Powered by Deep Web Technologies
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.


1

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

2

Chancellor Water Colloids: Characterization and Radionuclide Association  

SciTech Connect

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

3

Critical review: Radionuclide transport, sediment transport, and water quality mathematical modeling; and radionuclide adsorption/desorption mechanisms  

SciTech Connect

This report describes the results of a detailed literature review of radionuclide transport models applicable to rivers, estuaries, coastal waters, the Great Lakes, and impoundments. Some representatives sediment transport and water quality models were also reviewed to evaluate if they can be readily adapted to radionuclide transport modeling. The review showed that most available transport models were developed for dissolved radionuclide in rivers. These models include the mechanisms of advection, dispersion, and radionuclide decay. Since the models do not include sediment and radionuclide interactions, they are best suited for simulating short-term radionuclide migration where: (1) radionuclides have small distribution coefficients; (2) sediment concentrations in receiving water bodies are very low. Only 5 of the reviewed models include full sediment and radionuclide interactions: CHMSED developed by Fields; FETRA SERATRA, and TODAM developed by Onishi et al, and a model developed by Shull and Gloyna. The 5 models are applicable to cases where: (1) the distribution coefficient is large; (2) sediment concentrations are high; or (3) long-term migration and accumulation are under consideration. The report also discusses radionuclide absorption/desorption distribution ratios and addresses adsorption/desorption mechanisms and their controlling processes for 25 elements under surface water conditions. These elements are: Am, Sb, C, Ce, Cm, Co, Cr, Cs, Eu, I, Fe, Mn, Np, P, Pu, Pm, Ra, Ru, Sr, Tc, Th, {sup 3}H, U, Zn and Zr.

Onishi, Y.; Serne, R.J.; Arnold, E.M.; Cowan, C.E.; Thompson, F.L. [Pacific Northwest Lab., Richland, WA (United States)

1981-01-01T23:59:59.000Z

4

Water Quality Regulations (Rhode Island)  

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

The purpose of these regulations is to establish water quality standards for the state's surface waters. These standards are intended to restore, preserve and enhance the physical, chemical and...

5

Ground Water Management Regulations (Louisiana)  

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

The rules and regulations apply to the management of the state's ground water resources. In addition, the Commissioner of Conservation has recommended that oil and gas operators with an interest...

6

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...

7

Radiological conditions at Bikini Atoll: Radionuclide concentrations in vegetation, soil, animals, cistern water, and ground water  

SciTech Connect

This report is intended as a resource document for the eventual cleanup of Bikini Atoll and contains a summary of the data for the concentrations of /sup 137/Cs, /sup 90/Sr, /sup 239 +240/Pu, and /sup 241/Am in vegetation through 1987 and in soil through 1985 for 14 islands at Bikini Atoll. The data for the main residence island, Bikini, and the most important island, Eneu, are extensive; these islands have been the subject of a continuing research and monitoring program since 1974. Data for radionuclide concentrations in ground water, cistern water, fish and other marine species, and pigs from Bikini and Eneu Islands are presented. Also included are general summaries of our resuspension and rainfall data from Bikini and Eneu Islands. The data for the other 12 islands are much more limited because samples were collected as part of a screening survey and the islands have not been part of a continuing research and monitoring program. Cesium-137 is the radionuclide that produces most of the estimated dose for returning residents, mostly through uptake by terrestrial foods and secondly by direct external gamma exposure. Remedial measures for reducing the /sup 137/Cs uptake in vegetation are discussed. 40 refs., 32 figs., 131 tabs.

Robison, W.L.; Conrado, C.L.; Stuart, M.L.

1988-05-31T23:59:59.000Z

8

NATURAL RADIONUCLIDES MEASUREMENTS IN DRINKING WATER BY LIQUID SCINTILLATION COUNTING. METHODS AND RESULTS  

E-Print Network (OSTI)

to dose evaluation, namely gross alpha and beta activity, uranium and radium isotopes content. For tritium activity and uranium isotope concentration have been measured. A Quantulus-Wallac scintillation counter hasNATURAL RADIONUCLIDES MEASUREMENTS IN DRINKING WATER BY LIQUID SCINTILLATION COUNTING. METHODS

9

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

10

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

11

Regulated water production to control water coning in oil wells  

E-Print Network (OSTI)

REGULATED WATER PRODUCTION TO CONTROL WATER CONING IN OIL WELLS A Thesis by ISHWAR SINGH Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE May 1975 Major... Subject: Petroleum Engineering REGULATED WATER PRODUCTION TO CONTROL WATER CONING IN OIL WELLS A Thesis by ISHWAR SINGH Approved as to style and content by (Chairman of Committee) (Membe ) (Head of Departmen lVlemb ) May 1975 ( I ABST RACT...

Sim?ha, I?s?vara

1975-01-01T23:59:59.000Z

12

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

13

An assessment of natural radionuclides in water of Langat River estuary, Selangor  

SciTech Connect

An estuary is an area that has a free connection with the open sea and it is a dynamic semi-enclosed coastal bodies. Ex-mining, aquaculture and industrial areas in Selangor are the sources of pollutants discharged into the estuary water. Radionuclides are considered as pollutants to the estuary water. Gamma radiations emitted by natural radionuclides through their decaying process may give impact to human. The radiological effect of natural radionuclides which are {sup 226}Ra, {sup 228}Ra, {sup 40}K, {sup 238}U and {sup 232}Th, were explored by determining the respective activity concentrations in filtered water along the Langat estuary, Selangor. Meanwhile, in- situ water quality parameters such as temperature, dissolve oxygen (DO), salinity, total suspended solid (TSS), pH and turbidity were measured by using YSI portable multi probes meter. The activity concentration of {sup 226}Ra, {sup 228}Ra and {sup 40}K were determined by using gamma-ray spectrometry with high-purity germanium (HPGe) detector. The activity concentrations of {sup 226}Ra, {sup 228}Ra and {sup 40}K in samples are in the range of 0.17 - 0.67 Bq/L, 0.16 - 0.97 Bq/L and 1.22 - 5.57 Bq/L respectively. On the other hand, the concentrations of uranium-238 and thorium-232 were determined by using Energy Dispersive X-ray Fluorescence Spectrometry (EDXRF). The thorium concentrations are between 0.17 ppm to 0.28 ppm and uranium concentrations were 0.25 ppm to 0.31 ppm. The results show activity concentrations of radionuclides are slightly high near the river estuary. The Radium Equivalent, Absorbed Dose Rate, External Hazard Index, and Annual Effective Dose of {sup 226}Ra, {sup 228}Ra and {sup 40}K are also studied.

Hamzah, Zaini, E-mail: tengkuliana88@gmail.com; Rosli, Tengku Nurliana Tuan Mohd, E-mail: tengkuliana88@gmail.com; Saat, Ahmad, E-mail: tengkuliana88@gmail.com; Wood, Ab. Khalik, E-mail: tengkuliana88@gmail.com [Faculty of Applied Sciences, Universiti Teknologi MARA, 40450 Shah Alam, Selangor (Malaysia)

2014-02-12T23:59:59.000Z

14

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...

15

Naturally-Occurring Radionuclides In Drinking Water From Surface And Groundwater Reservoirs  

SciTech Connect

Radioactivity in water for human consumption is under closer scrutiny than ever before and many countries adopted guideline values based on total alpha and total beta activity measurements. Although most waters from surface circulation meet these guidelines, it is frequently found that groundwater exceed guideline values. Results of water analyses by alpha spectrometry clarified that the main radionuclides present are from the uranium decay series, such as uranium isotopes, radium ({sup 226}Ra), radon ({sup 222}Rn), and also {sup 210}Pb and {sup 210}Po. Occasionally, groundwater displayed {sup 226}Ra concentrations higher than 1 Bq L{sup -1} and {sup 222}Rn concentrations above 1000 Bq L{sup -1}. Nevertheless, lack of conformity of these waters with guidelines adopted, generally, is not due to anthropogenic inputs.

Carvalho, F. P.; Madruga, M. J.; Oliveira, J. M.; Lopes, I.; Ferrador, G.; Sequeira, M. M. [Nuclear and Technological Institute (ITN) Department of Radiological Protection and Nuclear Safety E.N. 10, 2686-953 Sacavem (Portugal)

2008-08-07T23:59:59.000Z

16

Radionuclide concentrations and dose assessment of cistern water and groundwater at the Marshall Islands  

SciTech Connect

A radiological survey was conducted from September through November of 1978 to determine the concentrations of radionuclides in the terrestrial and marine environments of 11 atolls and 2 islands in the Northern Marshall Islands. More than 70 cistern and groundwater samples were collected at the atolls; the volume of each sample was between 55 and 100 l. The concentration of /sup 90/Sr in cistern water at most atolls is that expected from world-wide fallout in wet deposition. Except for Bikini and Rongelap, /sup 137/Cs concentrations in cistern water are in agreement with the average predicted concentrations from wet deposition. The /sup 239 +240/Pu concentrations are everywhere less than the predicted fallout concentrations except at Rongelap, Ailinginae, and Bikini where the measured and predicted concentrations are in general agreement. During the period sampled, most groundwater concentrations of /sup 90/Sr and /sup 137/Cs were everywhere higher than the concentrations in cistern water. Concentrations of the transurancies in filtered groundwater solution were everywhere comparable to or less than the concentrations in cistern water. It is concluded that the concentrations of radionuclides detected during any single period may not necessarily reflect the long-term average concentrations or the concentrations that might be observed if a lined well were extended above the surface. In any case, at all atolls the /sup 90/Sr and /sup 137/Cs concentrations in groundwater are below the concentration guidelines for drinking water recommended by the Environmental Protection Agency. The maximum annual dose rates and the 30- and 50-y integral doses are calculated for the intake of both cistern water and groundwater for each of the atolls.

Noshkin, V.E.; Eagle, R.J.; Wong, K.M.; Jokela, T.A.; Robison, W.L.

1981-03-16T23:59:59.000Z

17

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

18

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

19

Unsaturated zone waters from the Nopal I natural analog, Chihuahua, Mexico -- Implications for radionuclide mobility at Yucca Mountain  

SciTech Connect

Chemical and U-Th isotopic data on unsaturated zone waters from the Nopal I natural analog reveal effects of water-rock interaction and help constrain models of radionuclide release and transport at the site and, by analogy, at the proposed nuclear waste repository at Yucca Mountain. Geochemical reaction-path modeling indicates that, under oxidizing conditions, dissolution of uraninite (spent fuel analog) by these waters will lead to eventual schoepite precipitation regardless of initial silica concentration provided that groundwater is not continuously replenished. Thus, less soluble uranyl silicates may not dominate the initial alteration assemblage and keep dissolved U concentrations low. Uranium-series activity ratios are consistent with models of U transport at the site and display varying degrees of leaching versus recoil mobilization. Thorium concentrations may reflect the importance of colloidal transport of low-solubility radionuclides in the unsaturated zone.

Pickett, D.A.; Murphy, W.M.

1999-07-01T23:59:59.000Z

20

Removal of Radionuclides from Waste Water at Fukushima Daiichi Nuclear Power Plant: Desalination and Adsorption Methods - 13126  

SciTech Connect

Waste water containing high levels of radionuclides due to the Fukushima Daiichi Nuclear Power Plant accident, has been treated by the adsorption removal and reverse-osmosis (RO) desalination to allow water re-use for cooling the reactors. Radionuclides in the waste water are collected in the adsorbent medium and the RO concentrate (RO brine) in the water treatment system currently operated at the Fukushima Daiichi site. In this paper, we have studied the behavior of radionuclides in the presently applied RO desalination system and the removal of radionuclides in possible additional adsorption systems for the Fukushima Daiichi waste water treatment. Regarding the RO desalination system, decontamination factors (DFs) of the elements present in the waste water were obtained by lab-scale testing using an RO unit and simulated waste water with non-radioactive elements. The results of the lab-scale testing using representative elements showed that the DF for each element depended on its hydrated ionic radius: the larger the hydrated ionic radius of the element, the higher its DF is. Thus, the DF of each element in the waste water could be estimated based on its hydrated ionic radius. For the adsorption system to remove radionuclides more effectively, we studied adsorption behavior of typical elements, such as radioactive cesium and strontium, by various kinds of adsorbents using batch and column testing. We used batch testing to measure distribution coefficients (K{sub d}s) for cesium and strontium onto adsorbents under different brine concentrations that simulated waste water conditions at the Fukushima Daiichi site. For cesium adsorbents, K{sub d}s with different dependency on the brine concentration were observed based on the mechanism of cesium adsorption. As for strontium, K{sub d}s decreased as the brine concentration increased for any adsorbents which adsorbed strontium by intercalation and by ion exchange. The adsorbent titanium oxide had higher K{sub d}s and it was used for the column testing to obtain breakthrough curves under various conditions of pH and brine concentration. The breakthrough point had a dependency on pH and the brine concentration. We found that when the pH was higher or the brine concentration was lower, the longer it took to reach the breakthrough point. The inhibition of strontium adsorption by alkali earth metals would be diminished for conditions of higher pH and lower brine concentration. (authors)

Kani, Yuko; Kamosida, Mamoru; Watanabe, Daisuke [Hitachi Research Laboratory, Hitachi, Ltd., 7-2-1 Omika-cho, Hitachi, Ibaraki, 319-1221 (Japan)] [Hitachi Research Laboratory, Hitachi, Ltd., 7-2-1 Omika-cho, Hitachi, Ibaraki, 319-1221 (Japan); Asano, Takashi; Tamata, Shin [Hitachi Works, Hitachi-GE Nuclear Energy, Ltd. (Japan)] [Hitachi Works, Hitachi-GE Nuclear Energy, Ltd. (Japan)

2013-07-01T23:59:59.000Z

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.


21

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

22

Safety regulations of food and water implemented in the first year following the Fukushima nuclear accident  

Science Journals Connector (OSTI)

......ordered. So far, tap water, raw milk, vegetables...the emergency diesel generators successfully started...afterwards, and the generators became inoperable...outflow of contaminated water into the open sea as...and large-scale atmospheric radionuclide releases......

Nobuyuki Hamada; Haruyuki Ogino; Yuki Fujimichi

2012-09-01T23:59:59.000Z

23

Sorption-capacity limited retardation of radionuclides transport in water-saturated packing materials  

SciTech Connect

Radionuclides breakthrough times as calculated through constant retardation factors obtained in dilute solutions are non-conservative. The constant retardation approach regards the solid as having infinite sorption capacity throughout the solid. However, as the solid becomes locally saturated, such as in the proximity of the waste form-packing materials interface, it will exhibit no retardation properties, and transport will take place as if the radionuclides were locally non-reactive. The magnitude of the effect of finite sorption capacity of the packing materials on radionuclide transport is discussed with reference to high-level waste package performance. An example based on literature sorption data indicates that the breakthrough time may be overpredicted by orders of magnitude using a constant retardation factor as compared to using the entire sorption isotherm to obtain a concentration-dependent retardation factor. 8 references, 3 figures, 3 tables.

Pescatore, C.; Sullivan, T.

1984-01-01T23:59:59.000Z

24

Water Balance in Terrestrial PlantsWater Balance in Terrestrial Plants Water Regulation on LandWater Regulation on Land --PlantsPlants WWipip= W= Wrr + W+ Waa --WWtt --WWss  

E-Print Network (OSTI)

1 Water Balance in Terrestrial PlantsWater Balance in Terrestrial Plants Water Regulation on LandWater waters internal water WWrr =Roots=Roots WWaa = Air= Air WWtt = Transpiration= Transpiration WWss = Secretions= Secretions Water Regulation on Land - Plants Water Balance in Terrestrial PlantsWater Balance

Cochran-Stafira, D. Liane

25

radionuclides | EMSL  

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

radionuclides radionuclides Leads No leads are available at this time. Magnesium behavior and structural defects in Mg+ ion implanted silicon carbide. Abstract: As a candidate...

26

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

27

Toxicology 198 (2004) 3944 Arsenic drinking water regulations in developing  

E-Print Network (OSTI)

Toxicology 198 (2004) 39­44 Arsenic drinking water regulations in developing countries identified 10 g/l as a goal which later became the World Health Organization Guideline for drinking water in 1992. Epidemiological studies have shown that about one in 10 people drinking water containing 500 g

California at Berkeley, University of

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

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

31

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

32

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

33

Viscosity of interfacial water regulates ice nucleation  

SciTech Connect

Ice formation on solid surfaces is an important phenomenon in many fields, such as cloud formation and atmospheric icing, and a key factor for applications in preventing freezing. Here, we report temperature-dependent nucleation rates of ice for hydrophilic and hydrophobic surfaces. The results show that hydrophilic surface presents a lower ice nucleation rate. We develop a strategy to extract the thermodynamic parameters, J{sub 0} and ?, in the context of classical nucleation theory. From the extracted J{sub 0} and ?, we reveal the dominant role played by interfacial water. The results provide an insight into freezing mechanism on solid surfaces.

Li, Kaiyong; Chen, Jing; Zhang, Qiaolan; Zhang, Yifan [Beijing National Laboratory for Molecular Sciences (BNLMS), Key Laboratory of Green Printing, Institute of Chemistry, Chinese Academy of Sciences, Beijing 100190 (China) [Beijing National Laboratory for Molecular Sciences (BNLMS), Key Laboratory of Green Printing, Institute of Chemistry, Chinese Academy of Sciences, Beijing 100190 (China); University of Chinese Academy of Sciences, Beijing 100049 (China); Xu, Shun; Zhou, Xin [School of Physics, University of Chinese Academy of Sciences, Beijing 100049 (China)] [School of Physics, University of Chinese Academy of Sciences, Beijing 100049 (China); Cui, Dapeng; Wang, Jianjun, E-mail: wangj220@iccas.ac.cn; Song, Yanlin [Beijing National Laboratory for Molecular Sciences (BNLMS), Key Laboratory of Green Printing, Institute of Chemistry, Chinese Academy of Sciences, Beijing 100190 (China)] [Beijing National Laboratory for Molecular Sciences (BNLMS), Key Laboratory of Green Printing, Institute of Chemistry, Chinese Academy of Sciences, Beijing 100190 (China)

2014-03-10T23:59:59.000Z

34

Significance of apparent discrepanices in water ages derived from atmospheric radionuclides at Yucca Mountain, Nevada  

SciTech Connect

Cosmogenic {sup 36}Cl and {sup 14}C produced in the atmosphere are being used to estimate water residence times in the unsaturated zone at Yucca Mountain. Results thus far show a systematic discordance in that {sup 14}C-based ages are generally one to two orders of magnitude younger than {sup 36}Cl-based ages. This lack of concordance probably arises from one or more of the following reasons: (1) different transport mechanisms, e.g., vapor transport for {sup 14}C; (2) different magnitudes and timing of bomb-pulse signals; (3) mixing of waters from different flow paths; and (4) possibly inadequate methods for correcting for the effect of sample contamination by carbon or chlorine from sources other than the infiltrating water. Preliminary numerical simulation results using the FEHMN code suggest that spatial variation in infiltration rates can enhance lateral flow and mixing that leads to discordance in apparent ages depending on the dating technique. Examples are presented to show that disparate radiometric ages are inevitable and to be expected where mixing of waters of markedly different ages occurs.

Liu, B.; Fabryka-Martin, J.; Wolfsberg, A.; Robinson, B. [Los Alamos National Lab., NM (United States); Sharma, P. [Purdue Univ., Lafayette, IN (United States). Dept. of Physics

1995-02-23T23:59:59.000Z

35

Removal of radionuclides in drinking water by membrane treatment using ultrafiltration, reverse osmosis and electrodialysis reversal  

Science Journals Connector (OSTI)

A pilot plant had been built to test the behaviour of ultrafiltration (UF), reverse osmosis (RO), and electrodialysis reversal (EDR) in order to improve the quality of the water supplied to Barcelona metropolitan area from the Llobregat River. This paper presents results from two studies to reduce natural radioactivity. The results from the pilot plant with four different scenarios were used to design the full-scale treatment plant built (SJD WTP). The samples taken at different steps of the treatment were analysed to determine gross alpha, gross beta and uranium activity. The results obtained revealed a significant improvement in the radiological water quality provided by both membrane techniques (RO and EDR showed removal rates higher than 60%). However, UF did not show any significant removal capacity for gross alpha, gross beta or uranium activities. RO was better at reducing the radiological parameters studied and this treatment was selected and applied at the full scale treatment plant. The RO treatment used at the SJD WTP reduced the concentration of both gross alpha and gross beta activities and also produced water of high quality with an average removal of 95% for gross alpha activity and almost 93% for gross beta activity at the treatment plant.

M. Montaa; A. Camacho; I. Serrano; R. Devesa; L. Matia; I. Valls

2013-01-01T23:59:59.000Z

36

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

37

H.A.R. 13-171 - Designation and Regulation of Water Management...  

Open Energy Info (EERE)

- Designation and Regulation of Water Management Areas Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: H.A.R. 13-171 -...

38

EMSL - radionuclides  

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

radionuclides en Composition and Interface Analysis of InGaNGaN Multiquantum-Wells on GaN Substrates Using Atom Probe Tomography. http:www.emsl.pnl.govemslwebpublications...

39

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.

40

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,...

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

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

SciTech Connect

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

42

Radionuclides in sediments and seawater at Rongelap Atoll  

SciTech Connect

The present concentrations and distributions of long-lived, man-made radionuclides in Rongelap Atoll lagoon surface sediments, based on samples collected and analyzed in this report. The radionuclides were associated with debris generated with the 1954 Bravo thermonuclear test at Bikini Atoll. Presently, only {sup 90}Sr and the transuranic radionuclides are found associated with the surface sediments in any quantity. Other radionuclides, including {sup 60}Co and {sup 137} Cs, are virtually absent and have either decayed or migrated from the deposits to the overlying seawater. Present inventories of {sup 241}Am and {sup 249+240}Pu in the surface layer at Rongelap are estimated to be 3% of the respective inventories in surface sediments from Bikini Atoll. There is a continuous slow release of the transuranics from the sediments back to the water column. The inventories will only slowly change with time unless the chemical-physical processes that now regulate this release to the water column are changed or altered.

Noshkin, V.E.; Robison, W.L.; Eagle, R.J.; Brunk, J.L.

1998-03-01T23:59:59.000Z

43

Estimation of distribution coefficient of natural radionuclides in soil around uranium mines and its effect with ionic strength of water  

Science Journals Connector (OSTI)

......which may contaminate the soil and ground water around uranium mining areas, have been considered. Soil and ground water samples were collected from a...release, accidental, disposal or remediation scenarios requires the availability......

S. Mishra; S. Maity; G. G. Pandit

2012-11-01T23:59:59.000Z

44

DECEMBER 2008 WATER QUALITY AND LAND USE: IMPLICATIONS FOR REGULATION AND  

E-Print Network (OSTI)

DECEMBER 2008 WATER QUALITY AND LAND USE: IMPLICATIONS FOR REGULATION AND URBAN PLANNING WRRI Technical Completion Report No. 346 Gwendolyn A. Aldrich Janie Chermak Jennifer A. Thacher NEW MEXICO WATER-0001 Telephone (505) 646-4337 FAX (505) 646-6418 email: nmwrri@wrri.nmsu.edu #12;WATER QUALITY AND LAND USE

Johnson, Eric E.

45

Sediments can be important in regulating stream water P concentrations, and this has implications for establishing  

E-Print Network (OSTI)

607 Sediments can be important in regulating stream water P concentrations, and this has and biotic processes to better understand the role of sediments in determining stream water dissolved P concentrations. Sediment and stream water samples were collected during low discharge from 105 streams across

David, Mark B.

46

Managing water demand as a regulated open MAS. (Work in progress)  

E-Print Network (OSTI)

1 Managing water demand as a regulated open MAS. (Work in progress) Vicente Botti1 , Antonio Scientific Research Council, {vbotti,agarridot,agiret}@dsic.upv.es, pablo@iiia.csic.es I. WATER MANAGEMENT management models are based on equa- tional descriptions of aggregate supply and demand in a water basin [2

Garrido, Antonio

47

Managing water demand as a regulated open MAS. (Work in progress)  

E-Print Network (OSTI)

1 Managing water demand as a regulated open MAS. (Work in progress) Vicente Botti 1 , Antonio Scientific Research Council, {vbotti,agarridot,agiret}@dsic.upv.es, pablo@iiia.csic.es I. WATER MANAGEMENT management models are based on equa­ tional descriptions of aggregate supply and demand in a water basin [2

Garrido, Antonio

48

Estimation of radiation doses to members of the public in Italy from intakes of some important naturally occurring radionuclides (238U, 234U, 235U, 226Ra, 228Ra, 224Ra and 210Po) in drinking water  

Science Journals Connector (OSTI)

The radiological quality in some samples of drinking water collected in Italy has been evaluated in the paper. As far as the measured ? or ? radionuclides are concerned, the doses for all the analysed samples of drinking water are in the range of 1.8036.2?Svyr?1, all being well below the reference level of the committed effective dose (100?Svyr?1) recommended by the WHO. As far as each measured ? or ? radionuclide is concerned, the dose contributions for most of the analysed water samples are in this order: 210Po>228Ra>226Ra>234U>238U>224Ra>235U, and 210Po and 228Ra can yield a significant contribution to the doses from the analysed drinking water samples. As far as the elements are concerned, the dose contributions are 48.027.9% from radium, 31.723.1% from polonium, and 20.314.1% from uranium. The water samples, No. 2, 7, 13, and 15, can lead to a dose of >10?Svyr?1, mainly due to the dose contribution from 210Po and 228Ra, especially water samples No. 2 and 13. The obtained data can provide basic information for consumers and competent authorities regarding the internal exposure risk due to drinking water intake, and can possibly serve as a comparison when evaluating the dose contribution from artificial radionuclides released to the environment as a result of any human practices and accidents in the studied area.

Guogang Jia; Giancarlo Torri

2007-01-01T23:59:59.000Z

49

Chemical speciation of radionuclides migrating in groundwaters  

SciTech Connect

In order to more accurately predict the rates and mechanisms of radionuclide migration from low-level waste disposal facilities via groundwater transport, ongoing studies are being conducted at field sites at Chalk River Laboratories to identify and characterize the chemical speciation of mobile, long-lived radionuclides migrating in groundwaters. Large-volume water sampling techniques are being utilized to separate and concentrate radionuclides into particular, cationic, anionic, and nonionic chemical forms. Most radionuclides are migrating as soluble, anionic species that appear to be predominantly organoradionuclide complexes. Laboratory studies utilizing anion exchange chromatography have separated several anionically complexed radionuclides, e.g., {sup 60}Co and {sup 106}Ru, into a number of specific compounds or groups of compounds. Further identification of the anionic organoradionuclide complexes is planned utilizing high resolution mass spectrometry. Large-volume ultra-filtration experiments are characterizing the particulate forms of radionuclides being transported in these groundwaters.

Robertson, D.; Schilk, A.; Abel, K.; Lepel, E.; Thomas, C.; Pratt, S. [Pacific Northwest Lab., Richland, WA (United States); Cooper, E.; Hartwig, P.; Killey, R. [Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.

1994-04-01T23:59:59.000Z

50

Drift-Scale Radionuclide Transport  

SciTech Connect

The purpose of this model report is to document the drift scale radionuclide transport model, taking into account the effects of emplacement drifts on flow and transport in the vicinity of the drift, which are not captured in the mountain-scale unsaturated zone (UZ) flow and transport models ''UZ Flow Models and Submodels'' (BSC 2004 [DIRS 169861]), ''Radionuclide Transport Models Under Ambient Conditions'' (BSC 2004 [DIRS 164500]), and ''Particle Tracking Model and Abstraction of Transport Process'' (BSC 2004 [DIRS 170041]). The drift scale radionuclide transport model is intended to be used as an alternative model for comparison with the engineered barrier system (EBS) radionuclide transport model ''EBS Radionuclide Transport Abstraction'' (BSC 2004 [DIRS 169868]). For that purpose, two alternative models have been developed for drift-scale radionuclide transport. One of the alternative models is a dual continuum flow and transport model called the drift shadow model. The effects of variations in the flow field and fracture-matrix interaction in the vicinity of a waste emplacement drift are investigated through sensitivity studies using the drift shadow model (Houseworth et al. 2003 [DIRS 164394]). In this model, the flow is significantly perturbed (reduced) beneath the waste emplacement drifts. However, comparisons of transport in this perturbed flow field with transport in an unperturbed flow field show similar results if the transport is initiated in the rock matrix. This has led to a second alternative model, called the fracture-matrix partitioning model, that focuses on the partitioning of radionuclide transport between the fractures and matrix upon exiting the waste emplacement drift. The fracture-matrix partitioning model computes the partitioning, between fractures and matrix, of diffusive radionuclide transport from the invert (for drifts without seepage) into the rock water. The invert is the structure constructed in a drift to provide the floor of the drift. The reason for introducing the fracture-matrix partitioning model is to broaden the conceptual model for flow beneath waste emplacement drifts in a way that does not rely on the specific flow behavior predicted by a dual continuum model and to ensure that radionuclide transport is not underestimated. The fracture-matrix partitioning model provides an alternative method of computing the partitioning of radionuclide releases from drifts without seepage into rock fractures and rock matrix. Drifts without seepage are much more likely to have a significant fraction of radionuclide releases into the rock matrix, and therefore warrant additional attention in terms of the partitioning model used for TSPA.

J. Houseworth

2004-09-22T23:59:59.000Z

51

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

52

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

53

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

54

National Low-Level Waste Management Program Radionuclide Report Series  

SciTech Connect

This volume serves as an introduction to the National Low-Level Radioactive Waste Management Program Radionuclide Report Series. This report includes discussions of 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 five years). Each report includes information regarding radiological and chemical characteristics of specific radionuclides. Information is also included discussing waste streams and waste forms that may contain each radionuclide, and radionuclide behavior in the environment and in the human body. Not all radionuclides commonly found at low-level radioactive waste sites are included in this report. The discussion in this volume explains the rationale of the radionuclide selection process.

Rudin, M.J.; Garcia, R.S.

1992-02-01T23:59:59.000Z

55

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.

56

Drinking Water Problems: Radionuclides (Spanish)  

E-Print Network (OSTI)

materiales, pueden transmitir radion?clidos al agua potable. Con mayor frecuencia se encuentran altos niveles de radion?clidos en el agua subterr?nea (por exemplo, de agua de pozos) que en el agua superficial (tales como lagos y arroyos). Muchos aparatos y... de agua potable, ?ste puede dar una idea de cu?l debe ser el nivel apropiado de un contaminante en los pozos priva- dos para aquellos que utilizan dichas fuentes. Actualmente no existe un MCL para el rad?n. Sin embargo, la EPA est? proponiendo dos...

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

2006-12-21T23:59:59.000Z

57

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 FLESCOTs 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

58

Radionuclide absorbers development program overview.  

