Plowshare radiation protection guidance

International Nuclear Information System (INIS)

Parker, H.M.

1969-01-01

The recommendations of the ICRP and the NCRP were developed primarily for occupational radiation exposures. They were later modified and applied to non-occupational exposures of populations. These, with appropriate interpretations, can be used to provide Plowshare radiation protection guidance. Exposures from Plowshare operations will tend to be acute, arising from radionuclides of relatively short half-life, but will have some chronic aspects due to small amounts of long-lived radionuclides generated. In addition, the neutron activation process of Plowshare technology will produce radionuclides not commonly encountered in routine nuclear energy programs. How these radionuclides contribute to personnel exposure is known for only a few situations that may not be representative of Plowshare exposure. Further complications arise from differences in radionuclide deposition and physiological sensitivity among individuals of different ages and states of health in the exposed population. All parameters necessary to evaluate such exposures are not available, even for good quantitative approximations, resulting in the need for interpretive experience. (author)

Plowshare radiation protection guidance

Energy Technology Data Exchange (ETDEWEB)

Parker, H M [Environmental and Life Sciences Division, Battelle Memorial Institute, Pacific Northwest Laboratory, Richland, WA (United States)

1969-07-01

The recommendations of the ICRP and the NCRP were developed primarily for occupational radiation exposures. They were later modified and applied to non-occupational exposures of populations. These, with appropriate interpretations, can be used to provide Plowshare radiation protection guidance. Exposures from Plowshare operations will tend to be acute, arising from radionuclides of relatively short half-life, but will have some chronic aspects due to small amounts of long-lived radionuclides generated. In addition, the neutron activation process of Plowshare technology will produce radionuclides not commonly encountered in routine nuclear energy programs. How these radionuclides contribute to personnel exposure is known for only a few situations that may not be representative of Plowshare exposure. Further complications arise from differences in radionuclide deposition and physiological sensitivity among individuals of different ages and states of health in the exposed population. All parameters necessary to evaluate such exposures are not available, even for good quantitative approximations, resulting in the need for interpretive experience. (author)

Applicability of federal and state environmental requirements to selected DOE field installations and recommendations for development of generic compliance guidance. Final report

International Nuclear Information System (INIS)

1982-01-01

This final report identifies and describes federal and state environmental requirements applicable to selected Department of Energy (DOE) nuclear field installations, establishes priorities for the requirements, determines the need for development of additional compliance guidance, and recommends development of compliance guidance for specific priority requirements. Compliance guidance developed as part of the study is summarized. The applicability of environmental requirements to 12 DOE field installations was reviewed. Five installations were examined under Task 4. They are: Nevada Test Site; Lawrence Berkeley Laboratory; Paducah Gaseous Diffusion Plant; Oak Ridge Y-12 Plant; and Los Alamos Scientific Laboratory. Seven other installations were reviewed under Task 2 and included: Idaho National Engineering Laboratory; Hanford; Savannah River Plant; Oak Ridge Gaseous Diffusion Plant; Pantex Plant; Rocky Flats Plant; and Lawrence Livermore Laboratory. This report combines results of the two tasks. The objective of the study was to identify the set of environmental requirements which are applicable to DOE field installations, track changes in the requirements, and prepare compliance guidance for important requirements and important regulatory developments as necessary. A cumulative calendar update for July 1982 represents the current status of applicable requirements. Environmental profiles of each facility, along with ambient monitoring results, are presented. Applicable federal requirements are identified. The specific applicability of federal and state requirements is detailed for each installation. Compliance guidance available from various agencies is described. Each requirement described is ranked by priority, and recommendations are made for development of additional guidance

Soiled-based uranium disequilibrium and mixed uranium-thorium series radionuclide reference materials

International Nuclear Information System (INIS)

Donivan, S.; Chessmore, R.

