The MSL contains only sources classified as fugitive emissions. Despite the fact that the regulations are intended for application to point source emissions, fugitive emissions are included with regard to complying with the EPA standard. The dose to the Sequim Site MEI due to routine operations in 2012 was 9E-06 mrem (9E-08 mSv). No non-routine emissions occurred in 2012. The MSL is in compliance with the federal and state 10 mrem/yr standard.

Snyder, Sandra F.; Barnett, J. M.; Gervais, Todd L.

2013-04-01T23:59:59.000Z

170

Diffusion and Leaching Behavior of Radionuclides in Category 3 Waste Encasement Concrete and Soil Fill Material – Summary Report  

SciTech Connect

One of the methods being considered for safely disposing of Category 3 low-level radioactive wastes is to encase the waste in concrete. Such concrete encasement would contain and isolate the waste packages from the hydrologic environment and would act as an intrusion barrier. The current plan for waste isolation consists of stacking low-level waste packages on a trench floor, surrounding the stacks with reinforced steel, and encasing these packages in concrete. These concrete-encased waste stacks are expected to vary in size with maximum dimensions of 6.4 m long, 2.7 m wide, and 4 m high. The waste stacks are expected to have a surrounding minimum thickness of 15 cm of concrete encasement. These concrete-encased waste packages are expected to withstand environmental exposure (solar radiation, temperature variations, and precipitation) until an interim soil cover or permanent closure cover is installed, and to remain largely intact thereafter. Any failure of concrete encasement may result in water intrusion and consequent mobilization of radionuclides from the waste packages. The mobilized radionuclides may escape from the encased concrete by mass flow and/or diffusion and move into the surrounding subsurface environment. Therefore, it is necessary to assess the performance of the concrete encasement structure and the ability of the surrounding soil to retard radionuclide migration. The retardation factors for radionuclides contained in the waste packages can be determined from measurements of diffusion coefficients for these contaminants through concrete and fill material. Some of the mobilization scenarios include (1) potential leaching of waste form before permanent closure cover is installed; (2) after the cover installation, long-term diffusion of radionuclides from concrete waste form into surrounding fill material; (3) diffusion of radionuclides from contaminated soils into adjoining concrete encasement and clean fill material. Additionally, the rate of diffusion of radionuclides may be affected by the formation of structural cracks in concrete, the carbonation of the buried waste form, and any potential effect of metallic iron (in the form of rebars) on the mobility of radionuclides. The radionuclides iodine-129 ({sup 129}I), technetium-99 ({sup 99}Tc), and uranium-238 ({sup 238}U) are identified as long-term dose contributors in Category 3 waste (Mann et al. 2001; Wood et al. 1995). Because of their anionic nature in aqueous solutions, {sup 129}I, {sup 99}Tc, and carbonate-complexed {sup 238}U may readily leach into the subsurface environment (Serne et al. 1989, 1992a, b, 1993, and 1995). The leachability and/or diffusion of radionuclide species must be measured to assess the long-term performance of waste grouts when contacted with vadose-zone pore water or groundwater. Although significant research has been conducted on the design and performance of cementitious waste forms, the current protocol conducted to assess radionuclide stability within these waste forms has been limited to the Toxicity Characteristic Leaching Procedure, Method 1311 Federal Registry (EPA 1992) and ANSI/ANS-16.1 leach test (ANSI 1986). These tests evaluate the performance under water-saturated conditions and do not evaluate the performance of cementitious waste forms within the context of waste repositories which are located within water-deficient vadose zones. Moreover, these tests assess only the diffusion of radionuclides from concrete waste forms and neglect evaluating the mechanisms of retention, stability of the waste form, and formation of secondary phases during weathering, which may serve as long-term secondary hosts for immobilization of radionuclides. The results of recent investigations conducted under arid and semi-arid conditions (Al-Khayat et al. 2002; Garrabrants et al. 2002; Garrabrants and Kosson 2003; Garrabrants et al. 2004; Gervais et al. 2004; Sanchez et al. 2002; Sanchez et al. 2003) provide valuable information suggesting structural and chemical changes to concrete waste forms which may affect contaminant containm

Mattigod, Shas V.; Wellman, Dawn M.; Bovaird, Chase C.; Parker, Kent E.; Clayton, Libby N.; Powers, Laura; Recknagle, Kurtis P.; Wood, Marcus I.

2011-08-31T23:59:59.000Z

171

Radionuclide air emissions report for the Hanford site calendar year 1995  

SciTech Connect

This report documents radionuclide air emissions from the Hanford Site in 1995, and the resulting effective dose equivalent (FDE) to the maximally exposed member of the public, referred to as the `MEI.` The report has been prepared and will be submitted in accordance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, `National Emissions Standards for Hazardous Air Pollutants,` Subpart H, `National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.` This report has also been prepared for and will be submitted in accordance with the reporting requirements of the Washington Administrative Code Chapter 246-247, `Radiation Protection-Air Emissions.`

Gleckler, B.P., Westinghouse Hanford

1996-06-26T23:59:59.000Z

172

Techniques for assessing the performance of in situ bioreduction and immobilization of metals and radionuclides in contaminated subsurface environments  

E-Print Network (OSTI)

Immobilization of Metals and Radionuclides in Contaminatedsubsurface metals and radionuclides. Research within DOE’stoxic metals and radionuclides (e.g. Cr, U, Tc, Co) into a

2004-01-01T23:59:59.000Z

173

Radionuclide Air Emissions Report for the Hanford Site Calendar year 1998  

SciTech Connect

This report documents radionuclide air emissions from the Hanford Site in I998 and the resulting effective dose equivalent to the maximally exposed individual (MEI) member of the public. The report has been prepared in accordance with the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (40 CFR SI), Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities,'' and with the Washington Administrative Code Chapter 246-247, Radiation Protection--Air Emissions. The federal regulations in 40 CFR 61, Subpart H; require the measurement and reporting of radionuclides emitted from Department of Energy facilities and the resulting offsite dose from those emissions. A standard of 10 mrem/yr effective dose equivalent (EDE) is imposed on them. The EDE to the MEI due to routine emissions in 1998 from Hanford Site point sources was 1.3 E-02 mrem (1.3 E-04 mSv), which is 0.13 percent of the federal standard. Chapter 246-247 of the Washington Administrative Code (WAC) requires the reporting of radionuclide emissions from all Department of Energy Hanford Site sources. The state has adopted into these regulations the 40 CFR 61 standard of 10 mrem/yr EDE. The EDE to the MEI attributable to diffuse and fugitive radionuclide air emissions from the Hanford Site in 1998 was 2.5 E-02 mrem (2.5 E-04 mSv). This dose added to the dose from point sources gives a total for all sources of 3.8 E-02 mrem/yr (3.8 E-04 mSv) EDE, which is 0.38 percent of the 10 mrem/yr standard. An unplanned release on August 26, 1998, in the 300 Area of the Hanford Site resulted in a potential dose of 4.1 E-02 mrem to a hypothetical individual at the nearest point of public access to that area. This hypothetical individual was not the MEI since the wind direction on the day of the release was away from the MEI residence. The potential dose from the unplanned event was similar in magnitude to that from routine releases during 1998. Were the release from this unplanned event combined with routine releases, the total dose would be less than 1 percent ofthe 10 mrem/yr standard.

DIEDIKER, L.P.

1999-06-15T23:59:59.000Z

174

Transuranic radionuclides dispersed into the aquatic environment, a bibliography  

Science Conference Proceedings (OSTI)

The purpose of this project was to compile a bibliography of references containing environmental transuranic radionuclide data. Our intent was to identify those parameters affecting transuranic radionuclide transport that may be generic and those that may be dependent on chemical form and/or environmental conditions (i.e., site specific) in terrestrial, aquatic and atmospheric environments An understanding of the unique characteristics and similarities between source terms and environmental conditions relative to transuranic radionuclide transport and cycling will provide the ability to assess and predict the long term impact on man and the environment. An additional goal of our literature review, was to extract the ranges of environmental transuranic radionuclide data from the identified references for inclusion in a data base. Related to source term, these ranges of data can be used to calculate the dose to man from the radionuclides, and to perform uncertainty analyses on these dose assessments. On the basis of our reviews, we have arbitrarily outlined five general source terms. These are fallout, fuel cycle waste, accidents, disposal sites and resuspension. Resuspension of the transuranic radionuclides is a unique source term, in that the radionuclides can originate from any of the other source terms. If these transuranic radionuclides become resuspended into the air, they then become important as a source of inhaled radionuclides.

Noshkin, V.E.; Stoker, A.C.; Wong, Kai M. [and others

1994-04-01T23:59:59.000Z

175

Airborne remote sensing of estuarine intertidal radionuclide concentrations.  

E-Print Network (OSTI)

??The ability to map industrial discharges through remote sensing provides a powerful tool in environmental monitoring. Radionuclide effluents have been discharged, under authorization, into the… (more)

Rainey, Michael Patrick

1999-01-01T23:59:59.000Z

176

VANESA: a mechanistic model of radionuclide release and aerosol generation during core debris interactions with concrete  

Science Conference Proceedings (OSTI)

This document describes a model, called VANESA, of the release of radionuclides and generation of aerosol accompanying reactor core melt interactions with structural concrete. The document also serves as a user's manual for an implementation of the VANESA model as a computer code. The technical bases for the VANESA model are reviewed. Mechanical generation of aerosols as bubbles burst at melt surfaces or as a result of liquid entrainment is considered. A description of these processes based on data for gas-sparged water systems is included in the VANESA model. Some limiting solutions to the problem of the competitive processes of nucleation of particles from vapor, condensation of vapors on surfaces, and coagulation of particles are examined. From these examinations an approximate model of the aerosol particle size produced during core debris interactions with concrete is devised. The attenuation of aerosol emission during core debris/concrete interactions by an overlying water pool is discussed. The document concludes with a description of a computer code implementation of the VANESA model. This implementation of the model was used in recent assessments of the behavior of radionuclides during severe reactor accidents. Comparisons of the predictions of radionuclide release during core debris/concrete interactions obtained with the VANESA model and with older models are presented.

Powers, D.A.; Brockmann, J.E.; Shiver, A.W.

1986-07-01T23:59:59.000Z

177

Radionuclide decay effects on waste glass corrosion and weathering  

Science Conference Proceedings (OSTI)

The release of glass components into solution, including radionuclides, may be influenced by the presence of radiolytically produced nitric acid, carboxylic acid, and transient water dissociation products such as {center_dot}OH and O{sub 2}{sup {minus}}. Under batch test conditions, glass corrosion has been shown to increase up to a maximum of three-to five-fold in irradiated tests relative to nonirradiated tests, while in other studies the presence of radiolytic products has actually decreased glass corrosion rates. Bicarbonate groundwaters will buffer against pH decreases and changes in corrosion rates. Under high surface area-to-solution volume (S/V) conditions, the bicarbonate buffering reservoir may be quickly overwhelmed by radiolytic acids that are concentrated in the thin films of water contacting the samples. Glass reaction rates have been shown to increase up to 10-to-15-fold due to radiation exposure under high S/V conditions. Radiation damage to solid glass materials results in bond damage and atomic displacements. This type of damage has been shown to increase the release rates of glass components up to four-fold during subsequent corrosion tests, although under actual disposal conditions, glass annealing processes may negate the solid radiation damage effects.

Wronkiewicz, D.J.

1993-12-31T23:59:59.000Z

178

Method of separating short half-life radionuclides from a mixture of radionuclides  

DOE Patents (OSTI)

The present invention is a method of removing an impurity of plutonium, lead or a combination thereof from a mixture of radionuclides that contains the impurity and at least one parent radionuclide. The method has the steps of (a) insuring that the mixture is a hydrochloric acid mixture; (b) oxidizing the acidic mixture and specifically oxidizing the impurity to its highest oxidation state; and (c) passing the oxidized mixture through a chloride form anion exchange column whereupon the oxidized impurity absorbs to the chloride form anion exchange column and the 22.sup.9 Th or 2.sup.27 Ac "cow" radionuclide passes through the chloride form anion exchange column. The plutonium is removed for the purpose of obtaining other alpha emitting radionuclides in a highly purified form suitable for medical therapy. In addition to plutonium; lead, iron, cobalt, copper, uranium, and other metallic cations that form chloride anionic complexes that may be present in the mixture; are removed from the mixture on the chloride form anion exchange column.

Bray, Lane A. (Richland, WA); Ryan, Jack L. (West Richland, WA)

1999-01-01T23:59:59.000Z

179

Method of separating short half-life radionuclides from a mixture of radionuclides  

DOE Patents (OSTI)

The present invention is a method of removing an impurity of plutonium, lead or a combination thereof from a mixture of radionuclides that contains the impurity and at least one parent radionuclide. The method has the steps of (a) insuring that the mixture is a hydrochloric acid mixture; (b) oxidizing the acidic mixture and specifically oxidizing the impurity to its highest oxidation state; and (c) passing the oxidized mixture through a chloride form anion exchange column whereupon the oxidized impurity absorbs to the chloride form anion exchange column and the {sup 229}Th or {sup 227}Ac ``cow`` radionuclide passes through the chloride form anion exchange column. The plutonium is removed for the purpose of obtaining other alpha emitting radionuclides in a highly purified form suitable for medical therapy. In addition to plutonium, lead, iron, cobalt, copper, uranium, and other metallic cations that form chloride anionic complexes that may be present in the mixture are removed from the mixture on the chloride form anion exchange column. 8 figs.

Bray, L.A.; Ryan, J.L.

1999-03-23T23:59:59.000Z

180

Wastewater Regulations for National Pollutant Discharge Elimination...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

this regulation. This effectively exempts natural gas extraction using hydraulic fracturing from the regulation. Importantly, water, gas and other materials injected into a...

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Radionuclide Partitioning in an Underground Nuclear Test Cavity  

SciTech Connect

In 2004, a borehole was drilled into the 1983 Chancellor underground nuclear test cavity to investigate the distribution of radionuclides within the cavity. Sidewall core samples were collected from a range of depths within the re-entry hole and two sidetrack holes. Upon completion of drilling, casing was installed and a submersible pump was used to collect groundwater samples. Test debris and groundwater samples were analyzed for a variety of radionuclides including the fission products {sup 99}Tc, {sup 125}Sb, {sup 129}I, {sup 137}Cs, and {sup 155}Eu, the activation products {sup 60}Co, {sup 152}Eu, and {sup 154}Eu, and the actinides U, Pu, and Am. In addition, the physical and bulk chemical properties of the test debris were characterized using Scanning Electron Microscopy (SEM) and Electron Microprobe measurements. Analytical results were used to evaluate the partitioning of radionuclides between the melt glass, rubble, and groundwater phases in the Chancellor test cavity. Three comparative approaches were used to calculate partitioning values, though each method could not be applied to every nuclide. These approaches are based on: (1) the average Area 19 inventory from Bowen et al. (2001); (2) melt glass, rubble, and groundwater mass estimates from Zhao et al. (2008); and (3) fission product mass yield data from England and Rider (1994). The U and Pu analyses of the test debris are classified and partitioning estimates for these elements were calculated directly from the classified Miller et al. (2002) inventory for the Chancellor test. The partitioning results from this study were compared to partitioning data that were previously published by the IAEA (1998). Predictions of radionuclide distributions from the two studies are in agreement for a majority of the nuclides under consideration. Substantial differences were noted in the partitioning values for {sup 99}Tc, {sup 125}Sb, {sup 129}I, and uranium. These differences are attributable to two factors: chemical volatility effects that occur during the initial plasma condensation, and groundwater remobilization that occurs over a much longer time frame. Fission product partitioning is very sensitive to the early cooling history of the test cavity because the decay of short-lived (t{sub 1/2} < 1 hour) fission-chain precursors occurs on the same time scale as melt glass condensation. Fission product chains that include both volatile and refractory elements, like the mass 99, 125, and 129 chains, can show large variations in partitioning behavior depending on the cooling history of the cavity. Uranium exhibits similar behavior, though the chemical processes are poorly understood. The water temperature within the Chancellor cavity remains elevated (75 C) more than two decades after the test. Under hydrothermal conditions, high solubility chemical species such as {sup 125}Sb and {sup 129}I are readily dissolved and transported in solution. SEM analyses of melt glass samples show clear evidence of glass dissolution and secondary hydrothermal mineral deposition. Remobilization of {sup 99}Tc is also expected during hydrothermal activity, but moderately reducing conditions within the Chancellor cavity appear to limit the transport of {sup 99}Tc. It is recommended that the results from this study should be used together with the IAEA data to update the range in partitioning values for contaminant transport models at the Nevada National Security Site (formerly known as the Nevada Test Site).

Rose, T P; Hu, Q; Zhao, P; Conrado, C L; Dickerson, R; Eaton, G F; Kersting, A B; Moran, J E; Nimz, G; Powell, B A; Ramon, E C; Ryerson, F J; Williams, R W; Wooddy, P T; Zavarin, M

2009-01-09T23:59:59.000Z

182

Alabama State Regulations  

NLE Websites -- All DOE Office Websites (Extended Search)

State Regulations » Alabama State Regulations » Alabama State Regulations: Alabama State of Alabama The State Oil and Gas Board of Alabama, under the direction of the State Geologist and Oil and Gas Supervisor, is responsible for the regulation of oil and gas operations. The Board is divided into two administrative regions-north and south. The Board has broad authority in Alabama's oil and gas conservation statutes to promulgate and enforce rules and regulations to ensure the conservation and proper development of Alabama's petroleum resources. A major duty of the Board is to prevent pollution of fresh water supplies by oil, gas, salt water, or other contaminants resulting from oil and gas operations. The Alabama Department of Environmental Management (ADEM) administers the major federal environmental protection laws through regulations governing air pollution, water quality and supply, solid and hazardous waste management.

183

THE SUPERPOSITION SOLUTION OF THE TRANSPORT OF A RADIONUCLIDE CHAIN THROUGH A SORBING MEDIUM  

E-Print Network (OSTI)

of the Transport of a Radionuclide Chain Through a SorbingRelease of Decaying Radionuclides Through Sorbing Media,"of the Trans- port of a Radionuclide Chain Through a Sorbing

Foglia, M.

2013-01-01T23:59:59.000Z

184

Pacific Northwest National Laboratory Facility Radionuclide Emissions Units and Sampling Systems  

SciTech Connect

Battelle-Pacific Northwest Division operates numerous research and development (R and D) laboratories in Richland, WA, including those associated with Pacific Northwest National Laboratory (PNNL) on the U.S. Department of Energy (DOE)'s Hanford Site and PNNL Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all emission units that have the potential for radionuclide air emissions. Potential emissions are assessed annually by PNNL staff members. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission unit system performance, operation, and design information. For sampled systems, a description of the buildings, exhaust units, control technologies, and sample extraction details is provided for each registered emission unit. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided. Deregistered emission unit details are provided as necessary for up to 5 years post closure.

Barnett, J. M.; Brown, Jason H.; Walker, Brian A.

2012-04-01T23:59:59.000Z

185

Pacific Northwest National Laboratory Site Radionuclide Air Emissions Report for Calendar Year 2012  

SciTech Connect

This report documents radionuclide air emissions that result in the highest effective dose equivalent (EDE) to a member of the public, referred to as the maximally exposed individual (MEI). The report has been prepared in compliance with the Code of Federal Regulations (CFR), Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (NESHAP), Subpart H, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities and Washington Administrative Code (WAC) Chapter 246-247, Radiation Protection Air Emissions. The dose to the PNNL Site MEI due to routine major and minor point source emissions in 2012 from PNNL Site sources is 9E-06 mrem (9E-08 mSv) EDE. The dose from fugitive emissions (i.e., unmonitored sources) is 1E-7 mrem (1E-9 mSv) EDE. The dose from radon emissions is 2E-6 mrem (2E-08 mSv) EDE. No nonroutine emissions occurred in 2012. The total radiological dose for 2012 to the MEI from all PNNL Site radionuclide emissions, including fugitive emissions and radon, is 1E-5 mrem (1E-7 mSv) EDE, or 100,000 times smaller than the federal and state standard of 10 mrem/yr, to which the PNNL Site is in compliance.

Snyder, Sandra F.; Barnett, J. M.; Bisping, Lynn E.

2013-06-06T23:59:59.000Z

186

Pacific Northwest National Laboratory Site Radionuclide Air Emissions Report for Calendar Year 2011  

SciTech Connect

This report documents radionuclide air emissions that result in the highest effective dose equivalent (EDE) to a member of the public, referred to as the maximally exposed individual (MEI). The report has been prepared in compliance with the Code of Federal Regulations (CFR), Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (NESHAP), Subpart H, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities and Washington Administrative Code (WAC) Chapter 246-247, Radiation Protection Air Emissions. The EDE to the PNNL Site MEI due to routine emissions in 2011 from PNNL Site sources was 1.7E 05 mrem (1.7E-7 mSv) EDE. No nonroutine emissions occurred in 2011. The total radiological dose for 2011 to the MEI from all PNNL Site radionuclide emissions was more than 10,000 times smaller than the federal and state standard of 10 mrem/yr, to which the PNNL Site is in compliance.

Snyder, Sandra F.; Barnett, J. M.; Bisping, Lynn E.

2012-06-12T23:59:59.000Z

187

Estimation of Radionuclide Content in Contaminated Laundry  

SciTech Connect

Radioactively contaminated laundry is normally sent off site for processing. Laundry is defined as radiologically contaminated anti-cs and respirators. This laundry is shipped as "limited quantity," in accordance with 49CFR173.421. This requires that 95% of the radionuclides shipped are characterized and quantified. In addition, the total quantity must be 10(-3) below the A2 limits specified in 49CFR173. In any facility evaluated, the most conservative (highest activity) waste stream was used as the source term. If a new waste stream is established for a facility, its normalized activity should be compared to the evaluated waste stream to ensure the limits are not exceeded. This article documents a method used for estimating the radionuclide content in contaminated laundry. The maximum values were compared to 49CFR173. Itwas determined that if the contaminated laundry/respirators are shipped in an Interstate Nuclear Services (INS), L-59, limited quantity shipping container and the highest contact radiation level on any side, as measured with an ion chamber, does not exceed 0.5 mR h(-1), the container complies with the requirements of 49CFR173 and could be shipped "limited quantity" from any of the facilities evaluated.

Schrader, Bradley J

2001-08-01T23:59:59.000Z

188

Quantitative Modeling of Cerenkov Light Production Efficiency from Medical Radionuclides  

E-Print Network (OSTI)

Quantitative Modeling of Cerenkov Light Production Efficiency from Medical Radionuclides Bradley J There has been recent and growing interest in applying Cerenkov radiation (CR) for biological applications) Quantitative Modeling of Cerenkov Light Production Efficiency from Medical Radionuclides. PLoS ONE 7(2): e31402

Hielscher, Andreas

189

Assessment of hydrologic transport of radionuclides from the Gasbuggy underground nuclear test site, New Mexico  

SciTech Connect

The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Gasbuggy site in northwestern New Mexico was the location of an underground detonation of a 29-kiloton nuclear device in 1967. The test took place in the Lewis Shale, approximately 182 m below the Ojo Alamo Sandstone, which is the aquifer closest to the detonation horizon. The conservative assumption was made that tritium was injected from the blast-created cavity into the Ojo Alamo Sandstone by the force of the explosion, via fractures created by the shot. Model results suggest that if radionuclides produced by the shot entered the Ojo Alamo, they are most likely contained within the area currently administered by DOE. The transport calculations are most sensitive to changes in the mean groundwater velocity, followed by the variance in hydraulic conductivity, the correlation scale of hydraulic conductivity, the transverse hydrodynamic dispersion coefficient, and uncertainty in the source size. This modeling was performed to investigate how the uncertainty in various physical parameters affects calculations of radionuclide transport at the Gasbuggy site, and to serve as a starting point for discussion regarding further investigation at the site; it was not intended to be a definitive simulation of migration pathways or radionuclide concentration values.

Earman, S.; Chapman, J.; Andricevic, R.

1996-09-01T23:59:59.000Z

190

ORISE: Dose Coefficients for Intakes of Radionuclides via Contaminated  

NLE Websites -- All DOE Office Websites (Extended Search)

Dose Coefficients for Intakes of Radionuclides via Contaminated Wounds Dose Coefficients for Intakes of Radionuclides via Contaminated Wounds Dose coefficients for 38 radionuclides based on NCRP Wound Model and ICRP biokinetic models This report is intended to assist health physics and medical staff in more rapidly assessing the potential dosimetric consequences of a contaminated wound. The National Council on Radiation Protection and Measurements Wound Model describing the retention of selected radionuclides at the site of a contaminated wound and their uptake into the transfer compartment has been combined with the International Commission on Radiological Protection element-specific systemic models for those radionuclides to derive dose coefficients for intakes via contaminated wounds. Examples are also provided on using the dose coefficients to generate derived reference

191

The gamma-ray lines of radionuclides, ordered by atomic and mass ...  

Science Conference Proceedings (OSTI)

This table contains a complete list of all -/-emitting radionuclides and of all of their .rlines. Additionally it ... The radionuclide data are supplemented by data ...

192

Underground Injection Control Regulations (Kansas)  

Energy.gov (U.S. Department of Energy (DOE))

This article prohibits injection of hazardous or radioactive wastes into or above an underground source of drinking water, establishes permit conditions and states regulations for design,...

193

Chapter 10 Water Quality Standards (Kentucky)  

Energy.gov (U.S. Department of Energy (DOE))

This administrative regulation establishes procedures to protect the surface waters of the Commonwealth, and thus protect water resources. It states the designated uses of surface water and...

194

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions, Calendar Year 2010  

SciTech Connect

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office operates the Nevada National Security Site (NNSS, formerly the Nevada Test Site) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NNSS. After nuclear testing ended in 1992, NNSS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations [CFR] Part 61 Subpart H) (CFR, 2010a) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as those from the damaged Fukushima nuclear power plant in Japan. Because this report is intended to discuss radioactive air emissions during calendar year 2010, data on radionuclides in air from the 2011 Fukushima nuclear power plant releases are not presented but will be included in the report for calendar year 2011. The NNSS demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations (U.S. Environmental Protection Agency [EPA] and DOE, 1995). This method was approved by the EPA for use on the NNSS in 2001(EPA, 2001a) and has been the sole method used since 2005. Six locations on the NNSS have been established to act as critical receptor locations to demonstrate compliance with the NESHAP limit. These locations are actually pseudo-critical receptor stations, because no member of the public actually resides at these onsite locations. Compliance is demonstrated if the measured annual average concentration is less than the NESHAP Concentration Levels (CLs) for Environmental Compliance listed in 40 CFR 61, Appendix E, Table 2 (CFR, 2010a). For multiple radionuclides, compliance is demonstrated when the sum of the fractions (determined by dividing each radionuclide's concentration by its CL and then adding the fractions together) is less than 1.0. In 2010, the potential dose from radiological emissions to air, resulting from both current and past NNSS activities, at onsite compliance monitoring stations was well below the 10 mrem/yr dose limit. Air sampling data collected at all air monitoring stations had average concentrations of radioactivity that were a fraction of the CL values. Concentrations ranged from less than 1 percent to a maximum of 17 percent of the allowed NESHAP limit. Because the nearest member of the public resides about 20 kilometers from potential release points on the NNSS, dose to the public would be only a small fraction of that measured on the NNSS. The potential dose to the public from NLVF emissions was also very low at 0.000032 mrem/yr, more than 300,000 times lower than the 10 mrem/yr limit.

NSTec Ecological and Environmental Monitoring

2011-06-30T23:59:59.000Z

195

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions, Calendar Year 2011  

SciTech Connect

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office operates the Nevada National Security Site (NNSS) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NNSS. After nuclear testing ended in 1992, NNSS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of legacy-related tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations [CFR] Part 61 Subpart H) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as the damaged Fukushima nuclear power plant in Japan. Radionuclides from the Fukushima nuclear power plant were detected at the NNSS in March 2011 and are discussed further in Section III. The NNSS demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations. This method was approved by the EPA for use on the NNSS in 2001 and has been the sole method used since 2005. Six locations on the NNSS have been established to act as critical receptor locations to demonstrate compliance with the NESHAP limit. These locations are actually pseudo-critical receptor stations, because no member of the public actually resides at these onsite locations. Compliance is demonstrated if the measured annual average concentration is less than the NESHAP Concentration Levels (CLs) for Environmental Compliance listed in 40 CFR 61, Appendix E, Table 2. For multiple radionuclides, compliance is demonstrated when the sum of the fractions (determined by dividing each radionuclide's concentration by its CL and then adding the fractions together) is less than 1.0. In 2011, the potential dose from radiological emissions to air, resulting from both current and past NNSS activities, at onsite compliance monitoring stations was well below the 10 mrem/yr dose limit. Air sampling data collected at all air monitoring stations had average concentrations of radioactivity that were a fraction of the CL values. Concentrations ranged from less than 1% to a maximum of 12.2% of the allowed NESHAP limit. Because the nearest member of the public resides about 20 kilometers from potential release points on the NNSS, dose to the public would be only a small fraction of the value measured on the NNSS. The potential dose to the public from NLVF emissions was also very low at 0.000024 mrem/yr, more than 400,000 times lower than the 10 mrem/yr limit.