SciTech Connect

The proposed Yucca Mountain repository is anticipated to be the first facility for long-term disposal of commercial spent nuclear fuel and high-level radioactive waste in the United States. The facility, located in the southern Nevada desert, is currently in the planning stages with initial exploratory excavations completed. It is an underground facility mined into the tuffaceous volcanic rocks that sit above the local water table. The focus of the work described in this paper is the development of radionuclide absorbers or 'getter' materials for neptunium (Np), iodine (I), and technetium (Tc) for potential deployment in the repository. 'Getter' materials retard the migration of radionuclides through sorption, reduction, or other chemical and physical processes, thereby slowing or preventing the release and transport of radionuclides. An overview of the objectives and approaches utilized in this work with respect to materials selection and modeling of ion 'getters' is presented. The benefits of the 'getter' development program to the United States Department of Energy (US DOE) are outlined.

Jow, Hong-Nian

2005-02-01T23:59:59.000Z

59

Source terms of radionuclides in shallow-land-burial sites. [Maxey Flats, West Valley, Barnwell, Sheffield  

SciTech Connect

A research program is under way to provide source term data on the chemical and radionuclide contents of trench waters at low level radioactive waste disposal sites and to provide information on the geochemical behavior of radionuclides under simulated field conditions. Trench waters were sampled at four commercial waste burial sites and analyzed for chemical and radionuclide constituents. The sorption, diffusion and precipitation behavior of radionuclides were studied using site specific sediments and trench waters. Radionuclide leach rates from solidified waste, under simulated trench conditions, were also determined.

Pietrzak, R.F.; Dayal, R.

1982-01-01T23:59:59.000Z

60

Selected radionuclides important to low-level radioactive waste management  

SciTech Connect

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

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

Impact of Storage Time on the Needed Capture Efficiency for Volatile Radionuclides - 13369  

SciTech Connect

During the processing of used nuclear fuel (UNF), volatile radionuclides will be discharged from the facility stack if no recovery processes are in place to limit their release. The volatile radionuclides of concern are {sup 3}H, {sup 14}C, {sup 85}Kr, and {sup 129}I. There are three key regulations that address the release of these radionuclides to the environment- 40 CFR 61, 40 CFR 190, and 10 CFR 20. These regulations apply to the total radionuclide release and establish dose limits for the maximum exposed individual (MEI) in the public both in terms of whole body dose and dose to specific organs such as the thyroid. Each radionuclide released to the environment contributes to the total dose to some degree. In this paper we attempt to evaluate the efficiency requirements for the capture processes to limit the doses to the MEI to regulatory levels. Since the total amount of each volatile radionuclide present in the UNF changes with the age of the fuel, the respective capture requirements also change with time. Specifically, we are interested in the impact of the decreasing contribution of {sup 3}H and {sup 85}Kr, which have relatively short half-lives, 12.32 y and 10.76 y, respectively, with the increasing age of the fuel (i.e., time between when the UNF is removed from the reactor and the time it is processed) on the capture requirements. In this paper we examine the capture requirements for these four radionuclides for three fuel types (pressurized water reactor [PWR] with uranium oxide fuel [UOX], PWR with mixed oxide fuel [MOX], and an advanced high temperature gas-cooled reactor [AHTGR]), several burnup values, and time out of reactor extending to 200 y. We calculate doses to the MEI with the EPA code CAP-88 and look at two dose contribution cases. In the first case, we assume that the total allowable dose is attributed to only the four volatile radionuclides. This establishes the lowest capture efficiency value possible. Since this is unrealistic, because it assumes zero dose contribution from all other radionuclides, we also examine a second case, where only 10% of the allowable dose is assigned to the four volatile radionuclides. We calculate the required decontamination factors (DFs) for both of these cases for the three fuel types, multiple fuel burnups, and fuel ages and determine whether or not the dose to the whole body or to the thyroid that drives the capture requirements would require additional effluent controls for the shorter half-life volatile radionuclides based on dose considerations. This analysis indicates that the principal isotopes of concern are generally {sup 3}H and {sup 129}I, the latter requiring the highest DFs. The maximum DF value for {sup 129}I is 8000 for the evaluated cases and assumptions used. ?60 for fresh fuels. The DF for {sup 14}C could be as high as 30 for certain fuels. These values are based on just meeting the regulatory limits, and additional engineering margins (perhaps 3x to 10x or higher) should be applied to provide a safety factor for compliance. However, by assuming less conservative dose allocations, taller stacks, different radionuclide speciation, fuel aging, and other reprocessing facility design and location parameters, the DF requirements could be significantly reduced. (authors)

Jubin, R.T.; Ilas, G. [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37849 (United States)] [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37849 (United States); Soelberg, N.R. [Idaho National Laboratory (United States)] [Idaho National Laboratory (United States); Strachan, D.M. [Pacific Northwest National Laboratory (United States)] [Pacific Northwest National Laboratory (United States)

2013-07-01T23:59:59.000Z

62

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

63

Estimated environmental radionuclide transfer and deposition into outdoor swimming pools  

Science Journals Connector (OSTI)

Abstract In 2011, a large radioactive discharge occurred at the Fukushima Daiichi nuclear power plant. This plant is located within a climatically temperate region where outdoor swimming pools are popular. Although it is relatively easy to decontaminate pools by refilling them with fresh water, it is difficult to maintain safe conditions given highly contaminated diurnal dust falls from the surrounding contaminated ground. Our objectives in this paper were to conduct daily radioactivity measurements, to determine the quantity of radioactive contaminants from the surrounding environment that invade outdoor pools, and to investigate the efficacy of traditional pool cleaners in removing radioactive contaminants. The depositions in the paper filterable particulates ranged from 0 to62,5 Bq/m2/day, with the highest levels found in the southern Tohoku District containing Fukushima Prefecture and in the Kanto District containing Tokyo Metro. They were approximately correlated with the ground contamination. Traditional pool cleaners eliminated 99% of contaminants at the bottom of the pool, reducing the concentration to 41Bq/m2 after cleaning. Authors recommended the deposition or the blown radionuclides into outdoor swimming pools must be considered into pool regulations when the environments exactly polluted with radionuclides.

Kazumi Tagami; Izumi Nagata; Keisuke Sueki

2014-01-01T23:59:59.000Z

64

Idaho radionuclide exposure study: Literature review  

SciTech Connect

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

65

Modelling the impacts of building regulations and a property bubble on residential space and water heating  

Science Journals Connector (OSTI)

This paper develops a bottom-up model of space and water heating energy demand for new build dwellings in the Irish residential sector. This is used to assess the impacts of measures proposed in Ireland's National Energy Efficiency Action Plan (NEEAP). The impact of the housing construction boom, which resulted in 23% of occupied dwellings in 2008 having been built since 2002, and the subsequent bust, are also assessed. The model structure treats separately new dwellings added to the stock after 2007 and pre-existing occupied dwellings. The former is modelled as a set of archetype dwellings with energy end use affected by the relevant set of building regulations that apply during construction. Energy demand of existing dwellings is predicted by a simpler top down method based on historical energy use trends. The baseline scenario suggests residential energy demand will grow by 19% from 3206ktoe in 2007 to 3810ktoe in 2020. The results indicate that 2008 and 2010 building regulations will lead to energy savings of 305ktoe (8.0%) in 2020. Had the 2008 building regulations been introduced in 2002, at the start of the boom, there would be additional savings of 238ktoe (6.7%) in 2020.

D. Dineen; B.P. Gallachir

2011-01-01T23:59:59.000Z

66

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

SciTech Connect

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

Initial Radionuclide Inventories  

SciTech Connect

The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only. Bounding waste stream information and data were collected that capture probable limits. For commercially generated waste, this analysis considers alternative waste stream projections to bound the characteristics of wastes likely to be encountered using arrival scenarios that potentially impact the commercial spent nuclear fuel (CSNF) waste stream. For TSPA-LA, this radionuclide inventory analysis considers U.S. Department of Energy (DOE) high-level radioactive waste (DHLW) glass and two types of spent nuclear fuel (SNF): CSNF and DOE-owned (DSNF). These wastes are placed in two groups of waste packages: the CSNF waste package and the codisposal waste package (CDSP), which are designated to contain DHLW glass and DSNF, or DHLW glass only. The radionuclide inventory for naval SNF is provided separately in the classified ''Naval Nuclear Propulsion Program Technical Support Document'' for the License Application. As noted previously, the radionuclide inventory data presented here is intended only for TSPA-LA postclosure calculations. It is not applicable to preclosure safety calculations. Safe storage, transportation, and ultimate disposal of these wastes require safety analyses to support the design and licensing of repository equipment and facilities. These analyses will require radionuclide inventories to represent the radioactive source term that must be accommodated during handling, storage and disposition of these wastes. This analysis uses the best available information to identify the radionuclide inventory that is expected at the last year of last emplacement, currently identified as 2030 and 2033, depending on the type of waste. TSPA-LA uses the results of this analysis to decay the inventory to the year of repository closure projected for the year of 2060.

H. Miller

2004-09-19T23:59:59.000Z

68

RADIONUCLIDE RADIATION PROTECTION  

E-Print Network (OSTI)

COPYRIGHT 2002 Nuclear Technology Publishing #12;3 #12;4 #12;5 Radiation Protection Dosimetry Vol. 98, No'Energie Atomique, CEA/Saclay, France ISBN 1 870965 87 6 RADIATION PROTECTION DOSIMETRY Vol. 98 No 1, 2002 Published by Nuclear Technology Publishing #12;RADIONUCLIDE AND RADIATION PROTECTION DATA HANDBOOK 2nd Edition (2002

Healy, Kevin Edward

69

Improved temperature regulation of process water systems for the APS storage ring.  

SciTech Connect

Beam stability and operational reliability of critical mechanical systems are key performance issues for synchrotron accelerators such as the Advanced Photon Source (APS). Stability is influenced by temperature fluctuations of the process water (PW) used for cooling and/or temperature conditioning storage ring (SR) components such as vacuum chambers, magnets, absorbers, etc. Operational reliability is crucial in maintaining facility beam operations and remaining within downtime ''budgets.'' Water systems for the APS storage ring were originally provided with a distributive control system (DCS) capable of regulation to {+-}1.0 F, as specified by facility design requirements. After several years of operation, a particular mode of component mortality indicated a need for upgrade of the temperature control system. The upgrade that was implemented was chosen for both improved component reliability and temperature stability (now on the order of {+-}0.2 F for copper components and {+-}0.05 F for aluminum components). The design employs a network of programmable logic controllers (PLCs) for temperature control that functions under supervision of the existing DCS. The human-machine interface (HMI) of the PLC system employs RSView32 software. The PLC system also interfaces with the EPICS accelerator control system to provide monitoring of temperature control parameters. Eventual supervision of the PLC system by EPICS is possible with this design.

Putnam, C.; Dortwegt, R.

2002-10-10T23:59:59.000Z

70

Characterization of radionuclide behavior in low level waste sites  

SciTech Connect

This laboratory is investigating the subsurface migration of radionuclides in groundwater at the Maxey Flats, Kentucky, shallow land burial site and at a low-level aqueous waste disposal facility. At Maxey Flats, radionuclide and tracer data indicate groundwater communication between a waste trench and an adjacent experimental study area. Areal distributions of radionuclides in surface soil confirm that contamination at Maxey Flats has been largely contained on site. Of the radionuclides detected in the surface soil, only /sup 3/H and /sup 60/Co concentrations appear to be derived from waste. Plutonium exists in the anoxic subsurface waters at Maxey Flats as a reduced, anionic complex; some of the plutonium appears to be complexed with EDTA, whereas organic acids seem to be associated with /sup 137/Cs and /sup 90/Sr. At the aqueous waste disposal site, /sup 3/H and mainly anionic species of certain radionuclides, including /sup 60/Co, /sup 106/Ru, /sup 99/Tc, /sup 131/I, and TRACES OF /sup 238/Pu, /sup 239/Pu and /sup 240/Pu appear to migrate from a trench through soil adjacent to the trench. Radionuclides in the particulate and cationic forms appear to be efficiently retained by the soil. In general, observations indicate that the physicochemical form of the radionuclides mediates their subsurface migration in groundwater at both waste disposal sites.

Toste, A.P.; Abel, K.H.; Kirby, L.J.; Perkins, R.W.; Robertson, D.E.

1983-02-01T23:59:59.000Z

71

Targeted radionuclide therapy  

SciTech Connect

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

72

Will Federal Environmental Regulation be Permitted to Infringe on State Vested Water Rights?  

E-Print Network (OSTI)

Irrigation Dist. v. State Water Resources Control Bd. , 27516. See United States v. State Water Resources Control Bd. ,by the 8 deference to state water law. 372 U.S. 627, 630-

Dorrity, Kristen

1992-01-01T23:59:59.000Z

73

Radionuclide Air Emission Report for 2011  

E-Print Network (OSTI)

470E-201 Radionuclide Air Emission Report for Prepared by:Environmental Protection Agency, National Emission Standardsfor Emissions of Radionuclides Other Than Radon From

Wahl, Linnea

2012-01-01T23:59:59.000Z

74

Sorption of radionuclides on Yucca Mountain tuffs  

SciTech Connect

A substantial database of sorption coefficients for important radionuclides on Yucca Mountain tuffs has been obtained by Los Alamos National Laboratory over the past ten years. Current sorption studies are focussed on validation questions and augmentation of the existing database. Validation questions concern the effects of the use of crushed instead of solid rock samples in the batch experiments, the use of oversaturated stock solutions, and variations in water/rock ratios. Sorption mechanisms are also being investigated. Database augmentation activities include determination of sorption coefficients for elements with low sorption potential, sorption on psuedocolloids, sorption on fracture lining minerals, and sorption kinetics. Sorption can provide an important barrier to the potential migration of radionuclides from the proposed repository within Yucca Mountain to the accessible environment. In order to quantify this barrier, sorption coefficients appropriate for the Yucca Mountain groundwater system must be obtained for each of the important radionuclides in nuclear waste. Los Alamos National Laboratories has conducted numerous batch (crushed-rock) sorption experiments over the past ten years to develop a sorption coefficient database for the Yucca Mountain site. In the present site characterization phase, the main goals of the sorption test program will be to validate critical sorption coefficients and to augment the existing database where important data are lacking. 11 refs., 1 fig., 3 tabs.

Meijer, A.; Triay, I.; Knight, S.; Cisneros, M.

1989-11-01T23:59:59.000Z

75

Radionuclide K37  

Science Journals Connector (OSTI)

The radionuclide K37 has been produced by a (p,?) reaction on Ca40, using 12.8-Mev protons accelerated in the UCLA 20-Mev synchrocyclotron. The half-life of this activity was found to be 1.20.12 seconds. With a double-channel magnetic spectrometer the end point of the ? spectrum was determined as 5.100.07 Mev. The ft value determined as 4150500 seconds is within the expected range of the shell-model predictions. The Coulomb energy difference between K37 and A37 deduced from the end point agrees with Peaslee's analysis of the light nuclei. The pairing effect in Coulomb energies discussed by Carlson and Talmi is more clearly exhibited with the addition of the new data.

C. R. Sun and Byron T. Wright

1958-01-01T23:59:59.000Z

76

APT radionuclide production experiment  

SciTech Connect

Tritium ({sup 3}H, a heavy isotope of hydrogen) is produced by low energy neutron-induced reactions on various elements. One such reaction is n+{sup 3}He {yields}>{sup 3}H+{sup 1}H in which {sup 3}He is transmuted to tritium. Another reaction, which has been used in reactor production of tritium, is the n+{sup 6}Li {yields}> {sup 3}H+{sup 4}He reaction. Accelerator Production of Tritium relies on a high-energy proton beam to produce these neutrons using the spallation reaction, in which high-energy proton beam to produce these neutrons using the spallation reaction, in which high-energy protons reacting with a heavy nucleus produce a shower of low-energy neutrons and a lower-mass residual nucleus. It is important to quantify the residual radionuclides produced in the spallation target for two reasons. From an engineering point of view, one must understand short-lived isotopes that may contribute to decay heat. From a safety viewpoint, one must understand what nuclei and decay gammas are produced in order to design adequate shielding, to estimate ultimate waste disposal problems, and to predict possible effects due to accidental dispersion during operation. The authors have performed an experiment to measure the production of radioisotopes in stopping-length W and Pb targets irradiated by a 800 MeV proton beam, and are comparing the results to values obtained from calculations using LAHET and MCNP. The experiment was designed to pay particular attention to the short half-life radionuclides, which have not been previously measured. In the following, they present details of the experiment, explain how they analyzed the data and obtain the results, how they perform the calculations, and finally, how the experimental data agree with the calculations.

Ullmann, J.L.; Gavron, A.; King, J.D. [and others

1994-07-02T23:59:59.000Z

77

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...

78

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...

79

Anthropogenic radionuclides in the environment  

SciTech Connect

Studies of radionuclides in the environment have entered a new era with the renaissance of nuclear energy and associated fuel reprocessing, geological disposal of high-level nuclear wastes, and concerns about national security with respect to nuclear non-proliferation. This work presents an overview of anthropogenic radionuclide contamination in the environment, as well as the salient geochemical behavior of important radionuclides. We first discuss the following major anthropogenic sources and current development that contribute to the radionuclide contamination of the environment: (1) nuclear weapons program; (2) nuclear weapons testing; (3) nuclear power plants; (4) commercial fuel reprocessing; (5) geological repository of high-level nuclear wastes, and (6) nuclear accidents. Then, we summarize the geochemical behavior for radionuclides {sup 99}Tc, {sup 129}I, and {sup 237}Np, because of their complex geochemical behavior, long half-lives, and presumably high mobility in the environment. Biogeochemical cycling and environment risk assessment must take into account speciation of these redox-sensitive radionuclides.

Hu, Q; Weng, J; Wang, J

2007-11-15T23:59:59.000Z

80

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

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

Radionuclide detection devices and associated methods  

DOE Patents (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

82

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

83

Environmental regulations and technology: use and disposal of municipal waste-water sludge  

SciTech Connect

The document describes the five major sludge use/disposal options currently available--land application, distribution and marketing of sludge products, land-filling, incineration, and ocean disposal--and factors influencing their selection and implementation. It also provides an initial framework for evaluating sludge use/disposal alternatives, and describes accepted and proven use/disposal technologies and Federal regulations pertinent to sludge management.

Not Available

1984-09-01T23:59:59.000Z

84

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

85

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

86

The behavior of radionuclides in the soils of Rocky Flats, Colorado  

Science Journals Connector (OSTI)

Radionuclide contamination of soils in Rocky Flats, Colorado, resulted from leaking drums of Pu-contaminated oil stored at an outdoor area. To evaluate the mechanisms of radionuclide transport from the contaminated soils to groundwater, an advanced monitoring system was installed across a toposequence. The impact of natural rain, snowmelt, and large-scale rain simulations on the mobility and distribution of the radionuclides in soil interstitial water was studied. The distribution of radionuclides during the monitoring period from 1993 to 1995 suggested that Pu-239 + 240 and Am241 are largely immobile in semi-arid soils. Large-scale rain simulations with a 100-year recurrence interval occasionally remobilized large fluxes of radionuclides that constitute between 1 and 3.3% of the stored Pu and Am in these soils. Fractionation of Pu-239 + 240 and Am-241 to different particle sizes in the soil interstitial water suggested that most of the radionuclides (8397%) were associated with suspended particles, whereas the level of radionuclides associated with colloidal (0.45 ?m > X > 1nm) and nonfilterable (< 1 nm) fractions ranged from 1.5 to 15%.

M.I. Litaor; G. Barth; E.M. Zika; G. Litus; J. Moffitt; H. Daniels

1998-01-01T23:59:59.000Z

87

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

88

The regulation of water in Namibia in the context of property rights : a comparison with South African water legislation / John Matthew Thomas Pinto.  

E-Print Network (OSTI)

??The Water Resources Management Act 24 of 2004 will change the water regime in Namibia dramatically. Section 4 of the Water Resources Management Act provides (more)

Pinto, John Matthew Thomas

2014-01-01T23:59:59.000Z

89

Tritium issues in commercial pressurized water reactors  

SciTech Connect

Tritium has become an important radionuclide in commercial Pressurized Water Reactors because of its mobility and tendency to concentrate in plant systems as tritiated water during the recycling of reactor coolant. Small quantities of tritium are released in routine regulated effluents as liquid water and as water vapor. Tritium has become a focus of attention at commercial nuclear power plants in recent years due to inadvertent, low-level, chronic releases arising from routine maintenance operations and from component failures. Tritium has been observed in groundwater in the vicinity of stations. The nuclear industry has undertaken strong proactive corrective measures to prevent recurrence, and continues to eliminate emission sources through its singular focus on public safety and environmental stewardship. This paper will discuss: production mechanisms for tritium, transport mechanisms from the reactor through plant, systems to the environment, examples of routine effluent releases, offsite doses, basic groundwater transport and geological issues, and recent nuclear industry environmental and legal ramifications. (authors)

Jones, G. [Constellation Energy Group, R.E. Ginna Nuclear Power Plant, Ontario, NY (United States)

2008-07-15T23:59:59.000Z

90

Structures of the Ca2+-regulated photoprotein obelin Y138F mutant before and after bioluminescence support the catalytic function of a water molecule in the reaction  

Science Journals Connector (OSTI)

Crystal structures of the Y138F obelin mutant before and after bioluminescence have been determined at 1.72 and 1.30 ? resolution, respectively. Their spatial structures support the catalytic function of a water molecule found in an internal cavity in the light-emission reaction of Ca2+-regulated photoproteins.

Natashin, P.V.

2014-02-15T23:59:59.000Z

91

Borders and Discharges: Regulation of Tribal Activities under the Clean Water Act in States with NPDES Program Authority  

E-Print Network (OSTI)

finds a particular need. State water quality standards wouldpreempt ap- plication of state water quality laws pursuantwith a down- stream state's water quality standards. Clean

Craig, Robin Kundis

1997-01-01T23:59:59.000Z

92

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

93

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

94

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

95

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

96

Radionuclide Air Emissions Report for 2012  

E-Print Network (OSTI)

Air Emissions Annual Reports for DOE Sites, memo tooffices providing guidance for report preparation (March 22,470E-2012 Radionuclide Air Emission Report for Prepared by

Wahl, Linnea

2014-01-01T23:59:59.000Z

97

Sediment and radionuclide transport in rivers. Phase 2. Field sampling program for Cattaraugus and Buttermilk Creeks, New York  

SciTech Connect

As part of a study on sediment and radionuclide transport in rivers, Pacific Northwest Laboratory (PNL) is investigating the effect of sediment on the transport of radionuclides in Cattaraugus and Buttermilk Creeks, New York. A source of radioactivity in these creeks is the Western New York Nuclear Service Center which consists of a low-level waste disposal site and a nuclear fuel reprocessing plant. Other sources of radioactivity include fallout from worldwide weapons testing and natural background radioactivity. The major objective of the PNL Field Sampling Program is to provide data on sediment and radionuclide characteristics in Cattaraugus and Buttermilk Creeks to verify the use of the Sediment and Radionuclide Transport model, SERATRA, for nontidal rivers. This report covers the results of field data collection conducted during September 1978. Radiological analysis of sand, silt, and clay size fractions of suspended and bed sediment, and water were performed. Results of these analyses indicate that the principal radionuclides occurring in these two water courses, with levels significantly higher than background levels, during the Phase 2 sampling program were Cesium-137 and Strontium-90. These radionuclides had significantly higher activity levels above background in the bed sediment, suspended sediment, and water samples. Other radionuclides that are possibly being released into the surface water environment by the Nuclear Fuel Services facilities are Plutonium-238, 239, and 240, Americium-241, Curium-244, and Tritium. More radionuclides were consistently found in the bed sediment as compared to suspended sediment. The fewest radionuclides were found in the water of Buttermilk and Cattaraugus Creeks. The higher levels were found in the bed sediments for the gamma-emitters and in the suspended sediment for the alpha and beta-emitters (not including Tritium).

Walters, W.H.; Ecker, R.M.; Onishi, Y.

1982-04-01T23:59:59.000Z

98

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

SciTech Connect

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

99

Microbial transformations of natural organic compounds and radionuclides in subsurface environments  

SciTech Connect

A major national concern in the subsurface disposal of energy wastes is the contamination of ground and surface waters by waste leachates containing radionuclides, toxic metals, and organic compounds. Microorganisms play an important role in the transformation of organic compounds, radionuclides, and toxic metals present in the waste and affect their mobility in subsurface environments. Microbial processes involved in dissolution, mobilization, and immobilization of toxic metals under aerobic and anaerobic conditions are briefly reviewed. Metal complexing agents and several organic acids produced by microbial action affect mobilization of radionuclides and toxic metals in subsurface environments. Information on the persistence of and biodegradation rates of synthetic as well as microbiologically produced complexing agents is scarce but important in determining the mobility of metal organic complexes in subsoils. Several gaps in knowledge in the area of microbial transformation of naturally occurring organics, radionuclides, and toxic metals have been identified, and further basic research has been suggested. 31 refs., 1 fig., 3 tabs.

Francis, A.J.

1985-10-01T23:59:59.000Z

100

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

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

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

102

External detection and measurement of inhaled radionuclides using thermoluminescent dosimeters  

E-Print Network (OSTI)

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...

Prause, Christopher Alvin

2007-04-25T23:59:59.000Z

103

Detecting low levels of radionuclides in fluids  

DOE Patents (OSTI)

An apparatus and method for detecting low levels of one or more radionuclides in a fluid sample uses a substrate that includes an ion exchange resin or other sorbent material to collect the radionuclides. A collecting apparatus includes a collecting chamber that exposes the substrate to a measured amount of the fluid sample such that radionuclides in the fluid sample are collected by the ion exchange resin. A drying apparatus, which can include a drying chamber, then dries the substrate. A measuring apparatus measures emissions from radionuclides collected on the substrate. The substrate is positioned in a measuring chamber proximate to a detector, which provides a signal in response to emissions from the radionuclides. Other analysis methods can be used to detect non-radioactive analytes, which can be collected with other types of sorbent materials.

Patch, Keith D. (Lexington, MA); Morgan, Dean T. (Sudbury, MA)

2000-01-01T23:59:59.000Z

104

Radionuclide Releases During Normal Operations for Ventilated Tanks  

SciTech Connect

This calculation estimates the design emissions of radionuclides from Ventilated Tanks used by various facilities. The calculation includes emissions due to processing and storage of radionuclide material.

Blunt, B.

2001-09-24T23:59:59.000Z

105

Water Regulation I. Osmoregulation  

E-Print Network (OSTI)

= ectothermy Homeothermy = endothermy lTemperature appears as the main limiting factor in the distribution in extremely dry environments · Ctenophorus ornatus ­ "ant eater" Body temperature & thermoregulation I of ECTOTHERMY: SUN ­ ultimate heat source... Conduction & Convection ­ indirect heat source. Poikilothermy

Dever, Jennifer A.

106

Water Regulation I. Osmoregulation  

E-Print Network (OSTI)

= ectothermy Homeothermy = endothermy lTemperature appears as the main limiting factor in the distribution. Herps found in extremely dry environments · Ctenophorus ornatus ­ "ant eater" #12;6 Body temperature of ECTOTHERMY: SUN ­ ultimate heat source... Conduction & Convection ­ indirect heat source. Poikilothermy

Dever, Jennifer A.

107

Water Regulation I. Osmoregulation  

E-Print Network (OSTI)

/use of glands a. Decreased permeability of skin in some sp. b. Secretion of lipids (wax) from skin glands c

Dever, Jennifer A.

108

National radiation exposures and risks caused by implementing EPA`s proposed revised national primary drinking water regulations  

SciTech Connect

This report estimates risks to workers and the public associated with treatment processes and their associated waste products that would be mandated under proposed regulations of radium, radon, and uranium in drinking water. Three scenarios were examined: (1) all wastes flushed to the sanitary sewer; (2) all wastes disposed on land; (3) similar to (2) but radon removal by granulated activated carbon rather than packed tower aeration. Risks considered included accidental injury and cancer. Worker risks for both scenarios I and II were estimated to be 0.025 and 0.01 deaths per year of operation for radium-226 and radium-228, respectively. Worker risks for uranium were estimated to be 0.13 deaths/year of operation for scenario I and 0.5 deaths/year of operation for scenario II. Worker risks for radon removal were estimated to be 1.7 deaths/year of operation for scenario I and 2.2 deaths/year of operation for scenario II. Risks to the public for scenarios I and II for radium-226 were 4 {times} 10{sup {minus}4} and for radium-228 were 9 {times} 10{sup {minus}5} deaths/year of operation. Risks to the public for scenarios I and II for uranium were 7.3 {times} 10{sup {minus}2} and 2 {times} 10{sup {minus}4}, respectively. Risks to the public for scenario I and II for radon were 24 deaths/year of operation and for scenario III were nil. Public risks were quantified only for people exposed during a year of operation. For example, effects of public exposures in future years via groundwater contamination associated with landfill of treatment waste were not considered.

Morris, S.C.; Rowe, M.D.; Holtzman, S.; Meinhold, A.F.

1993-05-01T23:59:59.000Z

109

Evaluation of radionuclide migration in the homogeneous system of a geological repository  

Science Journals Connector (OSTI)

The aim of this paper is to study radionuclide migration and release from a deep underground repository situated in a clay formation. An insight into the processes influencing the radionuclide transport in the near field and far field will be presented. For the calculation, a set of radionuclides has been chosen, considering the half-life, decay chains, capacity of the sorption, solubility limits and diffusion coefficients. The migration of radionuclides is dependent on transport properties of the particular nuclide. Due to the low hydraulic conductivity of the backfill material and clay geological formation, the transport in the repository occurs mainly by diffusion. The migration rate will be influenced by the water chemistry, solubility, retardation and diffusive properties of the nuclides, and the water flow rate in the clay. The release rates of radionuclides from the geosphere to the biosphere will be converted into the indicative dose rates using dose conversion factors for ingestion. The impact of the critical group is considered via consumption of meat, root vegetables and drinking water from wells.

S. Prvakova; J. Duran; V. Necas

2005-01-01T23:59:59.000Z

110

E-Print Network 3.0 - a5 radionuclide transport Sample Search...  

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

...49 Sellafield - doses to seafood consumers - radionuclides 2... of radionuclides in food and the environment around...

111

National Emission Standards for Hazardous Air PollutantsCalendar Year 2013 INL Report for Radionuclides (2014)  

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 Energys 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

2014-06-01T23:59:59.000Z

112

Radionuclide release rates from spent fuel for performance assessment modeling  

SciTech Connect

In a scenario of aqueous transport from a high-level radioactive waste repository, the concentration of radionuclides in water in contact with the waste constitutes the source term for transport models, and as such represents a fundamental component of all performance assessment models. Many laboratory experiments have been done to characterize release rates and understand processes influencing radionuclide release rates from irradiated nuclear fuel. Natural analogues of these waste forms have been studied to obtain information regarding the long-term stability of potential waste forms in complex natural systems. This information from diverse sources must be brought together to develop and defend methods used to define source terms for performance assessment models. In this manuscript examples of measures of radionuclide release rates from spent nuclear fuel or analogues of nuclear fuel are presented. Each example represents a very different approach to obtaining a numerical measure and each has its limitations. There is no way to obtain an unambiguous measure of this or any parameter used in performance assessment codes for evaluating the effects of processes operative over many millennia. The examples are intended to suggest by example that in the absence of the ability to evaluate accuracy and precision, consistency of a broadly based set of data can be used as circumstantial evidence to defend the choice of parameters used in performance assessments.