1988-12-01

The US Department of Energy (DOE) Office of Remedial Action and Waste Technology has assigned the Technical Measurements Center (TMC), located at the DOE Grand Junction Colorado, Projects Office and operated by UNC Geotech (UNC), the task of supporting ongoing remedial action programs by providing both technical guidance and assistance in making the various measurements required in all phases of remedial action work. Pursuant to this task, the Technical Measurements Center prepared two sets of radionuclide reference materials for use by remedial action contractors and cognizant federal and state agencies. A total of six reference materials, two sets comprising three reference materials each, were prepared with varying concentrations of radionuclides using mill tailings materials, ores, and a river-bottom soil diluent. One set (disequilibrium set) contains varying amounts of uranium with nominal amounts of radium-226. The other set (mixed-nuclide set) contains varying amounts of uranium-238 and thorium-232 decay series nuclides. 14 refs., 10 tabs

76 FR 20686 - Draft Guidance for Industry on Safety Labeling Changes; Implementation of the Federal Food, Drug...

Science.gov (United States)

2011-04-13

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2011-D-0164] Draft Guidance for Industry on Safety Labeling Changes; Implementation of the Federal Food, Drug, and Cosmetic Act; Availability AGENCY: Food and Drug Administration, HHS. ACTION: Notice. SUMMARY: The Food and...

Practical Guidance on Peptide Receptor Radionuclide Therapy (PRRNT) for Neuroendocrine Tumours

International Nuclear Information System (INIS)

2013-01-01

Peptide receptor radionuclide therapy (PRRNT) using 90 Y-DOTATOC was first administered in 1996 in Basel, Switzerland, to a 40 year old patient with a gastroenteropancreatic neuroendocrine tumour (NET). The objective was to stabilize the progression of the tumour, which had proven refractory to conventional chemotherapy. The excellent subjective and objective responses after several treatment cycles prompted exhaustive pre-clinical and clinical research to explore the therapeutic potential of PRRNT for the treatment of NETs. Since then, PRRNT using 90 Y- or 177 Lu-DOTATOC has acquired wide acceptance and is now used in many medical centres in Europe and other parts of the world. NET is a unique subclass of cancer in which a good percentage of affected patients may experience disease control following several cycles of PRRNT, with improvement of symptoms and quality of life in the majority of cases. This book is a practical reference for specialists in clinical oncology and nuclear medicine embarking on deploying and executing a comprehensive programme for treating patients with NETs. It is part of a larger endeavour of the IAEA to enable medical centres in Member States to introduce therapeutic applications of unsealed radioisotopes in clinical routine practice. This publication provides comprehensive, multidisciplinary guidance on the use of PRRNT in order to enhance the effective, safe and standardized implementation of best practice for treating patients with NETs and gastroenteropancreatic cancers, with due regard to the recent international classifications of NETs. It provides comprehensive protocols for employing either 90 Y or 177 Lu tagged somatostatin receptor targeting peptides, as well as clinically assessed protocols for renal protection. It is a comprehensive compilation of clinically based evidence with input from experienced and renowned medical professionals in this field. The various sections cover clinical presentations, patient eligibility

Practical Guidance on Peptide Receptor Radionuclide Therapy (PRRNT) for Neuroendocrine Tumours

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-03-15

Peptide receptor radionuclide therapy (PRRNT) using {sup 90}Y-DOTATOC was first administered in 1996 in Basel, Switzerland, to a 40 year old patient with a gastroenteropancreatic neuroendocrine tumour (NET). The objective was to stabilize the progression of the tumour, which had proven refractory to conventional chemotherapy. The excellent subjective and objective responses after several treatment cycles prompted exhaustive pre-clinical and clinical research to explore the therapeutic potential of PRRNT for the treatment of NETs. Since then, PRRNT using {sup 90}Y- or {sup 177}Lu-DOTATOC has acquired wide acceptance and is now used in many medical centres in Europe and other parts of the world. NET is a unique subclass of cancer in which a good percentage of affected patients may experience disease control following several cycles of PRRNT, with improvement of symptoms and quality of life in the majority of cases. This book is a practical reference for specialists in clinical oncology and nuclear medicine embarking on deploying and executing a comprehensive programme for treating patients with NETs. It is part of a larger endeavour of the IAEA to enable medical centres in Member States to introduce therapeutic applications of unsealed radioisotopes in clinical routine practice. This publication provides comprehensive, multidisciplinary guidance on the use of PRRNT in order to enhance the effective, safe and standardized implementation of best practice for treating patients with NETs and gastroenteropancreatic cancers, with due regard to the recent international classifications of NETs. It provides comprehensive protocols for employing either {sup 90}Y or {sup 177}Lu tagged somatostatin receptor targeting peptides, as well as clinically assessed protocols for renal protection. It is a comprehensive compilation of clinically based evidence with input from experienced and renowned medical professionals in this field. The various sections cover clinical presentations

Significant Guidance Issued by the Federal Transit Administration

Data.gov (United States)

Department of Transportation — A list of Significant Guidance documents, which include guidance document disseminated to regulated entities or the general public that may reasonably be anticipated...