NSTec Ecological and Environmental Monitoring

2012-06-19T23:59:59.000Z

196

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions Calendar Year 2012  

SciTech Connect

The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) operates the Nevada National Security Site (NNSS) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NNSS. After nuclear testing ended in 1992, NNSS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of legacy-related tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations [CFR] Part 61 Subpart H) (CFR 2010a) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as the damaged Fukushima nuclear power plant in Japan in 2011. NNSA/NFO demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations on the NNSS (U.S. Environmental Protection Agency [EPA] and DOE 1995). This method was approved by the EPA for use on the NNSS in 2001 (EPA 2001a) and has been the sole method used since 2005. Six locations on the NNSS have been established to act as critical receptor locations to demonstrate compliance with the NESHAP limit. These locations are actually pseudo-critical receptor stations, because no member of the public actually resides at these onsite locations. Compliance is demonstrated if the measured annual average concentration is less than the NESHAP Concentration Levels (CLs) for Environmental Compliance listed in 40 CFR 61, Appendix E, Table 2 (CFR 2010a). For multiple radionuclides, compliance is demonstrated when the sum of the fractions (determined by dividing each radionuclide’s concentration by its CL and then adding the fractions together) is less than 1.0. In 2012, the potential dose from radiological emissions to air, resulting from both current and past NNSS activities, was well below the 10 mrem/yr dose limit. Air sampling data collected at all air monitoring stations had average concentrations of radioactivity that were a fraction of the CL values. Concentrations ranged from less than 0.5% to a maximum of 11.1% of the allowed NESHAP limit. Because the nearest member of the public resides about 9 kilometers from potential release points on the NNSS, dose to the public would be only a small fraction of the value measured on the NNSS. The potential dose to the public from NLVF emissions was also very low at 0.000024 mrem/yr, more than 400,000 times lower than the 10 mrem/yr limit.

Warren, R.

2013-06-10T23:59:59.000Z

197

TERMOD 2; an interactive code for analysing intake of radionuclides by man through terrestrial pathways  

E-Print Network (OSTI)

TERMOD 2; an interactive code for analysing intake of radionuclides by man through terrestrial pathways

Zach, R

1978-01-01T23:59:59.000Z

198

Production of Radionuclide Molybdenum 99 in a Distributed and...  

NLE Websites -- All DOE Office Websites (Extended Search)

Production of Radionuclide Molybdenum 99 in a Distributed and In Sit Fashion.---- Inventor(s): Charles Gentile, Adam B. Cohen and George Ascione. This patent application is for the...

199

SRNL RADIONUCLIDE FIELD LYSIMETER EXPERIMENT: BASELINE CONSTRUCTION AND IMPLEMENTATION  

SciTech Connect

The purpose of this document is to compile information regarding experimental design, facility design, construction, radionuclide source preparation, and path forward for the ten year Savannah River National Laboratory (SRNL) Radionuclide Field Lysimeter Experiment at the Savannah River Site (SRS). This is a collaborative effort by researchers at SRNL and Clemson University. The scientific objectives of this study are to: Study long-term radionuclide transport under conditions more representative of vadose zone conditions than laboratory experiments; Provide more realistic quantification of radionuclide transport and geochemistry in the vadose zone, providing better information pertinent to radioactive waste storage solutions than presently exists; Reduce uncertainty and improve justification for geochemical models such as those used in performance assessments and composite analyses.

Roberts, K.; Kaplan, D.; Bagwell, L.; Powell, B.; Almond, P.; Emerson, H.; Hixon, A.; Jablonski, J.; Buchanan, C.; Waterhouse, T.

2012-10-17T23:59:59.000Z

200

Natural-Matrix Radionuclide Standard Reference Materials  

Science Conference Proceedings (OSTI)

... out, a water pipe bursts, or temperature ... are irradiated with 60 Co gamma rays to an ... NIST Analysis. Gamma Ray Measurements. NaI Measurements. ...

2010-07-21T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Natural-Matrix Radionuclide Standard Reference Materials  

Science Conference Proceedings (OSTI)

... the electricity goes out, a water pipe bursts, or temperature ... materials are irradiated with 60 Co gamma rays to an ... 5.8.1 Gamma Ray Measurements ...

2010-07-21T23:59:59.000Z

202

Bioremediation of Metals and Radionuclides: What It Is and How It Works (2nd Edition)  

Science Conference Proceedings (OSTI)

This primer is intended for people interested in environmental problems of the U.S. Department of Energy (DOE) and in their potential solutions. It will specifically look at some of the more hazardous metal and radionuclide contaminants found on DOE lands and at the possibilities for using bioremediation technology to clean up these contaminants. The second edition of the primer incorporates recent findings by researchers in DOE's Natural and Accelerated Bioremediation Research (NABIR) Program. Bioremediation is a technology that can be used to reduce, eliminate, or contain hazardous waste. Over the past two decades, it has become widely accepted that microorganisms, and to a lesser extent plants, can transform and degrade many types of contaminants. These transformation and degradation processes vary, depending on the physical-chemical environment, microbial communities, and nature of the contaminant. This technology includes intrinsic bioremediation, which relies on naturally occurring processes, and accelerated bioremediation, which enhances microbial degradation or transformation through the addition of nutrients (biostimulation) or inoculation with microorganisms (bioaugmentation). Over the past few years, interest in bioremediation has increased. It has become clear that many organic contaminants such as hydrocarbon fuels can be degraded to relatively harmless products such as CO{sub 2} (the end result of the degradation process). Waste water managers and scientists have also found that microorganisms can interact with metals and convert them from one chemical form to another. Laboratory tests and ex situ bioremediation applications have shown that microorganisms can change the valence, or oxidation state, of some heavy metals (e.g., chromium and mercury) and radionuclides (e.g., uranium) by using them as electron acceptors. In some cases, the solubility of the altered species decreases and the contaminant is immobilized in situ, i.e., precipitated into an insoluble salt in the sediment. In other cases, the opposite occurs--the solubility of the altered species increases, increasing the mobility of the contaminant and allowing it to be more easily flushed from the environment. Both of these kinds of transformations present opportunities for bioremediation of metals and radionuclides--either to lock them in place, or to accelerate their removal. DOE's goal is to reduce the risk and related exposure to ground water, sediment, and soil contamination at Department of Energy facilities. Subsurface bioremediation of metals and radionuclides at the site of contamination (in situ bioremediation) is not yet in widespread use. However, successful in situ applications of bioremediation to petroleum products and chlorinated solvents provide experience from which scientists can draw. Taken together, the accomplishments in these areas have led scientists and engineers to be optimistic about applying this technology to the mixtures of metals and radionuclides that are found at some of the most contaminated DOE sites. This primer examines some of the basic microbial and chemical processes that are a part of bioremediation, specifically the bioremediation of metals and radionuclides. The primer is divided into six sections, with the information in each building on that of the previous. The sections include features that highlight topics of interest and provide background information on specific biological and chemical processes and reactions. The first section briefly examines the scope of the contamination problem at DOE facilities. The second section gives a summary of some of the most commonly used bioremediation technologies, including successful in situ and ex situ techniques. The third discusses chemical and physical properties of metals and radionuclides found in contaminant mixtures at DOE sites, including solubility and the most common oxidation states in which these materials are found. The fourth section is an overview of the basic microbial processes that occur in bioremediation. The fifth section looks at specific in s

Palmisano, Anna; Hazen, Terry

2003-09-30T23:59:59.000Z

203

Natural chelating agents for radionuclide decorporation  

DOE Patents (OSTI)

This invention relates to the production of metal-binding compounds useful for the therapy of heavy metal poisoning, for biological mining and for decorporation of radionuclides. The present invention deals with an orderly and effective method of producing new therapeutically effective chelating agents. This method uses challenge biosynthesis for the production of chelating agents that are specific for a particular metal. In this approach, the desired chelating agents are prepared from microorganisms challenged by the metal that the chelating agent is designed to detoxify. This challenge induces the formation of specific or highly selective chelating agents. The present invention involves the use of the challenge biosynthetic method to produce new complexing/chelating agents that are therapeutically useful to detoxify uranium, plutonium, thorium and other toxic metals. The Pseudomonas aeruginosa family of organisms is the referred family of microorganisms to be used in the present invention to produce the new chelating agent because this family is known to elaborate strains resistant to toxic metals.

Premuzic, E.T.

1985-06-11T23:59:59.000Z

204

A rugged continuous air monitor for sampling radionuclides  

E-Print Network (OSTI)

A new rugged continuous air monitor (CAM) for sampling radionuclide has been developed. The sampler was designed for analyzing aerosols from occupied environments of laboratories and samples extracted from stacks and ducts. Experiments were conducted to characterize the collection efficiency of the aerosol sampler system and to characterize the uniformity of particulate deposition on the filter surface as affected by variations in particle size and sampler flow rates. An experimental parametric analysis was conducted to determine the best internal geometric flow configuration, in order to achieve optimum aerosol collection. The results showed that at a flow rate of 56.6 L/min, 90% of 10 []m aerodynamic diameter (AD) aerosol particles penetrated through the sampler. The 10% loss was attributed to particle impaction at the location where the aerosol stream is turned from the vertical direction and then enters a 4 mm gap between a sampler filter and a planar detector, both of which are horizontally oriented. The cut point for the sampler was 20 []m AD. Uniformity of aerosol collection on the filter, as characterized by the coefficient of variation of the areal density deposits, was less than 10% for 10 []m AD aerosol particles. The sampler sealing integrity with respect to air leaks was tested by placing the sampler in a pressurized container and operating the sampler with the pressure in the container higher than that in the sampler for in-leakage, and with the pressure in the container less than that in the sampler for out-leakage. The pressure inside the container did not exceed 10 inches of water. For in-leakage tests, sulfur hexafluoride (SF?) was diluted with air and released into the container, external to the sampler. The ratio of the SF? concentration in the sampler to the SF? concentration in the container was calculated to characterize the integrity of the sampler system. For pressure differences of 5 and 10 inches of water, the in-leakage was 0.03% and 0.02%, respectively. The same procedure was repeated for out-leakage except that the diluted SF? was released into the sampler. The leakage results for this procedure were 0.04% and 0.02% for pressure differences of 5 and 10 inches of water, respectively.

Martinez, Joseph Thaddeus

2002-01-01T23:59:59.000Z

205

Unclassified Source Term and Radionuclide Data for Corrective Action Unit 97: Yucca Flat/Climax Mine, Nevada Test Site, Nevada, Revision 1  

Science Conference Proceedings (OSTI)

This report documents the evaluation of the information and data available on the unclassified source term and radionuclide contamination for CAU 97: Yucca Flat/Climax Mine. The total residual inventory of radionuclides associated with one or more tests is known as the radiologic source term (RST). The RST is comprised of radionuclides in water, glass, or other phases or mineralogic forms. The hydrologic source term (HST) of an underground nuclear test is the portion of the total RST that is released into the groundwater over time following the test. In this report, the HST represents radionuclide release some time after the explosion and does not include the rapidly evolving mechanical, thermal, and chemical processes during the explosion. The CAU 97: Yucca Flat/Climax Mine has many more detonations and a wider variety of settings to consider compared to other CAUs. For instance, the source term analysis and evaluation performed for CAUs 101 and 102: Central and Western Pahute Mesa and CAU 98: Frenchman Flat did not consider vadose zone attenuation because many detonations were located near or below the water table. However, the large number of Yucca Flat/Climax Mine tests and the location of many tests above the water table warrant a more robust analysis of the unsaturated zone.

Peter Martian

2009-05-01T23:59:59.000Z

206

REPORTABLE RADIONUCLIDES IN DWPF SLUDGE BATCH 7A (MACROBATCH 8)  

Science Conference Proceedings (OSTI)

The Waste Acceptance Product Specifications (WAPS) 1.2 require that the waste producer 'shall report the curie inventory of radionuclides that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115.' As part of the strategy to meet WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type all radionuclides that have half-lives longer than 10 years and contribute greater than 0.01 percent of the total curie inventory from the time of production through the 1100 year period from 2015 through 3115. The initial list of radionuclides to be reported is based on the design-basis glass identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report. However, it is required that the list be expanded if other radionuclides with half-lives greater than 10 years are identified that meet the 'greater than 0.01% of the curie inventory' criterion. Specification 1.6 of the WAPS, International Atomic Energy Agency Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, and U-238; and Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete list of reportable radionuclides must also include these sets of U and Pu isotopes - and the U and Pu isotopic mass distributions must be identified. The DWPF receives HLW sludge slurry from Savannah River Site (SRS) Tank 40. For Sludge Batch 7a (SB7a), the waste in Tank 40 contained a blend of the heel from Sludge Batch 6 (SB6) and the Sludge Batch 7 (SB7) material transferred to Tank 40 from Tank 51. This sludge blend is also referred to as Macrobatch 8. Laboratory analyses of a Tank 40 sludge sample were performed to quantify the concentrations of pertinent radionuclides in the SB7a waste. Subsequently, radiological decay and in-growth were calculated over the time period from 2015 to 3115. This provided a basis for characterizing the radionuclide content of SB7a over time and for identifying the 'reportable radionuclides.' Details of the characterization methodology and the analytical results are the focus of this report. This work was performed at the request of the Waste Solidification Engineering Department of Savannah River Remediation, initiated via Technical Task Request (TTR) HLW-DWPF-TTR-2010-0031. A minor revision in the reporting requirements was requested via a subsequent email communication. The work was conducted in accordance with the protocols identified in Task Technical and Quality Assurance Plan SRNL-RP-2010-01218 and Analytical Study Plan SRNL-RP-2010-01219. All of the raw data related to this scope have been recorded in laboratory notebook SRNL-NB-2011-00061. The overall goal of this task was to characterize the radionuclide content of the SB7a waste sufficiently to meet the WAPS and DWPF reporting requirements. The specific objectives were: (1) Quantify the current concentrations of all radionuclides impacting (or potentially-impacting) the total curie content between calendar years 2011 and 3115. Also quantify the current concentrations of other radionuclides specifically requested in the TTR or required by the WAPS. (2) Calculate future concentrations of decayed and in-grown radionuclides impacting the total curie content between calendar years 2015 and 3115; (3) Identify as 'reportable' all radionuclides contributing {ge} 0.01% of the total curie content from 2015 to 3115 and having half-lives {ge} 10 years.

Reboul, S.; Diprete, D.; Click, D.; Bannochie, C.

2011-12-20T23:59:59.000Z

207

Drinking Water Standards  

E-Print Network (OSTI)

This publication explains the federal safety standards for drinking water provided by public water supply systems. It discusses the legal requirements for public water supplies, the maximum level allowed for contaminants in the water, and the potential health effects of each contaminant regulated. People who use water from private sources such as wells can also use these standards as a guide in checking whether their water is safe.

Dozier, Monty; McFarland, Mark L.

2006-04-26T23:59:59.000Z

208

Air Pollution Control Regulations: No. 13 - Particulate Emissions...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Pollution Control Regulations: No. 13 - Particulate Emissions from Fossil Fuel Fired Steam or Hot Water Generating Units (Rhode Island) Air Pollution Control Regulations: No. 13...

209

Experimental and Modeling Investigation of Radionuclide Interaction and  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Experimental and Modeling Investigation of Radionuclide Interaction Experimental and Modeling Investigation of Radionuclide Interaction and Transport in Representative Geologic Media Experimental and Modeling Investigation of Radionuclide Interaction and Transport in Representative Geologic Media The natural system is an integral part of a geologic nuclear waste repository; it extends from the disturbed rock zone (DRZ) around a disposal room, created by mechanical, thermal and chemical perturbations due to underground excavation or waste emplacement, to the surrounding geologic media, and out to a specified repository boundary. The natural system evaluation and tool development work supports anticipated future site screening, site selection, site characterization, and site suitability. This work is conducted to reduce uncertainty in natural system performance

210

On the Disposition of Graphite Containing TRISO Particles and the Aqueous Transport of Radionuclides via Heterogeneous Geological Formations  

E-Print Network (OSTI)

9] J. Ahn, "Integrated Radionuclide Transport Model for athe evaluation of the radionuclide transport equation over a2.4 Solubility Data for Radionuclide Inventory. Table 2.5

van den Akker, Bret Patrick

2012-01-01T23:59:59.000Z

211

Environmental Regulators  

NLE Websites -- All DOE Office Websites (Extended Search)

and Reports Brookhaven's Environmental Regulators When it comes to the environment, Brookhaven National Laboratory must comply with the regulations of many local, state and...

212

Radionuclide Concentrations in Terrestrial Vegetation and Soil Samples On and Around the Hanford Site, 1971 Through 2008  

SciTech Connect

Environmental monitoring is conducted on the U.S. Department of Energy (DOE) Hanford Site to comply with DOE Orders and federal and state regulations. Major objectives of the monitoring are to characterize contaminant levels in the environment and to determine site contributions to the contaminant inventory. This report focuses on surface soil and perennial vegetation samples collected between 1971 and 2008 as part of the Pacific Northwest National Laboratory Surface Environmental Surveillance Project performed under contract to DOE. Areas sampled under this program are located on the Hanford Site but outside facility boundaries and on public lands surrounding the Hanford Site. Additional samples were collected during the past 8 years under DOE projects that evaluated parcels of land for radiological release. These data were included because the same sampling methodology and analytical laboratory were used for the projects. The spatial and temporal trends of six radionuclides collected over a 38-year period were evaluated. The radionuclides----cobalt-60, cesium-137, strontium-90, plutonium-238, plutonium-239/240, and uranium (reported either as uranium-238 or total uranium)----were selected because they persist in the environment and are still being monitored routinely and reported in Hanford Site environmental reports. All these radionuclides were associated with plutonium production and waste management of activities occurring on the site. Other sources include fallout from atmospheric testing of nuclear weapons, which ended in 1980, and the Chernobyl explosion in 1986. Uranium is also a natural component of the soil. This assessment of soil and vegetation data provides important information on the distribution of radionuclides in areas adjacent to industrial areas, established perimeter locations and buffer areas, and more offsite nearby and distant locations. The concentrations reflect a tendency for detection of some radionuclides close to where they were utilized onsite, but as one moves to unindustrialized areas on the site, surrounding buffer areas and perimeter location into the more distant sites, concentrations of these radionuclides approach background and cannot be distinguished from fallout activity. More importantly, concentrations in soil and vegetation samples did not exceed environmental benchmark concentrations, and associated exposure to human and ecological receptors were well below levels that are demonstratively hazardous to human health and the environment.

Simmons, Mary Ann; Poston, Ted M.; Fritz, Brad G.; Bisping, Lynn E.

2011-07-29T23:59:59.000Z

213

An Innovative Approach for the Calculation of Exposure Point Concentrations for Large Areas of Surface Radionuclide Contamination  

SciTech Connect

The Department of Energy Rocky Flats site was designated as a wildlife refuge by the Rocky Flats National Wildlife Refuge Act of 2001. Rocky Flats was considered to be one of the most highly contaminated radiological sites in the country. Some portions of the site have low-level radionuclide contamination in surface soils. A site-wide risk and dose assessment to evaluate threats to human health and the environment were performed, so that the site could be released for this land use. The aggressive accelerated action program combined with defensible and innovative risk assessment methods resulted in there being no radionuclides of concern in the final comprehensive risk assessment (DOE 2006). An innovative approach for delineating functional exposure areas and area-weighted exposure point concentration-activities (EPCs) was negotiated with the regulatory agencies in Colorado. This procedure leads to realistic estimates of risk and dose to workers and visitors. This innovative approach to the calculation of EPCs was negotiated with both State and Federal regulators. The value of developing and maintaining good working relationships with regulators responsible for a site can not be overestimated. The building of trust and confidence among responsible parties and regulators is essential for the development and implementation of innovative methods and technologies.

Winchester Chromec, F.; Myers, Jeffrey C. [7800 E. Union Avenue, Denver, Colorado, 801237 (United States)

2008-01-15T23:59:59.000Z

214

Method for image reconstruction of moving radionuclide source distribution  

SciTech Connect

A method for image reconstruction of moving radionuclide distributions. Its particular embodiment is for single photon emission computed tomography (SPECT) imaging of awake animals, though its techniques are general enough to be applied to other moving radionuclide distributions as well. The invention eliminates motion and blurring artifacts for image reconstructions of moving source distributions. This opens new avenues in the area of small animal brain imaging with radiotracers, which can now be performed without the perturbing influences of anesthesia or physical restraint on the biological system.

Stolin, Alexander V.; McKisson, John E.; Lee, Seung Joon; Smith, Mark Frederick

2012-12-18T23:59:59.000Z

215

Radionuclide Generator ^{111}In\\to^{111m}Cd  

E-Print Network (OSTI)

Radionuclide generator ^{111}In\\to^{111m}Cd with chemical yield > 95 % and contamination of the ^{111m}Cd by parent isotope (^{111}In) less than 0.6 % (of ^{111m}Cd activity) is developed. Extraction chromatography with di-2-ethylhexyl-phosphoric acid as an extragent is used for the radiochemical separation of the parent and the daughter radionuclides. Probability of the electron capture on the isomeric level 396 keV (^{111m}Cd) in the ^{111}In decay process is determinated to be (6.01\\pm 0.14_{stat}\\pm0.18_{syst})\\cdot10^{-5}.

Filossofov, D V; Lebedev, N A; Starodub, G Ya; Novgorodov, A F

2001-01-01T23:59:59.000Z

216

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2001  

Science Conference Proceedings (OSTI)

Assessments were performed to evaluate compliance with the airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAP - U.S. Code of Federal Regulations, Title 40 Part 61, Subpart H) and Washington Administrative Code (WAC) 246-247: Radiation Protection - Air Emissions. In these assessments, potential unabated offsite doses were evaluated for emission locations at facilities owned by the U.S. Department of Energy and operated by Pacific Northwest National Laboratory (PNNL) on the Hanford Site. This report describes the inventory-based methods, and provides the results, for the assessment performed in 2001.

Ballinger, Marcel Y.; Sula, Monte J.; Gervais, Todd L.; Shields, Keith D.; Edwards, Daniel R.

2001-09-28T23:59:59.000Z

217

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2010  

SciTech Connect

Assessments were performed to evaluate compliance with the airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants ([NESHAP]; U.S. Code of Federal Regulations, Title 40, Part 61, Subpart H) and Washington Administrative Code 246-247: Radiation Protection - Air Emissions. In these NESHAP assessments, potential unabated off-site doses were evaluated for emission locations at buildings that are part of the consolidated laboratory campus of the Pacific Northwest National Laboratory. This report describes the inventory-based methods and provides the results for the NESHAP assessment performed in 2010.

Ballinger, Marcel Y.; Gervais, Todd L.; Barnett, J. M.

2011-05-13T23:59:59.000Z

218

Assessment of Unabated Facility Emission Potentials for Evaluating Airborne Radionuclide Monitoring Requirements at Pacific Northwest National Laboratory - 2007  

SciTech Connect

Assessments were performed to evaluate compliance with the airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAP – U.S. Code of Federal Regulations, Title 40, Part 61, Subpart H) and Washington Administrative Code (WAC) 246-247: Radiation Protection – Air Emissions. In these NESHAP assessments, potential unabated offsite doses were evaluated for emission locations at buildings that are part of the consolidated laboratory campus of the Pacific Northwest National Laboratory. This report describes the inventory-based methods and provides the results for the NESHAP assessment performed in 2007.

Ballinger, Marcel Y.; Barfuss, Brad C.; Gervais, Todd L.

2008-01-01T23:59:59.000Z

219

Time-averaged fluxes of lead and fallout radionuclides to sediments in Florida Bay  

E-Print Network (OSTI)

Time-averaged fluxes of lead and fallout radionuclides to sediments in Florida Bay J. A. Robbins,1 between the maximum atmospheric radionuclide fallout and peaks in sediment temporal records of 137 Cs

220

Sources of secondary radionuclide releases from Hanford Operations  

SciTech Connect

This report considers Hanford facilities and operations with the potential to be secondary radionuclide release sources. Facilities that produced radionuclides or processed products of fission reactions and were not covered in previous source term reports are included in this report. The following facilities are described and any potentially significant releases from them are estimated: PUREX (1956--1972, 1983--1988) and REDOX (1952--1967)--campaigns with non-standard feed material (materials other than fuel from single-pass reactors); C PLANT (Hot Semi-Works)--pilot plant and strontium recovery; Z Plant--plutonium finishing; U and UO{sub 3} Plants--uranium recovery; 108 B Plant--tritium extraction; 300 Area Plutonium Recycle Test Reactor (PRTR); 300 Area Low Power Test Reactors; Criticality Accidents; and 400 Area Fast Flux Test Facility (FFTF). The method of analysis was to examine each facility, give a brief description of its purpose and operations, and describe the types of material the facility processed as an indication of the radionuclides it had the potential to release. Where possible, specific radionuclides are estimated and values from the original documents are reported.

Heeb, C.M.; Gydesen, S.P.

1994-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Hydrology and radionuclide migration program 1987 progress report  

SciTech Connect

This report presents results from the Lawrence Livermore National Laboratory's participation in the Hydrology and Radionuclide Migration Program at the Nevada Test Site (NTS) during the fiscal year 1987. The report discussed initial data from a new well (UE20n-1) drilled at the Cheshire site; presents a description of a proposed laboratory study of migration of colloids in fractured media; lists data collected during the drilling and initial sampling of UE20n-1; and describes a tentative proposal for work to be performed in FY88 by Lamont-Doherty Geological Observatory. Groundwater sampled from the new well at the Cheshire site contains tritium concentrations comparable to those measured in previous years from locations above and within the Cheshire cavity. This presence of tritium, as well as several other radionuclides, in a well 100 m away from the cavity region indicates transport of radionuclides, validates a proposed model of the flow path, and provides data on rates of groundwater flow. Previous work at the Cheshire site has shown that radionuclides are transported by colloids through fractured media. However, we have no data that can be used for predictive modeling, and existing theories are not applicable. While physical transport mechanisms of sub-micrometer colloids to defined mineral surfaces are well known, predictions based on well-defined conditions differ from experimental observations by orders of magnitude. The U.C. Berkeley group has designed a laboratory experiment to quantify colloid retention and permeability alteration by the retained colloids.

Marsh, K.V. (comp.)

1991-03-01T23:59:59.000Z

222

Waste site reclamation with recovery of radionuclides and metals  

DOE Patents (OSTI)

A method for decontaminating radionuclides and other toxic metal-contaminate The U.S. government has certain rights in this invention pursuant to Contract Number DE-AC02-76CH00016 between the U.S. Department of Energy and Associated Universities, Inc.

Francis, A.J.; Dodge, C.J.

1994-03-08T23:59:59.000Z

223

Isonitrile radionuclide complexes for labelling and imaging agents  

DOE Patents (OSTI)

A coordination complex of an isonitrile ligand and radionuclide such as Tc, Ru, Co, Pt, Fe, Os, Ir, W, Re, Cr, Mo, Mn, Ni, Rh, Pd, Nb and Ta, is useful as a diagnostic agent for labelling liposomes or vesicles, and selected living cells containing lipid membranes, such as blood clots, myocardial tissue, gall bladder tissue, etc.

Jones, Alun G. (Newton Centre, MA); Davison, Alan (Needham, MA); Abrams, Michael J. (Allston, MA)

1984-06-04T23:59:59.000Z

224

External detection and measurement of inhaled radionuclides using thermoluminescent dosimeters  

E-Print Network (OSTI)

Many radiation detection programs use bio-assays, whole-body counters, or air sampling to estimate internal doses. This study examines the possibility of using a common external thermoluminescent dosimeter (TLD) badge as a device for detecting inhaled radionuclides through radiation those radionuclides emit which escape the body. The three common radionuclides chosen for modeling due to their varying decay modes and use or production in the nuclear industry were Cs-137, U-238, and Sr-90. These three radionuclides were modeled for biological and radiological removal in the dynamic systems modeling program of STELLA II and modeled for TLD dose per organ in the geometry and radiation simulation program of MCNP. The results show that none of the nuclides in the study can be detected at air concentrations below regulatory limits for acute inhalation exposures. To achieve a detectable dose from an 8-hour work exposure, with a 90-day wait until the TLD is read, the airborne concentrations for the inhalation classes that produced the most dose per Bq would be 37.9 kBq/m3, 146 MBq/m3, and 1.67 MBq/m3 for Cs-137, U-238, and Sr-90, respectively.

Prause, Christopher Alvin

2006-12-01T23:59:59.000Z

225

Soil Erosion and Sediment Control Act, Soil and Water Conservation...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Act, Soil and Water Conservation District, and Council on Soil and Water Conservation Regulations (Connecticut) Soil Erosion and Sediment Control Act, Soil and Water Conservation...