Curtis, D.B.

1994-11-01T23:59:59.000Z

113

Yucca Mountain Project - Science & Technology Radionuclide Absorbers Development Program Overview  

SciTech Connect

The proposed Yucca Mountain repository is anticipated to be the first facility for long-term disposal of commercial spent nuclear fuel and high-level radioactive waste in the United States. The facility, located in the southern Nevada desert, is currently in the planning stages with initial exploratory excavations completed. It is an underground facility mined into the tuffaceous volcanic rocks that sit above the local water table. The focus of the work described in this paper is the development of radionuclide absorbers or ''getter'' materials for neptunium (Np), iodine (I), and technetium (Tc) for potential deployment in the repository. ''Getter'' materials retard the migration of radionuclides through sorption, reduction, or other chemical and physical processes, thereby slowing or preventing the release and transport of radionuclides. An overview of the objectives and approaches utilized in this work with respect to materials selection and modeling of ion ''getters'' is presented. The benefits of the ''getter'' development program to the United States Department of Energy (US DOE) are outlined.

Hong-Nian Jow; R.C. Moore; K.B. Helean; S. Mattigod; M. Hochella; A.R. Felmy; J. Liu; K. Rosso; G. Fryxell; J. Krumhansl; Y. Wang

2005-01-14T23:59:59.000Z

114

Uptake, depuration, and radiation dose estimation in zebrafish exposed to radionuclides via aqueous or dietary routes  

Science Journals Connector (OSTI)

Understanding uptake and depuration of radionuclides in organisms is necessary to relate exposure to radiation dose and ultimately to biological effects. We investigated uptake and depuration of a mixture of radionuclides to link bioaccumulation with radiation dose in zebrafish, Danio rerio. Adult zebrafish were exposed to radionuclides (54Mn, 60Co, 65Zn, 75Se, 109Cd, 110mAg, 134Cs and 241Am) at tracer levels (dose rates were modelled from activity concentrations in whole body and exposure medium (water or diet). After 14-day aqueous exposure, radionuclides were detected in decreasing activity concentrations: 75Se>65Zn>109Cd>110mAg>54Mn>60Co>241Am>134Cs (range: 1758Bqg1). After dietary exposure the order of radionuclide activity concentration in tissues (Bqg?1) was: 65Zn>60Co>75Se>109Cd>110mAg>241Am>54Mn>134Cs (range: 911Bqg?1). Aqueous exposure resulted in higher whole body activity concentrations for all radionuclides except 60Co. Route of exposure did not appear to influence activity concentrations in gonads, except for 54Mn, 65Zn, and 75Se, which had higher activity concentrations in gonads following aqueous exposure. Highest gonad activity concentrations (Bqg?1) were for 75Se (211), 109Cd (142), and 65Zn (117), and highest dose rates (?Gyh?1) were from 241Am (aqueous, 1050; diet 242). This study links radionuclide bioaccumulation data obtained in laboratory experiments with radiation dose determined by application of a dosimetry modelling tool, an approach that will enable better linkages to be made between exposure, dose, and effects of radionuclides in organisms.

Helena C. Reinardy; Jean-Louis Teyssie; Ross A. Jeffree; David Copplestone; Theodore B. Henry; Awadhesh N. Jha

2011-01-01T23:59:59.000Z

115

Chemical species of migrating radionuclides at a shallow land low-level radioactive-waste burial site  

SciTech Connect

A research program at the Maxey Flats, Kentucky (U.S.A.) waste disposal site has been undertaken to define the chemical species contributing to the migration or retention of radionuclides contained in waste buried at that site. An experimental trench and inert atmosphere sampling wells were installed to sample water for determination of the chemical species of migrating radionuclides. The organic ligands are studied by gas chromatography, steric exclusion chromatography and mass spectrometry; and the data correlated with specific radionuclide counting data to determine precise chemical species. Preliminary data are reported in the text.

Kirby, L.J.; Toste, A.P.; Wilkerson, C.L.

1981-01-01T23:59:59.000Z

116

RADIONUCLIDE MIGRATION IN TUFF UNDER UNSATURATED CONDITIONS  

SciTech Connect

An understanding of the transport of radionuclides through unsaturated and saturated tuffaceous material is essential in assessing the safety of the proposed high-level waste repository at Yucca Mountain. Migration experiments with conservative and chemically reactive non-radioactive tracers have been performed at the Busted Butte Unsaturated Zone underground facility, SE of Yucca Mountain, and with radionuclides in columns of crushed tuff at the Los Alamos National Laboratory. In this paper, complementary radionuclide migration experiments, performed under unsaturated conditions in a small block of tuff excavated from Busted Butte, are described.

T.T. Vandergraaf

2000-10-25T23:59:59.000Z

117

Appendix II. Calculation of Slope Factors for Naturally Occurring Radionuclides  

E-Print Network (OSTI)

Appendix II. Calculation of Slope Factors for Naturally Occurring Radionuclides In developing calculates the slope factors for the naturally occurring radionuclides under consideration. The Radionuclide products with half-lives of less than 6 months). As explained below, naturally occurring radionuclides

118

System and method for assaying a radionuclide  

DOE Patents (OSTI)

A system for assaying a radionuclide includes a liquid scintillation detector, an analyzer connected to the liquid scintillation detector, and a delay circuit connected to the analyzer. A gamma detector and a multi-channel analyzer are connected to the delay circuit and the gamma detector. The multi-channel analyzer produces a signal reflective of the radionuclide in the sample. A method for assaying a radionuclide includes selecting a sample, detecting alpha or beta emissions from the sample with a liquid scintillation detector, producing a first signal reflective of the alpha or beta emissions, and delaying the first signal a predetermined time. The method further includes detecting gamma emissions from the sample, producing a second signal reflective of the gamma emissions, and combining the delayed first signal with the second signal to produce a third signal reflective of the radionuclide.

Cadieux, James R; King, III, George S; Fugate, Glenn A

2014-12-23T23:59:59.000Z

119

Interlayer Water Regulates the Bio-nano Interface of a \\b{eta}-sheet Protein stacking on Graphene  

E-Print Network (OSTI)

Using molecular dynamics simulations, we investigated an integrated bio-nano interface consisting of a \\b{eta}-sheet protein stacked onto graphene. We found that the stacking assembly of the model protein on graphene could be controlled by water molecules. The interlayer water filled within interstices of the bio-nano interface could suppress the molecular vibration of surface groups on protein, and could impair the CH...{\\pi} interaction driving the attraction of the protein and graphene. The intermolecular coupling of interlayer water would be relaxed by the relative motion of protein upon graphene due to the interaction between water and protein surface. This effect reduced the hindrance of the interlayer water against the assembly of protein on graphene, resulting an appropriate adsorption status of protein on graphene with a deep free energy trap. Thereby, the confinement and the relative sliding between protein and graphene, the coupling of protein and water, and the interaction between graphene and water all have involved in the modulation of behaviors of water molecules within the bio-nano interface, governing the hindrance of interlayer water against the protein assembly on hydrophobic graphene. These results provide a deep insight into the fundamental mechanism of protein adsorption onto graphene surface in water.

Wenping Lv; Guiju Xu; Hongyan Zhang; Xin Li; Shengju Liu; Huan Niu; Dongsheng Xu; Renan Wu

2014-06-29T23:59:59.000Z

120

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

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

Library Regulations Library Regulations  

E-Print Network (OSTI)

Library Regulations 2012-13 Library Regulations UNIVERSITY OF BIRMINGHAM REGULATIONS LIBRARY REGULATIONS Preamble: The Library Regulations apply to all users of library facilities managed on behalf of the University by Library Services, and thus there are sections that apply also to non- members of the University

Birmingham, University of

122

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

SciTech Connect

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 Energys (DOEs) 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

123

Interlayer Water Regulates the Bio-nano Interface of a \\b{eta}-sheet Protein stacking on Graphene  

E-Print Network (OSTI)

Interfacial interactions between biomolecules and nanomaterials are essential for the design of bionanomaterials and biomedical devices. Using molecular dynamics simulations, we investigated an integrated bio-nano interface consisting of a \\b{eta}-sheet protein stacked onto graphene. The stacking of the model protein on graphene was found to be controlled by water molecules. The CH...{\\pi} interaction driving the attraction of the \\b{eta}-sheet protein and graphene was impaired by interlayer water molecules confined within the \\b{eta}-sheet protein-graphene bio-nano interface. The hindering role of the interlayer water on the assembly of protein on graphene was reduced via the transversal motion of protein searching for the appropriate adsorption site on graphene. This transversal motion reduced intermolecular-coupling with water in the interlayer. Evaluation of the hydrogen bonding between the protein-bound and unbound water molecules in the interlayer demonstrated an atomic-level modulation of water towards the CH...{\\pi} attraction between protein and graphene. The modulations of the water molecules within the interlayer and the molecular details of the interactions between the protein, water and graphene provide deep insight into the fundamental mechanism of protein adsorption onto a graphene surface.

Wenping Lv; Guiju Xu; Hongyan Zhang; Xin Li; Shengju Liu; Huan Niu; Dongsheng Xu; Renan Wu

2014-06-29T23:59:59.000Z

124

Radionuclide characterization and associated dose from long-lived radionuclides in close-in fallout delivered to the marine environment at Bikini and Enewetak Atoll  

SciTech Connect

Between June 1946 and October 1958, Enewetak and Bikini Atolls were used by the United States as testing grounds for 66 nuclear devices. The combined explosive yield from these tests was 107 Mt (Mt TNT equivalents). This testing produced close-in fallout debris that was contaminated with quantities of radioactive fission and particle activated products, and unspent radioactive nuclear fuel that entered the aquatic environment of the atolls. Today, the sediments in the lagoons are reservoirs for 10's of TBq of the transuranics and some long-lived fission and activation products. The larger amounts of contamination are associated with fine and coarse sediment material adjacent to the locations of the high yield explosions. Radionuclides are also distributed vertically in the sediment column to various depths in all regions of the lagoons. Concentrations greater than fallout background levels are found in filtered water sampled over several decades from all locations and depths in the lagoons. This is a direct indication that the radionuclides are continuously mobilized to solution from the solid phases. Of particular importance is the fact that the long-lived radionuclides are accumulated to different levels by indigenous aquatic plants and organisms that are used as food by resident people. One might anticipate finding continuous high contamination levels in many of the edible marine organisms from the lagoons, since the radionuclides associated with the sediments are not contained and are available to the different organisms in a relatively shallow water environment. This is not the case. We estimate that the radiological dose from consumption of the edible parts of marine foods at Enewetak and Bikini is presently about 0.05% of the total 50-year integral effective dose from all other exposure pathways that include ingestion of terrestrial foods and drinking water, external exposure and inhalation. The total radiological dose from the marine pathway is dominated by the natural radionuclides, {sup 210}Po and {sup 210}Pb. Man-made radionuclides presently contribute less than 0.3% of the dose from these natural radionuclides in the marine food chain.

Noshkin, V. E.; Robison, W. L.

1998-09-01T23:59:59.000Z

125

1998 INEEL National Emission Standard for Hazardous Air Pollutants - Radionuclides  

SciTech Connect

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

126

Radionuclide distributions and migration mechanisms at shallow land burial sites. 1982 annual report of research investigations on the distribution, migration and containment of radionuclides at Maxey Flats, Kentucky  

SciTech Connect

Subsurface waters at Maxey Flats are anoxic, have a high alkalinity and contain high concentrations of ferrous, sulfide and ammonium ions and organic carbon. The trench leachates are extremely variable in composition. Prominent radionuclides include /sup 3/H, /sup 60/Co, /sup 90/Sr, /sup 137/Cs, /sup 238/ /sup 239/ /sup 240/Pu and /sup 241/Am. A wide spectrum of dissolved organic compounds is present in the leachates, including EDTA, polar organics and decomposition products from the waste forms. Cobalt-60 and plutonium are present as EDTA complexes and /sup 90/Sr and /sup 137/Cs are associated with carboxylic acid type compounds. The chemistry of these waters changes drastically as they become oxic and plutonium becomes less mobile under these new conditions. Water enters the trenches by infiltration through the trench caps, through subsidence areas, and through interfaces between new landfill and the original soil. Lateral flow is very complex and slow, and apparently occurs mainly by fracture flow. The plastic infiltration barrier installed in 1981 to 1982 has been effective in reducing soil moisture if cracks and leaks are eliminated. To date, no direct evidence of radionuclide transport to offsite locations by subsurface flow has been confirmed. The offsite distribution of radionuclides, except for tritium, is comparable to the ambient fallout from nuclear weapons testing. Tritium concentrations in water offsite are orders of magnitude below MPC levels. 24 figures, 31 tables.

Kirby, L.J. (ed.)

1984-02-01T23:59:59.000Z

127

Concentrations of radionuclides in reef and lagoon pelagic fish from the Marshall Islands  

SciTech Connect

A radiological survey was conducted from September through November of 1978 to assess the concentrations of persistent man-made radionuclides in the terrestrial and marine environments of 11 atolls and 2 islands of the Northern Marshall Islands. The atolls and islands include Rongelap, Utirik, Taka, Bikar, Rongerik, Ailinginae, Likiep, Jemo, Ailuk, Mejet, Wotho, Ujelang and Bikini. Over 4000 terrestrial and marine samples were collected for radionuclide analysis from 76 different islands. Soils, vegetation, indigenous animals, and cistern and groundwater were collected from the islands. Reef fish, pelagic species, clams, lagoon water, and sediments were obtained from the lagoons. A report is given of all available concentration data for /sup 137/Cs, /sup 90/Sr, /sup 239+240/Pu, /sup 238/Pu, /sup 241/Am as well as naturally occurring /sup 40/K and other gamma emitting radionuclides in tissues and organs of different species of fish collected from the atolls.

Noshkin, V.E.; Eagle, R.J.; Wong, K.M.; Jokela, T.A.; Brunk, J.L.; Marsh, K.V.

1981-07-01T23:59:59.000Z

128

Radionuclide Migration through Sediment and Concrete: 16 Years of Investigations  

SciTech Connect

The Waste Management Project provides safe, compliant, and cost-effective waste management services for the Hanford Site and the U.S. Department of Energy (DOE) complex. Part of these services includes safe disposal of low-level waste and mixed low-level waste at the Hanford Low-Level Waste Burial Grounds in accordance with the requirements of DOE Order 435.1, Radioactive Waste Management. To partially satisfy these requirements, performance assessment analyses were completed and approved. DOE Order 435.1 also requires continuing data collection to increase confidence in the critical assumptions used in these analyses to characterize the operational features of the disposal facility that are relied on to satisfy the performance objectives identified in the order. Cement-based solidification and stabilization is considered for hazardous waste disposal because it is easily done and cost-efficient. One critical assumption is that concrete will be used as a waste form or container material at the Hanford Site to control and minimize the release of radionuclide constituents in waste into the surrounding environment. Concrete encasement would contain and isolate the waste packages from the hydrologic environment and 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 radionuclides iodine-129, selenium-75, technetium-99, and uranium-238 have been identified as long-term dose contributors (Mann et al. 2001; Wood et al. 1995). Because of their anionic nature in aqueous solutions, these constituents of potential concern may be released from the encased concrete by mass flow and/or diffusion and migrate into the surrounding subsurface environment (Serne et al. 1989; 1992; 1993a, b; 1995). Therefore, it is necessary to assess the performance of the concrete encasement structure and the ability of the surrounding soil to retard radionuclide migration. Each of the test methods performed throughout the lifetime of the project has focused on different aspects of the concrete waste form weathering process. Diffusion of different analytes [technetium-99 (Tc-99), iodine-125 (I-125), stable iodine (I), uranium (U), and rhenium (Re)] has been quantified from experiments under both saturated and unsaturated conditions. The water-saturated conditions provide a conservative estimate of the concretes performance in situ, and the unsaturated conditions provide a more accurate estimate of the diffusion of contaminants from the concrete.

Golovich, Elizabeth C.; Mattigod, Shas V.; Snyder, Michelle MV; Powers, Laura; Whyatt, Greg A.; Wellman, Dawn M.

2014-11-06T23:59:59.000Z

129

Remote sensing of soil radionuclide fluxes in a tropical ecosystem  

SciTech Connect

We are using a transponding geostationary satellite to collect surface environmental data to describe the fate of soil-borne radionuclides. The remote, former atomic testing grounds at the Eniwetok and Bikini Atolls present a difficult environment in which to collect continuous field data. Our land-based, solar-powered microprocessor and environmental data systems remotely acquire measurements of net and total solar radiation, rain, humidity, temperature, and soil-water potentials. For the past year, our water flux model predicts wet season plant transpiration rates nearly equal to the 6 to 7 mm/d evaporation pan rate, which decreases to 2 to 3 mm/d for the dry season. Radioisotopic analysis confirms the microclimate-estimated 1:3 to 1:20 soil to plant /sup 137/Cs dry matter concentration ratio. This ratio exacerbates the dose to man from intake of food plants. Nephelometer measurements of airborne particulates presently indicate a minimum respiratory radiological dose.

Clegg, B.; Koranda, J.; Robinson, W.; Holladay, G.

1980-11-06T23:59:59.000Z

130

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

131

Elements of an environmental decision support system for seasonal wetland salt management in a river basin subjected to water quality regulation  

SciTech Connect

Seasonally managed wetlands in the Grasslands Basin on the west-side of California's San Joaquin Valley provide food and shelter for migratory wildfowl during winter months and sport for waterfowl hunters during the annual duck season. Surface water supply to these wetlands contain salt which, when drained to the San Joaquin River during the annual drawdown period, can negatively impact water quality and cause concern to downstream agricultural riparian water diverters. Recent environmental regulation, limiting discharges salinity to the San Joaquin River and primarily targeting agricultural non-point sources, now also targets return flows from seasonally managed wetlands. Real-time water quality management has been advocated as a means of continuously matching salt loads discharged from agricultural, wetland and municipal operations to the assimilative capacity of the San Joaquin River. Past attempts to build environmental monitoring and decision support systems (EDSS's) to implement this concept have enjoyed limited success for reasons that are discussed in this paper. These reasons are discussed in the context of more general challenges facing the successful implementation of a comprehensive environmental monitoring, modelling and decision support system for the San Joaquin River Basin.

Quinn, N.W.T.

2009-06-01T23:59:59.000Z

132

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

133

Computation Of The Residual Radionuclide Activity Within Three Natural Waterways At The Savannah River Site  

SciTech Connect

In 2010 a Composite Analysis (CA) of the U.S. Department of Energys (DOEs) Savannah River Site (SRS) was completed. This investigation evaluated the dose impact of the anticipated SRS End State residual sources of radionuclides to offsite members of the public. Doses were assessed at the locations where SRS site streams discharge into the Savannah River at the perimeter of the SRS. Although the model developed to perform this computation indicated that the dose constraint of 0.3 mSv/yr (30 mrem/yr), associated with CA, was not approached at the Points of Assessment (POAs), a significant contribution to the total computed dose was derived from the radionuclides (primarily Cs-137) bound-up in the soil and sediment of the drainage corridors of several SRS streams. DOEs Low Level Waste Federal Review Group (LFRG) reviewed the 2010 CA and identified several items to be addressed in the SRS Maintenance Program. One of the items recognized Cs-137 in the Lower Three Runs (LTR) Integrator Operable Unit (IOU), as a significant CA dose driver. The item made the recommendation that SRS update the estimated radionuclide inventory, including Cs-137, in the LTR IOU. That initial work has been completed and its radionuclide inventory refined. There are five additional streams at SRS and the next phase of the response to the LFRG concern was to obtain a more accurate inventory and distribution of radionuclides in three of those streams, Fourmile Branch (FMB), Pen Branch (PB) and Steel Creek (SC). Each of these streams is designated as an IOU, which are defined for the purpose of this investigation as the surface water bodies and associated wetlands, including the channel sediment, floodplain sed/soil, and related biota. If present, radionuclides associated with IOUs are adsorbed to the streambed sediment and soils of the shallow floodplains that lie immediately adjacent to stream channels. The scope of this effort included the evaluation of any previous sampling and analysis data that had been collected for various SRS investigations, as well as the additional streambed and floodplain sampling and analysis data acquired more recently as part of the ongoing SRS IOU program, and associated specifically with the FMB, PB, and SC IOUs. Samples have been acquired along the waterways, within the stream channels themselves and in the adjacent floodplain zones. While Cs-137 is the most significant and abundant radionuclide associated with the SRS waterways, it is not the only radionuclide, hence work was conducted to evaluate all radionuclides present.

Hiergesell, R. A.; Phifer, M. A.

2014-01-07T23:59:59.000Z

134

Alaska ADEC Wetlands Regulation | Open Energy Information  

Open Energy Info (EERE)

Regulation Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Alaska ADEC Wetlands Regulation Author Alaska Division of Water Published Alaska Department...

135

Annual report, October 1980-September 1981 Multimedia radionuclide exposure assessment modeling.  

SciTech Connect

Pacific Northwest Laboratory (PNL) and Los Alamos National Laboratory (LANL) are jointly developing a methodology for assessing exposures of the air, water, and plants to radionuclides as part of an overall development effort of a radionuclide disposal site evaluation methodology. Work in FY-1981 continued the development of the Multimedia Contaminant Environmental Exposure Assessment (MCEA) methodology and initiated an assessment of radionuclide migration in Los Alamos and Pueblo Canyons, New Mexico, using the methodology. The AIRTRAN model was completed, briefly tested, and documented. In addition, a literature search for existing validation data for AIRTRAN was performed. The feasibility and advisability of including the UNSAT moisture flow model as a submodel of the terrestrial code BIOTRAN was assessed. A preliminary application of the proposed MCEA methodology, as it related to the Mortandad-South Mortandad Canyon site in New Mexico is discussed. This preliminary application represented a scaled-down version of the methodology in which only the terrestrial, overland, and surface water components were used. An update describing the progress in the assessment of radionuclide migration in Los Alamos and Pueblo Canyons is presented. 38 references, 47 figures, 11 tables.

Whelan, G.; Onishi, Y.; Simmons, C.S.; Horst, T.W.; Gupta, S.K.; Orgill, M.M.; Newbill, C.A.

1982-12-01T23:59:59.000Z

136

Radionuclide characterization, migration, and monitoring at a commercial low-level waste disposal site  

SciTech Connect

A commercial low-level radioactive waste disposal facility is being studied to characterize the physicochemical forms of the radionuclides and their behavior during migration in ground waters. Environmental monitoring studies are also in progress to identify and assess migration pathways of the radionuclides. At the Maxey Flats, Kentucky low-level waste burial site, mobile species of various radionuclides have migrated short distances on-site (meters to tens of meters) from the trenches. Plutonium is migrating as a soluble anionic complex in the Pu(III) and Pu(IV) oxidation states. Empirical evidence suggests that EDTA contained in the trench water has formed strong organic complexes with plutonium and /sup 60/Co, thereby increasing their mobility. Mobile forms of /sup 90/Sr and /sup 137/Cs are associated with a variety of polar organic species, e.g. carboxylic acids. Environmental monitoring studies at the Maxey Flats site are assessing surface contamination and biological monitoring techniques which can be used for long-term surveillance. Deciduous forests growing near the Maxey Flats site offer the potential to detect the migration of radionuclides, particularly tritium, occurring by subterranean flow from the waste trenches of the flow is within the rooting depth of the trees.

Kirby, L.J.; Toste, A.P.; Rickard, W.H.

1983-05-01T23:59:59.000Z

137

Automated two column generator systems for medical radionuclides  

Science Journals Connector (OSTI)

This work describes automated chromatographic methods for the separation of medically useful radionuclides from source material containing their parent radionuclides. The separation techniques employ two chromatographic columns to ensure high chemical and radiochemical purity of the product radionuclide. The separations were performed using an automated system, the automated radionuclide separator (ARS2), consisting of syringe pumps and multiport valves controlled through a computer interface. Generator systems for 68Ga, 99mTc, 188Re and 213Bi will be described.

Daniel R. McAlister; E. Philip Horwitz

2009-01-01T23:59:59.000Z

138

Physiological regulation of evaporative water loss in endotherms: is the little red kaluta (Dasykaluta rosamondae) an exception or the rule?  

Science Journals Connector (OSTI)

...is determined essentially by physics [1-3], and not by physiological...thermolabile T b, low basal metabolic rate and EWL, high point of relative...between EWL and deltawvp that passes through the origin (no EWL...determination of basal metabolic rate and evaporative water loss of...

2014-01-01T23:59:59.000Z

139

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

SciTech Connect

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

140

Colloid-facilitated radionuclide transport in fractured porous rock  

E-Print Network (OSTI)

radionuclide on the fracture surface [kg ? nuclide / m' - surface]. 23 3. 4 The Radionuclide transport in the aqueous phase within the fracture The radionuclide transport in the aqueous phase within the fracture is expressed as: BN cf rr r ? +V J +VV...

Baek, Inseok

2012-06-07T23:59:59.000Z

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

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.

142

Radionuclide Air Emission Report May 21, 2007  

E-Print Network (OSTI)

Environment, Safety, and Health Division Ernest Orlando Lawrence Berkeley National Laboratory Prepared Lawrence Berkeley National Laboratory Operation Office Information Office: U.S. Department of Energy Radionuclide Air Emission Report for 2006 (in compliance with 40 CFR 61, Subpart H) Site Name: Ernest Orlando

143

Strontium and cesium radionuclide leak detection alternatives in a capsule storage pool  

SciTech Connect

A study was performed to assess radionuclide leak-detection systems for use in locating a capsule leaking strontium-90 or cesium-137 into a water-filled pool. Each storage pool contains about 35,000 L of water and up to 715 capsules, each of which contains up to 150 kCi strontium-90 or 80 kCi cesium-137. Potential systems assessed included instrumental chemical analyses, radionuclide detection, visual examination, and other nondestructive nuclear-fuel examination techniques. Factors considered in the assessment include: cost, simplicity of maintenance and operation, technology availability, reliability, remote operation, sensitivity, and ability to locate an individual leaking capsule in its storage location. The study concluded that an adaption of the spent nuclear-fuel examination technique of wet sipping be considered for adaption. In the suggested approoch, samples would be taken continuously from pool water adjacent to the capsule(s) being examined for remote radiation detection. In-place capsule isolation and subsequent water sampling would confirm that a capsule was leaking radionuclides. Additional studies are needed before implementing this option. Two other techniques that show promise are ultrasonic testing and eddy-current testing.

Larson, D.E.; Crawford, T.W.; Joyce, S.M.

1981-08-01T23:59:59.000Z

144

The minimum gas temperature at the inlet of regulators in natural gas pressure reduction stations (CGS) for energy saving in water bath heaters  

Science Journals Connector (OSTI)

Abstract In this study a computational procedure for the computation of JouleThomson coefficient of natural gas has been developed using fundamental thermodynamic equations and AGA-8 equation of state, and then the minimum possible temperature of the natural gas entering to the pressure regulator of city gate stations (CGS) is calculated. As a case study, a CGS located in Bistoon (of Iran's CGSs) with nominal capacity of 20,000 SCMH has been considered. A comparison has been made between the calculated results and corresponding collected data from the station within 10 months. Results of this study help to determine the minimum temperature values of entering gas with different pressures to the regulator in order to avoid hydrate formation of the outlet gas, and can be used to design appropriate temperature control systems for water bath heaters and in turn save consumed energy for gas heating. The results show that heating the gas up to calculated minimum temperatures can save energy consumption of heaters by 43%. Also, it is indicated that by applying a control system, based on the result of this study, in the CGS the payback period would be less than a year.

Esmail Ashouri; Farzad Veysi; Ehsan Shojaeizadeh; Maryam Asadi

2014-01-01T23:59:59.000Z

145

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,

146

The COMPLY computer program for demonstrating compliance with national radionuclide air emission standards  

SciTech Connect

The Environmental Protection Agency (EPA) has proposed national radionuclide air emission standards for a number of source categories. One of these standards applies to Nuclear Regulatory Commission Licensees and non-Department of Energy facilities having the potential to release radionuclides to the atmosphere. Approximately 6000 facilities are subject to the standard, which limits the effective whole-body dose commitment to the maximally exposed individual from radionuclide releases to the atmosphere. A computer program to assist the regulated community in determining compliance has been developed by the EPA's Office of Radiation Programs. The computer program COMPLY calculates the dose to an individual residing outside the facility. The program considers dose from inhalation, ingestion of contaminated food, air immersion, and ground deposition. It is based on models developed by the National Council on Radiation Protection and Measurements (NCRP). Compliance procedures provided in COMPLY are designed to reduce the burden on the regulated community. The approach begins with simple-to-use methods that are very conservative in determining compliance. The methods become progressively less conservative but more complicated at succeeding levels. Each higher level requires the input of site-specific information, but allows a more realistic estimate of dose. This paper describes the COMPLY program, and provides estimates of the work required and the degree of conservatism in the dose computed at each level.

Colli, A.; Beal, S.; Loomis, D. (Environmental Protection Agency, Washington, DC (USA))

1990-04-01T23:59:59.000Z

147

Effect of Reducing Groundwater on the Retardation of Redox-Sensitive Radionuclides  

SciTech Connect

Laboratory batch sorption experiments were used to investigate variations in the retardation behavior of redox-sensitive radionuclides. Water-rock compositions used during these experiments were designed to simulate subsurface conditions at the Nevada Test Site (NTS), where a suite of radionuclides were deposited as a result of underground nuclear testing. Experimental redox conditions were controlled by varying the oxygen content inside an enclosed glove box and by adding reductants into the testing solutions. Under atmospheric (oxidizing) conditions, the radionuclide distribution coefficients varied with the mineralogical composition of the sorbent and the water chemistry. Under reducing conditions, distribution coefficients showed marked increases for {sup 99}Tc and {sup 237}Np in devitrified tuff, but much smaller variations in alluvium, carbonate rock, and zeolitic tuff. This effect was particularly important for {sup 99}Tc, which tends to be mobile under oxidizing conditions. Unlike other redox-sensitive radionuclides, iodine sorption may decrease under reducing conditions when I{sup -} is the predominant species. Overall, sorption of U to alluvium, devitrified tuff, and zeolitic tuff under atmospheric conditions was less than in the glove-box tests. However, the mildly reducing conditions achieved here were not likely to result in substantial U(VI) reduction to U(IV). Sorption of Pu was not affected by the decreasing redox conditions achieved in this study, as the predominant sorbed Pu species in all conditions was expected to be the low-solubility and strongly sorbing Pu(OH){sub 4}. Depending on the aquifer lithology, the occurrence of reducing conditions along a groundwater flowpath could potentially contribute to the retardation of redox-sensitive radionuclides {sup 99}Tc and {sup 237}Np, which are commonly identified as long-term dose contributors in the risk assessment in various nuclear facilities.