Significant Guidance Issued by the Federal Aviation Administration

Data.gov (United States)

Department of Transportation — A list of Significant Guidance documents, which include guidance document disseminated to regulated entities or the general public that may reasonably be anticipated...

Significant Guidance Issued by the Federal Highway Administration

Data.gov (United States)

Department of Transportation — A list of Significant Guidance documents, which include guidance document disseminated to regulated entities or the general public that may reasonably be anticipated...

Federal Transit Administration's noise and vibration Guidance Manual: Updates after 10 years of experience

Science.gov (United States)

Hanson, Carl E.

2005-09-01

In April 1995, the Federal Transit Administration of the U.S. Department of Transportation issued its guidance manual, ``Transit Noise and Vibration Impact Assessment.'' The manual was written to provide direction for the preparation of noise and vibration sections of environmental documents for public transportation projects in the interest of promoting quality and uniformity in assessments. In the 10 years since its release, the guidance manual has been used as the basis of noise and vibration assessments in over 80 environmental documents and has been used worldwide as a standard method for performing transit noise analyses. An updated version has recently been prepared that takes account of improvements in tools, changes in the environmental assessment procedures, modifications of impact criteria, and experience with mitigation measures. These factors, and other background information, will be discussed to provide insight regarding the revisions in the new edition.

Status report on radionuclide transfer

International Nuclear Information System (INIS)

1980-01-01

At the suggestion of the Federal Minstry of the Interior, in June 1978, a group of scientists from several institutions who are active in the field of radionuclide transfer or are interested in these problems got together. During the discussions of the work team, especially the transfer soil/plants was emphasized. Then the work team set up a status report on the transfer of the radionuclides relevant in the sense of the radiation protection act. The nuclides H 3 and C14, the isotopes of the Sr, J, and Cs, Tc99, the so-called corrosion nuclides Mn54, Fe59, co-isotopes and Zn65, and isotopes of Pu, Am, and Cm were regarded as important for a possible radiation exposition. Recent investigations revealed that also the natural radionuclides Ra226, Po210, and Pb210 should be covered by the investigations. The goal of this status report is to present the level of knowledge on the transfer of these radionuclides to man in a brief form, giving hints at the most important literature. It was requested by the Federal Ministry of the Interior, as fas as possible, to indicate transfer factors which are necessary for the radio-occology act to be decreed according to Para. 45 of the radiation protection act. Another goal of the report was to show the gap in the knowledge on the radio nuclide transfer. This was thought to help to create a basis for the decisions of the Federal Ministry concerning the support of other investigation projects in the field of transfer of radionuclides. (orig./MG) [de

Implications of DOE O 1027 Guidance on Rad-NESHAP Programs

International Nuclear Information System (INIS)

Fuehne, David P.; Fong, Stephen C.

2012-01-01

This presentation is for the national Radionuclide NESHAP meeting, an embedded topic of the 2012 Health Physics Society Annual Meeting in Sacramento, CA. The Radionuclide NESHAP program is responsible for measuring and reporting the amount of airborne radioactive material released from DOE facilities. The issue at hand is recent guidance put forth by the Department of Energy regarding threshold limits for Category 3 and Category 2 nuclear facilities. Updates to calculation methods have resulted in increased amounts of radioactive material allowed in inventory for facilities before they reach levels which require them to be categorized as a Category 2 or 3 nuclear facility. With larger radioactive material inventories, there may be a corresponding increase in overall facility emissions. This can have permitting and monitoring impacts for DOE sites, as well as political ramifications with citizen organizations. This presentation is intended to raise awareness of the new guidance and associated issues, and to stimulate discussion among DOE Radionuclide NESHAP representatives.

Geographical-radioecological aspects of nuclear energy exploitation and environment contamination by man-made radionuclides in Russian Federation

International Nuclear Information System (INIS)

Kurucova, S.; Blazik, T.; Kuruc, J.