226

Health implications of radionuclide levels in cattle raised near U mining and milling facilities in Ambrosia Lake, New Mexico  

SciTech Connect

This study was conducted to determine radionuclide tissue levels in cattle raised near U mining and milling facilities. Ambrosia Lake, New Mexico, has been the site of extensive U mining for 30 y and contains several underground U mines, a processing mill, and two large U tailings piles. Ten cows were purchased from two grazing areas in Ambrosia Lake and ten control animals were purchased from Crownpoint, New Mexico. Muscle, liver, kidney, and bone tissue taken from these animals, and environmental samples, including water, grasses and soil collected from the animals' grazing areas, were analyzed for /sup 238/U, /sup 234/U, /sup 230/Th, /sup 226/Ra, /sup 210/Pb, and /sup 210/Po. Mean radionuclide levels in cattle tissue and environmental samples from Ambrosia Lake were higher in almost every comparison than those found in respective controls. Liver and kidney tissues were particularly elevated in /sup 226/Ra and /sup 210/Po. Radiation dose commitments from eating cattle tissue with these radionuclide concentrations were calculated. We concluded that the health risk to the public from eating exposed cattle is minimal, unless large amounts of this tissue, especially liver and kidney, are ingested.

Lapham, S.C.; Millard, J.B.; Samet, J.M.

1989-03-01T23:59:59.000Z

227

Techniques for assessing the performance of in situ bioreduction and immobilization of metals and radionuclides in contaminated subsurface environments  

Science Conference Proceedings (OSTI)

Department of Energy (DOE) facilities within the weapons complex face a daunting challenge of remediating huge below inventories of legacy radioactive and toxic metal waste. More often than not, the scope of the problem is massive, particularly in the high recharge, humid regions east of the Mississippi river, where the off-site migration of contaminants continues to plague soil water, groundwater, and surface water sources. As of 2002, contaminated sites are closing rapidly and many remediation strategies have chosen to leave contaminants in-place. In situ barriers, surface caps, and bioremediation are often the remedial strategies of chose. By choosing to leave contaminants in-place, we must accept the fact that the contaminants will continue to interact with subsurface and surface media. Contaminant interactions with the geosphere are complex and investigating long term changes and interactive processes is imperative to verifying risks. We must be able to understand the consequences of our action or inaction. The focus of this manuscript is to describe recent technical developments for assessing the performance of in situ bioremediation and immobilization of subsurface metals and radionuclides. Research within DOE's NABIR and EMSP programs has been investigating the possibility of using subsurface microorganisms to convert redox sensitive toxic metals and radionuclides (e.g. Cr, U, Tc, Co) into a less soluble, less mobile forms. Much of the research is motivated by the likelihood that subsurface metal-reducing bacteria can be stimulated to effectively alter the redox state of metals and radionuclides so that they are immobilized in situ for long time periods. The approach is difficult, however, since subsurface media and waste constituents are complex with competing electron acceptors and hydrogeological conditions making biostimulation a challenge. Performance assessment of in situ biostimulation strategies is also difficult and typically requires detailed monitoring of coupled hydrological, geochemical/geophysical, and microbial processes. In the following manuscript we will (1) discuss contaminant fate and transport problems in humid regimes, (2) efforts to immobilize metals and radionuclides in situ via bioremediation, and (3) state-of-the-art techniques for assessing the performance of in situ bioreduction and immobilization of metals and radionuclides. These included (a) in situ solution and solid phase monitoring, (b) in situ and laboratory microbial community analysis, (c) noninvasive geophysical methods, and (d) solid phase speciation via high resolution spectroscopy.

Jardine, P.M.; Watson, D.B.; Blake, D.A.; Beard, L.P.; Brooks, S.C.; Carley, J.M.; Criddle, C.S.; Doll, W.E.; Fields, M.W.; Fendorf, S.E.; Geesey, G.G.; Ginder-Vogel, M.; Hubbard, S.S.; Istok, J.D.; Kelly, S.; Kemner, K.M.; Peacock, A.D.; Spalding, B.P.; White, D.C.; Wolf, A.; Wu, W.; Zhou, J.

2004-11-14T23:59:59.000Z

228

MODEL IMPLEMENTATION TO EVALUATE THE COLLECTIVE FUTURE RADIONUCLIDE RELEASES FROM MULTIPLE FACILITIES AT THE SAVANNAH RIVER SITE  

Science Conference Proceedings (OSTI)

A comprehensive Composite Analysis (CA) has been performed considering 152 sources of residual radioactive material at the Savannah River Site (SRS). As part of the CA a model was developed to perform deterministic base case calculations using the commercial GoldSim software. The model treated transport and decay of radionuclides as they are released at the source location and transported through the source region, vadose zone and aquifer to stream outcrops and from there to the Savannah River. A dose to the public was calculated assuming recreational use of stream water and residential use of river water. The specific results from the GoldSim modeling evaluation conducted as part of the CA indicate that the collective maximum dose resulting from the release of radionuclides from all 152 anticipated SRS End State sources of residual radionuclides demonstrate that maximum exposures expected to occur to any offsite MOP will not approach the 300 uSv/yr (30 mrem/yr) dose constraint, and in fact are currently estimated to be only 10% of this. For each of the POA's evaluated, the highest cumulative dose is realized at the Lower Three Runs POA and is calculated to be 29.7 uSv/yr (2.97 mrem/yr). The major dose contributing radionuclide for all of the POA's, with the exception of Upper Three Runs, was {sup 137}Cs in the contaminated streambed sediments. In Upper Three Runs {sup 237}Np from the H-Area Canyon Building was the major dose contributing radionuclide. The major exposure pathway for the SRS streams (where the Recreational Scenario was evaluated) was by the ingestion of fish. In the Savannah River, where the Residential Scenario was evaluated, ingestion of vegetation was the dominant exposure pathway. The uncertainty evaluation lends added assurance to the conclusion that the 30 mrem/yr dose constraint will not be exceeded, in that even at the 95th Percentile, this performance measure is not expected to be exceeded. It must also be added that these conclusions should be regarded as 'preliminary' since the DOE review process of the SRS CA has not yet been completed.

Hiergesell, R.; Smith, F.; Hamm, L.; Phifer, M.; Swingle, R.

2009-12-15T23:59:59.000Z

229

Rhode Island Pretreatment Regulations (Rhode Island)  

Energy.gov (U.S. Department of Energy (DOE))

These regulations set standards for water pretreatment prior to release to Publicly Owned Treatment Works (POTWs), and require effluent data including the identity, amount, frequency, concentration...

230

LONG-TERM ASSESSMENT OF CRITICAL RADIONUCLIDES AND ASSOCIATED ENVIRONMENTAL MEDIA AT THE SAVANNAH RIVER SITE  

Science Conference Proceedings (OSTI)

During the operational history of the Savannah River Site (SRS), many different radionuclides have been released from site facilities. However, only a relatively small number of the released radionuclides have been significant contributors to doses and risks to the public. At SRS dose and risk assessments indicate tritium oxide in air and surface water, and Cs-137 in fish and deer have been, and continue to be, the critical radionuclides and pathways. In this assessment, indepth statistical analyses of the long-term trends of tritium oxide in atmospheric and surface water releases and Cs-137 concentrations in fish and deer are provided. Correlations also are provided with 1) operational changes and improvements, 2) geopolitical events (Cold War cessation), and 3) recent environmental remediation projects and decommissioning of excess facilities. For example, environmental remediation of the F- and H-Area Seepage Basins and the Solid Waste Disposal Facility have resulted in a measurable impact on the tritium oxide flux to the onsite Fourmile Branch stream. Airborne releases of tritium oxide have been greatly affected by operational improvements and the end of the Cold War in 1991. However, the effects of SRS environmental remediation activities and ongoing tritium operations on tritium concentrations in the environment are measurable and documented in this assessment. Controlled hunts of deer and feral hogs are conducted at SRS for approximately six weeks each year. Before any harvested animal is released to a hunter, SRS personnel perform a field analysis for Cs-137 concentrations to ensure the hunter’s dose does not exceed the SRS administrative game limit of 0.22 millisievert (22 mrem). However, most of the Cs-137 found in SRS onsite deer is not from site operations but is from nuclear weapons testing fallout from the 1950’s and early 1960’s. This legacy source term is trended in the SRS deer, and an assessment of the “effective” half-life of Cs-137 in deer (including the physical decay half-life and the environmental dispersion half-life) is provided. The “creek mouth” fisherman is the next most critical pathway at SRS. On an annual basis, three species of fish (panfish, catfish, and bass) are sampled from the mouths of the five SRS streams. Three composites of up to five fish of each species are analyzed from each sampling location. Long-term trending of the Cs-137 concentrations in fish and the subsequent doses from consumption of SRS fish is provided.

Jannik, T.; Baker, R.; Lee, P.; Eddy, T.; Blount, G.; Whitney, G.

2012-11-06T23:59:59.000Z

231

Long-Term Assessment of Critical Radionuclides and Associated Environmental Media at the Savannah River Site  

SciTech Connect

During the operational history of the Savannah River Site (SRS), many different radionuclides have been released from site facilities. However, only a relatively small number of the released radionuclides have been significant contributors to doses and risks to the public. At SRS dose and risk assessments indicate tritium oxide in air and surface water, and Cs-137 in fish and deer have been, and continue to be, the critical radionuclides and pathways. In this assessment, indepth statistical analyses of the long-term trends of tritium oxide in atmospheric and surface water releases and Cs-137 concentrations in fish and deer are provided. Correlations also are provided with 1) operational changes and improvements, 2) geopolitical events (Cold War cessation), and 3) recent environmental remediation projects and decommissioning of excess facilities. For example, environmental remediation of the F- and H-Area Seepage Basins and the Solid Waste Disposal Facility have resulted in a measurable impact on the tritium oxide flux to the onsite Fourmile Branch stream. Airborne releases of tritium oxide have been greatly affected by operational improvements and the end of the Cold War in 1991. However, the effects of SRS environmental remediation activities and ongoing tritium operations on tritium concentrations in the environment are measurable and documented in this assessment. Controlled hunts of deer and feral hogs are conducted at SRS for approximately six weeks each year. Before any harvested animal is released to a hunter, SRS personnel perform a field analysis for Cs-137 concentrations to ensure the hunter's dose does not exceed the SRS administrative game limit of 0.22 millisievert (22 mrem). However, most of the Cs-137 found in SRS onsite deer is not from site operations but is from nuclear weapons testing fallout from the 1950's and early 1960's. This legacy source term is trended in the SRS deer, and an assessment of the ''effective'' half-life of Cs-137 in deer (including the physical decay half-life and the environmental dispersion half-life) is provided. The ''creek mouth'' fisherman is the next most critical pathway at SRS. On an annual basis, three species of fish (panfish, catfish, and bass) are sampled from the mouths of the five SRS streams. Three composites of up to five fish of each species are analyzed from each sampling location. Long-term trending of the Cs-137 concentrations in fish and the subsequent doses from consumption of SRS fish is provided.

2012-11-06T23:59:59.000Z

232

LONG-TERM COLLOID MOBILIZATION AND COLLOID-FACILITATED TRANSPORT OF RADIONUCLIDES IN A SEMI-ARID VADOSE ZONE  

Science Conference Proceedings (OSTI)

The main purpose of this project was to improve the fundamental mechanistic understanding and quantification of long-term colloid mobilization and colloid-facilitated transport of radionuclides in the vadose zone, with special emphasis on the semi-arid Hanford site. While we focused some of the experiments on hydrogeological and geochemical conditions of the Hanford site, many of our results apply to colloid and colloid-facilitated transport in general. Specific objectives were (1) to determine the mechanisms of colloid mobilization and colloid-facilitated radionuclide transport in undisturbed Hanford sediments under unsaturated flow, (2) to quantify in situ colloid mobilization and colloid-facilitated radionuclidetransport from Hanford sediments under field conditions, and (3) to develop a field-scale conceptual and numerical model for colloid mobilization and transport at the Hanford vadose zone, and use that model to predict long-term colloid and colloid- facilitated radionuclide transport. To achieve these goals and objectives, we have used a combination of experimental, theoretical, and numerical methods at different spatial scales, ranging from microscopic investigationsof single particle attachment and detachment to larger-scale field experiments using outdoor lysimeters at the Hanford site. Microscopic and single particle investigations provided fundamental insight into mechanisms of colloid interactions with the air-water interface. We could show that a moving air water interface (such as a moving water front during infiltration and drainage) is very effective in removing and mobilizing particles from a stationary surface. We further demonstrated that it is particularly the advancing air-water interface which is mainly responsible for colloid mobilization. Forces acting on the colloids calculated from theory corroborated our experimental results, and confirm that the detachment forces (surface tension forces) during the advancing air-water interface movement were stronger than during the receding movement. Theory indicates that, for hydrophilic colloids, the advancing interface movement generally exerts a stronger detachment force than the receding, except when the hysteresis of the colloid-air-water contact angle is small. These results of our study are particularly relevant for colloid mobilization and transport related to three process in the vadose zone at Hanford: (1) water infiltration into sediments during rainfall or snowmelt events, (2) groundwater fluctuations as caused by river stage fluctuations, and (3) steady-state, low-flow recharge in deep vadose zone sediments. Transient water flow, like during infiltration or groundwater level fluctuations, are most conducive for colloid mobilization, but even during steady-state, low-flow recharge, colloids can be mobile, although to a much lesser extent. The results of this project have led to a comprehensive and fundamental understanding of colloid transport and mobilization under unsaturated flow conditions at the Hanford site.

Markus Flury; James B. Harsh; Fred Zhang; Glendon W. Gee; Earl D. Mattson; Peter C. L

2012-08-01T23:59:59.000Z

233

Radionuclide Inventory Distribution Project Data Evaluation and Verification White Paper  

Science Conference Proceedings (OSTI)

Testing of nuclear explosives caused widespread contamination of surface soils on the Nevada Test Site (NTS). Atmospheric tests produced the majority of this contamination. The Radionuclide Inventory and Distribution Program (RIDP) was developed to determine distribution and total inventory of radionuclides in surface soils at the NTS to evaluate areas that may present long-term health hazards. The RIDP achieved this objective with aerial radiological surveys, soil sample results, and in situ gamma spectroscopy. This white paper presents the justification to support the use of RIDP data as a guide for future evaluation and to support closure of Soils Sub-Project sites under the purview of the Federal Facility Agreement and Consent Order. Use of the RIDP data as part of the Data Quality Objective process is expected to provide considerable cost savings and accelerate site closures. The following steps were completed: - Summarize the RIDP data set and evaluate the quality of the data. - Determine the current uses of the RIDP data and cautions associated with its use. - Provide recommendations for enhancing data use through field verification or other methods. The data quality is sufficient to utilize RIDP data during the planning process for site investigation and closure. Project planning activities may include estimating 25-millirem per industrial access year dose rate boundaries, optimizing characterization efforts, projecting final end states, and planning remedial actions. In addition, RIDP data may be used to identify specific radionuclide distributions, and augment other non-radionuclide dose rate data. Finally, the RIDP data can be used to estimate internal and external dose rates. The data quality is sufficient to utilize RIDP data during the planning process for site investigation and closure. Project planning activities may include estimating 25-millirem per industrial access year dose rate boundaries, optimizing characterization efforts, projecting final end states, and planning remedial actions. In addition, RIDP data may be used to identify specific radionuclide distributions, and augment other non-radionuclide dose rate data. Finally, the RIDP data can be used to estimate internal and external dose rates.

NSTec Environmental Restoration

2010-05-17T23:59:59.000Z

234

Water Rights (Texas) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Water Rights (Texas) Water Rights (Texas) Water Rights (Texas) < Back Eligibility Utility Fed. Government Commercial Investor-Owned Utility Industrial Construction Municipal/Public Utility Local Government Rural Electric Cooperative Tribal Government Savings Category Water Buying & Making Electricity Home Weatherization Program Info State Texas Program Type Environmental Regulations Provider Texas Water Development Board The Texas Commission on Environmental Quality regulates the water rights for the state of Texas. Water and state water may be appropriated, stored, or diverted in the state of Texas for beneficial uses in reasonable amounts, with certain conditions. The Commission issues permits and regulations for water rights in Texas. Included in beneficial uses are: agricultural and industrial uses;

235

Life of Plant Activity Estimates for a Nominal 1000 MWe Pressurized Water Reactor and Boiling Water Reactor  

Science Conference Proceedings (OSTI)

Decommissioning nuclear power plant and disposal site managers must understand the radioactive source term of a nuclear power plant to effectively manage disposition of these materials. This study estimates the radioactive source term from nominal 1000 MWe pressurized water and boiling water reactors to support decisions related to radioactive waste storage, processing, and disposal through decommissioning.BackgroundThis study examines the radionuclide ...

2012-12-05T23:59:59.000Z

236

New Mexico State Regulations  

NLE Websites -- All DOE Office Websites (Extended Search)

New Mexico New Mexico State Regulations: New Mexico State of New Mexico The Oil Conservation Division (OCD) in the New Mexico Energy, Minerals and Natural Resources Department regulates oil and gas and geothermal operations in New Mexico. The OCD has the responsibility to gather oil and gas production data, permit new wells, establish pool rules and oil and gas allowables, issue discharge permits, enforce rules and regulations of the division, monitor underground injection wells and ensure that abandoned wells are properly plugged and the land is responsibly restored. Otherwise, the New Mexico Environment Department (NMED) administers the major environmental protection laws. The Water Quality Control Commission (WQCC), which is administratively attached to the NMED, assigns responsibility for administering its regulations to constituent agencies, including the OCD.

237

Virginia State Regulations  

NLE Websites -- All DOE Office Websites (Extended Search)

Virginia Virginia State Regulations: Virginia State of Virginia The Division of Gas and Oil in the Virginia Department of Mines, Minerals and Energy (DMME) regulates the effects of gas and oil operations both on and below the surface. The Virginia Gas and Oil Board is to foster, encourage, and promote the safe and efficient exploration for and development, production, and utilization of gas and oil resources. Otherwise, three regulatory citizen boards are responsible for adopting Virginia 's environmental regulations. The Virginia Department of Environmental Quality (DEQ) staff administers the regulations as approved by the boards. Finally, the U.S. Environmental Protection Agency (EPA) Region 3, through its Water Protection Division, administers Class II underground injection control (UIC) programs in Virginia in direct implementation.

238

URANIUM-SERIES CONSTRAINTS ON RADIONUCLIDE TRANSPORT AND GROUNDWATER FLOW AT NOPAL I URANIUM DEPOSIT, SIERRA PENA BLANCA, MEXICO  

Science Conference Proceedings (OSTI)

Uranium-series data for groundwater samples from the vicinity of the Nopal I uranium ore deposit are used to place constraints on radionuclide transport and hydrologic processes at this site, and also, by analogy, at Yucca Mountain. Decreasing uranium concentrations for wells drilled in 2003 suggest that groundwater flow rates are low (uranium isotopic constraints also suggest that groundwater flow and mixing is limited at this site. The uranium isotopic systematics for water collected in the mine adit are consistent with longer rock-water interaction times and higher uranium dissolution rates at the front of the adit where the deposit is located. Short-lived nuclide data for groundwater wells are used to calculate retardation factors that are on the order of 1,000 for radium and 10,000 to 10,000,000 for lead and polonium. Radium has enhanced mobility in adit water and fractures near the deposit.

S. J. Goldstein, S. Luo, T. L. Ku, and M. T. Murrell

2006-04-01T23:59:59.000Z

239

URANIUM-SERIES CONSTRAINTS ON RADIONUCLIDE TRANSPORT AND GROUNDWATER FLOW AT NOPAL I URANIUM DEPOSIT, SIERRA PENA BLANCA, MEXICO  

SciTech Connect

Uranium-series data for groundwater samples from the vicinity of the Nopal I uranium ore deposit are used to place constraints on radionuclide transport and hydrologic processes at this site, and also, by analogy, at Yucca Mountain. Decreasing uranium concentrations for wells drilled in 2003 suggest that groundwater flow rates are low (< 10 m/yr). Field tests, well productivity, and uranium isotopic constraints also suggest that groundwater flow and mixing is limited at this site. The uranium isotopic systematics for water collected in the mine adit are consistent with longer rock-water interaction times and higher uranium dissolution rates at the front of the adit where the deposit is located. Short-lived nuclide data for groundwater wells are used to calculate retardation factors that are on the order of 1,000 for radium and 10,000 to 10,000,000 for lead and polonium. Radium has enhanced mobility in adit water and fractures near the deposit.

S. J. Goldstein, S. Luo, T. L. Ku, and M. T. Murrell

2006-04-01T23:59:59.000Z

240

Colorado State Regulations  

NLE Websites -- All DOE Office Websites (Extended Search)

Colorado Colorado State Regulations: Colorado State of Colorado The Colorado Oil and Gas Conservation Commission (COGCC), a division of the Department of Natural Resources (DNR), regulates oil and gas activities in Colorado. The COGCC has broad statutory authority with respect to impacts on any air, water, soil, or biological resources resulting from oil and gas operations. The COGCC implements the state ground water standards and classifications as they relate to oil and gas exploration and production (E&P) activities. The COGCC has jurisdiction for all Class II injection wells except those on Indian lands. The COGCC has jurisdiction for the management of all E&P wastes except at commercial disposal facilities. The Colorado Department of Public Health and Environment (CDPHE) administers the environmental protection laws related to air quality, waste discharge to surface water, and commercial disposal facilities.

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241

Progress in evaluation of radionuclide geochemical information developed by DOE high-level nuclear waste repository site projects: report for January-March 1985. Volume 2  

Science Conference Proceedings (OSTI)

Geochemical information relevant to the retention of radionuclides by the Hanford Site (in basalt) and the Yucca Mountain site (in tuff), candidate high-level nuclear waste geologic repositories being developed by US Department of Energy (DOE) projects, is being evaluated by Oak Ridge National Laboratory (ORNL) for the US Nuclear Regulatory Commission (NRC). Our evaluation of the sorption of technetium by basalt/groundwater systems was essentially completed this quarter and the results summarized; we conclude that the experimental methodology and results reported by the DOE for the Hanford Site have not conclusively established that significant retardation of technetium migration may be provided by phases present in the basalts of the Hanford Site. We have shown that sodium boltwoodite is the saturating uranium solid phase in two basalt/groundwater systems. Because thermodynamic data are not available for sodium boltwoodite, calculated solubilities for uranium are erroneous in these systems. Results of radionuclide solubility/speciation calculations, published by the DOE for the Yucca Mountain site, were evaluated this quarter under our geochemical modeling task. We express concerns relative to the inherent limitations of such calculations. Samples of Yucca Mountain tuff and J-13 well water were received for use in our planned radionuclide sorption/solubility experiments. These Yucca Mountain materials will be used to evaluate radionuclide sorption and apparent concentration limit values published by the Nevada Nuclear Waste Storage Investigations (NNWSI) project. 40 refs., 5 figs., 16 tabs.

Kelmers, A.D.; Seeley, F.G.; Arnold, W.D.; Blencoe, J.G.; Meyer, R.E.; Jacobs, G.K.; Whatley, S.K.

1985-09-01T23:59:59.000Z

242

Natural and anthropogenic radionuclides in the marginal seas of Siberia: implications for the fate and removal of pollutants  

E-Print Network (OSTI)

Natural and anthropogenic radionuclides have been widely used to trace the sources and fate of radioactive pollutants in the marine environment. In this study, particle-reactive radionuclides such as ... Ph and 214 Th have been employed for scavenging studies. The inventories of Pu and radiocesium and activity ratios of Pu (such as 238PU/239,24OPu) have been utilized to determine the sources and transport of anthropogenic pollutants. Water soluble tracers such as Ra isotopes and radiocesium have been used to determine the water mass movements as well as residence time of water masses. This will help to define the processes related to estuarine mixing over the continental shelf which control radioactive and other pollutants entering surface waters of the Arctic Ocean. 21OPb and 214 Th concentrations were measured in a suite of water samples (dissolved and particulate phases) from the marginal seas of the Russian Arctic (Pechora, Kara, Laptev, and East Siberian Seas) in order to better understand scavenging within the water column. To elucidate the sources of Pu and 131CS to the study area, Pu and "'Cs concentrations and 238PU/239,240puactivity ratios were measured in water samples. Concentrations of Ra isotopes were also determined for the estimation of the residence time of river water entering the Kara Sea. The model-derived scavenging parameters for 114 Th and "OPb clearly indicate particle concentrations, influenced by resuspension, ice melt, and continental runoff, primarily control the removal of these nuclides. Concentrations and inventories of Pu and "'Cs as well the activity ratio of "IpU/219,l4OpU suggest two main sources of Pu and "'Cs to the waters over the Siberian shelf. an oceanic source, likely from Sellafield and La Hague nuclear reprocessing plants, and a riverine source emanating from estuarine sediments . 21lpU/219,24OPu activity ratios suggest all of the Pu entering into shelf waters by way of Siberian rivers is from Global Fallout. The Pu concentrations are also primarily controlled by the particle concentrations in the water column. River water residence times for the surface and subsurface waters of the Kara Sea were estimated, using2l'Ra/22'Ra activity ratios, to be on the order of one year and 30 years, respectively.

Schwantes, Jon Michael

1996-01-01T23:59:59.000Z

243

Radionuclide air emissions report for the Hanford Site -- calendar year 1997  

SciTech Connect

This report documents radionuclide air emission from the Hanford Site in 1997, and the resulting effective dose equivalent to the maximally exposed member of the public, referred to as the MEI. The report has been prepared in accordance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, National Emissions Standards for Hazardous Air Pollutants, Subpart H, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities. This report has also been prepared in accordance with the reporting requirements of the Washington Administrative Code Chapter 246-247, Radiation Protection-Air Emissions. The effective dose equivalent to the MEI from the Hanford Site`s 1997 point source emissions was 1.2 E-03 mrem (1.2 E-05 mSv), which is well below the 40 CFR 61 Subpart H regulatory limit of 10 mrem/yr. Radon and thoron emissions, exempted from 40 CFR 61 Subpart H, resulted in an effective dose equivalent to the MEI of 2.5 E-03 mrem (2.5 E-05 mSv). The effective dose equivalent to the MEI attributable to diffuse and fugitive emissions was 2.2 E-02 mrem (2.2 E-04 mSv). The total effective dose equivalent from all of the Hanford Site`s air emissions was 2.6 E-02 mrem (2.6 E-04 mSv). The effective dose equivalent from all of the Hanford Site`s air emissions is well below the Washington Administrative Code, Chapter 246-247, regulatory limit of 10 mrem/yr.

Gleckler, B.P.; Rhoads, K.

1998-06-17T23:59:59.000Z

244

Colloid-Facilitated Transport of Radionuclides Through The Vadose Zone  

SciTech Connect

The main purpose of this project was to advance the basic scientific understanding of colloid and colloid-facilitated Cs transport of radionuclides in the vadose zone. We focused our research on the hydrological and geochemical conditions beneath the leadking waste tanks at the USDOE Hanford reservation. Specific objectives were (1) to determine the lability and thermodynamic stability of colloidal materials, which form after reacting Hanford sediments with simulated Hanford Tank Waste, (2) to characterize the interactions between colloidal particles and contaminants, i.e., Cs and Eu, (3) to determine the potential of Hanford sediments for in situe mobilization of colloids, (4) to evaluate colloid-facilitated radionuclide transport through sediments under unsaturated flow, (5) to implement colloid-facilitated contaminant transport mechanisms into a transport model, and (6) to improve conceptual characterization of colloid-contaminant-soil interactions and colloid-facilitated transport for clean-up procedures and long-term risk assessment.

Markus Flury; James B. Harsh; John F. McCarthy' Peter C. Lichtner; John M. Zachara

2007-06-22T23:59:59.000Z

245

LITERATURE REVIEW ON MAXIMUM LOADING OF RADIONUCLIDES ON CRYSTALLINE SILICOTITANATE  

SciTech Connect

Plans are underway to use small column ion exchange (SCIX) units installed in high-level waste tanks to remove Cs-137 from highly alkaline salt solutions at Savannah River Site. The ion exchange material slated for the SCIX project is engineered or granular crystalline silicotitanate (CST). Information on the maximum loading of radionuclides on CST is needed by Savannah River Remediation for safety evaluations. A literature review has been conducted that culminated in the estimation of the maximum loading of all but one of the radionuclides of interest (Cs-137, Sr-90, Ba-137m, Pu-238, Pu-239, Pu-240, Pu-241, Am-241, and Cm-244). No data was found for Cm-244.

Adu-Wusu, K.; Pennebaker, F.

2010-10-13T23:59:59.000Z

246

Summary Report for the Development of Materials for Volatile Radionuclides  

Science Conference Proceedings (OSTI)

The materials development summarized here is in support of the Waste Forms campaign, Volatile Radionuclide task. Specifically, materials are being developed for the removal and immobilization of iodine and krypton, specifically 129I and 85Kr. During FY 2010, aerogel materials were investigated for removal and immobilization of 129I. Two aerogel formulations were investigated, one based on silica aerogels and the second on chalcogenides. For 85Kr, metal organic framework (MOF) structures were investigated.