Hu, Q; Zavarin, M; Rose, T P

2008-04-21T23:59:59.000Z

148

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

149

Estimate of radionuclide release characteristics into containment under severe accident conditions. Final report  

SciTech Connect

A detailed review of the available light water reactor source term information is presented as a technical basis for development of updated source terms into the containment under severe accident conditions. Simplified estimates of radionuclide release and transport characteristics are specified for each unique combination of the reactor coolant and containment system combinations. A quantitative uncertainty analysis in the release to the containment using NUREG-1150 methodology is also presented.

Nourbakhsh, H.P. [Brookhaven National Lab., Upton, NY (United States)

1993-11-01T23:59:59.000Z

150

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

151

(The fate of nuclides in natural water systems)  

SciTech Connect

Our research at Yale on the fate of nuclides in natural water systems has three components to it: the study of the atmospheric precipitation of radionuclides and other chemical species; the study of the behavior of natural radionuclides in groundwater and hydrothermal systems; and understanding the controls on the distribution of radionuclides and stable nuclides in the marine realm. In this section a review of our progress in each of these areas is presented.

Turekian, K.K. (Yale Univ., New Haven, CT (USA). Dept. of Geology and Geophysics)

1989-01-01T23:59:59.000Z

152

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

153

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,...

154

Plutonium, cesium and uranium series radionuclides in the Hudson River estuary and other environments. Annual technical progress report, December 1, 1979-November 30, 1980  

SciTech Connect

Radionuclide activities were measured in a large number of sediment cores and suspended particle samples throughout the salinity range of the Hudson River estuary. Activities of /sup 137/Cs, /sup 134/Cs and /sup 60/Co determined by gamma spectrometry and /sup 239/ /sup 240/Pu and /sup 238/Pu determined by alpha spectrometry indicate reasonably rapid accumulation rates in the sediments of marginal cove areas, and very rapid deposition in the harbor region adjacent to New York City, resulting in /sup 239/ /sup 240/Pu accumulations there more than an order of magnitude greater than the fallout delivery rate. Measurable amounts of reactor-derived /sup 134/Cs and /sup 60/Co are found in nearly al sediment samples containing appreciable /sup 137/Cs between 15 km upstream of Indian Point and the downstream extent of our sampling about 70 km south of the reactor. Fallout /sup 239/ /sup 240/Pu reaching the Hudson appears to be almost completely retained within the systems by particle deposition, while 70 to 90% of the /sup 137/Cs derived from both reactor releases and fallout has been exported to the coastal waters in solution. Activity levels of /sup 239/ /sup 240/Pu in New York harbor sediments indicate a significant source in addition to suspended particles carried down the Hudson. The most likely cause appears to be transport into the estuary of particles from offshore waters having higher specific activities of /sup 239/ /sup 240/Pu. Measurements of fallout /sup 239/ /sup 240/Pu in a saline lake with a high carbonate ion concentration yielded water column activities about two orders of magnitude greater than has been found for fallout plutonium in other continental waters, indicating extensive mobility in some natural water environments. Experiments using lake water suggest that carbonate ion may indeed be a critical factor in regulating plutonium solubility and that low molecular weight complexes are primarily responsible for enhanced plutonium solubility.

Simpson, H.J.; Trier, R.M.; Olsen, C.R.

1980-01-01T23:59:59.000Z

155

Regulation of Hydraulic Fracturing in California  

E-Print Network (OSTI)

APRIL 2013 Regulation of Hydraulic Fracturing in California: A WAsteWAteR And WAteR QuAlity Pe | Regulation of Hydraulic Fracturing in California Wheeler Institute for Water Law & Policy Center for Law #12;Regulation of Hydraulic Fracturing in California | 3Berkeley law | wheeler InstItute for water law

Kammen, Daniel M.

156

Water Resources Policy & Economics  

E-Print Network (OSTI)

Water Resources Policy & Economics FOR 4984 Selected Course Topics · Appropriative and riparian water institutions · Incentives for conservation · Water rights for in-stream environmental use · Surface water-groundwater management · Water quality regulations · Water markets · Economic and policy

Buehrer, R. Michael

157

Transuranic radionuclides from resuspension in the environment, a bibliography  

SciTech Connect

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. 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 an 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. This bibliography is a compilation of the references containing studies of plutonium and americium in the environment as a result of resuspension.

Stoker, A.C.; Shinn, J.H.; Noshkin, V.E. [and others

1994-04-01T23:59:59.000Z

158

Transuranic radionuclides dispersed into the aquatic environment, a bibliography  

SciTech Connect

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

159

Laboratory and field studies related to the Hydrology/Radionuclide Migration Project  

SciTech Connect

This annual report describes research conducted in FY 1990 by Los Alamos National Laboratory for the Hydrology/Radionuclide Migration Project. This multi-agency project measures the underground movement of radionuclides related to nuclear testing at the Nevada Test Site. This project continues the long-term experiment at the site of the Cambric nuclear test. Water pumped from a well adjacent to the explosion cavity continues to show decreasing amounts of tritium and Krypton 85 but no Cesium 139. Analyses of drillback debris shows a distinction between refractory and volatile materials in respect to both their location in the test cavity and their leachability with groundwater. We surveyed materials used during nuclear testing to evaluate any post-test hazard; we concluded that most such materials pose a minimal hazard. The Los Alamos drilling program provided an opportunity for us to sample a collapsed zone above the cavity of a test, which was fired 2 years ago. We continue our research in colloid characterization and in detection of low levels of Technetium 99 in Nevada Test Site water. During FY 1990, we drilled a new hole in the Yucca Flat area to study radionuclide migration. This report also describes Los Alamos management and planning activities in support of this project. 20 refs., 2 figs., 14 tabs.

Thompson, J.L. (comp.)

1991-05-01T23:59:59.000Z

160

Pacific Northwest National Laboratory Campus Radionuclide Air Emissions Report for Calendar Year 2013  

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 2013 from PNNL Site sources is 2E-05 mrem (2E-07 mSv) EDE. The dose from fugitive emissions (i.e., unmonitored sources) is 2E-6 mrem (2E-8 mSv) EDE. The dose from radon emissions is 1E-11 mrem (1E-13 mSv) EDE. No nonroutine emissions occurred in 2013. The total radiological dose for 2013 to the MEI from all PNNL Site radionuclide emissions, including fugitive emissions and radon, is 2E-5 mrem (2E-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.

2014-06-01T23:59:59.000Z

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.


161

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

162

NAC 445A Water Controls | Open Energy Information  

Open Energy Info (EERE)

RegulationRegulation: NAC 445A Water ControlsLegal Abstract Regulations for ground water controls and water quality in Nevada. Published NA Year Signed or Took Effect 2014 Legal...

163

The effect of gravel size fraction on the distribution coefficients of selected radionuclides radionuclides  

SciTech Connect

This manuscript addresses the consequences of the common practice of assuming that the gravel fraction of sediments does not participate in sorption reactions and thus sorption quantified by the distribution coefficient (Kd) construct can be estimated from laboratory tests on < 2mm fraction of sediments. As shown within the use of this common assumption can lead to inaccurate estimates of the mobility and sorption capacity of key radionuclides (Tc, U, and Np) at the Hanford Site where gravel dominates the lower Hanford formation and upper Ringold Formation. Batch sorption and column experiments showed that the distribution coefficient measured using only < 2mm fraction were not in agreement with those obtained from the bulk sediments depending on the radionuclide. The least reactive radionuclide, Tc showed the lowest effects from the presence of gravel. However, differences between measured Kds using < 2mm fractions of the sediment and the Kds measured on the bulk sediment were significant for strongly reactive radionuclides such as Np, especially on the sediment with gravel fractions that contained highly reactive sites. Highly reactive sites in the gravel fraction were attributed to the presence of Fe oxides coatings and/or reactive fracture faces on the gravel surfaces. Gravel correction factors that use the sum of the Kd,<2 mm and Kd,>2 mm values to estimate the Kd for the bulk sediment were found to best describe Kds for radionuclides on the bulk sediment. However, more detailed characterization of gravel surfaces should be also conducted to identify those gravels with higher reactive sorbents, if present. Gravel correction factors should be considered to predict precisely the sorption capacity of bulk sediments that contain more than 10% gravel and to estimate the mobility of contaminants in subsurface environments.

Um, Wooyong; Serne, R. Jeffrey; Last, George V.; Glossbrenner, Ellwood T.

2009-06-26T23:59:59.000Z

164

Reducing booster-pump-induced contaminant intrusion in Indian water systems with a self-actuated, back-pressure regulating valve  

E-Print Network (OSTI)

Intermittently-operated water systems struggle to equitably and effectively distribute clean water to customers. One common customer response to intermittency is to supplement the water system's pressure by using a household, ...

Taylor, David Donald James

2014-01-01T23:59:59.000Z

165

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

166

Radionuclide concentrations in white sturgeon from the Columbia River  

SciTech Connect

Although radioactive releases from the US Department of Energy's Hanford Site have been monitored in the environment since the reactors began operating in 1945, recent information regarding historical releases of radionuclides has led to renewed interest in estimating human exposure to radionuclides at Hanford. Knowledge of the fate of radionuclides in some fish species may be important because of the potential for food-chain transfer to humans. White sturgeon (Acipenser transmontanus) were selected for study because they are long-lived, reside year-round in the Hanford Reach, are benthic, and are an important commercial and sport species in the Columbia River. They also have a greater potential for accumulating persistent radionuclides than shorter-lived species with pelagic and/or anadromous life histories. The purpose of our study was to summarize data on historical concentrations of industrial radionuclides in white sturgeon and to collect additional data on current body burdens in the Columbia River.

Dauble, D.D.; Price, K.R.; Poston, T.M.

1992-09-01T23:59:59.000Z

167

Radionuclide concentrations in white sturgeon from the Columbia River  

SciTech Connect

Although radioactive releases from the US Department of Energy`s Hanford Site have been monitored in the environment since the reactors began operating in 1945, recent information regarding historical releases of radionuclides has led to renewed interest in estimating human exposure to radionuclides at Hanford. Knowledge of the fate of radionuclides in some fish species may be important because of the potential for food-chain transfer to humans. White sturgeon (Acipenser transmontanus) were selected for study because they are long-lived, reside year-round in the Hanford Reach, are benthic, and are an important commercial and sport species in the Columbia River. They also have a greater potential for accumulating persistent radionuclides than shorter-lived species with pelagic and/or anadromous life histories. The purpose of our study was to summarize data on historical concentrations of industrial radionuclides in white sturgeon and to collect additional data on current body burdens in the Columbia River.

Dauble, D.D.; Price, K.R.; Poston, T.M.

1992-09-01T23:59:59.000Z

168

Radionuclide Air Emission Report for 2010, LBNL Report number LBNL-470E  

E-Print Network (OSTI)

Radionuclide Air Emission Report for 2010 2010 Average Windat DOE Facilities, Final Report, Eastern Research Group,470E-2010 Radionuclide Air Emission Report for Prepared by:

,

2014-01-01T23:59:59.000Z

169

E-Print Network 3.0 - artificial radionuclides behavior Sample...  

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

-574-6251 Sponsor: United States Environmental Protection Agency Second edition of "Radionuclide Data and Decay... , and health physics. Emission of 333 radionuclides of...

170

Removal and recovery of radionuclides and toxic metals from wastes, soils and materials  

SciTech Connect

A process has been developed at Brookhaven National Laboratory (BNL) for the removal of metals and radionuclides from contaminated materials, soils, and waste sites (Figure 1). In this process, citric acid, a naturally occurring organic complexing agent, is used to extract metals such as Ba, Cd, Cr, Ni, Zn, and radionuclides Co, Sr, Th, and U from solid wastes by formation of water soluble, metal-citrate complexes. Citric acid forms different types of complexes with the transition metals and actinides, and may involve formation of a bidentate, tridentate, binuclear, or polynuclear complex species. The extract containing radionuclide/metal complex is then subjected to microbiological degradation followed by photochemical degradation under aerobic conditions. Several metal citrate complexes are biodegraded and the metals are recovered in a concentrated form with the bacterial biomass. Uranium forms binuclear complex with citric acid and is not biodegraded. The supernatant containing uranium citrate complex is separated and upon exposure to light, undergoes rapid degradation resulting in the formation of an insoluble, stable polymeric form of uranium. Uranium is recovered as a precipitate (uranium trioxide) in a concentrated form for recycling or for appropriate disposal. This treatment process, unlike others which use caustic reagents, does not create additional hazardous wastes for disposal and causes little damage to soil which can then be returned to normal use.

Francis, A.J.

1993-07-01T23:59:59.000Z

171

Waste Form and Indrift Colloids-Associated Radionuclide Concentrations: Abstraction and Summary  

SciTech Connect

This Model Report describes the analysis and abstractions of the colloids process model for the waste form and engineered barrier system components of the total system performance assessment calculations to be performed with the Total System Performance Assessment-License Application model. Included in this report is a description of (1) the types and concentrations of colloids that could be generated in the waste package from degradation of waste forms and the corrosion of the waste package materials, (2) types and concentrations of colloids produced from the steel components of the repository and their potential role in radionuclide transport, and (3) types and concentrations of colloids present in natural waters in the vicinity of Yucca Mountain. Additionally, attachment/detachment characteristics and mechanisms of colloids anticipated in the repository are addressed and discussed. The abstraction of the process model is intended to capture the most important characteristics of radionuclide-colloid behavior for use in predicting the potential impact of colloid-facilitated radionuclide transport on repository performance.

R. Aguilar

2003-06-24T23:59:59.000Z

172

Colloid-Associated Radionuclide Concentration Limits: ANL  

SciTech Connect

The purpose and scope of this report is to describe the analysis of available colloidal data from waste form corrosion tests at Argonne National Laboratory (ANL) to extract characteristics of these colloids that can be used in modeling their contribution to the source term for sparingly soluble radioelements (e.g., Pu). Specifically, the focus is on developing a useful description of the following waste form colloid characteristics: (1) composition, (2) size distribution, and (3) quantification of the rate of waste form colloid generation. The composition and size distribution information are intended to support analysis of the potential transport of the sparingly soluble radionuclides associated with the waste form colloids. The rate of colloid generation is intended to support analysis of the waste form colloid-associated radionuclide concentrations. In addressing the above characteristics, available data are interpreted to address mechanisms controlling colloid formation and stability. This report was developed in accordance with the ''Technical Work Plan for Waste Form Degradation Process Model Report for SR'' (CRWMS M&O 2000). Because the end objective is to support the source term modeling we have organized the conclusions into two categories: (1) data analysis conclusions and (2) recommendations for colloid source term modeling. The second category is included to facilitate use of the conclusions from the data analysis in the abstraction of a colloid source term model. The data analyses and conclusions that are presented in this report are based on small-scale laboratory tests conducted on a limited number of waste glass compositions and spent fuel types.

C. Mertz

2000-12-21T23:59:59.000Z

173

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

174

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

175

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions Calendar Year 2013  

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. Limitations 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 radionuclides concentration by its CL and then adding the fractions together) is less than 1.0. In 2013, 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 0.2% to a maximum of 10.1% 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 0.000011 mrem/yr, more than 900,000 times lower than the 10 mrem/yr limit.

Warren, R.

2014-06-04T23:59:59.000Z

176

Public Health Issues Associated with Small Drinking Water Systems  

E-Print Network (OSTI)

Public Health Issues Associated with Small Drinking Water Systems Not Regulated by the Safe Drinking Water Act From: Nonfederally Regulated Drinking Water Systems: State and Local Public Health ...........................................................................................5 Priority Environmental Public Health Challenges for Small Drinking Water Systems

177

Mobility of Source Zone Heavy Metals and Radionuclides: The Mixed Roles of Fermentative Activity on Fate and Transport of U and Cr. Final Report  

SciTech Connect

Various U. S. Department of Energy (DOE) low and medium-level radioactive waste sites contain mixtures of heavy metals, radionuclides and assorted organic materials. In addition, there are numerous sites around the world that are contaminated with a mixture of organic and inorganic contaminants. In most sites, over time, water infiltrates the wastes, and releases metals, radionuclides and other contaminants causing transport into the surrounding environment. We investigated the role of fermentative microorganisms in such sites that may control metal, radionuclide and organics migration from source zones. The project was initiated based on the following overarching hypothesis: Metals, radionuclides and other contaminants can be mobilized by infiltration of water into waste storage sites. Microbial communities of lignocellulose degrading and fermenting microorganisms present in the subsurface of contaminated DOE sites can significantly impact migration by directly reducing and immobilizing metals and radionuclides while degrading complex organic matter to low molecular weight organic compounds. These low molecular weight organic acids and alcohols can increase metal and radionuclide mobility by chelation (i.e., certain organic acids) or decrease mobility by stimulating respiratory metal reducing microorganisms. We demonstrated that fermentative organisms capable of affecting the fate of Cr6+, U6+ and trinitrotoluene can be isolated from organic-rich low level waste sites as well as from less organic rich subsurface environments. The mechanisms, pathways and extent of contaminant transformation depend on a variety of factors related to the type of organisms present, the aqueous chemistry as well as the geochemistry and mineralogy. This work provides observations and quantitative data across multiple scales that identify and predict the coupled effects of fermentative carbon and electron flow on the transport of radionuclides, heavy metals and organic contaminants in the subsurface; a primary concern of the DOE Environmental Remediation Science Division (ERSD) and Subsurface Geochemical Research (SBR) Program.

Gerlach, Robin [Montana State Univ., Bozeman, MT (United States); Peyton, Brent M. [Montana State Univ., Bozeman, MT (United States); Apel, William A. [Idaho National Lab., Idaho Falls, ID (United States)

2014-01-29T23:59:59.000Z

178

Water Scarcity, Climate Change, and Water Quality: Three Economic Essays  

E-Print Network (OSTI)

essays by implicitly incorporating uncertainty about future climate, water demand from all types of water use, a spatial river flow relationship, interaction between ground and surface water, institutional regulations, and the possibilities of inter-basin...

Cai, Yongxia

2010-07-14T23:59:59.000Z

179

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

SciTech Connect

Bioremediation of metals and radionuclides has had manyfield tests, demonstrations, and full-scale implementations in recentyears. Field research in this area has occurred for many different metalsand radionuclides using a wide array of strategies. These strategies canbe generally characterized in six major categories: biotransformation,bioaccumulation/bisorption, biodegradation of chelators, volatilization,treatment trains, and natural attenuation. For all field applicationsthere are a number of critical biogeochemical issues that most beaddressed for the successful field application. Monitoring andcharacterization parameters that are enabling to bioremediation of metalsand radionuclides are presented here. For each of the strategies a casestudy is presented to demonstrate a field application that uses thisstrategy.

Hazen, Terry C.; Tabak, Henry H.

2007-03-15T23:59:59.000Z

180

Surface Water Quality Standards (Kansas)  

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

This act states regulations for the quality of surface water in the state. It also states designated uses of classified surface waters, surface water quality criteria and an antidegradation policy...

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

Review of technical documents supporting proposed revisions to EPA (Environmental Protection Agency) regulations for the disposal/reuse of sewage sludge under Section 405(D) of the Clean Water Act. Final report  

SciTech Connect

In August 1985 the Environmental Engineering Committee of the Science Advisory Board was asked by the Office of Water Regulations and Standards (OWRS) to review technical documents supporting development of EPA regulations for the disposal/reuse of sewage sludge under Section 405(d) of the Clean Water Act. The Committee was also asked by the Office of Marine and Estuarine Protection (OMEP) to review technical documents supporting revisions of the EPA ocean dumping regulations. The Committee chose to review the two sets of documents together, since they both dealt with a common subject, and since they shared, in some respects, a common methodology. The report, however, covers only the review of the OWRS documents, which consist of a set of risk-assessment methodologies (1,2,3,4) for four sludge disposal/reuse options (landfilling, land application/distribution and marketing, incineration, and ocean disposal). The reviews of the OMEP documents are covered in separate Committee reports. The Committee's principal findings are outlined.

Not Available

1987-01-01T23:59:59.000Z

182

Regulate, Baby, Regulate  

Science Journals Connector (OSTI)

The gas and water mixture presumably bubbled-up from a deep aquifer due to hydraulic fracturing when fracking fluids were pumped at great pressures to shatter shale and freely connect tight pore spaces, thus releasing gas and water. ... Like the Corexit 9500 dispersant used in the Gulf, even the EPA does not know what proprietary chemicals are contained in fracking fluids. ... In all these situations, the worst case scenario of massive aquifer contamination by broken well casings during or after gas production is never really evaluated, and like the Deepwater Horizon, a response plan doesnt exist. ...

Jerald L. Schnoor

2010-08-03T23:59:59.000Z

183

Gas: A Neglected Phase in Remediation of Metals and Radionuclides  

SciTech Connect

The gas phase is generally ignored in remediation of metals and radionuclides because it is assumed that there is no efficient way to exploit it. In the literal sense, all remediations involve the gas phase because this phase is linked to the liquid and solid phases by vapor pressure and thermodynamic relationships. Remediation methods that specifically use the gas phase as a central feature have primarily targeted volatile organic contaminants, not metals and radionuclides. Unlike many organic contaminants, the vapor pressure and Henry's Law constants of metals and radionuclides are not generally conducive to direct air stripping of dissolved contaminants. Nevertheless, the gas phase can play an important role in remediation of inorganic contaminants and provide opportunities for efficient, cost effective remediation. The objective here is to explore ways in which manipulation of the gas phase can be used to facilitate remediation of metals and radionuclides.

Denham, Miles E.; Looney, Brian B

2005-09-28T23:59:59.000Z

184

Radionuclide distributions and migration mechanisms at shallow land burial sites  

SciTech Connect

During the past several years, Pacific Northwest Laboratory (PNL) has conducted research at the Maxey Flats Disposal Site (MFDS) for the US Nuclear Regulatory Commission (NRC). This work has identified the spectrum of radionuclides present in the waste trenches, determined the processes that were occurring relative to degradation of radioactive material within the burial trenches, determined the chemical and physical characteristics of the trench leachates and the chemical forms of the leached radionuclides, determined the mobility of these radionuclides, investigated the subsurface and surface transport processes, determined the biological uptake by the native vegetation, developed strategies for environmental monitoring, and investigated other factors that influence the long-term fate of the radionuclide inventory at the disposal site. This report is a final summary of the research conducted by PNL and presents the results and discussions relative to the above investigative areas. 45 refs., 31 figs., 17 tabs.

Kirby, L.J.; Toste, A.P.; Thomas, C.W.; Rickard, W.H.; Nielson, H.L.; Campbell, R.M.; McShane, M.C.; Wilkerson, C.L.; Robertson, D.E.

1991-02-01T23:59:59.000Z

185

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

186

Technical Assessment of DOE Savannah River Site-Sponsored Radionuclide...  

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

sampled by DOE-SR and SCDHEC each year to allow for direct comparison and validation of radionuclide data. We suggest that future Annual Reports for the SRS Environmental...

187

Radionuclide Sensors and Systems for Environmental Monitoring...  

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

and detection units that are fluidically linked. We have demonstrated detection of strontium-90 to levels below drinking water standards by this approach. We are developing...

188

6 - Nuclear Waste Regulations  

Science Journals Connector (OSTI)

The most influential national and international bodies providing recommendations on radiation protection are described, including the International Commission on Radiological Protection (ICRP) and the International Atomic Energy Agency (IAEA). Protection philosophies and the ICRP general principles of radiation protection are discussed. Radioactive material regulations and sources of radiation are explained. Criteria of exemption from regulatory control are discussed with examples of exemption levels for naturally occurring and radioactive waste radionuclides. Clearance of both moderate and bulk amounts of materials from regulatory control is also explained, including examples of EU and the UK regulations. Dose limits recommended by the ICRP are given, as well as the main principles of control of radiation hazards. Nuclear waste classification schemes are outlined, including the IAEA classification scheme. A brief explanation of nuclear waste classes including exempt waste, very short-lived waste, very low-level waste, low-level waste, intermediate-level waste and high-level waste is given. Examples of waste classification schemes are given, including that of the UK.

M.I. Ojovan; W.E. Lee

2014-01-01T23:59:59.000Z

189

Reconstruction of Long-Lived Radionuclide Intakes for Techa Riverside Residents: Cesium-137  

SciTech Connect

Radioactive contamination of the Techa River (Southern Urals, Russia) occurred from 19491956 due to routine and accidental releases of liquid radioactive wastes from the Mayak Production Association. The long-lived radionuclides in the releases were 90Sr and 137Cs. Contamination of the components of the Techa River system resulted in chronic external and internal exposure of about 30,000 residents of riverside villages. Data on radionuclide intake with diet are used to estimate internal dose in the Techa River Dosimetry System (TRDS), which was elaborated for the assessment of radiogenic risk for Techa Riverside residents. The 90Sri ntake function was recently improved taking into account the recently available archival data on radionuclide releases and in-depth analysis of the extensive data on 90Sr measurements in Techa Riverside residents. The main purpose of this paper is to evaluate the dietary intake of 137Cs by Techa Riverside residents. The 137Cs intake with river water used for drinking was reconstructed on the basis of the 90Sr intake-function and the concentration ratio 137Cs/90Sr in river water. Intake via 137Cs transfer from floodplain soil to grass and cows milk was evaluated for the first time. As a result, the maximal 137Cs intake level was indicated near the site of releases in upper-Techa River settlements (8,0009,000 kBq). For villages located on the lower Techa River the 137Cs intake was significantly less (down to 300 kBq). Cows milk was the main source of 137Cs in diet in the upper-Techa.

Tolstykh, E. I.; Degteva, M. O.; Peremyslova, L. M.; Shagina, N. B.; Vorobiova, M. I.; Anspaugh, L. R.; Napier, Bruce A.

2013-05-01T23:59:59.000Z

190

Screening Risk Assessment for Possible Radionuclides in the Amchitka Marine Environment  

SciTech Connect

As part of its environmental stewardship program the U.S. Department of Energy (DOE) is reevaluating three sites where underground nuclear tests were conducted in the deep subsurface of Amchitka Island, Alaska. The tests (i.e., Long Shot, Milrow, and Cannikin) were conducted in 1965, 1969, and 1971, respectively. Extensive investigations were conducted on these tests and their effect on the environment. Evaluations at the time of testing indicated limited release of radionuclides and absence of risk related to the testing; however, these are being reevaluated under the current DOE environmental stewardship program. A screening risk assessment of potential radionuclide release into the marine environment is an important part of this reevaluation. The risk assessment is one of three interrelated activities: a groundwater model and this screening risk assessment, both of which guide the decisions in the third activity, the site closure plan. Thus, the overall objective of the work is to understand, and subsequently manage, any risk to humans and the environment through a closure and long-term stewardship plan. The objective of this screening risk assessment is to predict whether possible releases of radionuclides at the ocean floor would represent potential risks to Native Alaskans by consumption of marine subsistence species. In addition, risks were predicted for consumers of commercial catches of marine organisms. These risks were calculated beginning with estimates of possible radionuclide release at the seafloor (from a groundwater modeling study), into the seawater, through possible uptake by marine organisms, and finally possible consumption by humans. The risk assessment model has 11 elements, progressing from potential release at the seafloor through water and food chains to human intake. Data for each of these elements were systematically found and synthesized from many sources, and represent the best available knowledge. Whenever precise data were lacking, the most conservative data were selected. Conservative assumptions and values were used for radionuclide uptake factors and for marine food ingestion rates by human receptors. The dispersion of material in the marine environment utilized a U.S. Environmental Protection Agency (EPA)-approved model (CORMIX). In addition, the screening level of 1 x 10{sup -6} or 1 excess cancer in 1 million is considered by the EPA to be below the level of concern. The end result, as presented in this report, is a highly conservative estimate of potential risks that are well below the EPA's most conservative risk threshold for both subsistence users and commercial-catch consumers.

NNSA /NV

2002-10-31T23:59:59.000Z

191

Environmental impact assessment of radionuclides and trace elements at the Kurday U mining site, Kazakhstan  

Science Journals Connector (OSTI)

The Kurday uranium mining site in Kazakhstan operated from 1954 to 1965 as part of the USSR nuclear weapon programme. To assess the environmental impact of radionuclides and trace elements associated with the Kurday mining site, field expeditions were performed in 2006. In addition to in situ gamma and 220Rn dose rate measurements, sampling included at site fractionation of water as well as sampling of water, fish, sediment, soils and vegetation. The concentrations of U and associated trace metals were enriched in the Pit Lake and in the artesian water (U exceeding the WHO guideline value for drinking water), and decreased downstream from the mining area. Uranium, As, Mo and Ni were predominantly present as mobile low molecular mass species in waters, while a significant proportion of Cr, Mn and Fe were associated with colloids and particles. Due to oxidation of divalent iron in the artesian ground water upon contact with air, Fe served as scavenger for other elements, and peak concentrations of U-, Ra-isotopes, As and Mn were seen. Most radionuclides and trace elements were contained in minerals in soils and sediments, and good correlations were obtained between U and As, Cd, Mo and 226Ra. Based on sequential extractions, a significant fraction of U, Pb and Cd could be considered mobile. Radioactive particles carrying significant amount of trace metals may represent a hazard during strong wind events. The transfer of radionuclides and metals from soils or sediments to water was in general low. The Kd levels varied with the element in question, ranging from 0.5 to 3נ102L/kg d.w. for 238U being relatively mobile, 103 for 226Ra, As, Cd, Ni, to 104L/kg d.w. for Cu, Cr and Pb being rather inert The transfer of radionuclides and metals from soils to vegetation (TF) was low, while higher if the transfer to vegetation, especially underwater mosses, occurred via water (e.g., BCF 37L/kg w.w. for 238U and 3נ103L/kg w.w. for 226Ra). The transfer of Cd, Pb and As from water to fish liver (BCF) was rather high, showing \\{BCFs\\} in the range of 102103L/kg w.w., and may, if eaten, represent a health risk. Furthermore, the high Hg level in fish filet reaching 0.3mg/kg w.w. muscle and the tendency of biomagnification call for dietary restrictions. Total gamma and Rn dose rate to man amounted to about 6mSv/y, while the highest calculated dose rate for non-human species based on the ERICA Assessment Tool were obtained in aquatic plants, with calculated mean doses of 700 ?Gy/hr, mostly due to the U exposure. Overall, it is concluded that measures such as restricted access to the Pit Lake as well as dietary restrictions with respect to drinking water and intake of fish should be taken to reduce the environmental risk to man and biota.

B. Salbu; M. Burkitbaev; G. Strmman; I. Shishkov; P. Kayukov; B. Uralbekov; B.O. Rosseland

2013-01-01T23:59:59.000Z

192

Temporary Waters  

Science Journals Connector (OSTI)

Temporary waters are lakes, ponds, streams, seeps, microhabitats, and other areas that hold water periodically and then dry. They occur across the globe, at all latitudes, and in all biomes, wherever water can collect long enough for aquatic life to develop. These waters are numerous, mostly small, and easily studied. Their biological communities are diverse, have much among-site variation, often include endemic species, and differ from those in permanent waters, contributing to regional biodiversity. Organisms survive through species-specific behavioral, physiological, and life-history adaptations. Community composition and structure change in response to environmental variations. Temporary waters are highly productive and their food webs are relatively simple. For all of these reasons, temporary waters lend themselves to surveys and experimental manipulations designed to test hypotheses about biological adaptation, population regulation, evolutionary processes, community composition and structure, and ecosystem functioning. In many parts of the world, most temporary waters have been lost. The conservation and restoration of vulnerable temporary waters is a major thrust of applied ecology. Also important are applications of ecological understanding to the control of disease vectors, especially pathogen-transmitting mosquitoes, from temporary water habitats. This article describes temporary waters, examines their biota and adaptations, and summarizes key questions about their ecology.

E.A. Colburn

2008-01-01T23:59:59.000Z

193

Modeling the Hydrogeochemical Transport of Radionuclides through Engineered Barriers System in the Proposed LLW Disposal Site of Taiwan - 12082  

SciTech Connect

A proposed site for final disposal of low-level radioactive waste located in Daren Township of Taitung County along the southeastern coast has been on the selected list in Taiwan. The geology of the Daren site consists of argillite and meta-sedimentary rocks. A mined cavern design with a tunnel system of 500 m below the surface is proposed. Concrete is used as the main confinement material for the engineered barrier. To investigate the hydrogeochemical transport of radionuclides through engineered barriers system, HYDROGEOCHEM5.0 model was applied to simulate the complex chemical interactions among radionuclides, the cement minerals of the concrete, groundwater flow, and transport in the proposed site. The simulation results showed that the engineered barriers system with the side ditch efficiently drained the ground water and lowered the concentration of the concrete degradation induced species (e.g., hydrogen ion, sulfate, and chloride). The velocity of groundwater observed at side ditch gradually decreased with time due to the fouling of pore space by the mineral formation of ettringite and thaumasite. The short half-life of Co-60, Sr-90 and Cs-137 significantly reduced the concentrations, whereas the long half-life of I-129(1.57x10{sup 7} years) and Am-241(432 years) remain stable concentrations at the interface of waste canister and concrete barrier after 300 years. The mineral saturation index (SI) was much less than zero due to the low aqueous concentration of radionuclide, so that the precipitation formation of Co-60, Sr-90, I-129, Cs-137 and Am-241 related minerals were not found. The effect of adsorption/desorption (i.e., surface complexation model) could be a crucial geochemical mechanism for the modeling of liquid-solid phase behavior of radionuclide in geochemically dynamic environments. Moreover, the development of advanced numerical models that are coupled with hydrogeochemical transport and dose assessment of radionuclide is required in the future. (authors)

Lin, Wen-Sheng [Hydrotech Research Institute, National Taiwan University, Taipei, Taiwan (China); Liu, Chen-Wuing; Tsao, Jui-Hsuan [Department of Bioenvironmental Systems Engineering, National Taiwan University, Taipei, Taiwan (China); Li, Ming-Hsu [Institute of Hydrological and Oceanic Sciences, National Central University, Jhongli, Taiwan (China)

2012-07-01T23:59:59.000Z

194

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.

195

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.

196

Safe new reactor for radionuclide production  

SciTech Connect

In late 1995, DOE is schedule to announce a new tritium production unit. Near the end of the last NPR (New Production Reactors) program, work was directed towards eliminating risks in current designs and reducing effects of accidents. In the Heavy Water Reactor Program at Savannah River, the coolant was changed from heavy to light water. An alternative, passively safe concept uses a heavy-water-filled, zircaloy reactor calandria near the bottom of a swimming pool; the calandria is supported on a light-water-coolant inlet plenum and has upflow through assemblies in the calandria tubes. The reactor concept eliminates or reduces significantly most design basis and severe accidents that plague other deigns. The proven, current SRS tritium cycle remains intact; production within the US of medical isotopes such as Mo-99 would also be possible.

Gray, P.L.

1995-02-15T23:59:59.000Z

197

Determination of operating limits for radionuclides for a proposed landfill at Paducah Gaseous Diffusion Plant  

SciTech Connect

The operating limits for radionuclides in sanitary and industrial wastes were determined for a proposed landfill at the Paducah Gaseous Diffusion Plant (PGDP), Kentucky. These limits, which may be very small but nonzero, are not mandated by law or regulation but are needed for rational operation. The approach was based on analyses of the potential contamination of groundwater at the plant boundary and the potential exposure to radioactivity of an intruder at the landfill after closure. The groundwater analysis includes (1) a source model describing the disposal of waste and the release of radionuclides from waste to the groundwater, (2) site-specific groundwater flow and contaminant transport calculations, and (3) calculations of operating limits from the dose limit and conversion factors. The intruder analysis includes pathways through ingestion of contaminated vegetables and soil, external exposure to contaminated soil, and inhalation of suspended activity from contaminated soil particles. In both analyses, a limit on annual effective dose equivalent of 4 mrem (0.04 mSv) was adopted. The intended application of the results is to refine the radiological monitoring standards employed by the PGDP Health Physics personnel to determine what constitutes radioactive wastes, with concurrence of the Commonwealth of Kentucky.

Wang, J.C.; Lee, D.W.; Ketelle, R.H.; Lee, R.R.; Kocher, D.C.

1994-05-24T23:59:59.000Z

198

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

SciTech Connect

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

199

Water, Power, and Development in Twenty-First Century China: The Case of the South-North Water Transfer Project  

E-Print Network (OSTI)

over basic water management and environmental concerns.to environmental regulation and water pollution managementfiguring into water management is the parallel environmental

Crow-Miller, Brittany Leigh

2013-01-01T23:59:59.000Z

200

Water, Power, and Development in Twenty-First Century China: The Case of the South-North Water Transfer Project  

E-Print Network (OSTI)

to environmental regulation and water pollution managementover basic water management and environmental concerns.figuring into water management is the parallel environmental

Crow-Miller, Brittany Leigh

2013-01-01T23:59:59.000Z

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.


201

Studies on unsaturated zone hydrology and radionuclide migration at a shallow-land burial site  

SciTech Connect

We studied unsaturated zone hydrology and the migration of radionuclides at a shallow-land burial site located at Maxey Flats, Kentucky. The initial results indicate that the principal pathway of water entry into the trench was by percolation through the trench caps. Tritium-bearing water was found to be moving upward from a saturated waste-burial trench through the trench cap to the soil surface. Evidence of tritium movement at a depth of 3 to 4 meters was observed to a distance of about 5 meters laterally. No /sup 137/Cs migration was observed, but very small amounts of /sup 238/Pu and /sup 60/Co were found to have migrated short distances from the trench.

Schulz, R.K. (Univ. of California, Berkeley); Fowler, E.B.; Essington, E.H.; Polzer, W.L.

1981-07-01T23:59:59.000Z

202

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.

203

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

204

Radionuclide distributions and migration mechanisms at shallow land burial sites. Annual report of research investigations on the distribution, migration and containment of radionuclides at Maxey Flats, Kentucky. [Maxey Flats  

SciTech Connect

Subsurface waters at Maxey Flats are anoxic systems with high alkalinity and high concentrations of dissolved ferrous ion. Americium and cobalt in these trench waters are made more soluble by the presence of EDTA, while strontium and cesium are unaffected under the same conditions. EDTA is the major organic complexing component in waste trench 27 leachate, but other polar, water-soluble organics are also present. Evidence points to the migration of plutonium between waste trench 27 and inert atmosphere wells as an EDTA complex. Polar organic compounds may influence the migration of /sup 90/Sr and /sup 137/Cs. The primary pathway of water entry into the waste burial trenches is through the trench caps, but major increases in water level have occurred in an experimental trench by subsurface flow. The areal distribution of radionuclides at Maxey Flats has been influenced by surface runoff, deposition from the evaporator plume, subsurface flow and the actions of burrowing animals or deep-rooted trees. Vegetal and surface contamination on site and near site are quite low, and only /sup 60/Co exceeds commonly observed fallout levels. Radionuclide concentrations in surface soil at Maxey Flats are comparable to concentrations resulting from normal fallout in other areas of high rainfall.

Kirby, L.J. (ed.)

1982-07-01T23:59:59.000Z

205

Radionuclide transport from yucca Mountain and Inter-basin Flow in Death Valley  

SciTech Connect

Hydrodynamics and the U.S. Geological survey conducted studies to evaluate far-field issues related to potential transport, by ground water, of radionuclide into Inyo County from Yucca Mountain, including Death Valley, and the evaluation of a connection between the Lower Carbonate Aquifer (LCA) and the biosphere. Our oversight and completed Cooperative Agreement research, and a number of other investigators research indicate that there is groundwater flow between the alluvial and carbonate aquifers both at Yucca Mountain and in Inyo County. The specific purpose of our research was to acquire geological, subsurface geology, and hydrologic data to: 1. Establish the existence of inter-basin flow between the Amargosa Basin and Death Valley Basin, 2. Characterize groundwater flow paths in the LCA through Southern Funeral Mountain Range, and 3. Evaluate the hydraulic connection between the Yucca Mountain repository and the major springs in Death Valley through the LCA. 4. Evaluate the hydraulic connection between the Yucca Mountain repository and Franklin Lake Playa. The hydraulic characterization of the LCA is of critical interest to Inyo County and the U.S. Department of Energy because: 1. The upward gradient in the LCA at Yucca Mountain provides a natural barrier to radionuclide transport, 2. The LCA is a necessary habitat resource for the endangered Devil's Hole pup fish, and 3. The LCA is the primary water supply and source of water to the major springs in Death Valley National Park. This paper presents the results of our study program to evaluate if inter-basin flow exists between the Amargosa and Death Valley Basins through the LCA. The study presents the results of our structural geology analysis of the Southern Funeral Mountain range, geochemical source analysis of spring waters in the region, and a numerical groundwater model to simulate inter-basin flow in the Southern Funeral Mountain range. (authors)

Bredehoeft, J. [The Hydrodynamics Group (United States); Fridrich, C. [U.S. Geological Survey-Denver (United States); King, C.HG.M. [The Hydrodynamics Group, LLC (United States)

2007-07-01T23:59:59.000Z

206

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

207

Marine Sciences Laboratory Radionuclide Air Emissions Report for Calendar Year 2013  

SciTech Connect

The U.S. Department of Energy Office of Science (DOE-SC) Pacific Northwest Site Office (PNSO) has oversight and stewardship duties associated with the Pacific Northwest National Laboratory (PNNL) Marine Sciences Laboratory (MSL) located on Battelle Land Sequim (Sequim). 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 Washington Administrative Code (WAC) Chapter 246-247, Radiation ProtectionAir Emissions. The EDE to the Sequim MEI due to routine operations in 2013 was 5E-05 mrem (5E-07 mSv). No non-routine emissions occurred in 2013. The MSL is in compliance with the federal and state 10 mrem/yr standard.

Snyder, Sandra F.; Barnett, J. M.; Ballinger, Marcel Y.

2014-05-01T23:59:59.000Z

208

Hadley cell influence on 7Be activity concentrations at Australian mainland IMS radionuclide particulate stations  

Science Journals Connector (OSTI)

Abstract Beryllium-7 (7Be) daily data from the four International Monitoring System (IMS) radionuclide particulate stations on mainland Australia are analysed over the period 2001 to 2011. The analysis indicates that levels of 7Be in surface air at the stations follow annual cycles, with yearly peak activity concentrations occurring later at stations further south. The yearly peak migrates northsouth at a rate of approximately 4.4 latitude per month. The change in phase of the 7Be annual cycle between the stations corresponds with the seasonal migration of the Southern Hemisphere Hadley cell across mainland Australia. The implication is that the changing position of the downward limb of the Southern Hemisphere Hadley cell regulates the phase of the annual cycle in 7Be activity concentrations in surface air in the Australian region.

Che Doering; Paul Saey

2014-01-01T23:59:59.000Z

209

ARM 17-30 - Water Quality | Open Energy Information  

Open Energy Info (EERE)

0 - Water Quality Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: ARM 17-30 - Water QualityLegal Abstract Water quality...

210

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

211

Chernobyl nuclear accident hydrologic analysis and emergency evaluation of radionuclide distributions in the Dnieper River, Ukraine, during the 1993 summer flood  

SciTech Connect

This report describes joint activities of Program 7.1.F, ``Radionuclide Transport in Water and Soil Systems,`` of the USA/Commonwealth of Independent States (CIS) Joint Coordinating Committee of Civilian Nuclear Reactor Safety to study the hydrogeochemical behavior of radionuclides released to the Pripyat and Dnieper rivers from the Chernobyl Nuclear Power Plant in Ukraine. These joint activities included rapid evaluation of radionuclide distributions in the Pripyat and Dnieper river system and field data evaluation and modeling for the 1993 summer flood to assist the Ukrainian government in their emergency response during the flood. In July-August 1993, heavy rainfall over the Pripyat River Catchment in Belarus and Ukraine caused severe flooding, significantly raising {sup 90}Sr concentrations in the river. Near the Chernobyl area, the maximum {sup 90}Sr concentration in the Pripyat River reached 20--25 PCi/L in early August; near the Pripyat River mouth, the concentration rose to 35 pCi/L. The peak {sup 90}Sr concentration in the Kiev Reservoir (a major source of drinking water for Kiev) was 12 pCi/L. Based on these measured radionuclide levels, additional modeling results and the assumption of water purification in a water treatment station, {sup 90}Sr concentrations in Kiev`s drinking water were estimated to be less than 8 pCi/L. Unlike {sup 90}Sr, {sup 137}Cs concentrations in the Pripyat River during the flood did not rise significantly to the pre-flood levels. Estimated {sup 137}Cs concentrations for the Kiev drinking water were two orders of magnitude lower than the drinking water standard of 500 pCi/L for {sup 137}Cs.

Voitsekhovitch, O.V. [Ukrainian Hydrometeorological Inst., Kiev (Ukraine); Zheleznyak, M.J. [Ukrainian Academy of Sciences, Kiev (Ukraine). Cybernetics Center; Onishi, Y. [Pacific Northwest Lab., Richland, WA (United States)

1994-06-01T23:59:59.000Z

212

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

213

RADIONUCLIDE DISPERSION RATES BY AEOLIAN, FLUVIAL, AND POROUS MEDIA TRANSPORT  

SciTech Connect

Radionuclide transport was measured from high grade uranium ore boulders near the Nopal I Site, Chihuahua, Mexico. High grade uranium ore boulders were left behind after removal of a uranium ore stockpile at the Prior High Grade Stockpile (PHGS). During the 25 years when the boulder was present, radionuclides were released and transported by sheetflow during precipitation events, wind blown resuspension, and infiltration into the unsaturated zone. In this study, one of the boulders was removed, followed by grid sampling of the surrounding area. Measured gamma radiation levels in three dimensions were used to derive separate dispersion rates by the three transport mechanisms.

J. Walton; P. Goodell; C. Brashears; D. French; A. Kelts

2005-07-11T23:59:59.000Z

214

Nopal I uranium deposit: A study of radionuclide migration  

SciTech Connect

This summary reports on activities of naturally-occurring radionuclides for the Nopal I uranium deposit located in the Pena Blanca Uranium District, Chihuahua, Mexico. Activities were determined using gamma-ray spectroscopy. In addition, data reduction procedures and sample preparation (for Rn retention) will be discussed here. Nopal I uranium deposit has been identified as one of the most promising sites for analogue studies to the proposed high-level nuclear waste repository at Yucca Mountain, Nevada. The objective of this research is to study the potential for radionuclide migration by testing whether any portion of the deposit is in secular equilibrium.

Wong, V.; Anthony, E.; Goodell, P. [Univ. of Texas, El Paso, TX (United States)

1996-12-01T23:59:59.000Z

215

Radionuclide migration laboratory studies for validation of batch sorption data  

SciTech Connect

Advective and diffusive migration experiments (within the Dynamic Transport Column Experiments and Diffusion Studies of the Yucca Mountain Site Characterization Project) involve utilizing crushed material, intact, and fractured tuff in order to test and improve (if necessary) transport models by experimentally observing the migration of sorbing and non-sorbing radionuclides on a laboratory scale. Performing a validation of the sorption data obtained with batch techniques (within the Batch Sorption Study) is an integral part of the mission of the Dynamic Transport Column Experiments and Diffusion Studies. In this paper the work scope of the radionuclide migration laboratory experiments (as they apply to validation of batch sorption data) is reviewed.

Triay, I.R.; Mitchell, A.J.; Ott, M.A.

1991-12-31T23:59:59.000Z

216

Application of inorganic-contaminated groundwater to surface soils and compliance with toxicity characteristic (TCLP) regulations  

SciTech Connect

The Westinghouse Savannah River Company (WSRC) is currently implementing a Purged Water Management Program (PWMP) at the Savannah River Site (SRS) near Aiken, South Carolina. A variety of constituents and disposal strategies are being considered. Constituents investigated in the PWMP include radionuclides, organics, and inorganics (As, Ba, Cd, Cr, Pb, Hg, Se, and Ag). One practical disposal alternative is to discharge purged water (all constituents below regulatory levels) to the ground surface near the monitoring well that is being purged. The purpose of this investigation is to determine if long-term application of purged water that contains inorganic constituents (below regulatory levels) to surface soils will result in the accumulation of inorganics such that the soil becomes a hazardous waste according to the Toxicity Characteristic regulations (40 CFR Part 261.24). Two study soils were selected that encompass the range of soils found at the SRS: Lakeland and Orangeburg. Laboratory batch equilibrium studies indicate that the soils, although able to retain a large amount of inorganics, will not exceed Toxicity Characteristic concentrations when subjected to the TCLP. Field studies are underway to confirm this.

Bergren, C.L.; Flora, M.A. [Westinghouse Savannah River Co., Aiken, SC (United States); Jackson, J.L.; Hicks, E.M. [Sirrine Environmental Consultants, Greenville, SC (United States)

1991-12-31T23:59:59.000Z

217

Application of inorganic-contaminated groundwater to surface soils and compliance with toxicity characteristic (TCLP) regulations  

SciTech Connect

The Westinghouse Savannah River Company (WSRC) is currently implementing a Purged Water Management Program (PWMP) at the Savannah River Site (SRS) near Aiken, South Carolina. A variety of constituents and disposal strategies are being considered. Constituents investigated in the PWMP include radionuclides, organics, and inorganics (As, Ba, Cd, Cr, Pb, Hg, Se, and Ag). One practical disposal alternative is to discharge purged water (all constituents below regulatory levels) to the ground surface near the monitoring well that is being purged. The purpose of this investigation is to determine if long-term application of purged water that contains inorganic constituents (below regulatory levels) to surface soils will result in the accumulation of inorganics such that the soil becomes a hazardous waste according to the Toxicity Characteristic regulations (40 CFR Part 261.24). Two study soils were selected that encompass the range of soils found at the SRS: Lakeland and Orangeburg. Laboratory batch equilibrium studies indicate that the soils, although able to retain a large amount of inorganics, will not exceed Toxicity Characteristic concentrations when subjected to the TCLP. Field studies are underway to confirm this.

Bergren, C.L.; Flora, M.A. (Westinghouse Savannah River Co., Aiken, SC (United States)); Jackson, J.L.; Hicks, E.M. (Sirrine Environmental Consultants, Greenville, SC (United States))

1991-01-01T23:59:59.000Z

218

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

219

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

220

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;

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

Radiation Dose Estimation from the Analysis of Radionuclides in Marine Fish of the Bay of Bengal  

Science Journals Connector (OSTI)

...Radiation Protection Dosimetry Article Radiation Dose Estimation from the Analysis of Radionuclides in Marine Fish of the Bay of Bengal S. Ghose M.N. Alam M.N...respectively. The annual effective doses due to ingestion of radionuclides......

S. Ghose; M.N. Alam; M.N. Islam

2000-02-01T23:59:59.000Z

222

Louisiana Water Control Law (Louisiana)  

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

The Louisiana Department of Environmental Quality administers the proper protection and maintenance of the state's waters, and regulate the discharges of waste materials, pollutants, and other...

223

Water Quality Standards Implementation (Oklahoma)  

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

The Oklahoma Department of Environmental Quality regulates Oklahoma's Water Quality Standards. The law states the requirements and standards for point source discharges. It also establishes...

224

Transfer of radionuclides to animals: An historical perspective of work done in the United States  

SciTech Connect

This document describes historical aspects of the use of radionuclides in animals, particularly in the United States. (TEM)

Richmond, C.R.

1988-01-01T23:59:59.000Z

225

Measurement of 222RN concentration in drinking water in Sakarya, Turkey  

Science Journals Connector (OSTI)

......they are still below the World Health Organization recommended level...The radionuclides, which can be dangerous to human health because of their presence in the...drinking water represents a potential health risk due to human exposure through......

Hakan Yakut; Emre Tabar; Zemine Zenginerler; Nilufer Demirci; Filiz Ertugral

2013-12-01T23:59:59.000Z

226

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, Arokiasamy J. (Middle Island, NY); Dodge, Cleveland J. (Wading River, NY)

1994-01-01T23:59:59.000Z

227

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

228

Biologically mediated reductive dissolution and precipitation of metals and radionuclides  

E-Print Network (OSTI)

on transport of trace levels of uranium under natural condi- tions, as well as the effectiveness of uranium remedial strategy). Keywords: reactive transport, heterogeneity, modeling, groundwater, uranium. BACKGROUND) and radionuclides (e.g., uranium, strontium, cesium, technetium, and plutonium). These elements are long

Roden, Eric E.

229

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.

230

Microsoft PowerPoint - epa_clean_water_act.ppt  

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

for 2000 list by regulation 1992 Regulations (cont) Methodology used to develop list States use "all existing and readily available water quality-related information"...

231

Title 18 Alaska Administrative Code Chapter 70 Water Quality...  

Open Energy Info (EERE)

Document- RegulationRegulation: Title 18 Alaska Administrative Code Chapter 70 Water Quality StandardsLegal Published NA Year Signed or Took Effect 1997 Legal Citation Alaska...

232

Title 11 Alaska Administrative Code Chapter 93 Water Management...  

Open Energy Info (EERE)

Code Chapter 93 Water Management Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: Title 11 Alaska Administrative Code...

233

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...

234

Water Quality Control (Texas)  

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

The policy of the state of Texas is to promote the quality of the state's water by regulating existing industries, taking into consideration the economic development of the state, and by...

235

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

236

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.

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

2012-11-06T23:59:59.000Z

237

Revised ground-water monitoring compliance plan for the 300 area process trenches  

SciTech Connect

This document contains ground-water monitoring plans for process-water disposal trenches located on the Hanford Site. These trenches, designated the 300 Area Process Trenches, have been used since 1973 for disposal of water that contains small quantities of both chemicals and radionuclides. The ground-water monitoring plans contained herein represent revision and expansion of an effort initiated in June 1985. At that time, a facility-specific monitoring program was implemented at the 300 Area Process Trenches as part of a regulatory compliance effort for hazardous chemicals being conducted on the Hanford Site. This monitoring program was based on the ground-water monitoring requirements for interim-status facilities, which are those facilities that do not yet have final permits, but are authorized to continue interim operations while engaged in the permitting process. The applicable monitoring requirements are described in the Resource Conservation and Recovery Act (RCRA), 40 CFR 265.90 of the federal regulations, and in WAC 173-303-400 of Washington State's regulations (Washington State Department of Ecology 1986). The program implemented for the process trenches was designed to be an alternate program, which is required instead of the standard detection program when a facility is known or suspected to have contaminated the ground water in the uppermost aquifer. The plans for the program, contained in a document prepared by the US Department of Energy (USDOE) in 1985, called for monthly sampling of 14 of the 37 existing monitoring wells at the 300 Area plus the installation and sampling of 2 new wells. 27 refs., 25 figs., 15 tabs.

Schalla, R.; Aaberg, R.L.; Bates, D.J.; Carlile, J.V.M.; Freshley, M.D.; Liikala, T.L.; Mitchell, P.J.; Olsen, K.B.; Rieger, J.T.

1988-09-01T23:59:59.000Z

238

Conceptual Approach For Estimating Potential Air Toxics And Radionuclide Airborne Emissions From A Temporary Exhaust System For The 216-Z-9 Crib Removal Action  

SciTech Connect

The 216-Z-9 Crib, located at the Hanford Nuclear Reservation in southeastern Washington State, was the site of a successful mining effort to recover plutonium from the contaminated soils at the disposal site. A CERCLA Action Memorandum (AM) issued by the U.S. Department of Energy (DOE) requires the removal of the buildings associated with this mining effort to facilitate a remedial action planned for the near future. The decontamination and demolition of the 216 Z-9 Crib facilities is required under a consent order between the DOE, the U.S Environmental Protection Agency (EPA) and the Washington State Department of Ecology (Ecology). Removal of the buildings located on and near the concrete cover slab over the 216-Z-9 Crib will require removal of the large soil-packaging glovebox located inside the 216-Z- 9A Building. Prior to cleaning out the glovebox, it will be necessary to provide active filtered ventilation capability to ensure a negative pressure exists between the glovebox and the adjacent airspace while hands-on work proceeds within. The glovebox floor is open to the Z-9 crib cavern environment below. For this reason the crib and glovebox currently share a common airspace. The functional requirements for safely conducting work within the glovebox include provision of a negative pressure in the box of about 0.5 inches of water gage (nominal) less than the interior of the building. In addition, the building surrounding the glovebox will be maintained at a slight negative pressure with respect to outdoor ambient pressure. In order to assess the relevant and appropriate clean air requirements for the new temporary ventilation system and associated emissions monitoring, it was necessary to reliably predict the nature of the exhaust air stream. Factors used to predict the presence and concentrations of certain radionuclide particulates and certain gases considered to be air toxics, included reliability parameters, flow rates, radionuclide content, and off-gas compositions. Radionuclide content includes transuranic isotopes, primarily of plutonium and americium. Air toxics include carbon tetrachloride, butane, methanol, acetone and toluene. Flow rate prediction was based on available design and test data and considered equipment sizes, glovebox negative pressure requirements, and filter flow characteristics. The approach used to predict the off-gas composition from the crib required experience-based predictive analysis combined with crib head space analytical results. Input information for emission estimates included: (1) gas composition sample data obtained from recent samples taken within the crib head space during static conditions, and (2) air in-leakage/dilution estimates based on physical characteristics of both the crib and the new temporary ventilation system. The conceptual approach combined measurement-based data with conservative assumptions, and provides the estimates necessary to determine relevance and appropriateness of substantive requirements under federal and state laws and regulations. (authors)

Hopkins, A.; Sutter, C.; O'Brien, P.; Bates, J.; Klos, B. [Fluor Hanford Inc., Richland, WA (United States); Teal, J. [Fluor Federal Services, Richland, WA (United States); Oates, L. [Environmental Quality Management, Inc., Richland, WA (United States)

2008-07-01T23:59:59.000Z

239

Studies of transport of waste radionuclides, through soil at the Maxey Flats, Kentucky, waste-burial site  

SciTech Connect

Two areas at the waste-burial site are being used to study the interaction of soil with liquid waste - one near Trench 19S and the other between an experimental trench and Trench 27. Analyses of soil solutions near Trench 19S indicate that radionuclides have migrated from the waste-burial trench. The observed distribution of radionuclides in that area suggests that /sup 3/H, as tritiated water, has moved the greatest distance. Movement of /sup 137/Cs is essentially nonexistent. The migration of /sup 238/Pu and /sup 60/Co lies between those two extremes. The distance that /sup 3/H has moved, at an approximated depth of 4 m, is about 9 m. Additional porous cup samplers were installed at depths to 8 m to better evaluate the distribution of radionuclides near Trench 19S. Results from soil moisture measurements by R.K. Schulz of the University of California at Berkeley indicate a preferential movement of water into the waste trench through its cap. Our study of the /sup 3/H in surface soils outside the perimeter fence of the burial site suggests that contamination of the near-surface soil water occurs and could be from an airborne source, possible originating from the site evaporator. Another localized source could be associated with underflow from a burial trench that surfaces outside the perimeter fence. The /sup 3/H content in some soil solutions near an experimental trench suggest a preferential movement of water along an interface of an original soil profile and the overlying landfill. If such an interface were to intercept a burial trench and also outcrop off site, it could act as a preferential pathway for transport of radionuclides off site. The nonsorptive behavior of a small fraction of /sup 238/Pu in the Maxey Flats waste was interpreted as having been caused by an organic complex that is very slowly biodegradable. Organic constituents in the Maxey Flats soil, Tilsit Ap, may complex some of the /sup 238/Pu, making it mobile for some period of time.

Fowler, E.B.; Polzer, W.L.; Essington, E.H.

1983-01-01T23:59:59.000Z

240

Proposed changes for part N of suggested state regulations  

SciTech Connect

This paper discusses proposed changes for Part N regulations regarding naturally occuring radioactive materials. It describes the work of the Commission on NORM of the Conference of Radiation Control Program Directors (CRCPD), toward adjusting the regulations. A set of questions was formulated and a review panel established to address these questions and come back with recommended actions. The panel recommended the distinction that the material being regulated is `Technologically Enhanced Naturally Occurring Radioactive Material` (TENORM). By this they mean `naturally occurring radioactive material not regulated under the Atomic Energy Act (AEA) whose radionuclide concentrations have been increased by or as a result of human practices.` Recommendations also include: using a dose based instead of concentration based standard; refined definition of exemptions from regulations; exclusion of radon from Total Effective Dose Equivalent (TEDE) calculations; provide states flexibility in implementation; inclusion of prospective remedial and operations aspects for TENORM; provision of institutional controls.

Paris, R.

1997-02-01T23:59:59.000Z

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.


241

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

242

Water quality Water quantity  

E-Print Network (OSTI)

01-1 · Water quality · Water quantity · Remediation strategies MinE 422: Water Resources: Younger, Banwart and Hedin. 2002. Mine Water. Hydrology, Pollution, Remediation. Impacts of mining on water mining ­ Often the largest long term issue ­ Water quality affected, surface/ground water pollution

Boisvert, Jeff

243

Water quality Water quantity  

E-Print Network (OSTI)

· Water quality · Water quantity · Remediation strategies MinE 422: Water Resources: Younger, Banwart and Hedin. 2002. Mine Water. Hydrology, Pollution, Remediation. Impacts of mining on water mining ­ Often the largest long term issue ­ Water quality affected, surface/ground water pollution

Boisvert, Jeff

244

Risk Due to Radiological Terror Attacks With Natural Radionuclides  

Science Journals Connector (OSTI)

The naturally occurring radionuclides radium (Ra?226) and polonium (Po?210) have the potential to be used for criminal acts. Analysis of international incident data contained in the Database on Nuclear Smuggling Theft and Orphan Radiation Sources (CSTO) operated at the University of Salzburg shows that several acts of murder and terrorism with natural radionuclides have already been carried out in Europe and Russia. Five different modes of attack (T) are possible: (1) Covert irradiation of an individual in order to deliver a high individual dose; (2) Covert irradiation of a group of persons delivering a large collective dose; (3) Contamination of food or drink; (4) Generation of radioactive aerosols or solutions; (5) Combination of Ra?226 with conventional explosives (Dirty Bomb).