Strachan, Denis M.; Chun, Jaehun; Henager, Charles H.; Matyas, Josef; Riley, Brian J.; Ryan, Joseph V.; Thallapally, Praveen K.

2010-11-22T23:59:59.000Z

247

Oncogene mRNA Imaging with Radionuclide-PNA-Peptides  

Science Conference Proceedings (OSTI)

New cancer gene hybridization probes to carry radionuclides were made. Noninvasive technetium-99m gamma imaging of CCND1 cancer gene activity in human breast cancer tumors in mice was demonstrated, followed by noninvasive technetium-99m imaging of MYC cancer gene activity. Noninvasive imaging of CCND1 cancer gene activity in human breast cancer tumors in mice was demonstrated with a positron-emitting copper-64 probe, followed by noninvasive positron imaging of IRS1 cancer gene activity.

Wickstrom, Eric

2008-03-19T23:59:59.000Z

248

Effect of Concrete Waste Form Properties on Radionuclide Migration  

Science Conference Proceedings (OSTI)

Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation) the mechanism of contaminant release, the significance of contaminant release pathways, how waste form performance is affected by the full range of environmental conditions within the disposal facility, the process of waste form aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility, the effect of waste form aging on chemical, physical, and radiological properties and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the waste forms come in contact with groundwater. Numerous sets of tests were initiated in fiscal years (FY) 2006-2009 to evaluate (1) diffusion of iodine (I) and technetium (Tc) from concrete into uncontaminated soil after 1 and 2 years, (2) I and rhenium (Re) diffusion from contaminated soil into fractured concrete, (3) I and Re (set 1) and Tc (set 2) diffusion from fractured concrete into uncontaminated soil, (4) evaluate the moisture distribution profile within the sediment half-cell, (5) the reactivity and speciation of uranium (VI) (U(VI)) compounds in concrete porewaters, (6) the rate of dissolution of concrete monoliths, and (7) the diffusion of simulated tank waste into concrete.

Mattigod, Shas V.; Bovaird, Chase C.; Wellman, Dawn M.; Skinner, De'Chauna J.; Cordova, Elsa A.; Wood, Marcus I.

2009-09-30T23:59:59.000Z

249

Laboratory column experiments for radionuclide adsorption studies of the Culebra dolomite member of the Rustler Formation  

SciTech Connect

Radionuclide transport experiments were carried out using intact cores obtained from the Culebra member of the Rustler Formation inside the Waste Isolation Pilot Plant, Air Intake Shaft. Twenty-seven separate tests are reported here and include experiments with {sup 3}H, {sup 22}Na, {sup 241}Am, {sup 239}Np, {sup 228}Th, {sup 232}U and {sup 241}Pu, and two brine types, AIS and ERDA 6. The {sup 3}H was bound as water and provides a measure of advection, dispersion, and water self-diffusion. The other tracers were injected as dissolved ions at concentrations below solubility limits, except for americium. The objective of the intact rock column flow experiments is to demonstrate and quantify transport retardation coefficients, (R) for the actinides Pu, Am, U, Th and Np, in intact core samples of the Culebra Dolomite. The measured R values are used to estimate partition coefficients, (kd) for the solute species. Those kd values may be compared to values obtained from empirical and mechanistic adsorption batch experiments, to provide predictions of actinide retardation in the Culebra. Three parameters that may influence actinide R values were varied in the experiments; core, brine and flow rate. Testing five separate core samples from four different core borings provided an indication of sample variability. While most testing was performed with Culebra brine, limited tests were carried out with a Salado brine to evaluate the effect of intrusion of those lower waters. Varying flow rate provided an indication of rate dependent solute interactions such as sorption kinetics.

Lucero, D.A.; Heath, C.E. [Sandia National Labs., Albuquerque, NM (United States); Brown, G.O. [Oklahoma State Univ., Stillwater, OK (United States). Biosystems and Agricultural Engineering Dept.

1998-04-01T23:59:59.000Z

250

REGULATION OF CARBON SEQUESTRATION AND WATER USE IN A OZARK FOREST: PROPOSING A NEW STRATEGICALLY LOCATED AMERIFLUX TOWER SITE IN MISSOURI  

Science Conference Proceedings (OSTI)

by June 14, 2004, the MOFLUX site was fully instrumented and data streams started to flow. A primary accomplished deliverable for the project period was the data streams of CO{sub 2} and water vapor fluxes and numerous meteorological variables (from which prepared datasets have been submitted to the AmeriFlux data archive for 2004-2006, Additionally, measurements of leaf biochemistry and physiology, biomass inventory, tree allometry, successional trends other variables were obtained.

Pallardy, Stephen G

2013-04-19T23:59:59.000Z

251

Technical Comments on the Environmental Protection Agency's (EPA's) National Pollutant Discharge Elimination System — Proposed Regulations to Establish Requirements for Cooling Water Intake Structures at Existing Facilities  

Science Conference Proceedings (OSTI)

This report presents the Electric Power Research Institute’s (EPRI’s) technical comments on the U.S. Environmental Protection Agency’s (EPA’s) June 11, 2012 Notice of Data Availability (NODA) Related to Impingement Mortality Control Requirements and its June 12, 2012 NODA Related to EPA’s Stated Preference Survey. These NODAs provide additional information to support EPA’s effort to develop a final Rule that implements the requirements of the Clean Water ...

2012-08-30T23:59:59.000Z

252

Long-Term Colloid Mobilization And Colloid-Facilitated Transport Of Radionuclides In A Semi-Arid Vadose Zone  

Science Conference Proceedings (OSTI)

The main purpose of this project was to improve the fundamental mechanistic understanding and quantification of long-term colloid mobilization and colloid-facilitated transport of radionuclides in the vadose zone, with special emphasis on the semi-arid Hanford site. While we focused some of the experiments on hydrogeological and geochemical conditions of the Hanford site, many of our results apply to colloid and colloid-facilitated transport in general. Specific objectives were (1) to determine the mechanisms of colloid mobilization and colloid-facilitated radionuclide transport in undisturbed Hanford sediments under unsaturated flow, (2) to quantify in situ colloid mobilization and colloid-facilitated radionuclide transport from Hanford sediments under field conditions, and (3) to develop a field-scale conceptual and numerical model for colloid mobilization and transport at the Hanford vadose zone, and use that model to predict long-term colloid and colloid- facilitated radionuclide transport. To achieve these goals and objectives, we have used a combination of experimental, theoretical, and numerical methods at different spatial scales, ranging from microscopic investigations of single particle attachment and detachment to larger-scale field experiments using outdoor lysimeters at the Hanford site. Microscopic and single particle investigations provided fundamental insight into mechanisms of colloid interactions with the air-water interface. We could show that a moving air water interface (such as a moving water front during infiltration and drainage) is very effective in removing and mobilizing particles from a stationary surface. Field experiment using a vadose zone lysimeter facility at the Hanford site showed that surface-applied Eu colloids can be translocated rapidly under natural precipitation as well as artificial irrigation. Small amounts of applied colloids were translocated from the surface to a depth of two meters within two months and only 20 mm of cumulative infiltration. Large water infiltration events, mimicking snow melt, enhanced movement of Eu colloids. Nonetheless the majority of Eu colloids remained in the top 30 cm of the soil after 3.5 years of monitoring. These results suggest that colloid and radionuclide transport can occur in the near-surface vadose zone at Hanford under field conditions, but that the magnitude of the transport is less than what has been reported from laboratory studies. We further studied colloid mobilization from undisturbed sediment cores under a flow rate of 18 mm/year, a typical low flow rate at Hanford. Under this low flow rate, we observed continuous colloid mobilization from the sediments, although the total amounts of colloids mobilized are small, only 0.5% of available colloids were mobilized during 5 years of observations. These results demonstrate that colloidal particles are mobile even under the low recharge rates found in a semi-arid site like Hanford. Under higher flow rates, we would expect colloid transport to be even more pronounced. These results of our study are particularly relevant for colloid mobilization and transport related to three process in the vadose zone at Hanford: (1) water infiltration into sediments during rainfall or snowmelt events, (2) groundwater fluctuations as caused by river stage fluctuations, and (3) steady-state, low-flow recharge in deep vadose zone sediments. Transient water flow, like during infiltration or groundwater level fluctuations, are most conducive for colloid mobilization, but even during steady-state, low-flow recharge, colloids can be mobile, although to a much lesser extent. The results of this project have led to a comprehensive and fundamental understanding of colloid transport and mobilization under unsaturated flow conditions at the Hanford site.

Flury, Markus; Harsh, James B; Zhang, Fred; Gee, Glendon W; Mattson, Earl D; Lichtner, Peter C

2012-11-05T23:59:59.000Z

253

Unclassified Sources Term and Radionuclide Data for Corrective Action Unit 97: Yucca Flat/Climax Mine, Nevada Test Site, Nevada, Revision 2  

Science Conference Proceedings (OSTI)

This report documents the evaluation of the information and data available on the unclassified source term and radionuclide contamination for CAU 97: Yucca Flat/Climax Mine. The total residual inventory of radionuclides associated with one or more tests is known as the radiologic source term (RST). The RST is comprised of radionuclides in water, glass, or other phases or mineralogic forms. The hydrologic source term (HST) of an underground nuclear test is the portion of the total RST that is released into the groundwater over time following the test. In this report, the HST represents radionuclide release some time after the explosion and does not include the rapidly evolving mechanical, thermal, and chemical processes during the explosion. The CAU 97: Yucca Flat/Climax Mine has many more detonations and a wider variety of settings to consider compared to other CAUs. For instance, the source term analysis and evaluation performed for CAUs 101 and 102: Central and Western Pahute Mesa and CAU 98: Frenchman Flat did not consider vadose zone attenuation because many detonations were located near or below the water table. However, the large number of Yucca Flat/Climax Mine tests and the location of many tests above the water table warrant a more robust analysis of the unsaturated zone. The purpose of this report is to develop and document conceptual models of the Yucca Flat/Climax Mine HST for use in implementing source terms for the Yucca Flat/Climax Mine models. This document presents future plans to incorporate the radionuclide attenuation mechanisms due to unsaturated/multiphase flow and transport within the Yucca Flat CAU scale modeling. The important processes that influence radionuclide migration for the unsaturated and saturated tests in alluvial, volcanic, and carbonate settings are identified. Many different flow and transport models developed by Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory (LANL), including original modeling of multiphase flow and transport by the Stoller-Navarro Joint Venture (SNJV), are integrated to form a general understanding of how the RST relates to the HST. This report is unlike the Frenchman Flat source term analysis because it does not calculate the HST for each test. Instead, this work only identifies the important processes that must be considered when the CAU-transport modeling is performed.

Peter Martian

2009-08-01T23:59:59.000Z

254

Nuclear regulation and safety  

SciTech Connect

Nuclear regulation and safety are discussed from the standpoint of a hypothetical country that is in the process of introducing a nuclear power industry and setting up a regulatory system. The national policy is assumed to be in favor of nuclear power. The regulators will have responsibility for economic, reliable electric production as well as for safety. Reactor safety is divided into three parts: shut it down, keep it covered, take out the afterheat. Emergency plans also have to be provided. Ways of keeping the core covered with water are discussed. (DLC)

Hendrie, J.M.

1982-01-01T23:59:59.000Z

255

Public Utility Regulation (Iowa) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Utility Regulation (Iowa) Utility Regulation (Iowa) Public Utility Regulation (Iowa) < Back Eligibility Agricultural Commercial Fuel Distributor Industrial Institutional Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Iowa Program Type Environmental Regulations Provider Iowa Utilities Board This section applies to any person, partnership, business association, or corporation that owns or operates any facilities for furnishing gas by piped distribution system, electricity, communications services, or water to the public for compensation. Regulations pertaining to these facilities can be found in this section. Some exemptions apply

256

Dam Safety Regulation (Mississippi) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Dam Safety Regulation (Mississippi) Dam Safety Regulation (Mississippi) Dam Safety Regulation (Mississippi) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Investor-Owned Utility Municipal/Public Utility Transportation Utility Savings Category Water Buying & Making Electricity Home Weatherization Program Info State Mississippi Program Type Environmental Regulations Siting and Permitting Provider Mississippi Department of Environmental Quality The purpose of the Dam Safety Regulation is to ensure that all dams constructed in the state of Mississippi are permitted and thus do not potentially harm wildlife, water supplies and property. Any person or entity proposing to construct, enlarge, repair, or alter a dam or reservoir

257

Department of Energy's team's analyses of Soviet designed VVERs (water-cooled water-moderated atomic energy reactors)  

SciTech Connect

This document contains apprendices A through P of this report. Topics discussed are: a cronyms and technical terms, accident analyses reactivity control; Soviet safety regulations; radionuclide inventory; decay heat; operations and maintenance; steam supply system; concrete and concrete structures; seismicity; site information; neutronic parameters; loss of electric power; diesel generator reliability; Soviet codes and standards; and comparisons of PWR and VVER features. (FI)

Not Available

1989-09-01T23:59:59.000Z

258

Method for immobilizing mixed waste chloride salts containing radionuclides and other hazardous wastes  

DOE Patents (OSTI)

The invention is a method for the encapsulation of soluble radioactive waste chloride salts containing radionuclides such as strontium, cesium and hazardous wastes such as barium so that they may be permanently stored without future threat to the environment. The process consists of contacting the salts containing the radionuclides and hazardous wastes with certain zeolites which have been found to ion exchange with the radionuclides and to occlude the chloride salts so that the resulting product is leach resistant.

Lewis, Michele A. (Naperville, IL); Johnson, Terry R. (Wheaton, IL)

1993-01-01T23:59:59.000Z

259

Method for preparing radionuclide-labeled chelating agent-ligand complexes  

DOE Patents (OSTI)

Radionuclide-labeled chelating agent-ligand complexes that are useful in medical diagnosis or therapy are prepared by reacting a radionuclide, such as .sup.90 Y or .sup.111 In, with a polyfunctional chelating agent to form a radionuclide chelate that is electrically neutral; purifying the chelate by anion exchange chromatography; and reacting the purified chelate with a targeting molecule, such as a monoclonal antibody, to form the complex.

Meares, Claude F. (Davis, CA); Li, Min (Davis, CA); DeNardo, Sally J. (El Macero, CA)

1999-01-01T23:59:59.000Z

260

Microbial stabilization and mass reduction of wastes containing radionuclides and toxic metals  

DOE Patents (OSTI)

A process is provided to treat wastes containing radionuclides and toxic metals with Clostridium sp. BFGl to release a large fraction of the waste solids into solution and convert the radionuclides and toxic metals to a more concentrated and stable form with concurrent volume and mass reduction. The radionuclides and toxic metals being in a more stable form are available for recovery, recycling and disposal. 18 figures.

Francis, A.J.; Dodge, C.J.; Gillow, J.B.

1991-09-10T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

The development and use of radionuclide generators in nuclear medicine -- recent advances and future perspectives  

SciTech Connect

Although the trend in radionuclide generator research has declined, radionuclide generator systems continue to play an important role in nuclear medicine. Technetium-99m obtained from the molybdenum-99/technetium-99m generator system is used in over 80% of all diagnostic clinical studies and there is increasing interest and use of therapeutic radioisotopes obtained from generator systems. This paper focuses on a discussion of the major current areas of radionuclide generator research, and the expected areas of future research and applications.

Knapp, F.F. Jr.

1998-03-01T23:59:59.000Z

262

Colloid and Colloid-Facilitated Radionuclide Transport at the Semi-Arid Hanford Site .  

E-Print Network (OSTI)

??Considerable amount of radioactive waste has been released to vadose zone sediments at the Hanford site. Colloids can facilitate the movement of radionuclides through the… (more)

[No author

2013-01-01T23:59:59.000Z

263

Biomedical research with cyclotron produced radionuclides. Progress report, January 1, 1979-June 30, 1980. [Lead Abstract  

SciTech Connect

Separate abstracts were prepared for the 24 papers presented in this progress report dealing with the use of radionuclides produced by the cyclotron. (KRM)

Laughlin, J.S.; Benua, R.S.; Gelbard, A.S.

1980-09-01T23:59:59.000Z

264

California State Regulations  

NLE Websites -- All DOE Office Websites (Extended Search)

California California State Regulations: California State of California The California Department of Conservation's Division of Oil, Gas, and Geothermal Resources oversees the drilling, operation, maintenance, and plugging and abandonment of oil, natural gas, and geothermal wells. The regulatory program emphasizes the development of oil, natural gas, and geothermal resources in the state through sound engineering practices that protect the environment, prevent pollution, and ensure public safety. Other agencies that may be involved in the regulation of drilling wastes include the State Water Resources Control Board and appropriate Regional Water Quality Control Boards, the California Integrated Waste Management Board, the California Air Resources Board and appropriate Air Quality Management Districts or Air Pollution Control Districts, and the Department of Toxic Substances Control.

265

Radionuclide-binding compound, a radionuclide delivery system, a method of making a radium complexing compound, a method of extracting a radionuclide, and a method of delivering a radionuclide  

DOE Patents (OSTI)

The invention pertains to compounds which specifically bind radionuclides, and to methods of making radionuclide complexing compounds. In one aspect, the invention includes a radionuclide delivery system comprising: a) a calix[n]arene-crown-[m]-ether compound, wherein n is an integer greater than 3, and wherein m is an integer greater than 3, the calix[n]arene-crown-[m]-ether compound comprising at least two ionizable groups; and b) an antibody attached to the calix[n]arene-crown-[m]-ether compound. In another aspect, the invention includes a method of making a radium complexing compound, comprising: a) providing a calix[n]arene compound, wherein n is an integer greater than 3, the calix[n]arene compound comprising n phenolic hydroxyl groups; b) providing a crown ether precursor, the crown ether precursor comprising a pair of tosylated ends; c) reacting the pair of tosylated ends with a pair of the phenolic hydroxyl groups to convert said pair of phenolic hydroxyl groups to ether linkages, the ether linkages connecting the crown ether precursor to the calix[n]arene to form a calix[n]arene-crown-[m]-ether compound, wherein m is an integer greater than 3; d) converting remaining phenolic hydroxyl groups to esters; e) converting the esters to acids, the acids being proximate a crown-[m]-ether portion of the calix[n]arene-crown-[m]-ether compound; and f) providing a Ra.sup.2+ ion within the crown-[m]-ether portion of the calix[n]arene-crown-[m]-ether compound.

Fisher, Darrell R. (Richland, WA); Wai, Chien M. (Moscow, ID); Chen, Xiaoyuan (Moscow, ID)

2000-01-01T23:59:59.000Z

266

Hanford Site radionuclide national emission standards for hazardous ari pollutants registered and and unregistered stack (powered exhaust) source assessment  

Science Conference Proceedings (OSTI)

On February 3, 1993, US DOE Richland Operations Office received a Compliance Order and Information Request from the Director of the Air and Toxics Div. of US EPA, Region X. The compliance order requires the Richland Operations Office to evaluate all radionuclide emission points at the Hanford site to determine which are subject to the continuous emission measurement requirements in Title 40, Code of Federal Regulations (CFR), Part 61, Subpart H, and to continuously measure radionuclide emissions in accordance with 40 CFR 61.93. The Information Request required The provision of a written compliance plan to meet the requirements of the compliance order. A compliance plan was submitted to EPA, Region X, on April 30, 1993. It set as one of the milestones, the complete assessment of the Hanford Site 84 stacks registered with the Washington State Department of Health, by December 17, 1993. This milestone was accomplished. The compliance plan also called for reaching a Federal Facility Compliance Agreement; this was reached on February 7, 1994, between DOE Richland Operations and EPA, Region X. The milestone to assess the unregistered stacks (powered exhaust) by August 31, 1994, was met. This update presents assessments for 72 registered and 22 unregistered stacks with potential emissions > 0.1 mrem/yr.

Davis, W.E.

1995-12-01T23:59:59.000Z

267

1996 Idaho National Engineering and Environmental Laboratory (INEEL) National Emissions Standards for Hazardous Air Pollutants (NESHAPs) -- Radionuclides. Annual report  

Science Conference Proceedings (OSTI)

Under Section 61.94 of Title 40, Code of Federal Regulations (CFR), Part 61, Subpart H, ``National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities,`` each Department of Energy (DOE) facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at the Idaho National Engineering and Environmental Laboratory (INEEL) for calendar year (CY) 1996. The Idaho Operations Office of the DOE is the primary contact concerning compliance with the National Emission Standards for Hazardous Air Pollutants (NESHAPs) at the INEEL. For calendar year 1996, airborne radionuclide emissions from the INEEL operations were calculated to result in a maximum individual dose to a member of the public of 3.14E-02 mrem (3.14E-07 Sievert). This effective dose equivalent (EDE) is well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year).

NONE

1997-06-01T23:59:59.000Z

268

Heat-pipe effect on the transport of gaseous radionuclides released from a nuclear waste container  

SciTech Connect

When an unsaturated porous medium is subjected to a temperature gradient and the temperature is sufficiently high, vadose water is heated and vaporizes. Vapor flows under its pressure gradient towards colder regions where it condenses. Vaporization and condensation produce a liquid saturation gradient, creating a capillary pressure gradient inside the porous medium. Condensate flows towards the hot end under the influence of a capillary pressure gradient. This is a heat pipe in an unsaturated porous medium. We study analytically the transport of gaseous species released from a spent-fuel waste package, as affected by a time-dependent heat pipe in an unsaturated rock. For parameter values typical of a potential repository in partially saturated fractured tuff at Yucca Mountain, we found that a heat pipe develops shortly after waste is buried, and the heat-pipe`s spatial extent is time-dependent. Water vapor movements produced by the heat pipe can significantly affect the migration of gaseous radionuclides. 12 refs., 6 figs., 1 tab.

Zhou, W.; Chambre, P.L.; Pigford, T.H.; Lee, W.W.L.

1990-11-01T23:59:59.000Z

269

Survey of Optimization of Reactor Coolant Cleanup Systems: For Boiling Water Reactors and Pressurized Water Reactors  

Science Conference Proceedings (OSTI)

Optimization of the reactor coolant cleanup systems in the boiling water reactor (BWR) and pressurized water reactor (PWR) environment is important for controlling the transport of corrosion products (metals and activated metals), fission products, and coolant impurities (soluble and insoluble) throughout the reactor coolant loop, and this optimization contributes to reducing primary system radiation fields. The removal of radionuclides and corrosion products is just one of many functions (both ...

2013-09-27T23:59:59.000Z

270

Radionuclide Partitioning in an Underground Nuclear Test Cavity  

Science Conference Proceedings (OSTI)

In 2004, a borehole was drilled into the 1983 Chancellor underground nuclear test cavity to investigate the distribution of radionuclides within the cavity. Sidewall core samples were collected from a range of depths within the re-entry hole and two sidetrack holes. Upon completion of drilling, casing was installed and a submersible pump was used to collect groundwater samples. Test debris and groundwater samples were analyzed for a variety of radionuclides including the fission products {sup 99}Tc, {sup 125}Sb, {sup 129}I, {sup 137}Cs, and {sup 155}Eu, the activation products {sup 60}Co, {sup 152}Eu, and {sup 154}Eu, and the actinides U, Pu, and Am. In addition, the physical and bulk chemical properties of the test debris were characterized using Scanning Electron Microscopy (SEM) and Electron Microprobe measurements. Analytical results were used to evaluate the partitioning of radionuclides between the melt glass, rubble, and groundwater phases in the Chancellor test cavity. Three comparative approaches were used to calculate partitioning values, though each method could not be applied to every nuclide. These approaches are based on: (1) the average Area 19 inventory from Bowen et al. (2001); (2) melt glass, rubble, and groundwater mass estimates from Zhao et al. (2008); and (3) fission product mass yield data from England and Rider (1994). The U and Pu analyses of the test debris are classified and partitioning estimates for these elements were calculated directly from the classified Miller et al. (2002) inventory for the Chancellor test. The partitioning results from this study were compared to partitioning data that were previously published by the IAEA (1998). Predictions of radionuclide distributions from the two studies are in agreement for a majority of the nuclides under consideration. Substantial differences were noted in the partitioning values for {sup 99}Tc, {sup 125}Sb, {sup 129}I, and uranium. These differences are attributable to two factors: chemical volatility effects that occur during the initial plasma condensation, and groundwater remobilization that occurs over a much longer time frame. Fission product partitioning is very sensitive to the early cooling history of the test cavity because the decay of short-lived (t{sub 1/2} data to update the range in partitioning values for contaminant transport models at the Nevada National Security Site (formerly known as the Nevada Test Site).

Rose, T P; Hu, Q; Zhao, P; Conrado, C L; Dickerson, R; Eaton, G F; Kersting, A B; Moran, J E; Nimz, G; Powell, B A; Ramon, E C; Ryerson, F J; Williams, R W; Wooddy, P T; Zavarin, M

2009-01-09T23:59:59.000Z

271

Parametric study of radionuclide characterization -- Low-level waste. Draft  

Science Conference Proceedings (OSTI)

The criteria and guidance given in this addendum specifically address the classification of low-level waste at the Hanford Reservation into Category 1, Category 3, and Greater Than Category 3 (GTC3). These categories are developed based on the performance assessment (PA) being conducted for the Hanford Site. The radionuclides and their concentration for each category are listed in the revised Table 1-1 (Attachment 1). The information to classify the waste for US Department of Transportation (DOT) and to classify Transuranic (TRU)/ Non-TRU, Contact Handled (CH)/Remote Handled (RH) waste is given in WHC-EP-0063-3 (WHC 1991).

Amir, S.J.

1993-04-01T23:59:59.000Z

272

Management of the Hanford water table and waste management implications  

SciTech Connect

The geology and hydrology of the Hanford Reservation are reviewed, with emphasis on ground water flow, to identify those areas that should be restricted from unconditional release due to radionuclide cortamination or radioactive waste storage as well as those areas that would have no hydrological restrictions. The effects of the discharge of large quantities of cooling water from the radiochemical plants on ground water flow were also evaluated. (CH)

Tomlinson, R.E.; Isaacson, R.E.; Brown, D.J.; Veatch, M.D.

1970-09-21T23:59:59.000Z

273

Reliability of Current Biokinetic and Dosimetric Models for Radionuclides: A Pilot Study  

Science Conference Proceedings (OSTI)

This report describes the results of a pilot study of the reliability of the biokinetic and dosimetric models currently used by the U.S. Nuclear Regulatory Commission (NRC) as predictors of dose per unit internal or external exposure to radionuclides. The study examines the feasibility of critically evaluating the accuracy of these models for a comprehensive set of radionuclides of concern to the NRC. Each critical evaluation would include: identification of discrepancies between the models and current databases; characterization of uncertainties in model predictions of dose per unit intake or unit external exposure; characterization of variability in dose per unit intake or unit external exposure; and evaluation of prospects for development of more accurate models. Uncertainty refers here to the level of knowledge of a central value for a population, and variability refers to quantitative differences between different members of a population. This pilot study provides a critical assessment of models for selected radionuclides representing different levels of knowledge of dose per unit exposure. The main conclusions of this study are as follows: (1) To optimize the use of available NRC resources, the full study should focus on radionuclides most frequently encountered in the workplace or environment. A list of 50 radionuclides is proposed. (2) The reliability of a dose coefficient for inhalation or ingestion of a radionuclide (i.e., an estimate of dose per unit intake) may depend strongly on the specific application. Multiple characterizations of the uncertainty in a dose coefficient for inhalation or ingestion of a radionuclide may be needed for different forms of the radionuclide and different levels of information of that form available to the dose analyst. (3) A meaningful characterization of variability in dose per unit intake of a radionuclide requires detailed information on the biokinetics of the radionuclide and hence is not feasible for many infrequently studied radionuclides. (4) The biokinetics of a radionuclide in the human body typically represents the greatest source of uncertainty or variability in dose per unit intake. (5) Characterization of uncertainty in dose per unit exposure is generally a more straightforward problem for external exposure than for intake of a radionuclide. (6) For many radionuclides the most important outcome of a large-scale critical evaluation of databases and biokinetic models for radionuclides is expected to be the improvement of current models. Many of the current models do not fully or accurately reflect available radiobiological or physiological information, either because the models are outdated or because they were based on selective or uncritical use of data or inadequate model structures. In such cases the models should be replaced with physiologically realistic models that incorporate a wider spectrum of information.

Leggett, Richard Wayne [ORNL; Eckerman, Keith F [ORNL; Meck, Robert A. [U.S. Nuclear Regulatory Commission

2008-10-01T23:59:59.000Z

274

Rules and Regulations for the Investigation and Remediation of Hazardous Material Releases (Rhode Island)  

Energy.gov (U.S. Department of Energy (DOE))

These regulations establish procedures for the investigation and remediation of contamination resulting from the unpermitted release of hazardous materials. The regulations aim to protect water...