Steinhusler Friedrich; Rydell Stan; Zaitseva Lyudmila

2008-01-01T23:59:59.000Z

245

Radio-nuclide mixture identification using medium energy resolution detectors  

DOE Patents (OSTI)

According to one embodiment, a method for identifying radio-nuclides includes receiving spectral data, extracting a feature set from the spectral data comparable to a plurality of templates in a template library, and using a branch and bound method to determine a probable template match based on the feature set and templates in the template library. In another embodiment, a device for identifying unknown radio-nuclides includes a processor, a multi-channel analyzer, and a memory operatively coupled to the processor, the memory having computer readable code stored thereon. The computer readable code is configured, when executed by the processor, to receive spectral data, to extract a feature set from the spectral data comparable to a plurality of templates in a template library, and to use a branch and bound method to determine a probable template match based on the feature set and templates in the template library.

Nelson, Karl Einar

2013-09-17T23:59:59.000Z

246

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

247

Trench water chemistry at commercially operated low-level radioactive waste disposal sites. [Trench waters from Maxey Flats, Kentucky and West Valley, New York  

SciTech Connect

Water samples from the disposal trenches of two low-level radioactive-waste-disposal sites were analyzed for their inorganic, organic, and radionuclide contents. Since oxidation of the trench waters can occur during their movement along the groundwater flow path, experiments were performed to measure the chemical and physical changes that occur in these waters upon oxidation. Low concentrations of chelating agents, shown to exist in trench waters, may be responsible for keeping radionuclides, particularly /sup 60/Co, in solution. 4 figures, 5 tables.

Pietrzak, R.F.; Dayal, R.; Kinsley, M.T.; Clinton, J.; Czyscinski, K.S.; Weiss, A.J.

1982-01-01T23:59:59.000Z

248

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

249

Environmental radionuclide distribution in Georgia after the Chernobyl accident  

SciTech Connect

Atmospheric Chernobyl-released radioactivity, assessed at about 2 x 10{sup 18} Bq, caused global environmental contamination. Contaminated air masses appeared in the Transcaucasian region in early May, 1986. Rains that month promoted intense radionuclide deposition all over Georgia. The contamination level of western Georgia considerably exceeded the contamination level of eastern Georgia. The Black Sea coast of Georgia suffered from the Chernobyl accident as much as did strongly contaminated areas of the Ukraine and Belarus`. Unfortunately, governmental decrees on countermeasures against the consequences of the Chernobyl accident at that time did not even refer to the coast of Georgia. The authors observed the first increase in radioactivity background in rainfall samples collected on May 2, 1986, in Tbilisi. {gamma}-Spectrometric measurements of aerosol filters, vegetation, food stuffs, and other objects, in addition to rainfall, persistently confirmed the occurrence of short-lived radionuclides, including {sup 131}I. At first, this fact seemed unbelievable, because the Chernobyl accident had occurred only 4-5 days earlier and far from Georgia. However, these arguments proved to be faulty. Soon, environmental monitoring of radiation in Georgia became urgent. Environmental radionuclide distribution in Georgia shortly after the Chernobyl accident, as well as the methods of analysis, are reported in this paper.

Mosulishvili, L.M.; Shoniya, N.I.; Katamadze, N.M. [Institute of Physics, Tbilisi, Georgia (Russian Federation)] [and others

1994-01-01T23:59:59.000Z

250

Bayesian statistics in radionuclide metrology: measurement of a decaying source  

Science Journals Connector (OSTI)

The most intuitive way of defining a probability is perhaps through the frequency at which it appears when a large number of trials are realized in identical conditions. The probability derived from the obtained histogram characterizes the so-called frequentist or conventional statistical approach. In this sense, probability is defined as a physical property of the observed system. By contrast, in Bayesian statistics, a probability is not a physical property or a directly observable quantity, but a degree of belief or an element of inference. The goal of this paper is to show how Bayesian statistics can be used in radionuclide metrology and what its advantages and disadvantages are compared with conventional statistics. This is performed through the example of an yttrium-90 source typically encountered in environmental surveillance measurement. Because of the very low activity of this kind of source and the small half-life of the radionuclide, this measurement takes several days, during which the source decays significantly. Several methods are proposed to compute simultaneously the number of unstable nuclei at a given reference time, the decay constant and the background. Asymptotically, all approaches give the same result. However, Bayesian statistics produces coherent estimates and confidence intervals in a much smaller number of measurements. Apart from the conceptual understanding of statistics, the main difficulty that could deter radionuclide metrologists from using Bayesian statistics is the complexity of the computation.

Fran?ois O Bochud; Claude J Bailat; Jean-Pascal Laedermann

2007-01-01T23:59:59.000Z

251

Radionuclide inventory for the Waste Isolation Pilot Plant  

SciTech Connect

This report updates the information previously submitted in the draft report DOE/WIPP 88-005, Radionuclide Source Term for the WIPP, dated 1987 (reference 1). The information in this report provides the projected radionuclide inventory at the WIPP based on the projected waste receipts through the year 2013. The information is based on the 1991 TRU Program Data submittals for the Integrated Data Base (DOE/RW-0006, Rev. 7) from each of the DOE sites generating or storing TRU waste for shipment to the WIPP. The data is based on existing characterization data on the waste in interim storage, waste estimates based on projected programs during the 1991 through 2013 time period, projected treatment processes required to meet WIPP Waste Acceptance Criteria (WAC), and a projection of the waste that will be declared low level waste when it is assayed as part of the certification program for waste shipments to WIPP. This data will serve as a standard reference for WIPP programs requiring radionuclide data, including safety programs, performance assessment, and regulatory compliance. These projections will continue to be periodically updated as the waste data estimates are refined by the generator sites as they participate in the annual update of the Integrated Data Base (IDB).

Not Available

1991-12-31T23:59:59.000Z

252

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

253

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

254

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

255

2 C.C.R. 410 - Rules and Regulations for the Management and Control...  

Open Energy Info (EERE)

and Regulations for the Management and Control of Designated Ground Water Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: 2...

256

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

257

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

SciTech Connect

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

258

Sediment studies at Bikini Atoll part 3. Inventories of some long-lived gamma-emitting radionuclides associated with lagoon surface sediments  

SciTech Connect

Surface sediment samples were collected during 1979 from 87 locations in the lagoon at Bikini Atoll. The collections were made to better define the concentrations and distribution of long-lived radionuclides associated with the bottom material and to show what modifications occurred to the composition of the surface sediment from the nuclear testing program conducted by the United States at the Atoll between 1946 and 1958. This is the last of three reports on Bikini sediment studies. In this report, we discuss the concentrations and inventories of the residual long-lived gamma-emitting radionuclides in sediments from the lagoon. The gamma-emitting radionuclides detected most frequently in sediments collected in 1979, in addition to Americium-241 ({sup 241}Am) (discussed in the second report of this series), included Cesium-137 ({sup 137}Cs), Bismuth-207 ({sup 207}Bi), Europium-155 ({sup 155}Eu), and Cobalt-60 ({sup 60}Co). Other man-made, gamma-emitting radionuclides such as Europium-152,154 ({sup 152,154}Eu), Antimony-125 ({sup 125}Sb), and Rhodium-101,102m ({sup 101,102m}Rh) were occasionally measured above detection limits in sediments near test site locations. The mean inventories for {sup 137}Cs, {sup 207}Ei, {sup 155}Eu, and {sup 60}Co in the surface 4 cm of the lagoon sediment to be 1.7, 0.56, 7.76, and 0.74 TBq, respectively. By June 1997, radioactive decay would reduce these values to 1.1, 0.38, 0.62, and 0.07 TBq, respectively. Some additional loss results from a combination of different processes that continuously mobilize and return some amount of the radionuclides to the water column. The water and dissolved constituents are removed from the lagoon through channels and exchange with the surface waters of the north equatorial Pacific Ocean. Highest levels of these radionuclides are found in surface deposits lagoonward of the Bravo Crater. Lowest concentrations and inventories are associated with sediment lagoonward of the eastern reef. The quantities in the 0-4 cm surface layer are estimated to be less than 35% of the total inventory to depth in the sediment column.

Noshkin, V.E.

1997-12-01T23:59:59.000Z

259

Potential Effects of Organic Carbon Production on Ecosystems and Drinking Water Quality  

E-Print Network (OSTI)

National Primary Drinking Water Regulations, disinfectantsand implications for drinking water quality and the Deltaand control in drinking water. American Chemical Society,

Brown, Larry R.

2003-01-01T23:59:59.000Z

260

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

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

23 CCR 3855 et seq. - Water Quality Certification | Open Energy...  

Open Energy Info (EERE)

3855 et seq. - Water Quality Certification Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: 23 CCR 3855 et seq. - Water...

262

30 TAC 297 Water Rights, Substantive | Open Energy Information  

Open Energy Info (EERE)

Water Rights, Substantive Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: 30 TAC 297 Water Rights, SubstantiveLegal...

263

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

264

Advanced Remedial Methods for Metals and Radionuclides in Vadose Zone Environments  

SciTech Connect

Functionally, the methods for addressing contamination must remove and/or reduce transport or toxicity of contaminants. This problem is particularly challenging in arid environments where the vadose zone can be up to hundreds of feet thick, rendering transitional excavation methods exceedingly costly and ineffective. Delivery of remedial amendments is one of the most challenging and critical aspects for all remedy-based approaches. The conventional approach for delivery is through injection of aqueous remedial solutions. However, heterogeneous vadose zone environments present hydrologic and geochemical challenges that limit the effectiveness. Because the flow of solution infiltration is dominantly controlled by gravity and suction, injected liquid preferentially percolates through highly permeable pathways, by-passing low-permeability zones which frequently contain the majority of the contamination. Moreover, the wetting front can readily mobilize and enhance contaminant transport to underlying aquifers prior to stabilization. Development of innovative, in-situ technologies may be the only way to meet remedial action objectives and long-term stewardship goals. Shear-thinning fluids (i.e., surfactants) can be used to lower the liquid surface tension and create stabile foams, which readily penetrate low permeability zones. Although surfactant foams have been utilized for subsurface mobilization efforts in the oil and gas industry, so far, the concept of using foams as a delivery mechanism for transporting reactive remedial amendments into deep vadose zone environments to stabilize metal and long-lived radionuclide contaminants has not been explored. Foam flow can be directed by pressure gradients, rather than being dominated by gravity; and, foam delivery mechanisms limit the volume of water (< 20% vol.) required for remedy delivery and emplacement, thus mitigating contaminant mobilization. We will present the results of a numerical modeling and integrated laboratory-/ intermediate-scale investigation to simulate, develop, demonstrate, and monitor (i.e. advanced geophysical techniques and advanced predictive biomarkers) foam-based delivery of remedial amendments to remediate metals and radionuclides in vadose zone environments.

Wellman, Dawn M.; Mattigod, Shas V.; Hubbard, Susan; Miracle, Ann L.; Zhong, Lirong; Foote, Martin; Wu, Yuxin; Jansik, Danielle P.

2010-10-03T23:59:59.000Z

265

PATHWAY: a simulation model of radionuclide-transport through agricultural food chains  

SciTech Connect

PATHWAY simulates the transport of radionuclides from fallout through an agricultural ecosystem. The agro-ecosystem is subdivided into several land management units, each of which is used either for grazing animals, for growing hay, or for growing food crops. The model simulates the transport of radionuclides by both discrete events and continuous, time-dependent processes. The discrete events include tillage of soil, harvest and storage of crops,and deposition of fallout. The continuous processes include the transport of radionuclides due to resuspension, weathering, rain splash, percolation, leaching, adsorption and desorption of radionuclides in the soil, root uptake, foliar absorption, growth and senescence of vegetation, and the ingestion assimilation, and excretion of radionuclides by animals. Preliminary validation studies indicate that the model dynamics and simulated values of radionuclide concentrations in several agricultural products agree well with measured values when the model is driven with site specific data on deposition from world-wide fallout.

Kirchner, T.B.; Whicker, F.W.; Otis, M.D.

1982-01-01T23:59:59.000Z

266

Trench water-soil chemistry and interactions at the Maxey Flats Site  

SciTech Connect

This report is part of an overall program designed to provide an understanding of and to monitor the behavior of existing low-level sites. This investigation will provide source term data for radionuclides and other solutes in trench waters and will describe the physical, chemical, and biological properties of the geochemical system that controls radionuclide movement. General conclusions can be made from the data in terms of source term information to be used in modeling efforts, as well as processes which may affect radionuclide migration. Trench waters are complex anoxic chemical systems which require more extensive investigation to assess their role in radionuclide retention and mobilization. No overall systematic changes in the disposal site trenches were observed during the brief sampling interval. However, changes in some radionuclide and cation concentrations were observed in several trenches. Numerous organic compounds were identified in trench waters at Maxey Flats, some of which have the potential for chelation with radionuclides. The presence of radionuclides and organic compounds in wells UB1 and UB1-A and in nearby trenches indicates communication between the wells and trench water leachates by subsurface migration. Radionuclides were also measured in the new experimental trench dug parallel to trench 27. Aerobic, anaerobic, sulfate reducing, denitrifying, and methanogenic bacteria are present in the leachate samples, and are able to grow anaerobically in trench leachates. Experimental results indicate that the observed sorption K/sub d/ is a function of both solid and liquid phase compositional variations as well as contact time. The observation that e lowest K/sub d/ results are observed with anoxic trench waters and ultrasonicated soils points to the need to use site specific materials and experimental conditions which simulate in situ conditions as closely as possible.

Weiss, A.J.; Czyscinski, K.S.

1980-01-01T23:59:59.000Z

267

Regulation 28: Library REGULATION 28: LIBRARY  

E-Print Network (OSTI)

Regulation 28: Library 180 REGULATION 28: LIBRARY The purpose of this Regulation is to safeguard the common interests of all Library users. All persons are admitted on the understanding that they have read and agreed to observe the Library Regulations. Breach of this Regulation could result in membership being

Sussex, University of

268

Nutrient Management Module No. 12 Water Quality  

E-Print Network (OSTI)

Nutrient Management Module No. 12 Water Quality Considerations and Regulations by Susan Mc Management Competency Area II: Nutrient movement in soil and water. Objectives After completing this module issues 3.Become familiar with federal and state water quality regulations 4.Identify Best Management

Lawrence, Rick L.

269

Investigation of magnetic nanoparticles for the rapid extraction and assay of alpha-emitting radionuclides from urine: Demonstration of a novel radiobioassay method  

SciTech Connect

In the event of an accidental or intentional release of radionuclides into a populated area, three things must occur in a timely manner: food and drinking water supplies must be determined to be safe to eat / drink, civilians and/or military personnel must be surveyed to ensure that they do not have external contamination, and they must be screened to ensure that significant ingestion or inhalation of radionuclides has not occurred (this paper is concerned with the latter). In the event of such a disaster, the volume of radiobioassays to be performed would be tremendous. If the event released significant levels of ?- or ?-emitting radionuclides, in vivo assays would be ineffective. Therefore, highly efficient and rapid analytical methods for radionuclide detection from submitted spot urine samples (? 50 mL) would be required. At present, the quantitative determination of ?-emitting radionuclides from urine samples is highly labor intensive, and requires significant sample preparation and analysis time. Sorbent materials that provide effective collection and enable rapid assay could significantly streamline the radioanalytical process. We have demonstrated the use of paramagnetic nanoparticles as a novel class of extracting media for four ?-emitting radionuclides of concern (Po, Ra, Am, and U) from chemically unmodified and pH 2 human urine. Herein the initial experimental sorption results are presented along with a novel method that utilizes paramagnetic nanoparticles for the extraction of radionuclides from unmodified human urine followed by the magnetic field-induced collection of the particles for subsequent ?-counting-source preparation. Additionally, we construct a versatile human dose model that determines the detector count times required to estimate internal human dose at specific protective action thresholds. The model provides a means to assess a methods detection capabilities and use fundamental health physics parameters and actual experimental data as core variables. The modeling shows that with effective sorbent materials, rapid screening for internalized ?-emitters is possible from a 50 mL spot urine sample volume collected within one week of exposure/intake.

O'Hara, Matthew J.; Carter, Jennifer C.; Maclellan, Jay A.; Warner, Cynthia L.; Warner, Marvin G.; Addleman, Raymond S.

2011-08-01T23:59:59.000Z

270

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

271

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

272

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 solutin 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.

Francis, Arokiasamy J. (Middle Island, NY); Dodge, Cleveland J. (Wading River, NY); Gillow, Jeffrey B. (Valley Cottage, NY)

1991-01-01T23:59:59.000Z

273

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

274

Applications of Extraction Chromatography in the Development of Radionuclide Generator Systems for Nuclear Medicine  

Science Journals Connector (OSTI)

Applications of Extraction Chromatography in the Development of Radionuclide Generator Systems for Nuclear Medicine ... Chemistry Division, Argonne National Laboratory, Argonne, Illinois 60439 ...

Mark L. Dietz; E. Philip Horwitz

2000-08-12T23:59:59.000Z

275

Testing and Evaluation Protocol for Handheld Radionuclide Identifiers for Use in Homeland Security  

E-Print Network (OSTI)

Testing and Evaluation Protocol for Handheld Radionuclide Identifiers for Use in Homeland Security................................................................................1 4. Test and evaluation steps .........................................................................................1 5. Recording test results

276

E-Print Network 3.0 - artificial radionuclides transport Sample...  

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

transport and sedimentology... on the detection of -radiation emitted by naturally occurring radionuclides play a major role in this thesis... radiation transport and play an...

277

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

278

Phase chemistry and radionuclide retention from simulated tank sludges  

SciTech Connect

Decommissioning high level nuclear waste tanks will leave small amounts of residual sludge clinging to the walls and floor of the structures. The permissible amount of material left in the tanks depends on the radionuclide release characteristics of the sludge. At present, no systematic process exists for assessing how much of the remaining inventory will migrate, and which radioisotopes will remain relatively fixed. Working with actual sludges is both dangerous and prohibitively expensive. Consequently, methods were developed for preparing sludge simulants and doping them with nonradioactive surrogates for several radionuclides and RCRA metals of concern in actual sludges. The phase chemistry of these mixes was found to be a reasonable match for the main phases in actual sludges. Preliminary surrogate release characteristics for these sludges were assessed by lowering the ionic strength and pH of the sludges in the manner that would occur if normal groundwater gained access to a decommissioned tank. Most of the Se, Cs and Tc in the sludges will be released into the first pulse of groundwater passing through the sludge. A significant fraction of the other surrogates will be retained indefinitely by the sludges. This prolonged sequestration results from a combination coprecipitated and sorbed into or onto relatively insoluble phases such as apatite, hydrous oxides of Fe, Al, Bi and rare earth oxides and phosphates. The coprecipitated fraction cannot be released until the host phase dissolves or recrystallizes. The sorbed fraction can be released by ion exchange processes as the pore fluid chemistry changes. However, these releases can be predicted based on a knowledge of the fluid composition and the surface chemistry of the solids. In this regard, the behavior of the hydrous iron oxide component of most sludges will probably play a dominant role for many cationic radionuclides while the hydrous aluminum oxides may be more important in governing anion releases.

KRUMHANSL,JAMES L.; LIU,J.; ARTHUR,SARA E.; HUTCHERSON,SHEILA K.; QIAN,MORRIS; ANDERSON,HOWARD L.

2000-05-19T23:59:59.000Z

279

Water, water everywhere  

Science Journals Connector (OSTI)

... available water resources, either locally or globally, are by no means exhausted. At present desalination -- the removal of salt from sea water or brackish water -- is very ... or brackish water -- is very expensive, mainly because it consumes so much energy. Desalination provides less than 0.2 per cent of all the water used in the world ...

Philip Ball

2000-01-27T23:59:59.000Z

280

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

SciTech Connect

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

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

Radionuclides identified at a US Customs Service site  

SciTech Connect

The movement of radionuclides through the U.S. Customs Service port of entry at Blaine, Washington, has been studied using a high-resolution gamma-ray spectrometer and an automated data logging system. Data covering about 10 weeks of operation were obtained and analyzed. The data-acquisition system and the site of the measurement are described. Results are reported and interpreted in light of the known traffic of radioisotopes produced at the Canadian TRIUMF facility and imported into the United States for use in radiopharmaceuticals.

Johnson, M.W.; Bounds, J.A.; Steadman, P.A. [and others

1997-05-01T23:59:59.000Z

282

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

SciTech Connect

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

Water Resources Water Quality and Water Treatment  

E-Print Network (OSTI)

Water Resources TD 603 Lecture 1: Water Quality and Water Treatment CTARA Indian Institute of Technology, Bombay 2nd November, 2011 #12;OVERVIEW Water Quality WATER TREATMENT PLANTS WATER TREATMENT PLANTS WATER TREATMENT PLANTS WATER TRE OVERVIEW OF THE LECTURE 1. Water Distribution Schemes Hand Pump

Sohoni, Milind

284

Y-12s Biomonitoring and Water Quality  

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

Biomonitoring and Water Quality The following details of the emerging environmental situation and public concerns that produced increased regulations for Y-12 is provided by Mick...

285

Regulators, Requirements, Statutes  

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

Statutes Regulators, Requirements, Statutes The Laboratory must comply with environmental laws and regulations that apply to Laboratory operations. Contact Environmental...

286

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

SciTech Connect

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

287

ASSESSMENT OF RELEASE RATES FOR RADIONUCLIDES IN ACTIVATED CONCRETE.  

SciTech Connect

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

288

A Radionuclide Transport Model for the Unsaturated Zone at Yucca Mountain Bruce A. Robinson  

E-Print Network (OSTI)

A Radionuclide Transport Model for the Unsaturated Zone at Yucca Mountain Bruce A. Robinson Zhiming model calculations for radionuclide transport in the unsaturated zone at Yucca Mountain. The model developed by the Yucca Mountain Project based on calibrations to site data. The particle-tracking technique

Lu, Zhiming

289

Environmental impact of natural radionuclides from a coal-fired power plant in Spain  

Science Journals Connector (OSTI)

......natural radionuclides from a coal-fired power plant in Spain...natural radionuclides of the coal. The three most important nuclides...20). Owing to considerable economic and environment importance and...from different processes of the coal industrial cycle. A radiological......

Elena Charro; Vctor Pea

2013-03-01T23:59:59.000Z

290

INSTRUCTIONS FOR OPENING RADIONUCLIDE SHIPMENTS All packages containing radioactive material are physically received at the Department of Environmental  

E-Print Network (OSTI)

are monitored and contamination of the package exterior is assessed. The radioactive stock vialINSTRUCTIONS FOR OPENING RADIONUCLIDE SHIPMENTS All packages containing radioactive material radionuclide packages. GENERAL PROCEDURES 1. Radioactive packages must be opened and inspected as soon

Firestone, Jeremy

291

Gasification characteristics to 14CO2 of 14C radionuclide desorbed from spent resin by phosphate solutions  

Science Journals Connector (OSTI)

The removal characteristics of H14CO3 ? ions from IRN-150 mixed resin contaminated with 14C radionuclide and the gasification effects of 14C radionuclide on 14CO2 are investigated in this study. T...

Ho-Yeon Yang; Ji-Hoon Lee; Jung-Jin Lee

2010-08-01T23:59:59.000Z

292

Ground-water contribution to dose from past Hanford Operations  

SciTech Connect

The Hanford Environmental Dose Reconstruction (HEDR) Project is being conducted to estimate radiation doses that populations and individuals could have received from Hanford Site operations from 1944 to the present. Four possible pathways by which radionuclides migrating in ground water on the Hanford Site could have reached the public have been identified: (1) through contaminated ground water migrating to the Columbia River; (2) through wells on or adjacent to the Hanford Site; (3) through wells next to the Columbia River downstream of Hanford that draw some or all of their water from the river (riparian wells); and (4) through atmospheric deposition resulting in contamination of a small watershed that, in turn, results in contamination of a shallow well or spring by transport in the ground water. These four pathways make up the ground-water pathway,'' which is the subject of this study. Assessment of the ground-water pathway was performed by (1) reviewing the existing extensive literature on ground water and ground-water monitoring at Hanford and (2) performing calculations to estimate radionuclide concentrations where no monitoring data were collected. Radiation doses that would result from exposure to these radionuclides were calculated.

Freshley, M.D.; Thorne, P.D.

1992-08-01T23:59:59.000Z

293

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

294

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,

295

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

296

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

297

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

298

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

299

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...

300

Potential Application Of Radionuclide Scaling Factors To High Level Waste Characterization  

SciTech Connect

Production sources, radiological properties, relative solubilities in waste, and laboratory analysis techniques for the forty-five radionuclides identified in Hanford?s Waste Treatment and Immobilization Plant (WTP) Feed Acceptance Data Quality Objectives (DQO) document are addressed in this report. Based on Savannah River Site (SRS) experience and waste characteristics, thirteen of the radionuclides are judged to be candidates for potential scaling in High Level Waste (HLW) based on the concentrations of other radionuclides as determined through laboratory measurements. The thirteen radionuclides conducive to potential scaling are: Ni-59, Zr-93, Nb-93m, Cd-113m, Sn-121m, Sn-126, Cs-135, Sm-151, Ra-226, Ra-228, Ac-227, Pa-231, and Th-229. The ability to scale radionuclides is useful from two primary perspectives: 1) it provides a means of checking the radionuclide concentrations that have been determined by laboratory analysis; and 2) it provides a means of estimating radionuclide concentrations in the absence of a laboratory analysis technique or when a complex laboratory analysis technique fails. Along with the rationale for identifying and applying the potential scaling factors, this report also provides examples of using the scaling factors to estimate concentrations of radionuclides in current SRS waste and into the future. Also included in the report are examples of independent laboratory analysis techniques that can be used to check results of key radionuclide analyses. Effective utilization of radionuclide scaling factors requires understanding of the applicable production sources and the chemistry of the waste. As such, the potential scaling approaches identified in this report should be assessed from the perspective of the Hanford waste before reaching a decision regarding WTP applicability.

Reboul, S. H.

2013-09-30T23:59:59.000Z

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.


301

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

302

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

303

FATE AND TRANSPORT OF RADIONUCLIDES [U(VI), Sr, Cs] IN VADOSE ZONE SEDIMENTS AT THE HANFORD SITE  

E-Print Network (OSTI)

FATE AND TRANSPORT OF RADIONUCLIDES [U(VI), Sr, Cs] IN VADOSE ZONE SEDIMENTS AT THE HANFORD SITE AND TRANSPORT OF RADIONUCLIDES [U(VI), Sr, Cs] IN VADOSE ZONE SEDIMENTS AT THE HANFORD SITE Abstract by Kenton A that influence radionuclide fate and transport in the Hanford vadose zone. Hanford was established for nuclear

Flury, Markus

304

Monitoring program for radionuclides in marketplace seafoods. Final report  

SciTech Connect

This report presents the results of a monitoring program, conducted in 1981 and 1982, by the Environmental Protection Agency (EPA) and the Food and Drug Administration (FDA) to measure concentrations of man-made radionuclides in seafoods to determine effects from previous U.S. ocean disposals of low-level radioactive wastes (LLW). Commercially-marketed seafood samples were collected from Boston, Massachusetts, Atlantic City, New Jersey and San Francisco, California. Each of these cities is near a previously-used U.S. ocean disposal site for LLW. The data obtained during this monitoring program shows that the concentrations of man-made radioactivity in seafoods sampled are below levels of public health concern. The data are considered to be of normal background level, attributable to global fallout over the oceans.

Curtis, W.R.

1988-06-01T23:59:59.000Z

305

Pretreatment/Radionuclide Separations of Cs/Tc from Supernates  

SciTech Connect

Significant improvements have been made in ion exchange and solvent extraction materials and processes available for separation of the radionuclides cesium and technetium from both acid and alkaline waste solutions. New ion exchange materials and solvent extraction reagents are more selective for Cs over sodium and potassium than previous materials. The higher selectivity gives higher Cs capacity and improved separation processes. Technetium removal has been improved by new ion exchange resins, which have either improved capacity or easier elution. Several different crown ethers have been shown to extract pertechnetate ion selectively over other anions. Organic complexants in some waste solutions reduce pertechnetate ion and stabilize the reduced species. Selective oxidation allows conversion to pertechnetate without oxidation of the organic complexants.

Thompson, M.C. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1998-09-01T23:59:59.000Z

306

The radionuclide research and production program at Brookhaven National Laboratory  

SciTech Connect

The DOE-supported, {open_quotes}Radionuclide and Radiopharmaceutical Research for Medicine{close_quotes} program at BNL has a long record of accomplishment. In the 1950s and 1960s the Hot Lab Division was responsible for the development for such important isotopes as {sup 90}Mo, {sup 90}Sr, {sup 132, 133}I, and especially the generator systems {sup 90}Mo/{sup 99m}Tc, {sup 90}Sr/{sup 90}Y and {sup 68}Ge/{sup 68}Ga. The role in the growth of nuclear medicine of the {sup 99}Mo generator was, and still is, critical. Another very important isotope, {sup 201}Tl for myocardial perfusion studies, was developed in the early 1970s. In 1972 program focus changed somewhat with the construction of the Brookhaven Linac Isotope Producer (BLIP). This was the world`s first facility to demonstrate the capability of a large proton linac for efficient no-carrier added radionuclide production by spallation reactions. It utilizes the excess beam capacity of the 200 MeV proton linac injector for the Alternating Gradient Synchroton. Over two dozen previously unavailable isotopes have been developed at the BLIP, including {sup 67}Cu, {sup 68}Ge, {sup 82}Sr, {sup 96}Tc, {sup 123}I, and {sub 127}Xe. Also, other promising isotopes were developed using the High Flux Beam Reactor, including {sup 117m}Sn, {sup 109}Pd, {sup 47}Sc, and {sup 199}Au. Year-round operation with increased beam current can be implemented to alleviate the shortage of, and the interruption in, the supply of medically useful isotopes.

Mausner, L.F.; Kurczak, S.; Schnakenberg, H.; Kolsky, K.L.; Srivastava, S.C. [Brookhaven National Laboratory, Upton, NY (United States)

1993-12-31T23:59:59.000Z

307

Committed effective dose from naturally occuring radionuclides in shellfish  

Science Journals Connector (OSTI)

Recognizing their importance in the average Malaysian daily diet, the radioactivity concentrations in mollusc- and crustacean-based food have been determined for key naturally occuring radionuclides. Fresh samples collected from various maritime locations around peninsular Malaysia have been processed using standard procedures; the radionuclide concentrations being determined using an \\{HPGe\\} ?-ray spectrometer. For molluscs, assuming secular equilibrium, the range of activities of 238U (226Ra), 232Th (228Ra) and 40K were found to be 3.280.35 to 5.340.52, 1.200.21 to 2.440.21 and 1186 to 28114Bqkg?1 dry weight, respectively. The respective values for crustaceans were 3.020.57 to 4.700.52, 1.380.21 to 2.400.35 and 21611 to 31615Bqkg?1. The estimated average daily intake of radioactivity from consumption of molluscs are 0.37Bqkg?1 for 238U (226Ra), 0.16Bqkg?1 for 232Th (228Ra) and 18Bqkg?1 for 40K; the respective daily intake values from crustaceans are 0.36Bqkg?1, 0.16Bqkg?1 and 23Bqkg?1. Associated annual committed effective doses from molluscs are estimated to be in the range 21.3 to 34.7?Sv for 226Ra, 19.3 to 39.1?Sv for 228Ra and 17.0 to 40.4?Sv for 40K. For crustaceans, the respective dose ranges are 19.6 to 30.5?Sv, 22.0 to 38.4?Sv and 31.1 to 45.5?Sv, being some several times world average values.