275

Records of cosmogenic radionuclides Be-10, Al-26 and Cl-36 in corals: First studies on coral erosion rates and potential of dating very old corals  

E-Print Network (OSTI)

of selected cosmogenic radionuclides by muons: 2. Capture ofRecords of cosmogenic radionuclides 10 Be, 26 Al and 36 Clal. (1994). Cosmogenic radionuclides Table 3. Measured 9 Be

2005-01-01T23:59:59.000Z

276

ASSESSMENT OF RELEASE RATES FOR RADIONUCLIDES IN ACTIVATED CONCRETE.  

Science Conference Proceedings (OSTI)

The Maine Yankee (MY) nuclear power plant is undergoing the process of decontamination and decommissioning (D&D). Part of the process requires analyses that demonstrate that any radioactivity that remains after D&D will not cause exposure to radioactive contaminants to exceed acceptable limits. This requires knowledge of the distribution of radionuclides in the remaining material and their potential release mechanisms from the material to the contacting groundwater. In this study the concern involves radionuclide contamination in activated concrete in the ICI Sump below the containment building. Figures 1-3 are schematic representations of the ICI Sump. Figure 2 and 3 contain the relevant dimensions needed for the analysis. The key features of Figures 2 and 3 are the 3/8-inch carbon steel liner that isolates the activated concrete from the pit and the concrete wall, which is between 7 feet and 7 feet 2 inches thick. During operations, a small neutron flux from the reactor activated the carbon steel liner and the concrete outside the liner. Current MY plans call for filling the ICI sump with compacted sand.

SULLIVAN,T.M.

2003-08-23T23:59:59.000Z

277

Chalcogen-Based Aerogels as Sorbents for Radionuclide Remediation  

SciTech Connect

The efficient capture of radionuclides having long half-lives such as technetium-99 (99Tc), uranium-238 (238U), and iodine-129 (129I) is pivotal to prevent their transport into groundwater and/or release into the atmosphere. While different sorbents have been considered for capturing each of them, in the current work, a new nanostructured chalcogen-based aerogel, called a chalcogel, is shown to be very effective to capture ionic forms of 99Tc and 238U, as well as nonradioactive gaseous iodine (i.e., a surrogate for 129I), irrespective of the sorbent polarity. Some of the chalcogels performed better than others but the PtGeS sorbent performed the best with capture efficiencies of 98% and 99.4% for 99Tc and 238U, respectively. All sorbents showed >99% capture efficiency for iodine over the test duration. This unified sorbent would be an attractive option in environmental remediation for various radionuclides associated with legacy wastes from nuclear weapons production, wastes from nuclear power production, or potential future nuclear fuel reprocessing.

Riley, Brian J.; Chun, Jaehun; Um, Wooyong; Lepry, William C.; Matyas, Josef; Olszta, Matthew J.; Li, Xiaohong; Polychronopoulou, Kyriaki; Kanatzidis, Mercouri G.

2013-06-13T23:59:59.000Z

278

Radionuclides, Metals, and Hydrocarbons in Oil and Gas Operational Discharges and Environmental Samples Associated with Offshore Production Facilities on the Texas/Louisiana Continental Shelf with an Environmental Assessment of Metals and Hydrocarbons  

Science Conference Proceedings (OSTI)

This report presents concentrations of radionuclides, metals, and hydrocarbons in samples of produced water and produced sand from oil and gas production platforms located offshore Texas and Louisiana. Concentrations in produced water discharge plume/receiving water, ambient seawater, sediment, interstitial water, and marine animal tissue samples collected in the vicinity of discharging platforms and reference sites distant from discharges are also reported and discussed. An environmental risk assessment is made on the basis of the concentrations of metals and hydrocarbons determined in the samples.

Continental Shelf Associates, Inc.

1999-08-16T23:59:59.000Z

279

Radionuclides, Metals, and Hydrocarbons in Oil and Gas Operational Discharges and Environmental Samples Associated with Offshore Production Facilities on the Texas/Louisiana Continental Shelf with an Environmental Assessment of Metals and Hydrocarbons.  

Science Conference Proceedings (OSTI)

This report presents concentrations of radionuclides, metals, and hydrocarbons in samples of produced water and produced sand from oil and gas production platforms located offshore Texas and Louisiana. concentrations in produced water discharge plume / receiving water, ambient seawater, sediment, interstitial water, and marine animal tissue samples collected in the vicinity of discharging platforms and reference sites distant from discharges are also reported and discussed. An environmental risk assessment is made on the basis of the concentration of metals and hydrocarbons determined in the samples.

NONE

1997-06-01T23:59:59.000Z

280

Government Regulation  

E-Print Network (OSTI)

Abstract. Interest in the use of so-called voluntary approaches to supplement or replace formal environmental regulation is on the rise, both in Europe and in the United States. These approaches fall into two general ...

Ashford, Nicholas

2005-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Improvements of oil-in-water analysis for produced water using membrane filtration.  

E-Print Network (OSTI)

??The accuracy of oil-in-water analysis for produced water is increasingly crucial as the regulations for disposal of this water are getting more stringent world wide.… (more)

Khor, Ee Huey

2011-01-01T23:59:59.000Z

282

1997 Idaho National Engineering and Environmental Laboratory (INEEL) National Emission Standards for Hazardous Air Pollutants (NESHAPs) -- Radionuclides annual report  

Science Conference Proceedings (OSTI)

Under Section 61.94 of Title 40, Code of Federal Regulations (CFR), Part 61, Subpart H, National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities, each Department of Energy (DOE) facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at the Idaho National Engineering and Environmental Laboratory (INEEL) for calendar year (CY) 1997. Section 1 of this report provides an overview of the INEEL facilities and a brief description of the radioactive materials and processes at the facilities. Section 2 identifies radioactive air effluent release points and diffuse sources at the INEEL and actual releases during 1997. Section 2 also describes the effluent control systems for each potential release point. Section 3 provides the methodology and EDE calculations for 1997 INEEL radioactive emissions.

NONE

1998-06-01T23:59:59.000Z

283

Alternative Regulation (Vermont)  

Energy.gov (U.S. Department of Energy (DOE))

Utility regulators, including the Public Service Board, have applied a new type of regulation, often called "alternative regulation" or "incentive regulation." There are many variants of this type...

284

Monitoring Environmental Recovery at Terminated Produced Water Discharge Sites in Coastal Louisiana Waters  

Science Conference Proceedings (OSTI)

This report presents the results of a study of terminated produced water discharge sites in the coastal waters of Louisiana. Environmental recovery at the sites is documented by comparing pre-termination and post-termination (six months and one year) data. Produced water, sediments, and sediment interstitial water samples were analyzed for radionuclides, metals, and hydrocarbons. Benthic infauna were identified from samples collected in the vicinity of the discharge and reference sites. Radium isotope activities were determined in fish and crustacean samples. In addition, an environmental risk assessment is made on the basis of the concentrations of metals and hydrocarbons determined in the samples.

Continental Shelf Associates, Inc.

1999-08-16T23:59:59.000Z

285

Real-Time Water Quality Monitoring and Habitat Assessment in the San Luis National Wildlife Refuge  

E-Print Network (OSTI)

interests is implemented, water quality compliance withfor computing crop water requirements. FAO Irrigation andof SEBAL for western US water rights regulation and

2005-01-01T23:59:59.000Z

286

Analysis of long-lived radionuclidic impurities in short-lived radiopharmaceutical waste using gamma spectrometry  

Science Conference Proceedings (OSTI)

Large hospitals and biomedical research centers utilize decay-in-storage programs to minimize the volume of their low level radioactive waste. However, some medically useful radionuclides often contain small amounts of long-lived radionuclidic impurities which may complicate simple waste management procedures. We have evaluated the extent of this problem in low level radioactive waste involving {sup 67}Cu and {sup 111}In over a 6-mo cycle of decay-in-storage by identifying the residual radionuclides in our dry waste using a multichannel analyzer. The multichannel analyzer was also used to quantify the radionuclide constituents of our liquid waste at the beginning of a decay-in-storage cycle. Radionuclides were identified by the presence of characteristic photopeaks of each isotope in the gamma spectrum and quantified by region of interest analysis. Gamma spectrometry can be used to aid waste segregation and final management decisions on low level radioactive waste. 10 refs., 1 fig., 2 tabs.

Salako, Q.; DeNardo, S.J. [Univ. of California, Sacramento, CA (United States)

1997-01-01T23:59:59.000Z

287

Technologies for destruction of long-lived radionuclides in high-level nuclear waste: Overview and requirements  

SciTech Connect

This paper, and this topical session on Nuclear Waste Minimization, Management and Remediation, focuses on two nuclear systems, and their associated technologies, that have the potential to address concerns surrounding long-lived radionuclides in high-level waste. Both systems offer technology applicable to HLW from present light-water reactors (LWR). Additionally these systems represent advanced nuclear power concepts that have important features associated with integrated management of wastes, long-term fuel supplies, and enhanced safety. The first system is the Integral Fast Reactor (IFR) concept. This system incorporates a metal-fueled fast reactor coupled with chemical separations based on pyroprocessing to produce power while simultaneously burning long-lived actinide waste. IFR applications include burning of actinides from current LWR spent fuel and energy production in a breeder environment. The second concept, Accelerator Transmutation of Waste (ATW), is based upon an accelerator-induced intense source of thermal neutrons and is aimed at destruction of long-lived actinides and fission products. This concept can be applied to long-lived radionuclides in spent fuel HLW as well as a future fission power source built around use of natural thorium or uranium as fuels coupled with concurrent waste destruction.

Arthur, E.D.

1993-10-01T23:59:59.000Z

288

A detailed calibration of a stack monitor used in the measurement of airborne radionuclides at a high energy proton accelerator  

E-Print Network (OSTI)

A detailed calibration of a stack monitor used in the measurement of airborne radionuclides at a high energy proton accelerator

Vaziri, K; Cossairt, J D; Böhnlein, D J; Elwyn, A J

1996-01-01T23:59:59.000Z

289

Depth Profiles of Radionuclides Induced in Shielding Concrete of the 12 GeV Proton Accelerator Facility at KEK  

E-Print Network (OSTI)

Depth Profiles of Radionuclides Induced in Shielding Concrete of the 12 GeV Proton Accelerator Facility at KEK

Miura, T; Ishihama, S; Ohotsuka, N; Kunifuda, T

2000-01-01T23:59:59.000Z

290

FLUKA calculations of radionuclides, star, and neutron fluence in soil around high-energy electron and proton linear accelerators  

E-Print Network (OSTI)

FLUKA calculations of radionuclides, star, and neutron fluence in soil around high-energy electron and proton linear accelerators

Puryear, A; Rokni, S H

2002-01-01T23:59:59.000Z

291

Evaluation of radionuclide, inorganic constituent, and organic compound data from selected wells and springs from the southern boundary of the Idaho National Engineering Laboratory to the Hagerman area, Idaho, 1989--1992  

Science Conference Proceedings (OSTI)

The U.S. Geological Survey and the Idaho Department of Water Resources, in cooperation with the U.S. Department of Energy, evaluated the water quality data collected from 55 wells and springs during 1989 and 1990 through 1992 from the southern boundary of the Idaho National Engineering Laboratory to the Hagerman area, Idaho. Water samples collected in 1989-92 were analyzed for selected radionuclides, inorganic constituents, and organic compounds. A statistical comparison between data collected in 1989 and data collected in 1990-92 along with a comparison of replicate pairs was used to evaluate changes in water quality between samples and to assess sampling and analysis precision for individual constituents. The comparisons of radionuclide data showed no pattern of water quality change between samples as concentrations randomly increased or decreased. Tritium concentrations did show a consistent pattern with location in the aquifer. The largest tritium concentrations occurred in water from wells in the Big Wood and Little Wood River drainages and in the southern part of the study area where heavy irrigation occurs. The variability of radionuclide concentrations may be attributed to the change in the contract laboratory used for radiochemical analyses between 1989 and 1990. The replicate data for radionuclides showed better overall reproducibility for data collected in 1990-92 than for 1989, as 70 of 76 replicate pairs were statistically equivalent for 1990-92 data whereas only 55 of 73 replicate pairs were equivalent for 1989 data. The comparisons of most of the inorganic constituent data showed no statistical change between samples. Exceptions include nitrite plus nitrate as nitrogen and orthophosphate as phosphorus data. Fifteen sample pairs for nitride plus nitrate and 18 sample pairs for orthophosphate were not statistically equivalent and concentrations randomly increased or decreased.

Bartholomay, R.C.; Williams, L.M.; Campbell, L.J.

1997-01-01T23:59:59.000Z

292

Water Management Act (Massachusetts) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Management Act (Massachusetts) Management Act (Massachusetts) Water Management Act (Massachusetts) < Back Eligibility Agricultural Industrial Institutional Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Savings Category Buying & Making Electricity Water Home Weatherization Program Info State Massachusetts Program Type Environmental Regulations Provider Department of Environmental Protection This Act regulates and registers water withdrawals in the Commonwealth of Massachusetts to enable effective planning and management of water use and conservation. The Act establishes a Water Resources Management Advisory Committee within the MA Department of Environmental Protection to oversee the development of standards, rules and regulations for water resources

293

Microscopic characterization of radionuclide contaminated soils to assist remediation efforts  

Science Conference Proceedings (OSTI)

A combination of optical, scanning, and analytical electron microscopies have been used to describe the nature of radionuclide contamination at several sites. These investigations were conducted to provide information for remediation efforts. This technique has been used successfully with uranium-contaminated soils from Fernald, OH, and Portsmouth, OH, thorium-contaminated soil from a plant in Tennessee, plutonium-contamination sand from Johnston Island in the Pacific Ocean, and incinerator ash from Los Alamos, NM. Selecting the most suitable method for cleaning a particular site is difficult if the nature of the contamination is not understood. Microscopic characterization allows the most appropriate method to be selected for removing the contamination and can show the effect a particular method is having on the soil. A method of sample preparation has been developed that allows direct comparison of scanning electron microscopy (SEM) and transmission electron microscopy (TEM) images, enabling characterization of TEM samples to be more representative of the bulk sample.

Buck, E.C.; Brown, N.R.; Dietz, N.L.; Fortner, J.A.; Bates, J.K.

1994-11-01T23:59:59.000Z

294

Carboxy, carboalkoxy and carbamile substituted isonitrile radionuclide complexes  

DOE Patents (OSTI)

A coordination complex comprising a radionuclide selected from the class consisting of radioactive isotopes of Tc, Ru, Co, Pt and Re and an isonitrile ligand of the formula: (CNX)R, where X is a lower alkyl group having 1 to 4 carbon atoms, wherein R is selected from the group consisting of COOR.sup.1 and CONR.sup.2 R.sup.3 where R.sup.1 can be H, a pharmaceutically acceptable cation, or a substituted or unsubstituted alkyl group having 1 to 4 carbon atoms. R.sup.2, and R.sup.3 can be H, or a substituted or unsubstituted alkyl group having 1 to 4 carbon atoms, and R.sup.2 and R.sup.3 can be the same of different is disclosed. Kits that can be used to form these complexes are also disclosed.

Jones, Alun G. (Newton Centre, MA); Davison, Alan (Needham, MA); Kronauge, James (Cambridge, MA); Abrams, Michael J. (Allston, MA)

1989-01-01T23:59:59.000Z

295

Carboxy, carboalkoxy and carbamile substituted isonitrile radionuclide complexes  

DOE Patents (OSTI)

A coordination complex comprising a radionuclide selected from the class consisting of radioactive isotopes of Tc, Ru, Co, Pt and Re and an isonitrile ligand of the formula: (CNX)R, where X is a lower alkyl group having 1 to 4 carbon atoms, wherein R is selected from the group consisting of COOR.sup.1 and CONR.sup.2 R.sup.3 where R.sup.1 can be H, a pharmaceutically acceptable cation, or a substituted or unsubstituted alkyl group having 1 to 4 carbon atoms, R.sup.2, and R.sup.3 can be H, or a substituted or unsubstituted alkyl group having 1 to 4 carbon atoms, and R.sup.2 and R.sup.3 can be the same or different is disclosed. Kits that can be used to form these complexes are also disclosed.

Jones, Alun G. (Newton Centre, MA); Davison, Alan (Needham, MA); Kronauge, James (Cambridge, MA); Abrams, Michael J. (Allston, MA)

1988-04-05T23:59:59.000Z

296

ASSESSMENT OF RADIONUCLIDE RELEASE FROM CONTAMINATED CONCRETE AT THE YANKEE NUCLEAR POWER STATION.  

Science Conference Proceedings (OSTI)

Yankee Atomic Energy Company (YAEC) is considering allowing portions of existing structures at the Yankee Nuclear Power Station (YNPS) to remain on site at the time of license termination. Accordingly, release of residual radioactive contaminants (i.e., H-3, C-14, Co-60, Ni-63, Sr-90, and Cs-137) from remaining subsurface concrete structures (Darman, 2004) and dose due to that release must be evaluated. Analyses were performed using DUST-MS to assess the rate of release for each radionuclide from the concrete, based upon an assumed concentration of 1 pCi/g and a concrete density of 2.5 g/cm{sup 3}. Using the same assumptions that were applied to the soil DCGL calculation (and where appropriate, the same input parameters), RESRAD was used to calculate the dose from water pathways. Values for selected RESRAD input parameters were chosen to match the release rate calculated by DUST-MS. The results indicated that Cs-137 yielded the highest dose.

SULLIVAN, T.

2004-03-01T23:59:59.000Z

297

Preliminary testing of turbulence and radionuclide transport modeling in deep ocean environment  

Science Conference Proceedings (OSTI)

Pacific Northwest Laboratory (PNL) performed a study for the US Environmental Protection Agency's Office of Radiation Programs to (1) identify candidate models for regional modeling of low-level waste ocean disposal sites in the mid-Atlantic ocean; (2) evaluate mathematical representation of the model's eddy viscosity/dispersion coefficients; and (3) evaluate the adequacy of the k-{epsilon} turbulence model and the feasibility of one of the candidate models, TEMPEST{copyright}/FLESCOT{copyright}, to deep-ocean applications on a preliminary basis. PNL identified the TEMPEST{copyright}/FLESCOT{copyright}, FLOWER, Blumberg's, and RMA 10 models as appropriate candidates for the regional radionuclide modeling. Among these models, TEMPEST/FLESCOT is currently the only model that solves distributions of flow, turbulence (with the k-{epsilon} model), salinity, water temperature, sediment, dissolved contaminants, and sediment-sorbed contaminants. Solving the Navier-Stokes equations using higher order correlations is not practical for regional modeling because of the prohibitive computational requirements; therefore, the turbulence modeling is a more practical approach. PNL applied the three-dimensional code, TEMPEST{copyright}/FLESCOT{copyright} with the k-{epsilon} model, to a very simple, hypothetical, two-dimensional, deep-ocean case, producing at least qualitatively appropriate results. However, more detailed testing should be performed for the further testing of the code. 46 refs., 39 figs., 6 tabs.

Onishi, Y.; Dummuller, D.C.; Trent, D.S. (Pacific Northwest Lab., Richland, WA (USA); Washington State Univ., Pullman, WA (USA); Pacific Northwest Lab., Richland, WA (USA))

1989-03-01T23:59:59.000Z

298

MODELLING OF COUPLED GROUNDWATER FLOW AND RADIONUCLIDE TRANSPORT IN CRYSTALLINE BASEMENT USING FEFLOW 5.0  

E-Print Network (OSTI)

Abstract. The strategy of radioactive waste management of Lithuania provides for evaluating the possibilities of disposal of spent nuclear fuel and long-lived radioactive waste originated from Ignalina NPP in deep geological formations. The initial studies performed in Lithuania during 2001–2004 focused on screening of all potentially prospective geological formations as host formations. Since most information is available on crystalline basement, this formation was selected for the model case studies. Taking into account the assumptions (canister defect scenario proposed by Swedish experts and evaluated by LEI experts), groundwater flow and radionuclide (iodine-129 as mobile and long-lived one) transport modelling using computer code FEFLOW was performed according to geosphere conditions and parameters characteristic of the southern part of Lithuania (0,8×0,6×0,52 km far-field block). The upward groundwater flow through defected canister located in tectonically damaged zone was simulated. The main results of calculations are the following: in the case of upward groundwater flow, the maximum I-129 volumetric activity in single tectonic fracture above defected canister will not exceed 1 Bq/l, and in the active water exchange zone, it is close to 10-2 Bq/l. These figures show that doses obtained by human recipient via aquatic pathway should be below the dose constraint (0,2 mSv/y). More complicated scenarios and assumptions should be investigated in future studies.

Vaidot? Jakimavi?i?t?-maselien?; Jonas Mažeika; Rimantas Petrošius

2006-01-01T23:59:59.000Z

299

Tracer Applications of Noble Gas Radionuclides in the Geosciences  

E-Print Network (OSTI)

1 Water in Alberta With Special Focus on the Oil and Gas Industry (Education Paper) Seyyed Ghaderi......................................................................................................................................14 5. Water and Unconventional Energy Resources in Alberta? ................................................................................17 What is Unconventional about CBM Production

Kemner, Ken

300

Determination Of Reportable Radionuclides For DWPF Sludge Batch 7B (Macrobatch 9)  

SciTech Connect

The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Sludge Batch 7a (SB7a) and Sludge Batch 7b (SB7b) that was transferred to Tank 40 from Tank 51. The blend of sludge in Tank 40 is also referred to as Macrobatch 9 (MB9). This report develops the list of reportable radionuclides and associated activities as a function of time. Twenty-seven radionuclides have been identified as reportable for DWPF SB7b. Each of these radionuclides has a half-life greater than ten years and contributes more than 0.01% of the radioactivity on a Curie basis at some point from production through the 1100 year period between 2015 and 3115. For SB7b, all of the radionuclides in the Design Basis glass are reportable except for three radionuclides: Pd-107, Cs-135, and Th-230. At no time during the 1100- year period between 2015 and 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. The radionuclide measurements made for SB7b are the most extensive conducted to date. Some method development/refinement occurred during the conduct of these measurements, leading to lower detection limits and more accurate measurement of some isotopes than was previously possible.

Crawford, C. L.; Diprete, D. P.

2012-12-17T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Radionuclide contaminant analysis of small mammels, plants and sediments within Mortandad Canyon, 1994  

SciTech Connect

Small mammals, plants and sediments were sampled at one upstream location (Site 1) and two downstream locations (Site 2 and Site 3) from the National Pollution Discharge Elimination System outfall {number_sign}051-051 in Mortandad Canyon, Los Alamos County, New Mexico. The purpose of the sampling was to identify radionuclides potentially present, to quantitatively estimate and compare the amount of radionuclide uptake at specific locations (Site 2 and Site 3) within Mortandad Canyon to an upstream site (Site 1), and to identify the primary mode (inhalation ingestion, or surface contact) of contamination to small mammals. Three composite samples of at least five animals per sample were collected at each site. Pelts and carcasses of each animal were separated and analyzed independently. In addition, three composite samples were also collected for plants and sediments at each site. Samples were analyzed for {sup 241}Am, {sup 90}Sr, {sup 238}Pu, {sup 239}Pu, and total U. With the exception of total U, all mean radionuclide concentrations in small mammal carcasses and sediments were significantly higher at Site 2 than Site 1 or Site 3. No differences were detected in the mean radionuclide concentration of plant samples between sites. However, some radionuclide concentrations found at all three sites were higher than regional background. No differences were found between mean carcass radionuclide concentrations and mean pelt radionuclide concentrations, indicating that the two primary modes of contamination may be equally occurring.

Bennett, K.; Biggs, J.; Fresquez, P.

1996-01-01T23:59:59.000Z

302

The Need for Research Programs to Provide Data Applicable to the Estimate of Maximum Permissible Exposure Values for Internally Deposited Radionuclides  

SciTech Connect

The nuclear age, which has been with us slightly more than 20 years, has brought with it an unusual awareness of a relatively new toxic agent--ionizing radiation. In fact, a new science, health physics, was created to give special attention to this problem. As a consequence and in spite of the unparalleled hazards associated with ionizing radiation, this new nuclear industry is growing rapidly into a benevolent giant bringing a better way of life while at the Same time maintaining radiation damage at an insignificant level. Although i n the past few decades we have learned much more about the hazards associated with ionizing radiation than those associated with some of the common industrial hazards and although maximum permissible exposure levels for the radionuclides have been established with greater reliability and confidence than have the levels for many chemical agents with which man has been familiar for many centuries, there still remains a considerable uncertainty in many of the basic assumptions and in the parameters used in the calculation of maximum permissible body burden and maximum permissible concentration of the various radionuclides in food, water and air. There is need to determine the uptake, distribution and elimination of a variety of chemical compounds of the approximately 300 common radionuclides. These data are needed for the several modes of intake by the various age groups, and differences due to race, sex, weight, eating habits, etc., should be investigated. There is need especially to obtain data from studies of human exposure and to examine the influence of the quantity and chemical form of the radionuclide and of other associated chemical elements taken into the body, both from single exposure and from continuous exposure.

Morgan, K.Z.

1964-08-21T23:59:59.000Z

303

Regulations of Wells (Florida) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Regulations of Wells (Florida) Regulations of Wells (Florida) Regulations of Wells (Florida) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Program Info State Florida Program Type Environmental Regulations Siting and Permitting Provider Florida Department of Environmental Protection The Department of Environmental Protection regulates the construction, repair, and abandonment of wells, as well as the persons and businesses undertaking such practices. Governing boards of water management districts

304

Forest Road Building Regulations | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

You are here You are here Home » Forest Road Building Regulations Forest Road Building Regulations < Back Eligibility Utility Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Schools Retail Supplier Institutional Fuel Distributor Nonprofit Transportation Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info Start Date 09/2010 State Wisconsin Program Type Environmental Regulations The Wisconsin Department of Natural Resources has regulations for building a forest road, if development requires one. Regulations include zoning ordinances and permits for stream crossing, grading, stormwater, and

305

Laws and Regulations | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Laws and Regulations Laws and Regulations Laws and Regulations Federal laws and regulations set multiple energy management requirements for Federal agencies spanning energy efficiency, renewable energy, water conservation, and alternative fuel use. This section outlines Federal energy management authorities through: Requirements by Subject Requirements by Regulation. The Federal Energy Management Program (FEMP) analyzes energy management authorities and develops rules and guidance to help Federal agencies comply with applicable requirements. Reporting requirements and Federal Government performance reports are also available through: Notices and Rules Facility Reporting Fleet Reporting. EISA 432 Compliance Tracking Track Federal agency progress toward Section 432 of the Energy Independence and Security Act (EISA) of 2007 using FEMP's EISA 432

306

North Dakota State Regulations  

NLE Websites -- All DOE Office Websites (Extended Search)

North Dakota North Dakota State Regulations: North Dakota State of North Dakota The North Dakota Industrial Commission (NDIC), through its Oil and Gas Division (OGD), is the regulatory agency for oil and gas exploration and production activities in North Dakota. The North Dakota Department of Health (NDDH) Environmental Health Section (EHS) has the responsibility to safeguard the quality of North Dakota's air, land, and water resources. Contact North Dakota Industrial Commission Oil and Gas Division 600 East Boulevard Avenue, Dept. 405 Bismarck, ND 58505-0840 (701) 328-8020 (phone) (701) 328-8022 (fax) North Dakota Department of Health Environmental Health Section 1200 Missouri Avenue P.O. Box 5520 Bismarck, ND 58506-5520 (701) 328-5150 (phone) (701) 328-5200 (fax) Disposal Practices and Applicable Regulations

307

Alternative Regulation (Vermont) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Regulation (Vermont) Regulation (Vermont) Alternative Regulation (Vermont) < Back Eligibility Agricultural Commercial Fuel Distributor Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative State/Provincial Govt Systems Integrator Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Vermont Program Type Generating Facility Rate-Making Utility regulators, including the Public Service Board, have applied a new type of regulation, often called "alternative regulation" or "incentive regulation." There are many variants of this type of regulation, but the common foundation is that rates are set differently from the traditional cost-of-service approach. Sometimes there is a performance-based aspect to

308

National low-level waste management program radionuclide report series, Volume 15: Uranium-238  

Science Conference Proceedings (OSTI)

This report, Volume 15 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of uranium-238 ({sup 238}U). The purpose of the National Low-Level Waste Management Program Radionuclide Report Series is to provide information to state representatives and developers of low-level radioactive waste disposal facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the waste disposal facility environment. This report also includes discussions about waste types and forms in which {sup 238}U can be found, and {sup 238}U behavior in the environment and in the human body.

Adams, J.P.

1995-09-01T23:59:59.000Z

309

Hanford Waste Vitrification Plant technical background document for best available radionuclide control technology demonstration  

Science Conference Proceedings (OSTI)

This report provides the background documentation to support applications for approval to construct and operate new radionuclide emission sources at the Hanford Waste Vitrification Plant (HWVP) near Richland, Washington. The HWVP is required to obtain permits under federal and state statutes for atmospheric discharges of radionuclides. Since these permits must be issued prior to construction of the facility, draft permit applications are being prepared, as well as documentation to support these permits. This report addresses the applicable requirements and demonstrates that the preferred design meets energy, environmental, and economic criteria for Best Available Radionuclide Control Technology (BARCT) at HWVP. 22 refs., 11 figs., 25 tabs.

Carpenter, A.B.; Skone, S.S.; Rodenhizer, D.G.; Marusich, M.V. (Ebasco Services, Inc., Bellevue, WA (USA))

1990-10-01T23:59:59.000Z

310

WORKER INHALATION DOSE COEFFICIENTS FOR RADIONUCLIDES NOT PREVIOUSLY IDENTIFIED IN ICRP PUBLICATION 68  

Science Conference Proceedings (OSTI)

While inhalation dose coefficients are provided for about 800 radionuclides in International Commission on Radiological Protection (ICRP) Publication 68, many radionuclides of practical dosimetric interest for facilities such as high-energy proton accelerators are not specifically addressed, nor are organ-specific dose coefficients tabulated. The ICRP Publication 68 methodology is used, along with updated radiological decay data and metabolic data, to identify committed equivalent dose coefficients [hT(50)] and committed effective dose coefficients [e(50)] for radionuclides produced at the Oak Ridge National Laboratory s Spallation Neutron Source.

McLaughlin, David A [ORNL; Schwahn, Scott O [ORNL

2011-01-01T23:59:59.000Z

311

Taps: The Dangers of Drinking Water  

E-Print Network (OSTI)

produced this study "as part of a formal petition to the FDA calling on the agency to strengthen national bottled water regulations

Burgess, Michael

1999-01-01T23:59:59.000Z

312

Water Rights: Surface Water (Indiana) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Surface Water (Indiana) Surface Water (Indiana) Water Rights: Surface Water (Indiana) < Back Eligibility Agricultural Construction Fed. Government Industrial Institutional Investor-Owned Utility Local Government Municipal/Public Utility Nonprofit Rural Electric Cooperative State/Provincial Govt Tribal Government Utility Savings Category Water Buying & Making Electricity Program Info State Indiana Program Type Environmental Regulations Provider Indiana Department of Natural Resources The Indiana Department of Natural Resources regulates the use and diversion of surface waters. An entity that creates additional stream volumes by releases from impoundments built and financed by the entity for the entity's purpose may use the increased flowage at all times. Any entity may be required to report the volume of water used. Diversion of water out of

313

Air Pollution Control Regulations: No. 6 - Continuous Emissions...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Program Type Environmental Regulations Stationary sources, including fossil fuel fired steam or hot water generating units, may be required to install and operate a continuous...

314

Rules and Regulations for the Management and Control of Designated...  

Open Energy Info (EERE)

Edit with form History Facebook icon Twitter icon Rules and Regulations for the Management and Control of Designated Ground Water Jump to: navigation, search GEOTHERMAL...

315

Management and Storage of Surface Waters (Florida)  

Energy.gov (U.S. Department of Energy (DOE))

The Department of Environmental Protection regulates the use and storage of surface waters in the state. A permit from either the Department or the local Water Management District is required for...

316

California Appliance Efficiency Regulations for Manufacturers  

E-Print Network (OSTI)

California Appliance Efficiency Regulations for Manufacturers CEC-400-2012-FS-004-En Updated 3 electricity or water, California law requires that such products comply with the Appliance Efficiency Regulations* in order to be sold or offered for sale in California. Designed to help California reduce energy

317

Water heater control module  

DOE Patents (OSTI)

An advanced electric water heater control system that interfaces with a high temperature cut-off thermostat and an upper regulating thermostat. The system includes a control module that is electrically connected to the high-temperature cut-off thermostat and the upper regulating thermostat. The control module includes a switch to open or close the high-temperature cut-off thermostat and the upper regulating thermostat. The control module further includes circuitry configured to control said switch in response to a signal selected from the group of an autonomous signal, a communicated signal, and combinations thereof.

Hammerstrom, Donald J

2013-11-26T23:59:59.000Z

318

Proceedings of Soil Decon `93: Technology targeting radionuclides and heavy metals  

SciTech Connect

The principal objective for convening this workshop was to exchange ideas and discuss with scientists and engineers methods for removing radionuclides and/or toxic metals from soils. Over the years there have been numerous symposia, conferences, and workshops directed at soil remediation. However, this may be the first where the scope was narrowed to the removal of radionuclides and toxic metals from soils. The intent was to focus on the separation processes controlling the removal of the radionuclide and/or metal from soil. Its purpose was not intended to be a soil washing/leaching workshop, but rather to identify a variety or combination of processes (chemical, physical, and biological) that can be used in concert with the applicable engineering approaches to decontaminate soils of radionuclides and toxic metals. Abstracts and visual aids used by the speakers of the workshop are presented in this document.

1993-09-01T23:59:59.000Z

319

Evaluation and selection of aqueous-based technology for partitioning radionuclides from ICPP calcine  

Science Conference Proceedings (OSTI)

Early in 1993 Westinghouse Idaho Nuclear Company (WINCO) chartered a Panel of Nuclear Separations Experts. The purpose of this Panel was to assist WINCO scientists and engineers in selecting, evaluating, and ranking candidate aqueous-based processes and technologies for potential use in partitioning selected radionuclides from nitric acid solutions of retrieved Idaho Chemical Processing Plant (ICPP) calcine. Radionuclides of interest are all transuranium elements, {sup 90}Sr, {sup 99}Tc, {sup 129}I, and {sup 137}Cs. The six man Panel met for 4 days (February 16--19, 1993) on the campus of the Idaho State University in Pocatello, Idaho. Principal topics addressed included: Available radionuclide removal technology; applicability of separations technology and processes to ICPP calcine; and potential integrated radionuclide partitioning schemes. This report, prepared from contributions from all Panel members, presents a comprehensive account of the proceedings and significant findings of the February, 1993 meeting in Pocatello.

Olson, A.L.; Schulz, W.W.; Burchfield, L.A.; Carlson, C.D.; Swanson, J.L.; Thompson, M.C.

1993-02-01T23:59:59.000Z

320

Water Pollution (Illinois) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

(Illinois) (Illinois) Water Pollution (Illinois) < Back Eligibility Agricultural Commercial Construction Fuel Distributor Industrial Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Program Info State Illinois Program Type Environmental Regulations Provider Illinois EPA This article states regulations for water quality standards, effluent standards, monitoring and reporting methods, sewer discharge criteria and information about permits. It is the purpose of these rules and regulations to designate the uses for which the various waters of the State shall be maintained and protected; to prescribe the water quality standards required to sustain the designated uses; to establish effluent standards to limit the contaminants discharged to the waters; and to prescribe additional

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

South Dakota State Regulations  

NLE Websites -- All DOE Office Websites (Extended Search)

Technology Identification Home Federal and State Regulations State Regulations South Dakota State Regulations: South Dakota State of South Dakota The South Dakota...

322

A Review of Radionuclide Release From HTGR Cores During Normal Operation  

Science Conference Proceedings (OSTI)

The release of radionuclides from the core of high-temperature gas-cooled reactors (HTGRs) -- especially direct-cycle HTGRs -- during normal plant operation has significant design, O&M, and safety implications. A hallmark philosophy of all modern HTGRs is to design the plant so that radionuclides are retained in the core during normal operation and postulated accidents. The key to achieving this safety goal is twofold: (1) a reliance on ceramic-coated fuel particles for primary fission product containmen...

2004-03-04T23:59:59.000Z

323

Technology and fabrication of plutonium-238 radionuclide heat sources  

Science Conference Proceedings (OSTI)

This paper outlines a brief technical description of the facility for production of plutonium-238 and fabrication of Radionuclide Heat Sources (RHS) containing Pu-238. Technical capabilities of the RHS fabrication facility are presented. The results of development of the RHS design for sea application are discussed. RHS fuel pellet comprises the tantalum shell with an annular slot intended for release of radiogenic helium and the Pu-238 dioxide core with reinforcing elements inside which contact with the shell. RHS is a double encapsulation consisting of the inner {open_quote}{open_quote}power{close_quote}{close_quote} capsule and the outer corrosion-resistant capsule. The chromium-nickel-molybdenum XH65MB alloy which is equivalent to Hastelloy-C alloy has been selected as a material for both capsules. Upon expiration of working life, RHS design is capable of withstanding the internal pressure of radiogenic helium at 1073 K within 30 minutes and the external hydrostatic pressure of 100 MPa at normal temperature. {copyright} {ital 1996 American Institute of Physics.}

Malikh, Y.A.; Aldoshin, A.I. [Production Association Mayak, 31 Lenin Street, Ozyorsk, 456780 (Russia); Danilkin, E.A. [The State Scientific Center of Russia, 5 Rogov Street, Moscow (Russia)

1996-03-01T23:59:59.000Z

324

Water Usage Law, Major Water Users (Missouri) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Water Usage Law, Major Water Users (Missouri) Water Usage Law, Major Water Users (Missouri) Water Usage Law, Major Water Users (Missouri) < Back Eligibility Agricultural Commercial Construction Fed. Government Industrial Institutional Investor-Owned Utility Local Government Municipal/Public Utility Retail Supplier Rural Electric Cooperative Systems Integrator Tribal Government Utility Savings Category Water Buying & Making Electricity Program Info State Missouri Program Type Environmental Regulations Provider Missouri Department of Natural Resources Any water user with the capability to withdraw or divert 100,000 gallons or more per day from any stream, river, lake, well, spring or other water source must register and file for a permit for water withdrawal and diversion from the Department of Natural Resources. Additionally, no major

325

Context: Policy & Regulation  

Science Conference Proceedings (OSTI)

... Regulation of Halon and Halon Substitutes. ... Disparities in Environmental Regulations and Their Effect ... Impediments and Incentives for Incorporating ...

2011-11-17T23:59:59.000Z

326

Contribution of maternal radionuclide burdens to prenatal radiation doses  

SciTech Connect

This report describes approaches to calculating and expressing radiation doses to the embryo/fetus from internal radionuclides. Information was obtained for selected, occupationally significant radioelements that provide a spectrum of metabolic and dosimetric characteristics. Evaluations are also presented for inhaled inert gases and for selected radiopharmaceuticals. Fractional placental transfer and/or ratios of concentration in the embryo/fetus to that in the woman were calculated for these materials. The ratios were integrated with data from biokinetic transfer models to estimate radioactivity levels in the embryo/fetus as a function of stage of pregnancy and time after entry into the transfer compartment or blood of the pregnant woman. These results are given as tables of deposition and retention in the embryo/fetus as a function of gestational age at exposure and elapsed time following exposure. Methodologies described by MIRD were extended to formalize and describe details for calculating radiation absorbed doses to the embryo/fetus. Calculations were performed using a model situation that assumed a single injection of 1 {mu}Ci into a woman`s blood; independent calculations were performed for administration at successive months of pregnancy. Gestational -stage-dependent dosimetric tabulations are given together with tables of correlations and relationships. Generalized surrogate dose factors and categorizations are provided in the report to provide for use in operational radiological protection situations. These approaches to calculation yield radiation absorbed doses that can be converted to dose equivalent by multiplication by quality factor. Dose equivalent is the most common quantity for stating prenatal dose limits in the United States and is appropriate for the types of effect that are usually associated with prenatal exposure. If it is desired to obtain alternatives for other purposes, this value can be multiplied by appropriate weighting factors.

Sikov, M.R.; Hui, T.E.

1996-05-01T23:59:59.000Z

327

Analysis of soil and water at the Four Mile Creek seepline near the F- and H-Areas of SRS  

Science Conference Proceedings (OSTI)

Several soil and water samples were collected along the Four Mile Creek (FMC) seepline at the F and H Areas of the Savannah River Site. The samples were analyzed for concentrations of metals, radionuclides, and inorganic constituents. The results of the analyses are summarized for the soil and water samples.

Haselow, J.S.

2000-05-24T23:59:59.000Z

328

Utility Regulation (Indiana) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Regulation (Indiana) Regulation (Indiana) Utility Regulation (Indiana) < Back Eligibility Agricultural Commercial General Public/Consumer Industrial Institutional Investor-Owned Utility Local Government Municipal/Public Utility Nonprofit Rural Electric Cooperative Schools State/Provincial Govt Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Indiana Program Type Generating Facility Rate-Making Provider Indiana Utility Regulatory Commission The Indiana Utility Regulatory Commission enforces regulations in this legislation that apply to all individuals, corporations, companies, and partnerships that may own, operate, manage, or control any equipment for the production, transmission, delivery, or furnishing of heat, light,

329

Dam Safety Regulations (Connecticut) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Regulations (Connecticut) Safety Regulations (Connecticut) Dam Safety Regulations (Connecticut) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Water Buying & Making Electricity Program Info State Connecticut Program Type Siting and Permitting Provider Department of Energy and Environmental Protection All dams, except those owned by the U.S., are under the jurisdiction of these regulations. These dams will be classified by hazard rating, and may

330

Comprehensive Everglades Restoration Plan Regulation Act (Florida) |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Comprehensive Everglades Restoration Plan Regulation Act (Florida) Comprehensive Everglades Restoration Plan Regulation Act (Florida) Comprehensive Everglades Restoration Plan Regulation Act (Florida) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Multi-Family Residential Municipal/Public Utility Nonprofit Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Florida Program Type Environmental Regulations Siting and Permitting Provider Florida Department of Environmental Protection

331

Massachusetts Endangered Species Act Regulations (Massachusetts) |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Endangered Species Act Regulations (Massachusetts) Endangered Species Act Regulations (Massachusetts) Massachusetts Endangered Species Act Regulations (Massachusetts) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Massachusetts Program Type Environmental Regulations Provider Department of Fish and Game

332

Quality Assurance Program Plan for radionuclide airborne emissions monitoring  

SciTech Connect

This Quality Assurance Program Plan (QAPP) describes the quality assurance requirements and responsibilities for radioactive airborne emissions measurements activities from regulated stacks are controlled at the Hanford Site. Detailed monitoring requirements apply to stacks exceeding 1% of the standard of 10 mrem annual effective dose equivalent to the maximally exposed individual from operations of the Hanford Site.

Vance, L.M.

1993-07-01T23:59:59.000Z

333

Rules and Regulations for Governing the Administration and Enforcement of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Rules and Regulations for Governing the Administration and Rules and Regulations for Governing the Administration and Enforcement of the Fresh Water Wetlands Act (Rhode Island) Rules and Regulations for Governing the Administration and Enforcement of the Fresh Water Wetlands Act (Rhode Island) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Municipal/Public Utility Retail Supplier Rural Electric Cooperative State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Solar Wind Program Info State Rhode Island Program Type Environmental Regulations Provider Department of Environmental Managemenet

334

Radionuclide releases to the Columbia River from Hanford Operations, 1944--1971. Hanford Environmental Dose Reconstruction Project  

Science Conference Proceedings (OSTI)

The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of radionuclide emissions since 1944 from the Hanford Site. One source of radionuclide releases to the Columbia River was from production reactor operations. This report provides a quantitative estimate of the amount of radioactivity released each month (1944--1971) to the Columbia River from eleven radionuclides as well as from gross beta activity.

Heeb, C.M.; Bates, D.J.

1994-05-01T23:59:59.000Z

335

Radionuclide releases to the Columbia River from Hanford Operations, 1944--1971. Hanford Environmental Dose Reconstruction Project  

SciTech Connect

The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of radionuclide emissions since 1944 from the Hanford Site. One source of radionuclide releases to the Columbia River was from production reactor operations. This report provides a quantitative estimate of the amount of radioactivity released each month (1944--1971) to the Columbia River from eleven radionuclides as well as from gross beta activity.

Heeb, C.M.; Bates, D.J.

1994-01-01T23:59:59.000Z

336

CAPTURE OR CONTRACT?: THE EARLY YEARS OF ELECTRIC UTILITY REGULATION  

E-Print Network (OSTI)

(forthcoming) study the historical origins of governance institutions for natural gas and water, respectivelyCAPTURE OR CONTRACT?: THE EARLY YEARS OF ELECTRIC UTILITY REGULATION Thomas P. Lyon Nathan Wilson prices rose in states that adopted state regulation before 1917, suggesting that regulators were

Lyon, Thomas P.

337

Water Rules (Alabama) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Water Rules (Alabama) Water Rules (Alabama) Water Rules (Alabama) < Back Eligibility Commercial Construction Developer Industrial Local Government Municipal/Public Utility Residential Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Alabama Program Type Environmental Regulations These rules and regulations shall apply to all water systems subject to the jurisdiction of the Alabama Public Service Commission. They are intended to promote good utility practices, to assure adequate and efficient service to the public at a reasonable cost, and to establish the rights and responsibilities of both the utility and the customer. Applications for certificates must be filed separately for each water system.

338

Water Quality  

NLE Websites -- All DOE Office Websites (Extended Search)

Water Quality Water Quality We protect water quality through stormwater control measures and an extensive network of monitoring wells and stations encompassing groundwater, surface...

339

Israel -the " BACK TO THE FUTURE" opportunity for the Global Water Arena  

E-Print Network (OSTI)

Consequences of climate change: Drought and lack of fresh drinking water The aging water infrastructure can with the water arena, involves many players Water Utility Government Regulator Solution Provider Technology

Mark, Pinsky

340

doi:10.1155/2010/953537 Review Article Nanotargeted Radionuclides for Cancer Nuclear Imaging and  

E-Print Network (OSTI)

which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited. Current progress in nanomedicine has exploited the possibility of designing tumor-targeted nanocarriers being able to deliver radionuclide payloads in a site or molecular selective manner to improve the efficacy and safety of cancer imaging and therapy. Radionuclides of auger electron-, ?-, ?-, and ?-radiation emitters have been surface-bioconjugated or after-loaded in nanoparticles to improve the efficacy and reduce the toxicity of cancer imaging and therapy in preclinical and clinical studies. This article provides a brief overview of current status of applications, advantages, problems, up-to-date research and development, and future prospects of nanotargeted radionuclides in cancer nuclear imaging and radiotherapy. Passive and active nanotargeting delivery of radionuclides with illustrating examples for tumor imaging and therapy are reviewed and summarized. Research on combing different modes of selective delivery of radionuclides through nanocarriers targeted delivery for tumor imaging and therapy offers the new possibility of large increases in cancer diagnostic efficacy and therapeutic index. However, further efforts and challenges in preclinical and clinical efficacy and toxicity studies are required to translate those advanced technologies to the clinical applications for cancer patients. 1.

Internal Radiotherapy; Gann Ting; Chih-hsien Chang; Hsin-ell Wang; Te-wei Lee

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Conceptual model for regional radionuclide transport from a basalt repository site. Final draft, technical memorandum  

SciTech Connect

This technical memorandum was prepared to: (1) describe a typical basalt radionuclide repository site, (2) describe geologic and hydrologic processes associated with regional radionuclide transport in basalts, (3) define the parameters required to model regional radionuclide transport from a basalt repository site, and (4) develop a ''conceptual model'' of radionuclide transport from a basalt repository site. In a general hydrological sense, basalts may be described as layered sequences of aquifers and aquitards. The Columbia River Basalt, centered near the semi-arid Pasco Basin, is considered by many to be typical basalt repository host rock. Detailed description of the flow system including flow velocities with high-low hydraulic conductivity sequences are not possible with existing data. However, according to theory, waste-transport routes are ultimately towards the Columbia River and the lengths of flow paths from the repository to the biosphere may be relatively short. There are many physical, chemical, thermal, and nuclear processes with associated parameters that together determine the possible pattern of radionuclide migration in basalts and surrounding formations. Brief process descriptions and associated parameter lists are provided. Emphasis has been placed on the use of the distribution coefficient in simulating ion exchange. The use of the distribution coefficient approach is limited because it takes into account only relatively fast mass transfer processes. In general, knowledge of hydrogeochemical processes is primitive.

Walton, W.C.; Voorhees, M.L.; Prickett, T.A.

1980-05-23T23:59:59.000Z

342

Wastewater Regulations for National Pollutant Discharge Elimination System  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Wastewater Regulations for National Pollutant Discharge Elimination Wastewater Regulations for National Pollutant Discharge Elimination System (NPDES) Permits, Underground Injection Control (UIC) Permits, State Permits, Water Quality Based Effluent Limitations and Water Quality Certification (Mississippi) Wastewater Regulations for National Pollutant Discharge Elimination System (NPDES) Permits, Underground Injection Control (UIC) Permits, State Permits, Water Quality Based Effluent Limitations and Water Quality Certification (Mississippi) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential

343

GRR/Section 19-TX-b - New Water Right Process For Surface Water and Ground  

Open Energy Info (EERE)

TX-b - New Water Right Process For Surface Water and Ground TX-b - New Water Right Process For Surface Water and Ground Water < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 19-TX-b - New Water Right Process For Surface Water and Ground Water 19TXBNewWaterRightProcessForSurfaceWaterAndGroundWater.pdf Click to View Fullscreen Contact Agencies Texas Commission on Environmental Quality Texas Water Development Board Regulations & Policies Tex. Water Code § 11 Triggers None specified Click "Edit With Form" above to add content 19TXBNewWaterRightProcessForSurfaceWaterAndGroundWater.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range.

344

Review of information on hydrology and radionuclide migration at the Nevada Test Site 1976--1988, and annotated bibliography  

Science Conference Proceedings (OSTI)

The purpose of this report is to provide information on changes in the state of knowledge on the hydrology and radionuclide migration that have occurred at the Nevada Test Site (NTS) since 1976. In the present study, a literature review was conducted to examine information published since 1976 about the various activities that have occurred at the NTS. Information was collected from the literature on the site's geological, hydrological, geochemical, and geomorphic characteristics related to the impacts on the ground water from weapons testing and the disposal of waste at the NTS. This information was used to identify the state of knowledge about the NTS and the potential impacts of NTS activities on the ground water. More than 250 reports were reviewed, of which about 200 contained information pertinent to the subject of this report. Because the reports have never been collected in a single location, only those that were supplied by the US Department of Energy and other cooperating organizations could be reviewed, and some pertinent documents may have been missed. Appendix A contains an annotated bibliography of the reports reviewed. 149 refs., 28 figs., 2 tabs.

Raymond, J.R.; Eddy, P.A.; Wallace, R.W.; Foley, M.G.; Bierschenk, W.H.; Harrison, R.P. (Pacific Northwest Lab., Richland, WA (USA); IT Corp., Richland, WA (USA); Pacific Northwest Lab., Richland, WA (USA))

1989-09-01T23:59:59.000Z

345

GRR/Section 19-ID-a - Water Access and Water Rights | Open Energy  

Open Energy Info (EERE)

19-ID-a - Water Access and Water Rights 19-ID-a - Water Access and Water Rights < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 19-ID-a - Water Access and Water Rights 19IDAWaterAccessAndWaterRightsIssues.pdf Click to View Fullscreen Contact Agencies Idaho Department of Water Resources Regulations & Policies Idaho Code Title 42 Triggers None specified Click "Edit With Form" above to add content 19IDAWaterAccessAndWaterRightsIssues.pdf 19IDAWaterAccessAndWaterRightsIssues.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative The Idaho Department of Water Resources (IDWR) has the exclusive authority for regulation of appropriation of the public surface and ground waters of

346

Preliminary Interpretation of a Radionuclide and Colloid Tracer Test in a Granodiorite Shear Zone at the Grimsel Test Site, Switzerland  

Science Conference Proceedings (OSTI)

In February and March 2012, a tracer test involving the injection of a radionuclide-colloid cocktail was conducted in the MI shear zone at the Grimsel Test Site, Switzerland, as part of the Colloids Formation and Migration (CFM) project. The colloids were derived from FEBEX bentonite, which is mined in Spain and is being considered as a potential waste package backfill in a Spanish nuclear waste repository. The tracer test, designated test 12-02 (second test in 2012), involved the injection of the tracer cocktail into borehole CFM 06.002i2 and extraction from the Pinkel surface packer at the main access tunnel wall approximately 6.1 m from the injection interval. The test configuration is depicted in Figure 1. This configuration has been used in several conservative tracer tests and two colloid-homologue tracer tests since 2007, and it is will be employed in an upcoming test involving the emplacement of a radionuclide-doped bentonite plug into CFM 06.002i2 to evaluate the swelling and erosion of the bentonite and the transport of bentonite colloids and radionuclides from the source to the extraction point at the tunnel wall. Interpretive analyses of several of the previous tracer tests, from 09-01 through 12-02 were provided in two previous Used Fuel Disposition Program milestone reports (Arnold et al., 2011; Kersting et al., 2012). However, only the data for the conservative tracer Amino-G Acid was previously analyzed from test 12-02 because the other tracer data from this test were not available at the time. This report documents the first attempt to quantitatively analyze the radionuclide and colloid breakthrough curves from CFM test 12-02. This report was originally intended to also include an experimental assessment of colloid-facilitated transport of uranium by bentonite colloids in the Grimsel system, but this assessment was not conducted because it was reported by German collaborators at the Karlsruhe Institute of Technology (KIT) that neither uranium nor neptunium adsorbed appreciably to FEBEX bentonite colloids in Grimsel groundwater (Huber et al., 2011). The Grimsel groundwater has a relatively high pH of {approx}9, so the lack of uranium and neptunium adsorption to clay is not surprising given the tendency for these actinides to form very stable negative or neutrally-charged uranyl- or calcium-uranyl-carbonate complexes at these pH, particularly in a water that is effectively saturated with respect to calcite. It was also observed in testing conducted at LANL earlier in 2012 that uranium did not adsorb measurably to Grimsel granodiorite in a synthetic Grimsel groundwater at pH {approx}8.5 (Kersting et al., 2012). Thus, the planned experimental work was not pursued because all the available information clearly pointed to an expected result that uranium transport would not be facilitated by clay colloids in the Grimsel system.

Reimus, Paul W. [Los Alamos National Laboratory

2012-08-30T23:59:59.000Z

347

Modeling of Groundwater Flow and Radionuclide Transport at the Climax Mine sub-CAU, Nevada Test Site  

SciTech Connect

The Yucca Flat-Climax Mine Corrective Action Unit (CAU) on the Nevada Test Site comprises 747 underground nuclear detonations, all but three of which were conducted in alluvial, volcanic, and carbonate rocks in Yucca Flat. The remaining three tests were conducted in the very different hydrogeologic setting of the Climax Mine granite stock located in Area 15 at the northern end of Yucca Flat. As part of the Corrective Action Investigation (CAI) for the Yucca Flat-Climax Mine CAU, models of groundwater flow and radionuclide transport will be developed for Yucca Flat. However, two aspects of these CAU-scale models require focused modeling at the northern end of Yucca Flat beyond the capability of these large models. First, boundary conditions and boundary flows along the northern reaches of the Yucca Flat-Climax Mine CAU require evaluation to a higher level of detail than the CAU-scale Yucca Flat model can efficiently provide. Second, radionuclide fluxes from the Climax tests require analysis of flow and transport in fractured granite, a unique hydrologic environment as compared to Yucca Flat proper. This report describes the Climax Mine sub-CAU modeling studies conducted to address these issues, with the results providing a direct feed into the CAI for the Yucca Flat-Climax Mine CAU. Three underground nuclear detonations were conducted for weapons effects testing in the Climax stock between 1962 and 1966: Hard Hat, Pile Driver, and Tiny Tot. Though there is uncertainty regarding the position of the water table in the stock, it is likely that all three tests were conducted in the unsaturated zone. In the early 1980s, the Spent Fuel Test-Climax (SFT-C) was constructed to evaluate the feasibility of retrievable, deep geologic storage of commercial nuclear reactor wastes. Detailed mapping of fractures and faults carried out for the SFT-C studies greatly expanded earlier data sets collected in association with the nuclear tests and provided invaluable information for subsequent modeling studies at Climax. The objectives of the Climax Mine sub-CAU work are to (1) provide simulated heads and groundwater flows for the northern boundaries of the Yucca Flat-Climax Mine CAU model, while incorporating alternative conceptualizations of the hydrogeologic system with their associated uncertainty, and (2) provide radionuclide fluxes from the three tests in the Climax stock using modeling techniques that account for groundwater flow in fractured granite. Meeting these two objectives required two different model scales. The northern boundary groundwater fluxes were addressed using the Death Valley Regional Flow System (DVRFS) model (Belcher, 2004) developed by the U.S. Geological Survey as a modeling framework, with refined hydrostratigraphy in a zone north of Yucca Flat and including Climax stock. Radionuclide transport was simulated using a separate model confined to the granite stock itself, but linked to regional groundwater flow through boundary conditions and calibration targets.

K. Pohlmann; M. Ye; D. Reeves; M. Zavarin; D. Decker; J. Chapman

2007-09-28T23:59:59.000Z

348

Chair, CTBT working group B Radionuclide Expert Group and the U.S.  