Mayeen Uddin Khandaker; Norfadira Binti Wahib; Yusoff Mohd. Amin; D.A. Bradley

2013-01-01T23:59:59.000Z

308

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

309

Water Efficiency  

Energy Savers (EERE)

Wheeler - Water Savers, LLC * fwheeler@watersaversllc.com Topics * Performance contracting analysis * Water industry terms * Federal reduction goals * Water balance * Water...

310

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

311

Radionuclide concentrations in agricultural products near the Hanford Site, 1982 through 1992  

SciTech Connect

The Pacific Northwest Laboratory reviewed monitoring data for agricultural products collected from 1982 through 1992 near the Hanford Site to determine radionuclide concentration trends. While samples were collected and analyzed, and results reported annual in Hanford Site environmental reports, an 11-year data set was reviewed for this report to increase the ability to assess trends and potential Hanford effects. Products reviewed included milk, chicken, eggs, beef, vegetables, fruit, wine, wheat, and alfalfa. To determine which radionuclides were detected sufficiently often to permit analysis for trends and effects, each radionuclide concentration and its associated uncertainty were ratioed. Radionuclides were considered routinely detectable if more than 50% of the ratios were between zero and one. Data for these radionuclides were then analyzed statistically, using analyses of variance. The statistical analyses indicated the following: for the most part, there were no measurable effects for Hanford operations; radionuclide concentrations in all products reviewed remained relatively low when compared to concentrations that would result in a 1-mrem effective dose equivalent to an individual; radionuclide concentrations are decreasing in general; however, {sup 90}Sr concentrations in all media and {sup 129}I in milk increased from 1982 to 1986, then decreased gradually for the remainder of the review period. The {sup 129}I concentrations may be correlated with processing of irradiated reactor fuel at the Plutonium-Uranium Extraction (PUREX) Plant.

Antonio, E.J.

1994-06-01T23:59:59.000Z

312

Report on Water Programs at Stanford University  

E-Print Network (OSTI)

for this century (percent of 1995-2005 average). equivalent (SWE), #12;Water Efficiency Program ­ Lots of New Regulations · AB 1881: CA Model Landscape Ordinance requiring more efficient outdoor water use · SB7 Consumption - Student Housing & Dining #12;Key to Reducing Our Water Footprint Water efficiency integral part

313

WATER DISTRIBUTION SYSTEM OPERATION: APPLICATION OF  

E-Print Network (OSTI)

CHAPTER 5 WATER DISTRIBUTION SYSTEM OPERATION: APPLICATION OF SIMULATED ANNEALING Fred E. Goldman Arizona State University, Tempe, Arizona 5.1 INTRODUCTION The operation of water distribution systems affects the water quality in these systems. EPA regulations require that water quality be maintained

Mays, Larry W.

314

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

315

Long-Term Assessment of Critical Radionuclides and Associated Environmental Media at the Savannah River Site - 13038  

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, 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 milli-sievert (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. (authors)

Jannik, G.T.; Baker, R.A.; Lee, P.L. [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)] [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States); Eddy, T.P.; Blount, G.C. [Savannah River Nuclear Solutions, Savannah River Site, Aiken, SC 29808 (United States)] [Savannah River Nuclear Solutions, Savannah River Site, Aiken, SC 29808 (United States); Whitney, G.R. [US Department of Energy, Savannah River Operations, Aiken, SC 29808 (United States)] [US Department of Energy, Savannah River Operations, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

316

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

SciTech Connect

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

317

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

SciTech Connect

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

318

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

319

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.

320

Public Versus Private: Does It Matter for Water Conservation? Insights from California  

E-Print Network (OSTI)

driver of water management was the environmental regulatorsEnvironmental and Resource Economics Marvin S, Guy S (1997) Consuming water: evolving strategies of water managements Urban Water Sector. Environmental Management 41(6):863877

Kallis, Giorgos; Ray, Isha; Fulton, Julian; McMahon, James E.

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.


321

West Valley-derived radionuclides in the Niagara river area of Lake Ontario  

Science Journals Connector (OSTI)

The presence of West Valley-derived radionuclides in the densely-populated Niagara...137Cs profile in a 210Pb-dated Lake Ontario sediment core is consistent with the pattern of West Valley discharges to the local...

S. R. Joshi

1988-01-01T23:59:59.000Z

322

Chemical and physical processes of radionuclide migration at Yucca Mountain, Nevada  

Science Journals Connector (OSTI)

The understanding and prediction of radionuclide migration within the geosphere of a high-level radioactive waste repository requires knowledge of chemical and physical processes. In this paper, we present an ove...

E. S. Patera; D. E. Hobart; A. Meijer

1990-09-01T23:59:59.000Z

323

The development of protection standards for intakes of radionuclides (1955?2005)  

Science Journals Connector (OSTI)

......is 110 that for workers. (c) 1 rem 10...abdomen of pregnant worker 2 mSv after declaration of...1949, RM-10 (1950) 8. International...radionuclides by workers. ICRP Publication...ORNL-4168 (Oak Ridge National Laboratory......

John W. Stather

2004-07-01T23:59:59.000Z

324

Radionuclides in the NaturalAnthropogenic System Comprising a Nuclear Power Plant and a Cooling Reservoir  

Science Journals Connector (OSTI)

The sources of technological radionuclides coming into the ecosystem of a nuclear power plant (NPP) cooling reservoir are considered and estimated. The information ... The activity reserve in the ecosystems of th...

Yu. A. Egorov

2002-07-01T23:59:59.000Z

325

Transuranic radionuclides in the environment surrounding radioactive waste diposal sites, a bibliography  

SciTech Connect

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). 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. In an attempt to gather relevant information about the transuranic radionuclides in a variety of environments, we conducted an extensive literature search. In our literature search we identified over 5700 potential written sources of information for review. In addition, we have identified many references which were not found through the literature searches, but which were known to contain useful data. A total of approximately 2600 documents were determined to contain information which would be useful for an in depth study of radionuclides in different environments. The journal articles, books, reports and other documents were reviewed to obtain the source term of the radionuclides studied. Most references containing laboratory study data were not included in our databases. Although these may contain valuable data, we were trying to compile references with information on the behavior of the transuranics in the specific environment being studied.

Stoker, A.C.; Noshkin, V.E.; Wong, K.M.; Brunk, J.L.; Conrado, C.L.; Jones, H.E.; Kehl, S.; Stuart, M.L.; Wasley, L.M.; Bradsher, R.V. [and others

1994-08-01T23:59:59.000Z

326

The enrichment behavior of natural radionuclides in pulverized oil shale-fired power plants  

Science Journals Connector (OSTI)

Abstract The oil shale industry is the largest producer of NORM (Naturally Occurring Radioactive Material) waste in Estonia. Approximately 1112 million tons of oil shale containing various amounts of natural radionuclides is burned annually in the Narva oil shale-fired power plants, which accounts for approximately 90% of Estonian electricity production. The radionuclide behavior characteristics change during the fuel combustion process, which redistributes the radionuclides between different ash fractions. Out of 24 operational boilers in the power plants, four use circulating fluidized bed (CFB) technology and twenty use pulverized fuel (PF) technology. Over the past decade, the PF boilers have been renovated, with the main objective to increase the efficiency of the filter systems. Between 2009 and 2012, electrostatic precipitators (ESP) in four PF energy blocks were replaced with novel integrated desulphurization technology (NID) for the efficient removal of fly ash and SO2 from flue gases. Using gamma spectrometry, activity concentrations and enrichment factors for the 238U (238U, 226Ra, 210Pb) and 232Th (232Th, 228Ra) family radionuclides as well as 40K were measured and analyzed in different PF boiler ash fractions. The radionuclide activity concentrations in the ash samples increased from the furnace toward the back end of the flue gas duct. The highest values in different PF boiler ash fractions were in the last field of the ESP and in the NID ash, where radionuclide enrichment factors were up to 4.2 and 3.3, respectively. The acquired and analyzed data on radionuclide activity concentrations in different PF boiler ashes (operating with an ESP and a NID system) compared to CFB boiler ashes provides an indication that changes in the fuel (oil shale) composition and boiler working parameters, as well as technological enhancements in Estonian oil shale fired power plants, have had a combined effect on the distribution patterns of natural radionuclides in the oil shale combustion products.

Taavi Vaasma; Madis Kiisk; Tnis Meriste; Alan Henry Tkaczyk

2014-01-01T23:59:59.000Z

327

Projected radionuclide inventories of DWPF glass from current waste at time of production  

SciTech Connect

The Waste Acceptance Preliminary Specifications (WAPS) require that the DWPF estimate the inventory of long-lived radionuclides present in the waste glass, and report the values in the Waste Form Qualification Report. In this report, conservative (biased high) estimates of the radionuclide inventory of glass produced from waste currently in the Tank Farm are provided. In most cases, these calculated values compare favorably with actual data. In those cases where the agreement is not good, the values reported here are conservative.

Plodinec, M.J.

1993-02-04T23:59:59.000Z

328

Projected radionuclide inventories of DWPF glass from current waste at time of production. Revision 1  

SciTech Connect

The Waste Acceptance Preliminary Specifications (WAPS) require that the DWPF estimate the inventory of long-lived radionuclides present in the waste glass, and report the values in the Waste Form Qualification Report. In this report, conservative (biased high) estimates of the radionuclide inventory of glass produced from waste currently in the Tank Farm are provided. In most cases, these calculated values compare favorably with actual data. In those cases where the agreement is not good, the values reported here are conservative.

Plodinec, M.J.

1993-02-04T23:59:59.000Z

329

ARM 17-30-101 - Water Quality: 401 Certification | Open Energy...  

Open Energy Info (EERE)

Water Quality: 401 Certification Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: ARM 17-30-101 - Water Quality: 401...

330

U.A.C. R317-15: Water Quality Certification | Open Energy Information  

Open Energy Info (EERE)

U.A.C. R317-15: Water Quality Certification Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: U.A.C. R317-15: Water Quality...

331

A.A.C. R18-11: Water Quality Standards | Open Energy Information  

Open Energy Info (EERE)

1: Water Quality Standards Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: A.A.C. R18-11: Water Quality StandardsLegal...

332

Ion beam analyses of radionuclide migration in heterogeneous rocks  

Science Journals Connector (OSTI)

The migration of radionuclides (RN) in the environment is a topic of general interest for its implications on public health and it is an issue for the long-term safety studies of deep geological repositories (DGR) for high-level radioactive waste. The role played by colloids on RN migration is also of great concern. Diffusion and sorption are fundamental mechanisms controlling RN migration in rocks and many experimental approaches are applied to determine transport parameters for low sorbing RN in homogeneous rocks. However it is difficult to obtain relevant data for high sorbing RN or colloids for which diffusion lengths are extremely short or within heterogeneous rocks where transport might be different in different minerals. The ion beam techniques Rutherford Backscattering Spectrometry (RBS) and micro-Particle Induced X-Ray Emission (?PIXE) rarely applied in the field were selected for their micro-analytical potential to study RN diffusion and surface retention within heterogeneous rocks. Main achievements obtained during last 12 years are highlighted.

Valentino Rigato

2013-01-01T23:59:59.000Z

333

Relative contributions of natural and waste-derived organics to the subsurface transport of radionuclides  

SciTech Connect

Our laboratory is studying the role of organic compounds in the subsurface transport of radionuclides at shallow-land burial sites of low-level nuclear waste, including a commercial site at Maxey Flats, Kentucky, and an aqueous waste disposal site. At the Maxey Flats site, several radionuclides, notably Pu and /sup 60/Co, appear to exist as anionic, organic complexes. Waste-derived organics, particularly chelating agents such as EDTA, HEDTA and associated degradation products (e.g., ED3A), are abundant in aqueous waste leachates and appear to account for the complexation. EDTA, and probably other waste-derived chelating agents as well, are chelated to the Pu and /sup 60/Co in the leachates, potentially mobilizing these radionuclides. In contrast, at the low-level aqueous waste disposal site, naturally-occurring organics, ranging from low molecular weight (MW) acids to high MW humic acids, account for the bulk of the groundwater's organic content. Certain radionuclides, notably /sup 60/Co, /sup 103/Ru and /sup 125/Sb, are mobile as anionic complexes. These radionuclides are clearly associated with higher MW organics, presumably humic and fulvic acids with nominal MW's > 1000. It is clear, therefore, that naturally-occurring organics may play an important role in radionuclide transport, particularly at nuclear waste burial sites containing little in the way of waste-derived organics.

Toste, A.P.; Myers, R.B.

1985-06-01T23:59:59.000Z

334

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:

335

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

336

Montana's Water very person who lives in or visits Montana participates in water manage-  

E-Print Network (OSTI)

Managing Montana's Water E very person who lives in or visits Montana participates in water manage management involves people who allocate water sup- plies, issue permits, regulate the resource according to state and federal laws, and enforce laws when violations occur. Without water management, more human

Lawrence, Rick L.

337

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.

338

Evaluation of Uranium Measurements in Water by Various Methods - 13571  

SciTech Connect

In December 2000, EPA amended its drinking water regulations for radionuclides by adding a Maximum Contaminant Level (MCL) for uranium (so called MCL Rule)[1] of 30 micrograms per liter (?g/L). The MCL Rule also included MCL goals of zero for uranium and other radionuclides. Many radioactively contaminated sites must test uranium in wastewater and groundwater to comply with the MCL rule as well as local publicly owned treatment works discharge limitations. This paper addresses the relative sensitivity, accuracy, precision, cost and comparability of two EPA-approved methods for detection of total uranium: inductively plasma/mass spectrometry (ICP-MS) and alpha spectrometry. Both methods are capable of measuring the individual uranium isotopes U-234, U- 235, and U-238 and both methods have been deemed acceptable by EPA. However, the U-238 is by far the primary contributor to the mass-based ICP-MS measurement, especially for naturally-occurring uranium, which contains 99.2745% U-238. An evaluation shall be performed relative to the regulatory requirement promulgated by EPA in December 2000. Data will be garnered from various client sample results measured by ALS Laboratory in Fort Collins, CO. Data shall include method detection limits (MDL), minimum detectable activities (MDA), means and trends in laboratory control sample results, performance evaluation data for all methods, and replicate results. In addition, a comparison will be made of sample analyses results obtained from both alpha spectrometry and the screening method Kinetic Phosphorescence Analysis (KPA) performed at the U.S. Army Corps of Engineers (USACE) FUSRAP Maywood Laboratory (UFML). Many uranium measurements occur in laboratories that only perform radiological analysis. This work is important because it shows that uranium can be measured in radiological as well as stable chemistry laboratories and it provides several criteria as a basis for comparison of two uranium test methods. This data will indicate which test method is the most accurate and most cost effective. This paper provides a benefit to Formerly Utilized Sites Remedial Action Program (FUSRAP) and other Department of Defense (DOD) programs that may be performing uranium measurements. (authors)

Tucker, Brian J. [Shaw Environmental and Infrastructure Group, 150 Royall Street, Canton, MA (United States)] [Shaw Environmental and Infrastructure Group, 150 Royall Street, Canton, MA (United States); Workman, Stephen M. [ALS Laboratory Group, Environmental Division, 225 Commerce Drive, Fort Collins, CO 80524 (United States)] [ALS Laboratory Group, Environmental Division, 225 Commerce Drive, Fort Collins, CO 80524 (United States)

2013-07-01T23:59:59.000Z

339

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

SciTech Connect

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

340

The Coordinated Control of a Central Air Conditioning System Based on Variable Chilled Water Temperature and Variable Chilled Water Flow  

E-Print Network (OSTI)

At present, regulation of water flow by means of pump frequency conversion is one of the major methods for power-saving in central air conditioning systems. In this article, optimization regulation for central air conditioning system on the basis...

Liu, J.; Mai, Y.; Liu, X.

2006-01-01T23:59:59.000Z

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

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

SciTech Connect

A major issue surrounding current nuclear power generation is the management and disposal of long-lived, high-level waste (HLW). The planned and scientifically acceptable destination for this waste is in deep underground, geologically stable, repositories. However, public concerns surrounding such disposal of long-lived nuclear wastes and other issues such as proliferation and safety negatively affect the potential role that nuclear power can play in meeting current and future national energy needs. This paper and this topical session on nuclear waste minimization, management, and remediation focus on two nuclear systems and their associated technologies that have the potential to address concerns surrounding long-lived radionuclides in HLW. Both systems offer technology applicable to HLW from current light water reactors (LWRs). In addition, 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 burning long-lived actinide waste. The IFR applications include the 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 on an accelerator-induced intense source of thermal neutrons and is aimed at the 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. (Los Alamos National Lab., NM (United States))

1993-01-01T23:59:59.000Z

342

RADIONUCLIDE INVENTORY AND DISTRIBUTION: FOURMILE BRANCH, PEN BRANCH, AND STEEL CREEK IOUS  

SciTech Connect

As a condition to the Department of Energy (DOE) Low Level Waste Disposal Federal Facility Review Group (LFRG) review team approving the Savannah River Site (SRS) Composite Analysis (CA), SRS agreed to follow up on a secondary issue, which consisted of the consolidation of several observations that the team concluded, when evaluated collectively, could potentially impact the integration of the CA results. This report addresses secondary issue observations 4 and 21, which identify the need to improve the CA sensitivity and uncertainty analysis specifically by improving the CA inventory and the estimate of its uncertainty. The purpose of the work described herein was to be responsive to these secondary issue observations by re-examining the radionuclide inventories of the Integrator Operable Units (IOUs), as documented in ERD 2001 and Hiergesell, et. al. 2008. The LFRG concern has been partially addressed already for the Lower Three Runs (LTR) IOU (Hiergesell and Phifer, 2012). The work described in this investigation is a continuation of the effort to address the LFRG concerns by re-examining the radionuclide inventories associated with Fourmile Branch (FMB) IOU, Pen Branch (PB) IOU and Steel Creek (SC) IOU. The overall approach to computing radionuclide inventories for each of the IOUs involved the following components: Defining contaminated reaches of sediments along the IOU waterways Identifying separate segments within each IOU waterway to evaluate individually Computing the volume and mass of contaminated soil associated with each segment, or compartment Obtaining the available and appropriate Sediment and Sediment/Soil analytical results associated with each IOU Standardizing all radionuclide activity by decay-correcting all sample analytical results from sample date to the current point in time, Computing representative concentrations for all radionuclides associated with each compartment in each of the IOUs Computing the radionuclide inventory of each DOE-added radionuclide for the compartments of each IOU by applying the representative, central value concentration to the mass of contaminated soil Totaling the inventory for all compartments associated with each of the IOUs Using this approach the 2013 radionuclide inventories for each sub-compartment associated with each of the three IOUs were computed, by radionuclide. The inventories from all IOU compartments were then rolled-up into a total inventory for each IOU. To put the computed estimate of radionuclide activities within FMB, PB, and SC IOUs into context, attention was drawn to Cs-137, which was the radionuclide with the largest contributor to the calculated dose to a member of the public at the perimeter of SRS within the 2010 SRS CA (SRNL 2010). The total Cs-137 activity in each of the IOUs was calculated to be 9.13, 1.5, and 17.4 Ci for FMB, PB, and SC IOUs, respectively. Another objective of this investigation was to address the degree of uncertainty associated with the estimated residual radionuclide activity that is calculated for the FMB, PB, and SC IOUs. Two primary contributing factors to overall uncertainty of inventory estimates were identified and evaluated. The first related to the computation of the mass of contaminated material in a particular IOU compartment and the second to the uncertainty associated with analytical counting errors. The error ranges for the mass of contaminated material in each IOU compartment were all calculated to be approximately +/- 9.6%, or a nominal +/-10%. This nominal value was added to the uncertainty associated with the analytical counting errors that were associated with each radionuclide, individually. This total uncertainty was then used to calculate a maximum and minimum estimated radionuclide inventories for each IOU.

Hiergesell, R.; Phifer, M.

2014-04-29T23:59:59.000Z

343

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

344

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

345

Fixation of Radionuclides in Soil and Minerals by Heating  

Science Journals Connector (OSTI)

Four mineral materials (a quartz sand, a feldspar sand, a calcitic limestone, and one soil from the DOE Hanford reservation (see Supporting Information, Table SI-1, for elemental compositions and descriptions)) were investigated after spiking with one of four radionuclides (85Sr, 134Cs, 57Co, and depleted U); leachability tests of these spiked materials were performed after thermal treatments up to 1200 C using the detailed 15-step sequential extraction protocol (18). ... Previously, a similar relationship was observed following heating of naturally 90Sr -contaminated field soil from the Department of Energy's Oak Ridge Reservation within a similar range of submelting tempera tures (15) which observations were merely documented in this obscure programmatic report because we were unaware, at the time, of any mechanistic interpretation for the effect and failed to recognize its now clear implication for remediation technology; those observations (reproduced in the Supporting Information, Figure SI-31) should allay skeptical concerns that the immobilization effects reported herein result from some artifact of the isotopic spiking technique or sample preparations. ... Detailed descriptions of the gamma spectroscopic assay techniques and the sequential extraction procedures along with the elemental analyses of the mineral materials (Table SI-1) used throughout this investigation; sequential extraction graphs for 134Cs, 85Sr, 57Co, and U from quartz, feldspar, calcite, and the Hanford soil (Figures SI-1 through SI-16); preheating and reheating extraction results for 134Cs, 85Sr, and 57Co from the Hanford soil (Figures SI-17?SI-19); sequential extraction results for intermediate temperature treatments for all four isotopes in the Hanford soil (Figures SI-20?SI-23); sequential extract pHs for quartz, feldspar, limestone, and Hanford soil (Figures SI-24?SI-27); mineral weight retention after extrac tions (Table SI-2), radioisotope distribution following preheating and reheating of Hanford soil (Table SI-3), sequential extraction summaries (Table SI-4 and SI-5), and 90Sr leach ability from Oak Ridge soil following thermal treatment (Figure SI-28). ...

Brian P. Spalding

2001-10-05T23:59:59.000Z

346

Past and present levels of some radionuclides in fish from Bikini and Enewetak atolls  

SciTech Connect

Bikini and Enewetak were the sites in the Northern Marshall Islands that were used by the United States as testing grounds for nuclear devices between 1946 and 1958. The testing produced close-in fallout debris that was contaminated with different radionuclides and which entered the aquatic environment. The contaminated lagoon sediments became a reservoir and source term of manmade radionuclides for the resident marine organisms. This report contains a summary of all the available data on the concentrations of {sup 137}Cs {sup 60}Co and {sup 217}Bi in flesh samples of reef and pelagic fish collected from Bikini and Enewetak Atolls between 1964 and 1995. The selection of these three radionuclides for discussion is based on the fact that these are the only radionuclides that have been routinely detected by gamma spectrometry in flesh samples from all fish for the last 20 y. Flesh from fish is an important source of food in the Marshallese diet. These radionuclides along with the transuranic radionuclides and {sup 90}Sr contribute most of the small radiological dose from ingesting marine foods. Some basic relationships among concentrations in different tissues and organs are discussed. The reef fish can be used as indicator species because their body burden is derived from feeding, over a lifetime, within a relatively small contaminated area of the lagoon. Therefore, the emphasis of this report is to use this extensive and unique concentration data base to describe the effective half lives and cycling for the radionuclides in the marine environments during the 31-y period between 1964 and 1995. 26 refs., 4 figs., 5 tabs.

Noshkin, V.E.; Robison, W.L.; Brunk, J.L. [Lawrence Livermore National Lab., CA (United States)] [and others

1997-07-01T23:59:59.000Z

347

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

348

Outdoor Laboratory Water System Clemson, SC  

E-Print Network (OSTI)

show about it, and other things you should know about drinking water. The U.S. Environmental Protection Agency (EPA) and the S.C. Department of Health and Environmental Control have strict standards for all the results of our water-quality analyses. Every regulated contaminant that was detected in the water, even

Duchowski, Andrew T.

349

Outdoor Laboratory Water System Clemson, SC  

E-Print Network (OSTI)

show about it, and other things you should know about drinking water. The U.S. Environmental Protection Agency (EPA) and the S.C. Department of Health and Environmental Control have strict standards for all of our water-quality analyses. Every regulated contaminant that was detected in the water, even

Duchowski, Andrew T.

350

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

351

Making Sustainable Energy Choices: Insights on the Energy/Water...  

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

complex web of connections, or nexus, between energy, water, and land. Economics, energy markets and policies, system performance, environmental regulations, carbon emissions, and...

352

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

353

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.

354

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

355

July 2010 Natural Gas and Produced Water Sampling at the Gasbuggy, New Mexico, Site  

SciTech Connect

Annual natural gas and produced water monitoring was conducted for gas wells adjacent to Section 36, where the Gasbuggy test was conducted, in accordance with the draft Long-Term Surveillance and Maintenance Plan for the Gasbuggy Site, Rio Arriba County, New Mexico. Sampling and analysis was conducted as specified in the Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites. (LMS/PLN/S04351, continually updated). Natural gas samples were collected for tritium and carbon-14 analysis. Produced water samples were collected and analyzed for tritium, gamma-emitting radionuclides (by high-resolution gamma spectrometry), gross alpha, and gross beta. An additional water sample was collected from well 29-6 Water Hole for analysis of tritium and gamma-emitting radionuclides. A duplicate produced water sample was collected from well 30-039-21743.

None

2011-01-01T23:59:59.000Z

356

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

SciTech Connect

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

357

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

358

Computer Use Regulation Introduction  

E-Print Network (OSTI)

Computer Use Regulation #12;Introduction · The following training materials will reference the contents of the Computer Use Regulations, but should not serve as a substitute for reading the actual responsibilities NCSU employees have under the regulations. · North Carolina State University's computer networks

Liu, Paul

359

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

360

Plant phytotoxicity: A self-regulating pathway  

SciTech Connect

During the session on regulating sludge utilization, held at BioCycle's 19th Annual National conference on Composting and Recycling, a participant asked one of the speakers, Dr. Alan Rubin of the US EPA's Office of Water Regulations and Standards, why the plant phytotoxicity pathway should be the most limiting, especially when there is no concern about human or animal health. The question related specifically to copper being the most limiting metal concentration limit for many sludge composting and land application programs under the proposed Part 503 regulations. And the most limiting pathway for copper is Pathway 7, sludge-soil-plant phytotoxicity. Rubin responded that the regulation is supposed to protect both human health and the environment, e.g. plants and animals other than humans.

Not Available

1989-07-01T23:59:59.000Z

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

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

362

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 , "

363

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

SciTech Connect

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

364

Radioanalytical technology for 10 CFR Part 61 and other selected radionuclides: Literature review  

SciTech Connect

A comprehensive literature review and assessment was conducted to identify and evaluate radioanalytical technology and procedures used for measuring 10CFR61 radionuclides and other long-lived isotopes. This review evaluated radiochemical procedures currently in use at a number of laboratories in the US, as well as identifying new advanced methods and techniques which could be adapted for routine radiochemical analyses of low-level radioactive waste. The 10CFR61 radionuclides include {sup 14}C, {sup 60}Cl, {sup 59,63}Ni, {sup 90}Sr, {sup 94}Nb, {sup 99}Tc, {sup 129}I, {sup 137}Cs, and TRU isotopes with half lives greater than 5 years. Other low-level radionuclides of interest include {sup 7,10}Be, {sup 26}Al, {sup 36}Cl, {sup 93}Mo, {sup 109,113m}Cd, and {sup 121m,126}Sn, which may be present in various types of waste streams from nuclear power stations.

Thomas, C.W.; Thomas, V.W.; Robertson, D.E. [Pacific Northwest National Lab., Richland, WA (United States)

1996-03-01T23:59:59.000Z

365

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

SciTech Connect

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

366

Interim Report: CHEMICAL SPECIES OF MIGRATING RADIONUCLIDES AT COMMERCIAL SHALLOW LAND BURIAL SITES  

SciTech Connect

This is the first quarterly report for .the project "Chemical Species of Migrating Radionuclides at Commercial Shallow Land Burial Site" under the new reporting schedule requested by the sponsor. Future reports will be issued following each fiscal quarter, with the next report scheduled in October, 1982. The primary purpose of this project is to develop an understanding of the processes responsible for radionuclide migration at low-level waste burial sites. Chemical measurements of waste trench leachate and identification of chemical changes in leachate during migration will provide a basis for geochemical waste transport models. This project will produce for the U.S. Nuclear Regulatory Commission information to support guidance for implementation of 10 CFR 61, particularly in the development of criteria for low level waste disposal site selection, management, permanent closure and monitoring. Topics covered include: Experimental Trench and Well Study; Chemical Species Characterization; Specific Radionuclide Mapping; Organic Complexing Compounds,

Kirby,, L. J.; Rickard,, W. H.; Toste,, A. P.

1982-08-01T23:59:59.000Z

367

Ground-water contribution to dose from past Hanford Operations. Hanford Environmental Dose Reconstruction Project  

SciTech Connect

The Hanford Environmental Dose Reconstruction (HEDR) Project is being conducted to estimate radiation doses that populations and individuals could have received from Hanford Site operations from 1944 to the present. Four possible pathways by which radionuclides migrating in ground water on the Hanford Site could have reached the public have been identified: (1) through contaminated ground water migrating to the Columbia River; (2) through wells on or adjacent to the Hanford Site; (3) through wells next to the Columbia River downstream of Hanford that draw some or all of their water from the river (riparian wells); and (4) through atmospheric deposition resulting in contamination of a small watershed that, in turn, results in contamination of a shallow well or spring by transport in the ground water. These four pathways make up the ``ground-water pathway,`` which is the subject of this study. Assessment of the ground-water pathway was performed by (1) reviewing the existing extensive literature on ground water and ground-water monitoring at Hanford and (2) performing calculations to estimate radionuclide concentrations where no monitoring data were collected. Radiation doses that would result from exposure to these radionuclides were calculated.

Freshley, M.D.; Thorne, P.D.