NLE Websites -- All DOE Office Websites (Extended Search)

Chair, CTBT working group B Radionuclide Expert Group and the U.S. Chair, CTBT working group B Radionuclide Expert Group and the U.S. Radionuclide Subgroup of the Verification Monitoring Task Force, Pacific Northwest National Laboratory | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Who We Are > In The Spotlight > Ted Bowyer

349

RADIONUCLIDES IN MARINE FISHES AND BIRDS FROM AMCHITKA AND KISKA ISLANDS IN THE ALEUTIANS:  

Office of Legacy Management (LM)

RADIONUCLIDES IN MARINE FISHES AND BIRDS FROM RADIONUCLIDES IN MARINE FISHES AND BIRDS FROM AMCHITKA AND KISKA ISLANDS IN THE ALEUTIANS: ESTABLISHING A BASELINE Joanna ~ur~er,*'"ichael Gochfeld,"% David ~osson,'** Charles W. ~owers,~~"an-y ~riedlander,':~ ~ i c h a e l tabi in,^** Derek ~avret,'** Stephen ~ewett,'." Daniel ~ n i ~ a r o f f , " Ronald ~ n i g a r o f f , ~ ~ Tim ~ t a m m , ~ ~ James Weston,*** Christian ~eitner,"' and Conrad ~olz'."' Abstmct-Amchitka Island (51" N lat, 179' E long) was the site of three underground nuclear tests from 1965-1971. There have been no substantive studies of radionuclides in marine fishes and birds in the area since the mid-1970's. In this study, levels of wCo, "Eu, 90Sr, 99Tc, "q, I3'Cs, and the actinides (241~m, U 8 ~ u , "

350

Bounding Radionuclide Inventory and Accident Consequence Calculation for the 1L Target  

Science Conference Proceedings (OSTI)

A bounding radionuclide inventory for the tungsten of the Los Alamos Neutron Science Center (LANSCE) IL Target is calculated. Based on the bounding inventory, the dose resulting from the maximum credible incident (MCI) is calculated for the maximally exposed offsite individual (MEOl). The design basis accident involves tungsten target oxidation following a loss of cooling accident. Also calculated for the bounding radionuclide inventory is the ratio to the LANSCE inventory threshold for purposes of inventory control as described in the target inventory control policy. A bounding radionuclide inventory calculation for the lL Target was completed using the MCNPX and CINDER'90 codes. Continuous beam delivery at 200 {micro}A to 2500 mA{center_dot}h was assumed. The total calculated activity following this irradiation period is 205,000 Ci. The dose to the MEOI from the MCI is 213 mrem for the bounding inventory. The LANSCE inventory control threshold ratio is 132.

Kelsey, Charles T. IV [Los Alamos National Laboratory

2011-01-01T23:59:59.000Z

351

Apparatus for real-time airborne particulate radionuclide collection and analysis  

DOE Patents (OSTI)

An improved apparatus for collecting and analyzing an airborne particulate radionuclide having a filter mounted in a housing, the housing having an air inlet upstream of the filter and an air outlet downstream of the filter, wherein an air stream flows therethrough. The air inlet receives the air stream, the filter collects the airborne particulate radionuclide and permits a filtered air stream to pass through the air outlet. The improvement which permits real time counting is a gamma detecting germanium diode mounted downstream of the filter in the filtered air stream. The gamma detecting germanium diode is spaced apart from a downstream side of the filter a minimum distance for a substantially maximum counting detection while permitting substantially free air flow through the filter and uniform particulate radionuclide deposition on the filter.

Smart, John E. (West Richland, WA); Perkins, Richard W. (Richland, WA)

2001-01-01T23:59:59.000Z

352

Conceptual model for regional radionuclide transport from a salt dome repository: a technical memorandum  

Science Conference Proceedings (OSTI)

Disposal of high-level radioactive wastes is a major environmental problem influencing further development of nuclear energy in this country. Salt domes in the Gulf Coast Basin are being investigated as repository sites. A major concern is geologic and hydrologic stability of candidate domes and potential transport of radionuclides by groundwater to the biosphere prior to their degradation to harmless levels of activity. This report conceptualizes a regional geohydrologic model for transport of radionuclides from a salt dome repository. The model considers transport pathways and the physical and chemical changes that would occur through time prior to the radionuclides reaching the biosphere. Necessary, but unknown inputs to the regional model involve entry and movement of fluids through the repository dome and across the dome-country rock interface and the effect on the dome and surrounding strata of heat generated by the radioactive wastes.

Kier, R.S.; Showalter, P.A.; Dettinger, M.D.

1980-05-30T23:59:59.000Z

353

Virginia Electric Utility Regulation Act (Virginia) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Electric Utility Regulation Act (Virginia) Electric Utility Regulation Act (Virginia) Virginia Electric Utility Regulation Act (Virginia) < Back Eligibility Commercial Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Systems Integrator Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Virginia Program Type Safety and Operational Guidelines Provider Virginia State Corporation Commission The Virginia Electric Utility Regulation Act constitutes the main legislation in Virginia that pertains to the regulation of the state's electric utilities. The Act directs the State Corporation Commission to construct regulations for electric utilities, and contains information on

354

Weighted exponential regression for characterizing radionuclide concentrations in soil depth profiles  

Science Conference Proceedings (OSTI)

Characterization of radionuclide concentrations in soil profiles requires accurate evaluation of the depth distribution of the concentrations as measured by gamma emissions. An ongoing study based on 137Cs activity has shown that such concentration data generally follow an exponential trend when the fraction of radioactivity below depth is plotted against the depth. The slope of the exponential regression fit is defined as alpha/rho, the depth profile parameter. A weighted exponential regression procedure has been developed to compute a mean ??? for a group of related soil samples. Regression results from different areas or from different time periods can be used to compare representative radionuclide concentrations for the specified groupings.

C.P.Oertel; J.R.Giles

2009-11-01T23:59:59.000Z

355

Combining the radial basis function eulerian and Lagrangian schemes with geostatistics for modeling of radionuclide migration through the geosphere  

Science Conference Proceedings (OSTI)

To assess the long-term safety of a radioactive waste disposal system, mathematical models are used to describe groundwater flow, chemistry, and potential radionuclide migration through geological formations. A number of processes need to be considered, ... Keywords: Eulerian method, Geostatistics, Lagrangian method, Radial basis function, Radionuclide migration

L. Vrankar; G. Turk; F. Runovc

2004-11-01T23:59:59.000Z

356

EPA Final Ground Water Rule  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Office of Nuclear Safety and Environment Office of Nuclear Safety and Environment Nuclear Safety and Environment Information Brief HS-20-IB-2007-02 (March 2007) EPA Final Ground Water Rule Safe Drinking Water Act: National Primary Drinking Water Regulations Ground Water Rule - 40 CFR Parts 9, 141 and 142 Final Rule: 71 FR 65574 Effective Date: January 8, 2007 1 RULE SYNOPSIS On November 8, 2006, the U.S. Environmental Protection Agency (EPA) published a final Ground Water Rule (GWR) to promote increased protection against microbial pathogens that may be present in public water systems (PWSs) that use ground water sources for their supply (these systems are known as ground water systems). This Rule establishes a risk-targeted approach

357

Alaska State Regulations  

NLE Websites -- All DOE Office Websites (Extended Search)

Alaska State Regulations: Alaska State of Alaska The Alaska Oil and Gas Conservation Commission (AOGCC) regulates the drilling for and production of oil and gas resources, the...

358

Arizona State Regulations  

NLE Websites -- All DOE Office Websites (Extended Search)

Arizona State Regulations: Arizona State of Arizona The Arizona Geological Survey (AZGS) Oil and Gas Conservation Commission (OGCC) regulates the drilling for and production of...

359

Mississippi State Regulations  

NLE Websites -- All DOE Office Websites (Extended Search)

Mississippi State Regulations: Mississippi State of Mississippi The Mississippi State Oil and Gas Board (MSOGB), an independent agency, promulgates and enforces rules to regulate...

360

DETERMINATION OF REPORTABLE RADIONUCLIDES FOR DWPF SLUDGE BATCH 6 (MACROBATCH 7)  

SciTech Connect

The Waste Acceptance Product Specifications (WAPS) 1.2 require that 'The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115'. As part of the strategy to comply with WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type, all radionuclides (with half-lives greater than 10 years) that have concentrations greater than 0.01 percent of the total inventory from time of production through the 1100 year period from 2015 through 3115. The initial listing of radionuclides to be included is based on the design-basis glass as identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report (WQR). However, it is required that this list be expanded if other radionuclides with half-lives greater than 10 years are identified that may meet the greater than 0.01% criterion for Curie content. Specification 1.6 of the WAPS, International Atomic Energy Agency (IAEA) Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete set of reportable radionuclides must also include this set of U and Pu isotopes. The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Sludge Batch 5 (SB5) with H-Canyon Np transfers completed after the start of processing SB5, and Sludge Batch 6 (SB6) that was transferred to Tank 40 from Tank 51. The blend of sludge in Tank 40 is also referred to as Macrobatch 7 (MB7). This report develops the list of reportable radionuclides and associated activities as a function of time. The DWPF will use this list and the activities as one of the inputs for the development of the Production Records that relate to radionuclide inventory. This work was initiated through Technical Task Request (TTR) HLW-DWPF-TTR-2009-0014; Rev. 2 entitled Sludge Batch 6 SRNL Shielded Cells Testing. Specifically, this report details results from performing Subtask III, Item 2 of the TTR and, in part, meets Deliverable 7 of the TTR. The work was performed following the Task Technical and Quality Assurance Plan (TTQAP), SRNL-RP-2009-00473, Rev. 15 and Analytical Study Plan (ASP), SRNL-RP-2009-00474, Rev. 1. In order to determine the reportable radionuclides for SB6 (MB7), a list of radioisotopes that may meet the criteria as specified by the Department of Energy's (DOE) WAPS was developed. All radioactive U-235 fission products and all radioactive activation products that could be in the SRS HLW were considered. In addition, all U and Pu isotopes identified in WAPS 1.6 were included in the list. This list was then evaluated and some isotopes were excluded from the projection calculations. Based on measurements and analytical detection limits, 30 radionuclides have been identified as reportable for DWPF SB6 as specified by WAPS 1.2. The WCP and WQR require that all of the radionuclides present in the Design Basis glass be considered as the initial set of reportable radionuclides. For SB6, all of the radionuclides in the Design Basis glass are reportable except for three radionuclides: Pd-107, Cs-135, and Th-230. At no time during the 1100-year period between 2015 and 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. Two additional uranium isotopes (U-235 and -236) must be added to the list of reportable radionuclides in order to meet WAPS 1.6. All of the Pu isotopes (Pu-238, -239, -240, -241, and -242) and other U isotopes (U-233, -234, and -238) identified in WAPS 1.6 were already determined to be reportable according to WAPS 1.2 This brings the total number of reportable radionuclides for SB6 to 32. The radionuclide measurements made for SB6 are the most extensive condu

Bannochie, C.; Diprete, D.

2011-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

DETERMINATION OF REPORTABLE RADIONUCLIDES FOR DWPF SLUDGE BATCH 7B (MACROBATCH 9)  

SciTech Connect

The Waste Acceptance Product Specifications (WAPS) 1.2 require that “The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115”. As part of the strategy to comply with WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type, all radionuclides (with half-lives greater than 10 years) that have concentrations greater than 0.01 percent of the total inventory from time of production through the 1100 year period from 2015 through 3115. The initial listing of radionuclides to be included is based on the design-basis glass as identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report (WQR). However, it is required that this list be expanded if other radionuclides with half-lives greater than 10 years are identified that may meet the greater than 0.01% criterion for Curie content. Specification 1.6 of the WAPS, International Atomic Energy Agency (IAEA) Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete set of reportable radionuclides must also include this set of U and Pu isotopes. The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Sludge Batch 7a (SB7a) and Sludge Batch 7b (SB7b) that was transferred to Tank 40 from Tank 51. The blend of sludge in Tank 40 is also referred to as Macrobatch 9 (MB9). This report develops the list of reportable radionuclides and associated activities as a function of time. The DWPF will use this list and the activities as one of the inputs for the development of the Production Records that relate to radionuclide inventory. This work was initiated through Technical Task Request (TTR) HLW-DWPF-TTR-2011-0004; Rev. 0 entitled Sludge Batch 7b Qualification Studies. Specifically, this report details results from performing Subtask II, Item 2 of the TTR and, in part, meets Deliverable 6 of the TTR. The work was performed following the Task Technical and Quality Assurance Plan (TTQAP), SRNL-RP-2011-00247, Rev. 0 and Analytical Study Plan (ASP), SRNL-RP-2011-00248, Rev. 0. In order to determine the reportable radionuclides for SB7b (MB9), a list of radioisotopes that may meet the criteria as specified by the Department of Energy’s (DOE) WAPS was developed. All radioactive U-235 fission products and all radioactive activation products that could be in the SRS HLW were considered. In addition, all U and Pu isotopes identified in WAPS 1.6 were included in the list. This list was then evaluated and some isotopes were excluded from the projection calculations. Based on measurements and analytical detection limits, 27 radionuclides have been identified as reportable for DWPF SB7b as specified by WAPS 1.2. The WCP and WQR require that all of the radionuclides present in the Design Basis glass be considered as the initial set of reportable radionuclides. For SB7b, all of the radionuclides in the Design Basis glass are reportable except for three radionuclides: Pd-107, Cs-135, and Th-230. At no time during the 1100-year period between 2015 and 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. Two additional uranium isotopes (U-235 and -236) must be added to the list of reportable radionuclides in order to meet WAPS 1.6. All of the Pu isotopes (Pu-238, -239, -240, -241, and -242) and other U isotopes (U-233, -234, and -238) identified in WAPS 1.6 were already determined to be reportable according to WAPS 1.2 This brings the total number of reportable radionuclides for SB7b to 29. The radionuclide measurements made for SB7b are similar to those performed in the previous SB7a MB8 work. Some method development/refine

Crawford, C. L.; Diprete, D. P.

2013-08-22T23:59:59.000Z

362

Water Use for Electric Power Generation  

Science Conference Proceedings (OSTI)

This report analyzes how thermoelectric plants use water and the strengths, limitations, and costs of available technologies for increasing water use efficiency (gal/MWh). The report will be of value to power company strategic planners, environmental managers, and generation managers as well as regulators, water resource managers, and environmentalists.

2008-02-25T23:59:59.000Z

363

Turbid water Clear water  

E-Print Network (OSTI)

: The submersible laser bathymetric (LBath) optical system is capable of simultaneously providing visual images- dynamical wing. This underwater package is pulled through the water by a single towed cable with fiber optic special high energy density optical fibers. A remote Pentium based PC also at the surface is used

Jaffe, Jules

364

GRR/Section 19-OR-a - Water Access & Water Rights Issues | Open Energy  

Open Energy Info (EERE)

19-OR-a - Water Access & Water Rights Issues 19-OR-a - Water Access & Water Rights Issues < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 19-OR-a - Water Access & Water Rights Issues 19ORAWaterAccessWaterRightsIssues.pdf Click to View Fullscreen Contact Agencies Oregon Water Resources Department Regulations & Policies ORS Chapter 537: Appropriation of Water Generally Triggers None specified Click "Edit With Form" above to add content 19ORAWaterAccessWaterRightsIssues.pdf 19ORAWaterAccessWaterRightsIssues.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative All water is publicly owned under Oregon law. All users must obtain a permit or water right from the Oregon Water Resources Department (WRD) to

365

Water Intoxication  

E-Print Network (OSTI)

2008, May 14). Too much water raises seizure risk in babies.id=4844 9. Schoenly, Lorry. “Water Intoxication and Inmates:article/246650- overview>. 13. Water intoxication alert. (

Lingampalli, Nithya

2013-01-01T23:59:59.000Z

366

DETERMINATION OF REPORTABLE RADIONUCLIDES FOR DWPF SLUDGE BATCH 5 (MACROBATCH 6)  

SciTech Connect

The Waste Acceptance Product Specifications (WAPS) 1.2 require that ''The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115''. As part of the strategy to comply with WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type, all radionuclides (with half-lives greater than 10 years) that have concentrations greater than 0.01 percent of the total inventory from time of production through the 1100 year period from 2015 through 3115. The initial listing of radionuclides to be included is based on the design-basis glass as identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report (WQR). However, it is required that this list be expanded if other radionuclides with half-lives greater than 10 years are identified that may meet the greater than 0.01% criterion for Curie content. Specification 1.6 of the WAPS, International Atomic Energy Agency (IAEA) Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete set of reportable radionuclides must also include this set of U and Pu isotopes. The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Tank 40 (Sludge Batch 4 (SB4)), Sludge Batch 5 (SB5) that was transferred to Tank 40 from Tank 51, and H-Canyon Np transfers completed after the start of processing. The blend of sludge in Tank 40 is also referred to as Macrobatch 6 (MB6). This report develops the list of reportable radionuclides and associated activities and determines the radionuclide activities as a function of time. The DWPF will use this list and the activities as one of the inputs for the development of the Production Records that relate to the radionuclide inventory. This work was initiated through Technical Task Request (TTR) HLW-DWPF-TTR-2008-0010; Rev. 2 entitled Sludge Batch 5 SRNL Shielded Cells Testing. Specifically, this report details results from performing Subtask II, 5 of the TTR and, in part, meets Deliverable 7 of the TTR. The work was performed following the Task Technical and Quality Assurance Plan (TTQAP), WSRC-RP-2008-00137, Rev. 2 and Analytical Study Plan (ASP), WSRC-RP-2008-00138, Rev. 2. In order to determine the reportable radionuclides for SB5 (MB6), a list of radioisotopes that may meet the criteria as specified by the Department of Energy's (DOE) WAPS was developed. All radioactive U-235 fission products and all radioactive activation products that could be in the SRS HLW were considered. In addition, all U and Pu isotopes identified in WAPS 1.6 were included in the list. This list was then evaluated and some isotopes excluded from the projection calculations. Based on measurements and analytical detection limits, twenty-six radionuclides have been identified as reportable for DWPF SB5 as specified by WAPS 1.2. The 26 reportable radionuclides are: Cl-36, Ni-59, Ni-63, Sr-90, Zr-93, Nb-93m, Tc-99, Sn-126, Cs-137, Sm-151, U-233, U-234, Np-237, U-238, Pu-238, Pu-239, Pu-240, Am-241, Pu-241, Pu-242, Am-242m, Am-243, Cm-244, Cm-245, Cm-246, Cf-251. Chlorine-36 is reported for the first time based on the upper bounding activity determined from the aqua regia digested sludge slurry. The WCP and WQR require that all of radionuclides present in the Design Basis glass be considered as the initial set of reportable radionuclides. For SB5 (MB6), all of the radionuclides in the Design Basis glass are reportable except for four radionuclides: Se-79, Pd-107, Cs-135, and Th-230. At no time through the year 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. Two additional uranium isotopes (U-235 and -236) must be added to

Bannochie, C.; Bibler, N.; Diprete, D.

2010-02-04T23:59:59.000Z

367

COLLOID AND COLLOID-FACILITATED RADIONUCLIDE TRANSPORT AT THE SEMI-ARID HANFORD SITE  

E-Print Network (OSTI)

COLLOID AND COLLOID-FACILITATED RADIONUCLIDE TRANSPORT AT THE SEMI-ARID HANFORD SITE By ZIRU LIU Hanford project. Unfortunately, he just passed away this January and could not see the completion-ARID HANFORD SITE Abstract by Ziru Liu, Ph.D. Washington State University May 2013 Chair: Markus Flury

Flury, Markus

368

Forage uptake of uranium series radionuclides in the vicinity of the anaconda uranium mill  

Science Conference Proceedings (OSTI)

Radiochemical analysis was performed on samples of soil and eight species of common vegetation growing on the Anaconda uranium mill site, located in New Mexico. The concentrations of the long-lived radionuclides U-238, U-234, Th-230, Ra-226, and Pb-210 in these forage plants were determined. The sampling procedures and analytical laboratory methods used are described. The highest radionuclide concentration found in a forage species was 130 pCi of Ra-226 per gram dry weight for grass growing on the main tailings pile at Anaconda, where the surface soil activity of Ra-226 was 236 pCi/g. A comparison of shoots activity with that of roots and soil was used to determine a distribution index and uptake coefficient for each species. The distribution index, the ratio of root activity to shoot activity, ranged from 0.30 (Th-230) in galleta grass (Hilaria jamesii) to 38.0 (Ra-226) in Indian ricegrass (Oryzopsis hymenoides). In nearly all instances, the roots contained higher radionuclide concentrations. The uptake coefficient, the ratio of vegetation activity to soil activity, ranged from 0.69 (U-238) in Indian ricegrass roots to 0.01 (U-238) in four-wing saltbush (Atriplex canescans) shoots. The range of radionuclide concentrations in plants growing on the Anaconda mill site is compared to that in vegetation from a control site 20 km away.

Rayno, D.R.; Momeni, M.H.; Sabau, C.

1980-01-01T23:59:59.000Z

369

National low-level waste management program radionuclide report series, Volume 14: Americium-241  

Science Conference Proceedings (OSTI)

This report, Volume 14 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of americium-241 ({sup 241}Am). This report also includes discussions about waste types and forms in which {sup 241}Am can be found and {sup 241}Am behavior in the environment and in the human body.

Winberg, M.R.; Garcia, R.S.

1995-09-01T23:59:59.000Z

370

Assessment of Dose to the Nursing Infant from Radionuclides in Breast Milk  

SciTech Connect

A computer software package was developed to predict tissue doses to an infant due to intake of radionuclides in breast milk based on bioassay measurements and exposure data for the mother. The package is intended mainly to aid in decisions regarding the safety of breast feeding by a mother who has been acutely exposed to a radionuclide during lactation or pregnancy, but it may be applied to previous intakes during the mother s adult life. The package includes biokinetic and dosimetric information needed to address intake of Co-60, Sr-90, Cs-134, Cs-137, Ir-192, Pu-238, Pu-239, Am-241, or Cf-252 by the mother. It has been designed so that the library of biokinetic and dosimetric files can be expanded to address a more comprehensive set of radionuclides without modifying the basic computational module. The methods and models build on the approach used in Publication 95 of the International Commission on Radiological Protection (ICRP 2004), Doses to Infants from Ingestion of Radionuclides in Mothers Milk . The software package allows input of case-specific information or judgments such as chemical form or particle size of an inhaled aerosol. The package is expected to be more suitable than ICRP Publication 95 for dose assessment for real events or realistic planning scenarios in which measurements of the mother s excretion or body burden are available.

Leggett, Richard Wayne [ORNL; Eckerman, Keith F [ORNL

2010-03-01T23:59:59.000Z

371

Water Quality Criteria for Intrastate, Interstate, and Coastal Water  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Quality Criteria for Intrastate, Interstate, and Coastal Quality Criteria for Intrastate, Interstate, and Coastal Water (Mississippi) Water Quality Criteria for Intrastate, Interstate, and Coastal Water (Mississippi) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Mississippi Program Type Environmental Regulations

372

A Serendipitous, Long-Term Infiltration Experiment: Water and Tritium Circulation Beneath the CAMBRIC Ditch at the Nevada Test Site  

Science Conference Proceedings (OSTI)

Underground nuclear weapons testing at the Nevada Test Site introduced numerous radionuclides that may be used to characterize subsurface hydrologic transport processes in arid climates. A sixteen year pumping experiment designed to examine radionuclide migration away from the CAMBRIC nuclear test, conducted in groundwater beneath Frenchman Flat in 1965, gave rise to an unintended second experiment involving radionuclide infiltration through the vadose zone, as induced by seepage of pumping effluents beneath an unlined discharge trench. The combined experiments have been reanalyzed using a detailed, three-dimensional numerical model of transient, variably saturated flow and mass transport, tailored specifically for large scale and efficient calculations. Simulations have been used to estimate radionuclide travel and residence times in various parts of the system for comparison with observations in wells. Model predictions of mass transport were able to clearly demonstrate radionuclide recycling behavior between the ditch and pumping well previously suggested by isotopic age dating information; match travel time estimates for radionuclides moving between the ditch, the water table, and monitoring wells; and provide more realistic ways in which to interpret the pumping well elution curves. Collectively, the results illustrate the utility of integrating detailed numerical modeling with diverse observational data in developing accurate interpretations and forecasts of contaminant migration processes.

Maxwell, R M; Tompson, A B; Kollet, S J

2008-11-20T23:59:59.000Z

373

Literature and data review for the surface-water pathway: Columbia River and adjacent coastal areas  

SciTech Connect

As part of the Hanford Environmental Dose Reconstruction Project, Pacific Northwest Laboratory reviewed literature and data on radionuclide concentrations and distribution in the water, sediment, and biota of the Columbia River and adjacent coastal areas. Over 600 documents were reviewed including Hanford reports, reports by offsite agencies, journal articles, and graduate theses. Certain radionuclide concentration data were used in preliminary estimates of individual dose for the 1964--1966 time period. This report summarizes the literature and database review and the results of the preliminary dose estimates.

Walters, W.H.; Dirkes, R.L.; Napier, B.A.

1992-04-01T23:59:59.000Z

374

Literature and data review for the surface-water pathway: Columbia River and adjacent coastal areas  

Science Conference Proceedings (OSTI)

As part of the Hanford Environmental Dose Reconstruction (HEDR) Project, Battelle, Pacific Northwest Laboratories reviewed literature and data on radionuclide concentrations and distribution in the water, sediment, and biota of the Columbia River and adjacent coastal areas. Over 600 documents were reviewed including Hanford reports, reports by offsite agencies, journal articles, and graduate theses. Radionuclide concentration data were used in preliminary estimates of individual dose for the period 1964 through 1966. This report summarizes the literature and database reviews and the results of the preliminary dose estimates.

Walters, W.H.; Dirkes, R.L.; Napier, B.A.

1992-11-01T23:59:59.000Z

375

Advanced Assay Systems for Radionuclide Contamination in Soils  

SciTech Connect

Through the support of the Department of Energy (DOE) Office of Environmental Management (EM) Technical Assistance Program, the Idaho National Laboratory (INL) has developed and deployed a suite of systems that rapidly scan, characterize, and analyze surface soil contamination. The INL systems integrate detector systems with data acquisition and synthesis software and with global positioning technology to provide a real-time, user-friendly field deployable turn-key system. INL real-time systems are designed to characterize surface soil contamination using methodologies set forth in the Multi-Agency Radiation Surveys and Site Investigation Manual (MARSSIM). MARSSIM provides guidance for planning, implementing, and evaluating environmental and facility radiological surveys conducted to demonstrate compliance with a dose or risk-based regulation and provides real-time information that is immediately available to field technicians and project management personnel. This paper discusses the history of the development of these systems and describes some of the more recent examples and their applications.

J. R. Giles; L. G. Roybal; M. V. Carpenter; C. P. Oertel; J. A. Roach

2008-02-01T23:59:59.000Z

376

Federal Energy Management Program: Laws & Regulations  

NLE Websites -- All DOE Office Websites (Extended Search)

Laws and Regulations Laws and Regulations EISA 432 Compliance Tracking Track Federal agency progress toward Section 432 of the Energy Independence and Security Act (EISA) of 2007 using FEMP's EISA 432 Compliance Tracking System. Federal laws and regulations set multiple energy management requirements for Federal agencies spanning energy efficiency, renewable energy, water conservation, and alternative fuel use. This section outlines Federal energy management authorities through: Requirements by Subject: Find regulatory requirements and related guidance by topic area. Requirements by Regulation: Take an in-depth look at individual laws and regulations. The Federal Energy Management Program (FEMP) analyzes energy management authorities and develops rules and guidance to help Federal agencies comply with applicable requirements. Reporting requirements and Federal Government performance reports are also available through:

377

Pharmaceutical Waters  

Science Conference Proceedings (OSTI)

Table 3   Water treatment process for water for injection (WFI)...deionization WFI production Evaporation still or vapor compression...

378

Water Snakes  

NLE Websites -- All DOE Office Websites (Extended Search)

of Cook County George W. Dunne, President Roland F. Eisenbeis, Supt. of Conservation WATER SNAKES Contrary to popular belief, the Water Moccasin commonly known as the...

379

Regulating the information gatekeepers  

Science Conference Proceedings (OSTI)

Concerns about biased manipulation of search results may require intervention involving government regulation.

Patrick Vogl; Michael Barrett

2010-11-01T23:59:59.000Z

380

Water Outlet Control Mechanism for Fuel Cell System Operation ...  

Self-Regulating Water Separation System for Fuel Cells Innovators at NASA’s Johnson Space ... Solar Thermal; Startup ... The system uses the flow energy of the fuel ...

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Louisiana Water Control Law (Louisiana) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Control Law. This law states regulations for water quality control and states the powers and duties of the secretary of environmental quality. It provides information about...