1992-08-01T23:59:59.000Z

368

University of Arizona Water Sustainability Program Conservation Easement Monitoring  

E-Print Network (OSTI)

and ranches as the single greatest threat to wildlife habitat, water supply and the long-term viability regulation of hydrological flows, storage and retention of water, and waste treatment and detoxification

Fay, Noah

369

www.VadoseZoneJournal.org Simula on of Radionuclide  

E-Print Network (OSTI)

: Applica on to Yucca Mountain, Nevada This paper describes the numerical methods developed to simulate at the Yucca Mountain. Regardless of the disposi on of the Yucca Mountain License Applica on, this method has to the water table through the unsaturated zone for the Yucca Mountain system. Abbrevia ons: ADE, advec on

Lu, Zhiming

370

Load regulating expansion fixture  

DOE Patents (OSTI)

A free standing self contained device for bonding ultra thin metallic films, such as 0.001 inch beryllium foils is disclosed. The device will regulate to a predetermined load for solid state bonding when heated to a bonding temperature. The device includes a load regulating feature, whereby the expansion stresses generated for bonding are regulated and self adjusting. The load regulator comprises a pair of friction isolators with a plurality of annealed copper members located therebetween. The device, with the load regulator, will adjust to and maintain a stress level needed to successfully and economically complete a leak tight bond without damaging thin foils or other delicate components. 1 fig.

Wagner, L.M.; Strum, M.J.

1998-12-15T23:59:59.000Z

371

Load regulating expansion fixture  

DOE Patents (OSTI)

A free standing self contained device for bonding ultra thin metallic films, such as 0.001 inch beryllium foils. The device will regulate to a predetermined load for solid state bonding when heated to a bonding temperature. The device includes a load regulating feature, whereby the expansion stresses generated for bonding are regulated and self adjusting. The load regulator comprises a pair of friction isolators with a plurality of annealed copper members located therebetween. The device, with the load regulator, will adjust to and maintain a stress level needed to successfully and economically complete a leak tight bond without damaging thin foils or other delicate components.

Wagner, Lawrence M. (San Jose, CA); Strum, Michael J. (San Jose, CA)

1998-01-01T23:59:59.000Z

372

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  

SciTech Connect

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

373

Surface Coal Mining Regulations (Mississippi) | Department of Energy  

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

Surface Coal Mining Regulations (Mississippi) Surface Coal Mining Regulations (Mississippi) Surface Coal Mining Regulations (Mississippi) < Back Eligibility Commercial Construction Developer Industrial Utility Program Info State Mississippi Program Type Environmental Regulations Siting and Permitting Provider Mississippi Department of Environmental Quality The Surface Coal Mining Regulations are a combination of permitting requirements and environmental regulations that limit how, where and when coal can be mined. It protects lands that are under special regulation due to their nature, and applies only to state lands. When applied to Coal with Carbon Capture and Storage projects the rules that would apply to a normal coal-mining project still apply. In addition to these measures, a CCS plant would need to adhere to all waste disposal requirements, water usage

374

MODELING OF THE THERMOHYDRODYNAMIC AND REACTIVE BEHAVIOR OF COMPACTED CLAY FOR HIGH-LEVEL RADIONUCLIDE WASTE-MANAGEMENT SYSTEMS  

Science Journals Connector (OSTI)

...proposed as an engineered-buffer material in high-level radionuclide...regarding the stability of benonite backfill in a high-level (HLW) repository...pp. Lide, D.R. (1997) Handbook of Chemistry and Physics...proposed as an engineered-buffer material in high-level radionuclide...

Ricardo Juncosa; Vicente Navarro; Jordi Delgado; Ana Vzquez

375

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

376

Comparison of predicted ground-level airborne radionuclide concentrations to measured values resulting from operation of the Los Alamos Meson Physics Facility  

E-Print Network (OSTI)

A comparison study of measured and predicted downwind radionuclide concentrations from the Los Alamos Meson Physics Facility (LAMPF) was performed. The radionuclide emissions consist primarily of the radioisotopes "C, 'IN, and 110. The gases...

Hoak, William Vandergrift

2012-06-07T23:59:59.000Z

377

Water Electrolysis  

Science Journals Connector (OSTI)

In this chapter, water electrolysis technology and its applications for nuclear hydrogen ... of the chapter, a general classification of water electrolysis systems is given, the fundamentals of water electrolysis

Greg F. Naterer; Ibrahim Dincer

2013-01-01T23:59:59.000Z

378

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

379

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

380

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

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

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 Energys (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/ref

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

2014-05-01T23:59:59.000Z

382

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

383

Public Versus Private: Does It Matter for Water Conservation? Insights from California  

E-Print Network (OSTI)

driver of water management was the environmental regulatorss Urban Water Sector. Environmental Management 41(6):863877Environmental Economics and Management 40(1):3755 Savedoff WD, Spiller PT (1999) Spilled water:

Kallis, Giorgos; Ray, Isha; Fulton, Julian; McMahon, James E.

2010-01-01T23:59:59.000Z

384

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,

385

May 2013 Groundwater and Surface Water Sampling at the Rio Blanco, Colorado, Site (Data Validation Package)  

SciTech Connect

Annual sampling was conducted at the Rio Blanco, Colorado, site for the Long-Term Hydrologic Monitoring Program May 14-16, 2013, to monitor groundwater and surface water for potential radionuclide contamination. Sampling and analyses were conducted as specified in Sampling and Analysis Plan for the U.S. Department of Energy Office of Legacy Management Sites (LMS/PRO/S04351, continually updated). A duplicate sample was collected from location CER #1 Black Sulphur. Samples were analyzed for gamma-emitting radionuclides by high-resolution gamma spectrometry and for tritium using the conventional and enrichment methods.

None

2013-10-01T23:59:59.000Z

386

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

387

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:

388

Gas and Electric Utilities Regulation (South Dakota) | Department of Energy  

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

Gas and Electric Utilities Regulation (South Dakota) Gas and Electric Utilities Regulation (South Dakota) Gas and Electric Utilities Regulation (South Dakota) < Back Eligibility Utility Commercial Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Installer/Contractor Rural Electric Cooperative Tribal Government Retail Supplier Institutional Systems Integrator Fuel Distributor Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State South Dakota Program Type Generation Disclosure Provider South Dakota Public Utilities Commission This legislation contains provisions for gas and electric utilities. As part of these regulations, electric utilities are required to file with the

389

Nonhazardous Solid Waste Management Regulations and Criteria (Mississippi)  

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

Nonhazardous Solid Waste Management Regulations and Criteria Nonhazardous Solid Waste Management Regulations and Criteria (Mississippi) Nonhazardous Solid Waste Management Regulations and Criteria (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

390

Pressure reducing regulator  

DOE Patents (OSTI)

A pressure reducing regulator that controls its downstream or outlet pressure to a fixed fraction of its upstream or inlet pressure is disclosed. The regulator includes a housing which may be of a titanium alloy, within which is located a seal or gasket at the outlet end which may be made of annealed copper, a rod, and piston, each of which may be made of high density graphite. The regulator is insensitive to temperature by virtue of being without a spring or gas sealed behind a diaphragm, and provides a reference for a system in which it is being used. The rod and piston of the regulator are constructed, for example, to have a 1/20 ratio such that when the downstream pressure is less than 1/20 of the upstream pressure the regulator opens and when the downstream pressure exceeds 1/20 of the upstream pressure the regulator closes. 10 figs.

Whitehead, J.C.; Dilgard, L.W.

1995-10-10T23:59:59.000Z

391

TOWARD MORE EFFECTIVE REGULATION  

SciTech Connect

This paper proposes a model relationship between the operator engaged in a hazardous activity, the regulator of that activity, and the general public. The roles and responsibilities of each entity are described in a way that allows effective communication flow. The role of the regulator is developed using the steam boiler as an example of a hazard subject to regulation; however, the model applies to any regulated activity. In this model the safety analyst has the extremely important role of communicating sometimes difficult technical information to the regulator in a way that the regulator can provide credible assurance to the general public as to the adequacy of the control of the hazardous activity. The conclusion asserts that acceptance of the model, understanding of the roles and responsibilities and definition of who communicates what information to whom will mitigate frustration on the part of each of the three entities.

J. GRAF

2000-06-01T23:59:59.000Z

392

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

393

The Role of Dispersion in Radionuclide Transport - Data and Modeling Requirements: Revision No. 1  

SciTech Connect

This document is the collaborative effort of the members of an ad hoc subcommittee of the Underground Test Area Project Technical Working Group. This subcommittee was to answer questions and concerns raised by the Nevada Division of Environmental Protection to the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, regarding Pahute Mesa Corrective Action Units (CAUs) 101 and 102. The document attempts to synthesize the combined comments made by each member of this subcommittee into insights made in the role of dispersion in radionuclide transport data and modeling. Dispersion is one of many processes that control the concentration of radionuclides in groundwater beneath the Nevada Test Site where CAUs 101 and 102 are located. In order to understand the role of dispersion in radionuclide transport, there is a critical need for CAU- or site-specific data related to transport parameters which is currently lacking, particularly in the case of Western a nd Central Pahute Mesa. The purpose of this technical basis document is to: (1) define dispersion and its role in contaminant transport, (2) present a synopsis of field-scale dispersion measurements, (3) provide a literature review of theories to explain field-scale dispersion, (4) suggest approaches to account for dispersion in CAU-scale radionuclide modeling, and (5) to determine if additional dispersion measurements should be made at this time.

Stoller-Navarro Joint Venture

2004-02-01T23:59:59.000Z

394

Radionuclide neutron sources in calibration laboratoryneutron and gamma doses and their changes in time  

Science Journals Connector (OSTI)

......oxfordjournals.org August 2007 research-article POSTER Presentations Radionuclide neutron sources in calibration...This work was partially supported by the Ministry of Science and Higher Education of Poland; grant No 2P05 D06530. REFERENCES 1 ISO......

K. Jzefowicz; N. Golnik; P. Tulik; M. Zielczynski

2007-08-01T23:59:59.000Z

395

Estimates of internal-dose equivalent from inhalation and ingestion of selected radionuclides  

SciTech Connect

This report presents internal radiation dose conversion factors for radionuclides of interest in environmental assessments of nuclear fuel cycles. This volume provides an updated summary of estimates of committed dose equivalent for radionuclides considered in three previous Oak Ridge National Laboratory (ORNL) reports. Intakes by inhalation and ingestion are considered. The International Commission on Radiological Protection (ICRP) Task Group Lung Model has been used to simulate the deposition and retention of particulate matter in the respiratory tract. Results corresponding to activity median aerodynamic diameters (AMAD) of 0.3, 1.0, and 5.0 ..mu..m are given. The gastorintestinal (GI) tract has been represented by a four-segment catenary model with exponential transfer of radioactivity from one segment to the next. Retention of radionuclides in systemic organs is characterized by linear combinations of decaying exponential functions, recommended in ICRP Publication 30. The first-year annual dose rate, maximum annual dose rate, and fifty-year dose commitment per microcurie intake of each radionuclide is given for selected target organs and the effective dose equivalent. These estimates include contributions from specified source organs plus the systemic activity residing in the rest of the body; cross irradiation due to penetrating radiations has been incorporated into these estimates. 15 references.

Dunning, D.E.

1982-01-01T23:59:59.000Z

396

National Low-Level Waste Management Program radionuclide report series. Volume 13, Curium-242  

SciTech Connect

This report, Volume 13 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of curium-242 ({sup 242}Cm). This report also includes discussions about waste types and forms in which {sup 242}Cm can be found and {sup 242}Cm behavior in the environment and in the human body.

Adams, J.P.

1995-08-01T23:59:59.000Z

397

An extremely radioresistant green eukaryote for radionuclide bio-decontamination in the nuclear  

E-Print Network (OSTI)

An extremely radioresistant green eukaryote for radionuclide bio-decontamination in the nuclear Blignyabcd Nuclear activities generate radioactive elements which require processes for their decontamination of an extremophile autotrophic eukaryote, Coccomyxa actinabiotis nov. sp., that we isolated from a nuclear facility

Boyer, Edmond

398

Transport of fallout and reactor radionuclides in the drainage basin of the Hudson River estuary  

SciTech Connect

The transport and fate of Strontium 90, Cesium 137 and Plutonium 239, 240 in the Hudson River Estuary is discussed. Rates of radionuclide deposition and accumulation over time and space are calculated for the Hudson River watershed, estuary, and continental shelf offshore. 37 references, 7 figures, 15 tables. (ACR)

Simpson, H.J.; Linsalata, P.; Olsen, C.R.

1982-01-01T23:59:59.000Z

399

Sr radionuclide in cement: An atomistic modeling study Mostafa Youssef a  

E-Print Network (OSTI)

: Available online xxxx Keywords: Molecular simulation Cement Nuclear waste storage Mechanical properties a b the interaction of each radionuclide with the cement matrix. Understanding on a fundamental level the long-term s t r a c t Cementitious materials are considered to be a waste form for the ultimate disposal

Yildiz, Bilge

400

National Low-Level Waste Management Program Radionuclide Report Series, Volume 17: Plutonium-239  

SciTech Connect

This report, Volume 17 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of plutonium-239 (Pu-239). This report also discusses waste types and forms in which Pu-239 can be found, waste and disposal information on Pu-239, and Pu-239 behavior in the environment and in the human body.

J. P. Adams; M. L. Carboneau

1999-03-01T23:59:59.000Z

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

Mapping subsurface radionuclide migration and groundwater flow with organic tracers. [Shallow-land burial  

SciTech Connect

At Pacific Northwest Laboratory we have had the opportunity to study the subsurface migration of radionuclides at the Maxey Flats burial site. We constructed an experimental study area adjacent to one of the waste-filled trenches at the site. In this report we describe some preliminary results of organic research currently underway at Maxey Flats. This research is aimed at: (1) elucidating the role of organic species in the subsurface migration of radionuclides; and (2) testing the usefulness of artificial and in situ organic groundwater tracers for mapping radionuclide migration and groundwater flow. We also describe two analytical procedures developed for this research. First, as part of a survey study of organics in Maxey Flats groundwater we have developed a procedure for the isolation and characterization of trace levels of organics in radioactive groundwaters. Second, for a detailed chemical speciation study we developed a procedure based on steric exclusion chromatography for testing whether or not organics are chelated to radionuclides. 1 figure, 1 table.

Toste, A.P.; Kirby, L.J.; Pahl, T.R.; Myers, R.B.

1983-10-01T23:59:59.000Z

402

Gamma-emitting radionuclides in the shallow marine sediments off the Sindh coast, Arabian Sea  

Science Journals Connector (OSTI)

......radionuclides in marine constituents (i.e. seawater, sea sediments and marine organisms...have monitored radioactivity levels in seawater, suspended sediments, sea bottom sediments...Lighthouse 66.9925 24.8056 S3C Near oil storage tanks 66.9900 24.8103 S3D Near Oyster......

M. Akram; Riffat M. Qureshi; Nasir Ahmad; Tariq Jamal Solaija

2006-07-01T23:59:59.000Z

403

DETERMINATION OF REPORTABLE RADIONUCLIDES FOR DWPF SLUDGE BATCH 4 MACROBATCH 5  

SciTech Connect

The Waste Acceptance Product Specifications (WAPS)1 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 meet 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)2 and Waste Form Qualification Report (WQR)3. 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 previous contents of Tank 40 (Sludge Batch 3) and the sludge that was transferred to Tank 40 from Tank 51. The blend of sludge from Tank 51 and Tank 40 defines Sludge Batch 4 (also referred to as Macrobatch 5 (MB5)). 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 Task Technical Request HLW/DWPF/TTR-2005-0034; Rev. 0 entitled Sludge Batch 4 SRNL Shielded Cells Testing4. Specifically, this report details results from performing, in part, Subtask 3 of the TTR and, in part, meets Deliverable 7 of the TTR. The work was performed following the Technical Task and Quality Assurance Plan (TTQAP), WSRC-RP-2006-00310, Rev. 15 and Analytical Study Plan (ASP), WSRC-RP-2006-00458, Rev. 16. In order to determine the reportable radionuclides for Sludge Batch 4 (SB4) (Macro Batch 5 (MB5)), 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-nine radionuclides have been identified as reportable for DWPF SB4 (MB5) as specified by WAPS 1.2. The 29 reportable nuclides are: Ni-59; Ni-63; Se-79; 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; Cm-247; Bk-247; Cm-248; and Cf-251. 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 SB4 (MB5), 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 through the calendar 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 the list of reportable radionuclides in order to meet WAPS 1.6. All of the Pu isotopes and other U isoto

Bannochie, C; Ned Bibler, N; David Diprete, D

2008-05-30T23:59:59.000Z

404

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

SciTech Connect

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

405

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

406

Aerobic uranium (VI) bioprecipitation by metal-resistant bacteria isolated from radionuclide-  

E-Print Network (OSTI)

Aerobic uranium (VI) bioprecipitation by metal-resistant bacteria isolated from radionuclide uranium [U(VI)] mediated by the intrinsic phosphatase acti- vities of naturally occurring bacteria leaks occur, these wastes come into contact with surrounding geologic media, allowing for migration

Skolnick, Jeff

407

Economic Costs & Adaptations for Alternative Delta Regulations: Appendix F  

E-Print Network (OSTI)

­ Wastewater reuse ­ Seawater desalination ­ Water markets Optimized for statewide economic benefits Highly1 Economic Costs & Adaptations for Alternative Delta Regulations: Appendix F Stacy Tanaka Economic effects of reducing water exports Effects of increasing net Delta outflows Comparisons of Delta

Pasternack, Gregory B.

408

Tidal Wetlands Regulations (Connecticut)  

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

Most activities occurring in or near tidal wetlands are regulated, and this section contains information on such activities and required permit applications for proposed activities. Applications...

409

Air-Quality Regulations  

Science Journals Connector (OSTI)

n...Federal, state and/or local regulations constructed for the purpose of protecting air quality, e.g., low volatile organic compounds...

Jan W. Gooch

2011-01-01T23:59:59.000Z

410

Air-quality regulations  

Science Journals Connector (OSTI)

n....Federal, state and/or local regulations constructed for the purpose of protecting air quality, e.g., low volatile organic compounds...

2007-01-01T23:59:59.000Z

411

Transport and transfer rates in the waters of the continental shelf. Annual report  

SciTech Connect

The goal of govern project is to understand and quantify the processes that the transport and dispersal of energy-related pollutants introduced to the waters of the continental shelf and slope. The report is divided into sections dealing with processes associated with suspended solids; processes associated with sediments sinks for radionuclides and other pollutants; and spreading of water characteristics and species in solution. (ACR)

Biscaye, P.E.

1980-09-01T23:59:59.000Z

412

The effect of gravel size fraction on the distribution coefficients of selected radionuclides  

SciTech Connect

This manuscript addresses the consequences of the common practice of assuming that the gravel fraction of sediments does not participate in sorption reactions and thus sorption quantified by the distribution coefficient (Kd) construct can be estimated from laboratory tests on sediments less than 2 mm size fraction. However, this common assumption can lead to inaccurate estimates of the mobility and sorption affinity of many radionuclides (e.g., Tc, U, and Np) on gravel dominated sediments at the Hanford Site and other locations. Laboratory batch sorption experiments showed that the distribution coefficients measured using only sediment less than 2 mm size fraction and correcting for inert gravel fraction were not in agreement with those obtained from the bulk sediments including gravel (larger than 2 mm size fraction), depending on the radionuclide. The least reactive radionuclide, Tc had Kd values for bulk sediment with negligible deviations from the inert gravel corrected Kd values measured on less than 2 mm size fraction. However, differences between measured Kd values using sediment less than 2 mm size fraction and the Kd values on the bulk sediment were significant for intermediately and strongly reactive radionuclides such as U and Np, especially on the sediment with gravel fractions that contained highly reactive sites. Highly reactive sites in the gravel fraction were attributed to the presence of Fe oxide coatings and/or reactive fracture faces on the gravel surfaces. Gravel correction factors that use the sum of the Kd,<2 mm and Kd,>2 mm values to estimate the Kd for the bulk sediment were found to best describe Kd values for radionuclides on the bulk sediment. Gravel correction factors should not be neglected to predict precisely the sorption capacity of the bulk sediments that contain more than 30% gravel. In addition, more detailed characterization of gravel surfaces should be conducted to identify whether higher reactive sorbents are present in the gravels.

Um, Wooyong; Serne, R. Jeffrey; Last, George V.; Clayton, Ray E.; Glossbrenner, Ellwood T.

2009-06-26T23:59:59.000Z

413

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

414

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

415

Watershed management: Clean water`s next act  

SciTech Connect

14 articles related to watershed management comprise this special advertising section of the Association of Metropolitan Sewerage Agencies. Subtopics include water quality, regulations, US Environmental Protection Agency activities, analysis tools, economics, flooding and erosions, and non-point source pollutions. Articles on arid and coastal are included. Several articles describe municipal watershed programs being planned or in place.

Hite, R.W. [Metro Wastewater Reclamation District, Denver, CO (United States)

1996-09-23T23:59:59.000Z

416

Uncharted Waters? The Future of the Electricity-Water Nexus  

Science Journals Connector (OSTI)

Electricity generation often requires large amounts of water, most notably for cooling thermoelectric power generators and moving hydroelectric turbines. ... The five variables identified include changes in 1) fuel consumption patterns, 2) cooling technology preferences, 3) environmental regulations, 4) ambient climate conditions, and 5) electric grid characteristics. ...

Kelly T. Sanders

2014-12-08T23:59:59.000Z

417

Marketing water  

E-Print Network (OSTI)

management, water conservation programs Story by Kathy Wythe tx H2O | pg. 17 public information programs and materials that increase awareness about regional water issues. The company recently opened the TecH2O, a water resource learning center...tx H2O | pg. 16 W ith rapid population growth and the memory of the worst drought in 50 years, cities and groups are promoting programs that educate their constituents about water quality, water conservation, and landscape management. Many...

Wythe, Kathy

2008-01-01T23:59:59.000Z

418

Recommendations to the Technical Steering Panel regarding approach for estimating individual radiation doses resulting from releases of radionuclides to the Columbia River  

SciTech Connect

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

419

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  

SciTech Connect

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

420

Ground Water Management Act (Virginia) | Department of Energy  

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

Ground Water Management Act (Virginia) Ground Water Management Act (Virginia) Ground Water Management Act (Virginia) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Municipal/Public Utility Nonprofit Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Tribal Government Utility Savings Category Water Buying & Making Electricity Home Weatherization Program Info State Virginia Program Type Environmental Regulations Siting and Permitting Provider Virginia Department of Environmental Quality Under the Ground Water Management Act of 1992, Virginia manages ground water through a program regulating the withdrawals in certain areas called

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.


421

Solid Waste Regulation No. 8 - Solid Waste Composting Facilities (Rhode  

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

Regulation No. 8 - Solid Waste Composting Facilities Regulation No. 8 - Solid Waste Composting Facilities (Rhode Island) Solid Waste Regulation No. 8 - Solid Waste Composting Facilities (Rhode Island) < Back Eligibility Commercial Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Program Info State Rhode Island Program Type Environmental Regulations Provider Department of Environmental Management Facilities which compost putrescible waste and/or leaf and yard waste are subject to these regulations. The regulations establish permitting, registration, and operational requirements for composting facilities. Operational requirements for putrescible waste facilities include siting, distance, and buffer requirements, as well as standards for avoiding harm to endangered species and contamination of air and water sources. Specific

422

Water Use Registration and Allocation (North Carolina) | Department of  

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

Use Registration and Allocation (North Carolina) Use Registration and Allocation (North Carolina) Water Use Registration and Allocation (North Carolina) < Back Eligibility Commercial Industrial Construction Transportation Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State North Carolina Program Type Siting and Permitting Provider Department of Environment and Natural Resources This rule states regulations for water withdrawals, permits required for withdrawals and water use during water droughts and emergencies. Self-supplied business and industrial water users subject to the water withdrawal registration shall prepare a written plan, for responding to water shortages that is consistent with industry water efficiency and

423

Determination of Reportable Radionuclides for DWPF Sludge Batch 3 (Macrobatch 4)  

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 meet 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 meet the greater than 0.01% criterion for Curie content. Specification 1.6 of the WAPS, IAEA Safeguards Reporting for 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 Defense Waste Processing Facility (DWPF) is receiving radioactive sludge slurry from High Level Waste Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the previous contents of Tank 40 (Sludge Batch 2) and the sludge that was transferred to Tank 40 from Tank 51. The blend of sludge from Tank 51 and Tank 40 defines Macrobatch 4 (also referred to as Sludge Batch 3). 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 radionuclide inventory. This work was initiated through Task Technical Request HLW/DWPF/TTR-03-0005, Revision 1 entitled Sludge Batch 3 SRTC Shielded Cells Testing. Specifically, this report details results from performing, in part, Subtask 3 of the TTR and, in part, meets Deliverable 6 of the TTR. The work was performed following the Technical Task and Quality Assurance Plan (TTQAP), WSRC-RP-2003-00249, Rev. 1 and Analytical Study Plan (ASP), WSRC-RP-2004-00262. In order to determine the reportable radionuclides for Sludge Batch 3 (Macro Batch 4), 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.

Bannochie, C

2005-05-01T23:59:59.000Z

424

Training for how to ship `excepted quantities' of regulated chemicals Addendum 1 to the Shipping Biological Materials Quick Reference Guide  

E-Print Network (OSTI)

hazardous chemicals, i.e. food and water samples Ethanol solutions 24% v/v International - not regulated solutions ethanol solutions 24% v/v Domestic - ground

California at Irvine, University of

425

Surface and subsurface cleanup protocol for radionuclides Gunnison, Colorado, UMTRA Project Processing Site. Revision 3, Final report  

SciTech Connect

The supplemental standards provisions of Title 40, Code of Federal Regulations, Part 192 (40 CFR Part 192) require the cleanup of radionuclides other than radium-226 (Ra-226) to levels ``as low as reasonably achievable`` (ALARA), taking into account site-specific conditions, if sufficient quantities and concentrations are present to constitute a significant radiation hazard. In this context, thorium-230 (Th-230) at the Gunnison, Colorado, processing site will require remediation. However, a seasonally fluctuating groundwater table at the site significantly complicates conventional remedial action with respect to cleanup. Characterization data indicate that in the offpile areas, the removal of residual in situ bulk Ra-226 and Th-230 such that the 1000-year projected Ra-226 concentration (Ra-226 concentration in 1000 years due to the decay of in situ Ra-226 and the in-growth of Ra-226 from in situ Th-230) complies with the US Environmental Protection Agency (EPA) cleanup standard for in situ Ra-226 and the cleanup protocol for in situ Th-230 can be readily achieved using conventional excavation techniques for bulk contamination without encountering significant impacts due to groundwater. The EPA cleanup standard and criterion for Ra-226 and the 1000-year projected Ra-226 are 5 and 15 picocuries per gram (pCi/g) above background, respectively, averaged over 15-centimeter (cm) deep surface and subsurface intervals and 100-square-meter (m{sup 2}) grid areas. Significant differential migration of Th-230 relative to Ra-226 has occurred over 40 percent of the subpile area. To effectively remediate the site with respect to Ra-226 and Th-230, supplemental standard is proposed and discussed in this report.

Not Available

1994-05-01T23:59:59.000Z

426

Clemson University Water System Clemson, SC  

E-Print Network (OSTI)

. The U.S. Environmental Protection Agency (EPA) and the S.C. Department of Health and Environmental the results of our water-quality analyses. Every regulated contaminant that was detected in the water, even of such contamination, footnotes explaining our findings, and a key to units of measurement. Definitions of MCL and MCLG

Duchowski, Andrew T.

427

Fant's Grove Water System Clemson, SC  

E-Print Network (OSTI)

.S. Environmental Protection Agency (EPA) and the S.C. Department of Health and Environmental Control have strict the results of our water-quality analyses. Every regulated contaminant that was detected in the water, even of such contamination, footnotes explaining our findings, and a key to units of measurement. Definitions of MCL and MCLG

Duchowski, Andrew T.

428

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

Open Energy Info (EERE)

GRR/Section 19-AK-a - Water Access and Water Rights Issues GRR/Section 19-AK-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-AK-a - Water Access and Water Rights Issues 19AKAWaterAccessWaterRights.pdf Click to View Fullscreen Contact Agencies Alaska Department of Natural Resources Alaska Division of Mining Land and Water Regulations & Policies Alaska Water Use Act Alaska Statutes Alaska Administrative Code Triggers None specified Click "Edit With Form" above to add content 19AKAWaterAccessWaterRights.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 In Alaska, water is declared a public resource belonging to the people of

429

GRR/Section 19-WA-d - Water Conservancy Board Transfer or Change of Water  

Open Energy Info (EERE)

19-WA-d - Water Conservancy Board Transfer or Change of Water 19-WA-d - Water Conservancy Board Transfer or Change of Water Right < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 19-WA-d - Water Conservancy Board Transfer or Change of Water Right 19-WA-d - Water Conservancy Board Transfer or Change of Water Right.pdf Click to View Fullscreen Contact Agencies Washington State Department of Ecology Regulations & Policies Revised Code of Washington Chapter 90.80 RCW 90.03.380 90.03.390 RCW 90.44.100 Triggers None specified In 1997, the Washington Legislature authorized the creation of water conservancy boards through the enactment of Revised Code of Washington Chapter 90.80 to expedite the administrative process for voluntary water right transfers within individual counties. In counties where a water

430

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

Open Energy Info (EERE)

9-WA-a - Water Access and Water Rights Overview 9-WA-a - Water Access and Water Rights Overview < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 19-WA-a - Water Access and Water Rights Overview 19-WA-a - Water Access and Water Rights Overview.pdf Click to View Fullscreen Contact Agencies Washington State Department of Ecology Regulations & Policies Revised Code of Washington Chapter 90.03 Revised Code of Washington Chapter 90.44 RCW 90.44.050 Triggers None specified Similar to many western states, only a small amount of water is available for appropriation in Washington. As a result, Washington has developed a comprehensive regulatory scheme for the distribution of water rights and use of water in the state. Washington employs a prior appropriation or

431

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

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

Ground Water (Indiana) Ground Water (Indiana) Water Rights: Ground Water (Indiana) < Back Eligibility Agricultural Commercial Construction Fed. Government Industrial Institutional Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative Schools State/Provincial Govt Tribal Government Utility Savings Category Water Buying & Making Electricity Home Weatherization Program Info State Indiana Program Type Environmental Regulations Provider Indiana Department of Natural Resources It is the policy of the state to provide for the conservation of groundwater resources and limit groundwater waste. The Indiana Department of Natural Resources may designate restricted use areas and limit groundwater withdrawals by existing users in those areas, thus making groundwater use greater than 100,000 gallons per day subject to permitting

432

Indiana State Regulations  

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

Indiana Indiana State Regulations: Indiana State of Indiana The Indiana Department of Natural Resources (DNR) Division of Oil and Gas regulates petroleum exploration, production, and site abandonment activities, underground injection control, test hole drilling, and geophysical surveying operations. Otherwise, the Indiana Department of Environmental Management (IDEM) administers the major environmental protection laws. Contact Division of Oil and Gas (Indianapolis Central Office) 402 West Washington Street, Room 293 Indianapolis, IN 46204 (317) 232-4055 (phone) (317) 232-1550 (fax) (Division Contacts) Indiana Department of Environmental Management P.O. Box 6015 Indianapolis, IN 46206-6015 (317) 232-8603 (phone) (317) 233-6647 (fax) Disposal Practices and Applicable Regulations