382

Radionuclide Migration Experiments in Tuff Blocks/Underunsaturated and Saturated Conditions at a Scale of Up to 1 Metre  

Science Conference Proceedings (OSTI)

To complement migration experiments with non-radioactive tracers in the Busted Butte experimental facility (BBTF) at the Nevada Test Site, an exploratory migration experiment has been performed under unsaturated conditions in a {approx}0.3m x {approx}0.3m x {approx}0.3m block of tuff. Longer term migration experiments, up to 600 days, under unsaturated and saturated conditions in {approx}1 m3 blocks of tuff have recently been completed. Na-fluorescein, 3H (as tritiated water), 22Na, 60Co, 95mTc and/or 99Tc (as the pertechnetate anion), 137Cs, and 237Np were used as tracers in all three experiments. Under unsaturated conditions, Tc is transported slightly faster than 3H, while under saturated conditions, the chemical conditions became highly reducing, leading to significant retardation of Tc along the flow field. If chemically reducing conditions can be demonstrated to exist in the saturated zone downstream from the proposed repository, the geological formations underlying the proposed repository horizon can potentially act as a geological barrier to the transport of some multivalent radionuclides.

Vandergraaf, T. T.; Drew, D. J.; Ticknor, K. V.; Hamon, C. J.; Seddon, W. A.

2003-02-25T23:59:59.000Z

383

Usefulness of specific calibration coefficients for gamma-emitting sources measured by radionuclide calibrators in nuclear medicine  

Science Conference Proceedings (OSTI)

Purpose: In nuclear medicine, the activity of a radionuclide is measured with a radionuclide calibrator that often has a calibration coefficient independent of the container type and filling. Methods: To determine the effect of the container on the accuracy of measuring the activity injected into a patient, The authors simulated a commercial radionuclide calibrator and 18 container types most typically used in clinical practice. The instrument sensitivity was computed for various container thicknesses and filling levels. Monoenergetic photons and electrons as well as seven common radionuclides were considered. Results: The quality of the simulation with gamma-emitting sources was validated by an agreement with measurements better than 4% in five selected radionuclides. The results show that the measured activity can vary by more than a factor of 2 depending on the type of container. The filling level and the thickness of the container wall only have a marginal effect for radionuclides of high energy but could induce differences up to 4%. Conclusions: The authors conclude that radionuclide calibrators should be tailored to the uncertainty required by clinical applications. For most clinical cases, and at least for the low-energy gamma and x-ray emitters, measurements should be performed with calibration coefficients specific to the container type.

Bochud, Francois O.; Laedermann, Jean-Pascal; Baechler, Sebastien; Kosinski, Marek; Bailat, Claude J. [Institute of Radiation Physics, University Hospital and University of Lausanne, Rue du Grand-Pre 1, CH-1007 Lausanne (Switzerland)

2011-07-15T23:59:59.000Z

384

WATER-TRAPPED WORLDS  

Science Conference Proceedings (OSTI)

Although tidally locked habitable planets orbiting nearby M-dwarf stars are among the best astronomical targets to search for extrasolar life, they may also be deficient in volatiles and water. Climate models for this class of planets show atmospheric transport of water from the dayside to the nightside, where it is precipitated as snow and trapped as ice. Since ice only slowly flows back to the dayside upon accumulation, the resulting hydrological cycle can trap a large amount of water in the form of nightside ice. Using ice sheet dynamical and thermodynamical constraints, I illustrate how planets with less than about a quarter the Earth's oceans could trap most of their surface water on the nightside. This would leave their dayside, where habitable conditions are met, potentially dry. The amount and distribution of residual liquid water on the dayside depend on a variety of geophysical factors, including the efficiency of rock weathering at regulating atmospheric CO{sub 2} as dayside ocean basins dry up. Water-trapped worlds with dry daysides may offer similar advantages as land planets for habitability, by contrast with worlds where more abundant water freely flows around the globe.

Menou, Kristen [Department of Astronomy, Columbia University, 550 West 120th Street, New York, NY 10027 (United States)

2013-09-01T23:59:59.000Z

385

Regulating with Carrots, Regulating with Sticks  

E-Print Network (OSTI)

of necessary brevity. To vehicle manufacturers, inconsistent1997: 461). Motor vehicle manufacturers successfully arguedonly on engine and vehicle manufacturers. 3. Regulating

Thornton, Dorothy; Kagan, Robert; Gunningham, Neil

2006-01-01T23:59:59.000Z

386

PWR Primary-Side Gas Management in Advanced Light Water Reactors  

Science Conference Proceedings (OSTI)

The designs for advanced light water reactors (ALWRs) have incorporated new water chemistry controls that have been developed over the past few decades to improve material and equipment reliability and fuel performance and to minimize radionuclide production and transport. It is important to ensure that the new designs operate within ranges that are considered safe based on current knowledge and that industry guidance for normal operation, startup, and shutdown are updated to account for expanding ...

2013-07-17T23:59:59.000Z

387

Fire as a long-term stewardship issue for soils contaminated with radionuclides in the western U.S  

SciTech Connect

On both U.S. Department of Energy (DOE) and U.S. Department of Defense sites in the southwestern United States (U.S.), significant areas of surface soils are contaminated with radionuclides from atmospheric nuclear testing, and with depleted uranium, primarily from military training. At DOE sites in Nevada, the proposed regulatory closure strategy for most sites is to leave contaminants in place with administrative controls and periodic monitoring. Closure-in-place is considered an acceptable strategy because the contaminated sites exist on access-restricted facilities, decreasing the potential risk to public receptor, the high cost and feasibility of excavating contaminated soils over large areas, and the environmental impacts of excavating desert soils that recover very slowly from disturbance. The largest of the contaminated sites on the Tonopah Test Range in Nevada covers over 1,200 hectares. However, a factor that has not been fully investigated in the long-term stewardship of these sites is the potential effects of fires. Because of the long half-lives of some of the contaminants (e.g., 24,100 years for {sup 239}Pu) and changes in land-cover and climatic factors that are increasing the frequency of fires throughout the western U.S., it should be assumed that all of these sites will eventually burn, possibly multiple times, during the time frame when they still pose a risk. Two primary factors are contributing to increased fire frequency. The first is the spread of invasive grasses, particularly cheat grass (Bromus tectorum and Bromus rubens), which have out-competed native annuals and invaded inter-spaces between shrubs, allowing fires to burn easier. The second is a sharp increase in fire frequency and size throughout the western U.S. beginning in the mid-1980's. This second factor appears to correlate with an increase in average spring and summer temperatures, which may be contributing to earlier loss of soil moisture and longer periods of dry plant biomass (particularly from annual plants). The potential risk to site workers from convective heat dispersion of radionuclide contaminants is an immediate concern during a fire. Long-term, post-fire concerns include potential changes in windblown suspension properties of contaminated soil particles after fires because of loss of vegetation cover and changes in soil properties, and soil erosion from surface water runoff and fluvial processes. (authors)

Shafer, David S.; DuBois, David; Etyemezian, Vic; Kavouras, Ilias; Miller, Julianne J.; Nikolich, George; Stone, Mark [Desert Research Institute, 755 East Flamingo Road, Las Vegas, Nevada, 89119 (United States)

2007-07-01T23:59:59.000Z

388

GRR/Section 19-TX-a - Water Access and Water Issues Overview | Open Energy  

Open Energy Info (EERE)

9-TX-a - Water Access and Water Issues Overview 9-TX-a - Water Access and Water Issues Overview < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 19-TX-a - Water Access and Water Issues Overview 19TXAWaterAccessAndWaterRightsIssuesOverview.pdf Click to View Fullscreen Contact Agencies Texas Commission on Environmental Quality Regulations & Policies Tex. Water Code § 11 Triggers None specified Click "Edit With Form" above to add content 19TXAWaterAccessAndWaterRightsIssuesOverview.pdf 19TXAWaterAccessAndWaterRightsIssuesOverview.pdf 19TXAWaterAccessAndWaterRightsIssuesOverview.pdf 19TXAWaterAccessAndWaterRightsIssuesOverview.pdf Flowchart Narrative In the late 1960's Texas transitioned its water law system, switching

389

GRR/Section 19-NV-a - Water Access and Water Rights Issues | Open Energy  

Open Energy Info (EERE)

GRR/Section 19-NV-a - Water Access and Water Rights Issues GRR/Section 19-NV-a - Water Access and Water Rights Issues < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 19-NV-a - Water Access and Water Rights Issues 19NVAWaterAccessAndWaterRightsIssues.pdf Click to View Fullscreen Contact Agencies Nevada Division of Water Resources Nevada Division of Environmental Protection Regulations & Policies Nevada Revised Statutes (NRS) NRS, Chapter 445A - water controls NRS, Chapter 533 - adjudication of vested water rights and appropriation of public waters NRS, Chapter 534 - outlines underground water and well NRS, Chapter 534A - geothermal resources Nevada Administrative Code (NAC) NAC, Chapter 445A - water controls Triggers None specified Click "Edit With Form" above to add content

390

Recommendations to the Technical Steering Panel regarding approach for estimating individual radiation doses resulting from releases of radionuclides to the Columbia River  

Science Conference Proceedings (OSTI)

At the direction of the Technical Steering Panel (TSP) of the Hanford Environmental Dose Reconstruction (HEDR) Project, Battelle staff have reviewed and analyzed available data regarding possible historical radiation doses to individuals resulting from radionuclide releases to the Columbia River. The objective of this review was to recommend to the TSP the spatial and temporal scope and level of effort on Columbia River work to most effectively extend work performed in Phase I of the project (PNL 1991a, PNL 1991b) to meet the project objectives. A number of options were analyzed. Four stretches of the Columbia River and adjacent Pacific coastal waters were defined and investigated for four time periods. Radiation doses arising from ten potentially major exposure pathways were evaluated for each of the time/location combinations, and several alternative methods were defined for estimating the doses from each pathway. Preliminary cost estimates were also developed for implementing dose estimation activities for each of the possible combinations.

Napier, B.A.; Brothers, A.J.

1992-07-01T23:59:59.000Z

391

Recommendations to the Technical Steering Panel regarding approach for estimating individual radiation doses resulting from releases of radionuclides to the Columbia River. Volume 1, Recommendations  

Science Conference Proceedings (OSTI)

At the direction of the Technical Steering Panel (TSP) of the Hanford Environmental Dose Reconstruction (HEDR) Project, Battelle staff have reviewed and analyzed available data regarding possible historical radiation doses to individuals resulting from radionuclide releases to the Columbia River. The objective of this review was to recommend to the TSP the spatial and temporal scope and level of effort on Columbia River work to most effectively extend work performed in Phase I of the project (PNL 1991a, PNL 1991b) to meet the project objectives. A number of options were analyzed. Four stretches of the Columbia River and adjacent Pacific coastal waters were defined and investigated for four time periods. Radiation doses arising from ten potentially major exposure pathways were evaluated for each of the time/location combinations, and several alternative methods were defined for estimating the doses from each pathway. Preliminary cost estimates were also developed for implementing dose estimation activities for each of the possible combinations.

Napier, B.A.; Brothers, A.J.

1992-07-01T23:59:59.000Z

392

Investigating Water  

E-Print Network (OSTI)

This 3-ring binder contains teaching plans for 12 lessons on topics such as "Water in Our Daily Lives," "The Water Cycle," "Amazing Aquifers," "Water and Soil," "Aquatic Ecosystems," and "Water Wise Use." Accompanying each lesson plan are activity and record sheets for hands-on learning experiences. This curriculum is intended for students in about 4th to 8th grades.

Howard Jr., Ronald A.

2002-01-02T23:59:59.000Z

393

New Stochastic Annual Limits on Intake for Selected Radionuclides  

SciTech Connect

Annual limits on intake (ALI) have historically been tabulated by the International Commission on Radiological Protection (e.g., ICRP 1979, 1961) and also by the Environmental Protection Agency (EPA 1988). These compilations have been rendered obsolete by more recent ICRP dosimetry methods, and, rather than provide new ALIs, the ICRP has opted instead to provide committed dose coefficients from which an ALI can be determined by a user for a specific set of conditions. The U.S. Department of Energy historically has referenced compilations of ALIs and has defined their method of calculation in its radiation protection regulation (10 CFDR 835), but has never provided a specific compilation. Under June 2007 amendments to 10 CFR 835, ALIs can be calculated by dividing an appropriate dose limit, either 5-rem (0.05 Sv) effective dose or 50 rem (0.5 Sv) equivalent dose to an individual organ or tissue, by an appropriate committed dose coefficient. When based on effective dose, the ALI is often referred to as a stochastic annual limit on intake (SALI), and when based on the individual organ or tissue equivalent limit, it has often been called a deterministic annual limit on intake (DALI).

Carbaugh, Eugene H.

2009-08-24T23:59:59.000Z

394

Tabulation of dose equivalent per microcurie-day for source and target organs of an adult for various radionuclides  

SciTech Connect

Data are tabulated on the radiation dose equivalent per microcurie-day for source and target organs of a human adult for 100 radionuclides. These are listed at the end of the volume. Included are several radionuclides where the parent has a daughter radionuclide of physical half-life less than five minutes. In such cases separate S tables are given for the parent and for the daughter as well as a composite table which contains S values for the parent plus S values for the daughter weighted according to the percent decay via the daughter. (CH)

Snyder, W.S.; Ford, M.R.; Warner, G.G.; Watson, S.B.

1975-11-01T23:59:59.000Z

395

Clean Water Act | Open Energy Information  

Open Energy Info (EERE)

Clean Water Act Clean Water Act Year 1972 Url CWA.jpg Description The Clean Water Act was established to restore and maintain the chemical, physical, and biological integrity of the nation's waters. References CWA[1] Federal Oil and Gas[2] The Clean Water Act (CWA) (33 U.S.C. § 1251 et seq.) - The Clean Water Act was established to restore and maintain the chemical, physical, and biological integrity of the nation's waters. The CWA aims to protect water quality through development of water quality standards, anti-degradation policies, water quality permitting procedures, water body monitoring and assessment programs, and elimination or point and nonpoint pollution sources. The CWA regulates the National Pollutant Discharge Elimination System (NPDES) permitting process, which establishes, through a permit,

396

Regulations For Electric Companies (Tennessee) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Regulations For Electric Companies (Tennessee) Regulations For Electric Companies (Tennessee) Regulations For Electric Companies (Tennessee) < Back Eligibility Investor-Owned Utility Municipal/Public Utility Retail Supplier Rural Electric Cooperative State/Provincial Govt Transportation Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Tennessee Program Type Generating Facility Rate-Making Net Metering Provider Tennessee Regulatory Authority The Regulations for Electric Companies are under the Authority of the Tennessee Regulatory Authority, which is the public service branch of the state government. These regulations establish the records electricity providers are required to keep and submit. It requires that all electricity

397

Georgia Water Quality Control Act (Georgia) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Georgia Water Quality Control Act (Georgia) Georgia Water Quality Control Act (Georgia) Georgia Water Quality Control Act (Georgia) < Back Eligibility Agricultural Commercial Construction Developer Fuel Distributor Industrial Installer/Contractor Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Systems Integrator Transportation Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Georgia Program Type Environmental Regulations Siting and Permitting Provider Georgia Department of Natural Resources The Georgia Water Quality Control Act (WQCA) is a set of environmental regulations and permitting requirements that comply with the federal Clean Water Act. The Georgia Water Quality Control Act is enforced by the Georgia

398

Radiation dose assessment methodology and preliminary dose estimates to support US Department of Energy radiation control criteria for regulated treatment and disposal of hazardous wastes and materials  

Science Conference Proceedings (OSTI)

This report provides unit dose to concentration levels that may be used to develop control criteria for radionuclide activity in hazardous waste; if implemented, these criteria would be developed to provide an adequate level of public and worker health protection, for wastes regulated under U.S, Environmental Protection Agency (EPA) requirements (as derived from the Resource Conservation and Recovery Act [RCRA] and/or the Toxic Substances Control Act [TSCA]). Thus, DOE and the US Nuclear Regulatory Commission can fulfill their obligation to protect the public from radiation by ensuring that such wastes are appropriately managed, while simultaneously reducing the current level of dual regulation. In terms of health protection, dual regulation of very small quantities of radionuclides provides no benefit.

Aaberg, R.L.; Baker, D.A.; Rhoads, K.; Jarvis, M.F.; Kennedy, W.E. Jr.

1995-07-01T23:59:59.000Z

399

Regulations of the Arkansas Operating Air Permit Program (Arkansas) |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Regulations of the Arkansas Operating Air Permit Program (Arkansas) Regulations of the Arkansas Operating Air Permit Program (Arkansas) Regulations of the Arkansas Operating Air Permit Program (Arkansas) < Back Eligibility Commercial Construction Fuel Distributor Industrial Investor-Owned Utility Retail Supplier Utility Program Info State Arkansas Program Type Environmental Regulations Siting and Permitting Provider Department of Environmental Quality The Regulations of the Arkansas Air Operating Program are adopted in accordance with the provisions of Part UU of the Arkansas Water and Air Pollution Control Act, Arkansas Code Annotated 8-4-101, and will be referred to in this description as "program", "regulations" and "regulation No. 26". The regulations are intended to meet the requirements of title of

400

Incentive regulation and the regulation of incentives  

Science Conference Proceedings (OSTI)

This thesis explores the regulatory problem of incentives and the question of how to create a regulatory framework that most nearly aligns the firm's private interests with the public good. The main themes are: (1) an efficiency loss is inherent in the regulatory relationship, as long as the regulator knows less about the firm's operations than the firm itself; and (2) regulation itself is an incentive mechanism, so that the regulator can choose how to motivate the firm but now whether to do so. An analytical model is used to show the tradeoff between inducing efficient production and efficient pricing. The thesis surveys and analyzes incentive regulation mechanisms adopted by state utility commissions, using a Washington state plan as a case study. A natural extension of incentive regulation is discussed, in which the firm's reward depends on the total gain in consumer surplus rather than just the reduction in expenditures. The ability of the regulator to commit to future actions is central to incentive regulation, as well as many other aspects of regulation.

Blackmon, B.G. Jr.

1991-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "water regulations radionuclides" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Rules and Regulations Governing Geophysical, Seismic or Other Type  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Rules and Regulations Governing Geophysical, Seismic or Other Type Rules and Regulations Governing Geophysical, Seismic or Other Type Exploration on State-Owned Lands Other Than State-Owned Marine Waters (Mississippi) Rules and Regulations Governing Geophysical, Seismic or Other Type Exploration on State-Owned Lands Other Than State-Owned Marine Waters (Mississippi) < Back Eligibility Commercial Developer Fuel Distributor General Public/Consumer Industrial Investor-Owned Utility Municipal/Public Utility Utility Program Info State Mississippi Program Type Environmental Regulations Siting and Permitting Provider Mississippi Development Authority The Rules and Regulations Governing Geophysical, seismic or Other Type Exploration on State-Owned Lands Other than State-Owned Marine Waters is applicable to the Natural Gas Sector and the Coal with CCS Sector. This law

402

IEP - Water-Energy Interface: Regulatory Drivers  

NLE Websites -- All DOE Office Websites (Extended Search)

Regulatory Drivers Regulatory Drivers Several legislative acts are in place that could potentially impact water quality requirements and water use for fossil energy production as well as electricity generation. These acts regulate pollutant discharge and water intake directly and indirectly. Under regulations established by the United States Environmental Protection Agency (EPA), these Acts serve to maintain and improve the Nation's water resources for uses including but not limited to agricultural, industrial, nutritional, and recreational purposes. The Clean Water Act - The Federal Water Pollution Control Act, more commonly known as the Clean Water Act, provides for the regulation of discharges to the nation's surface waters. To address pollution, the act specifies that the discharge of any pollutant by any person is unlawful except when in compliance with applicable permitting requirements. Initial emphasis was placed on "point source" pollutant discharge, but 1987 amendments authorized measures to address "non-point source" discharges, including stormwater runoff from industrial facilities. Permits are issued under the National Pollutant Discharge Elimination System (NPDES), which designates the highest level of water pollution or lowest acceptable standards for water discharges. NPDES permits are typically administered by the individual states. With EPA approval, the states may implement standards more stringent than federal water quality standards, but may not be less stringent. Certain sections of the Act are particularly applicable to water issues related to power generation. These include:

403

Environmental regulations handbook for enhanced oil recovery. Final report  

SciTech Connect

A guide to environmental laws and regulations which have special significance for enhanced oil recovery (EOR) is presented. The Clean Air Act, the Clean Water Act, the Safe Drinking Water Act, Resource Conservation and Recovery Act, federal regulations, and state regulations are discussed. This handbook has been designed as a planning tool and a convenient reference source. The 16 states included comprise the major oil-producing states in various regions of the state. The major topics covered are: general guidelines for complying with environmental laws and regulations; air pollution control; water pollution control; protecting drinking water: underground injection control; hazardous waste management; and federal laws affecting siting or operation of EOR facilities. (DMC)

Wilson, T.D.

1980-08-01T23:59:59.000Z

404

Proceedings: Second Thermal Ecology and Regulation Workshop  

Science Conference Proceedings (OSTI)

This report documents a recent thermal discharge issues workshop that examined recent developments and future trends. Thermal discharge issues are receiving increasing attention from government agencies and electric power companies. The report will be of particular value to power company environmental staff, government regulators, and water resource managers.

2008-07-02T23:59:59.000Z

405

GRR/Section 19-CA-a - Water Access and Water Rights Issues | Open Energy  

Open Energy Info (EERE)

GRR/Section 19-CA-a - Water Access and Water Rights Issues GRR/Section 19-CA-a - Water Access and Water Rights Issues < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 19-CA-a - Water Access and Water Rights Issues 19CAAWaterAccessWaterRightsIssues.pdf Click to View Fullscreen Contact Agencies California State Water Resources Control Board California Division of Water Rights Regulations & Policies California Water Code Triggers None specified Click "Edit With Form" above to add content 19CAAWaterAccessWaterRightsIssues.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative California's water acquisition process is governed by state law and common

406

Regulators, Requirements, Statutes  

NLE Websites -- All DOE Office Websites (Extended Search)

Regulators, Requirements, Statutes Regulators, Requirements, Statutes Regulators, Requirements, Statutes The Laboratory must comply with environmental laws and regulations that apply to Laboratory operations. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email Environmental laws and regulations LANL complies with more than 30 state and federal regulations and policies designed to protect human health and the environment. Regulators Regulators Environmental Protection Agency (EPA) EPA Homepage EPA - Region VI U.S. Department of Energy (DOE) DOE Homepage DOE Environmental Policy DOE Citizen's Advisory Board U.S. Fish and Wildlife Service (FWS) Southwest Region 2 New Mexico Environment Department (NMED) NMED Homepage NMED DOE Oversight Office

407

New York State Regulations  

NLE Websites -- All DOE Office Websites (Extended Search)

New York New York State Regulations: New York State of New York The primary responsibility for regulating oil and gas activities within New York resides with the Bureau of Oil and Gas Regulation in the Division of Mineral Resources (Office of Natural Resources) of the New York State Department of Environmental Conservation (NYSDEC). Other offices and divisions within the NYSDEC administer the major environmental protection laws. Contact New York State Department of Environmental Conservation Division of Mineral Resources Bureau of Oil and Gas Regulation 625 Broadway, 3rd Floor Albany, NY 12233-6500 (518) 402-8056 (phone) (518) 402-8060 (fax) Disposal Practices and Applicable Regulations Environmental conservation rules and regulations are contained in Title 6 of the Official Compilation of Codes, Rules and Regulations of the State of New York (6 NYCRR). The rules and regulations for oil, gas and solution mining are provided in 6 NYCRR Parts 550-559.

408

An attempt to explore the production routes of Astatine radionuclides: Theoretical approach  

E-Print Network (OSTI)

In order to fulfil the recent thrust of Astatine radionuclides in the field of nuclear medicine various production routes have been explored in the present work. The possible production routes of $^{209-211}$At comprise both light and heavy ion induced reactions at the bombarding energy range starting from threshold to maximum 100 MeV energy. For this purpose, we have used the nuclear reaction model codes TALYS, ALICE91 and PACE-II. Excitation functions of those radionuclides, produced through various production routes, have been calculated using nuclear reaction model codes and compared with the available measured data. Contribution of various reaction mechanisms, like, direct, preequilibrium and equilibrium reactions, to the total reaction cross section has been studied using the codes. Result shows that equilibrium reaction mechanism dominates in all cases over other reaction mechanisms.

Maiti, Moumita

2008-01-01T23:59:59.000Z

409

An attempt to explore the production routes of Astatine radionuclides: Theoretical approach  

E-Print Network (OSTI)

In order to fulfil the recent thrust of Astatine radionuclides in the field of nuclear medicine various production routes have been explored in the present work. The possible production routes of $^{209-211}$At comprise both light and heavy ion induced reactions at the bombarding energy range starting from threshold to maximum 100 MeV energy. For this purpose, we have used the nuclear reaction model codes TALYS, ALICE91 and PACE-II. Excitation functions of those radionuclides, produced through various production routes, have been calculated using nuclear reaction model codes and compared with the available measured data. Contribution of various reaction mechanisms, like, direct, preequilibrium and equilibrium reactions, to the total reaction cross section has been studied using the codes. Result shows that equilibrium reaction mechanism dominates in all cases over other reaction mechanisms.

Moumita Maiti; Susanta Lahiri

2008-12-16T23:59:59.000Z

410

Comparison of radionuclide scans with computer-assisted tomography in diagnosis of intracranial disease  

SciTech Connect

Radionuclide brain scans were compared with computer-assisted tomography (CAT) for the diagnosis of intracranial disorders in 297 patients. The diagnosis was confirmed in 281 patients who formed the population for the study. The radionuclide scan was false positive for 12 patients (3.9 percent) and false negative for eight (2.6 percent). The CAT was false positive for three patients (1 percent) and false negative for one (0.3 percent). In the 133 patients in whom both tests were negative, no evidence of central nervous system pathology has been found during the 6 to 18 month follow-up. Brain tumors and intracerebral hemorrhage are more readily detectable with CAT.

Clifford, J.R.; Connolly, E.S.; Voorhies, R.M.

1976-12-01T23:59:59.000Z

411

Protected Water Sources (Iowa) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Protected Water Sources (Iowa) Protected Water Sources (Iowa) Protected Water Sources (Iowa) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Iowa Program Type Environmental Regulations This chapter designates protected water sources, which are subject to additional special conditions regarding water use. Permit applications for

412

Limiting values of radionuclide intake and air concentration and dose conversion factors for inhalation, submersion, and ingestion: Federal guidance report No. 11  

Science Conference Proceedings (OSTI)

Radiation protection programs for workers are based, in the United States, on a hierarchy of limitations stemming from Federal guidance approved by the President. This guidance, which consists of principles, policies, and numerical primary guides, is used by Federal agencies as the basis for developing and implementing their own regulatory standards. The primary guides are usually expressed in terms of limiting doses to workers. The protection of workers against taking radioactive materials into the body, however, is accomplished largely through the use of regulations based on derived guides expressed in terms of quantities or concentrations of radionuclides. The values of these derived guides are chosen so as to assure that workers in work environments that conform to them are unlikely to receive radiation doses that exceed the primary guides. The purpose of the present report is to set forth derived guides that are consistent with current Federal radiation protection guidance. They are intended to serve as the basis for regulations setting upper bounds on the inhalation and ingestion of, and submersion in, radioactive materials in the workplace. The report also includes tables of exposure-to-dose conversion factors, for general use in assessing average individual committed doses in any population that is adequately characterized by Reference Man. 38 refs.

Eckerman, K.F.; Wolbarst, A.B.; Richardson, A.C.B.

1988-09-01T23:59:59.000Z

413

Energy Basics: Water Heating  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Storage Water Heaters Tankless Demand Water Heaters Heat Pump Water Heaters Solar Water Heaters Tankless Coil & Indirect Water Heaters Water Heating A variety of...

414

Total Inventory of Selected Radionuclides in Old Solvent Tanks S1 Through S22  

Science Conference Proceedings (OSTI)

The total inventory of fourteen radionuclides, three metals, and volatile organic compounds (VOCs) has been calculated for the twenty-two Old Solvent Tanks (OSTs). The inventory calculations are based upon extensive characterization data of the multiple liquid and sludge samples taken from the OSTs. In addition, the total inventory of sixteen actinides (including error) has been calculated. The actinide inventory will be useful for criticality safety considerations.

Leyba, J.D.

2001-07-26T23:59:59.000Z

415

Radionuclide Concentrations in Deer and Elk from Los Alamos National Laboratory: 1991-1998  

SciTech Connect

Mule deer (Odocoileus hemionus) and Rocky Mountain elk (Cervus elaphus) forage in many areas at Los Alamos National Laboratory (LANL) that may contain radioactivity above natural and/or worldwide fallout levels. This paper summarizes radionuclide concentrations 3H, 90Sr, 137Cs, 238Pu, 239,240Pu, 241Am, and total uranium in muscle and bone tissue of deer and elk collected from LANL lands from 1991 through 1998. Also, the committed effective dose equivalent (CEDE) and the risk of excess cancer fatalities (RECF) to p