2005-01-01

Radioactive contamination of the environment is one of the most dangerous forms of environmental pollution in Russian Federation. The aim of this work was to localize and analyse places of nuclear energy exploitation for peaceful and military purposes in Russian Federation, in aim to find out whether observed places are potential or real sources of contamination of Russian environment by man-made radionuclides. Nuclear activities in nuclear industry enterprises and research organizations, in Russian Northern fleet, Russian Pacific Fleet, Russian civilian nuclear fleet and in nuclear power plants were analysed and the places where the nuclear explosions were carried out were localized. In contaminated regions the goal was to analyse geographical and some radioecological aspects of contamination of environment. Great part of Russian territory has been subjected to some form of radioactive contamination, mainly because of large radiation accidents in Mayak Production Association (PA) in the Urals (1949-1956, 1957 and 1967) and in Chernobyl Nuclear Power Plant (1986). The largest region in Russian Federation with environment contaminated by man-made radionuclides is region of Chernobyl NPP accident influence, which is situated in central, densely populated and economically relatively good developed part of Russian Federation where the agriculture has an important role. The most contaminated administrative units in region are Bryansk Region, Kaluga Region, Oryol Region and Tula Region where high soil density of cesium-137 are observed. Present radioecological situation in this region is analysed. By analysing of dynamics of demographic indicators in four most contaminated regions authors found out similar trends with Russian nationwide indicators and with indicators for Central Federal District but much more unfavourable values were observed in four regions, particularly in Tula Region. Health situation of liquidators and of affected population who live in contaminated

National Low-Level Waste Management Program Radionuclide Report Series

International Nuclear Information System (INIS)

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

1992-02-01

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

Coral Reef Guidance

Science.gov (United States)

Guidance prepared by EPA and Army Corps of Engineers concerning coral reef protection under the Clean Water Act, Marine Protection, Research, and Sanctuaries Act, Rivers and Harbors Act, and Federal Project Authorities.

78 FR 12761 - Guidance for Industry: Guidance on the Labeling of Certain Uses of Lecithin Derived From Soy...

Science.gov (United States)

2013-02-25

...] (formerly 2006D-0169) Guidance for Industry: Guidance on the Labeling of Certain Uses of Lecithin Derived... on the Labeling of Certain Uses of Lecithin Derived From Soy Under Section 403(w) of the Federal Food.... The guidance explained FDA's then current thinking on the labeling of certain uses of lecithin derived...

Significant Guidance Issued by the Federal Motor Carrier Safety Administration

Data.gov (United States)

Department of Transportation — A list of Significant Guidance documents, which include guidance document disseminated to regulated entities or the general public that may reasonably be anticipated...

RIVER-RAD, Radionuclide Transport in Surface Waters

International Nuclear Information System (INIS)

1996-01-01

1 - Description of program or function: RIVER-RAD assesses the potential fate of radionuclides released to rivers. The model is simplified in nature and is intended to provide guidance in determining the potential importance of the surface water pathway, relevant transport mechanisms, and key radionuclides in estimating radiological dose to man. 2 - Method of solution: A compartmental linear transfer model is used in RIVER-RAD. The river system model in the code is divided into reaches (compartments) of equal size, each with a sediment compartment below it. The movement of radionuclides is represented by a series of transfers between the reaches, and between the water and sediment compartments of each reach. Within each reach (for both the water and sediment compartments), the radionuclides are assumed to be uniformly mixed. Upward volatilization is allowed from the water compartment, and the transfer of radionuclides between the reaches is determined by the flow rate of the river. Settling and resuspension velocities determine the transfer of absorbed radionuclides between the water and sediment compartments. Radioactive decay and decay-product buildup are incorporated into all transport calculations for all radionuclide chains specified by the user. Each nuclide may have unique input and removal rates. Volatilization and radiological decay are considered as linear rate constants in the model. 3 - Restrictions on the complexity of the problem: None noted

General program for the advancement of the radionuclide technology

International Nuclear Information System (INIS)

1979-12-01

The 'General Program for the Advancement of the Radionuclide Technology' was elaborated in 1978 by the 'Arbeitsgemeinschaft zur Foerderung der Radionuklidtechnik' (AFR) (Association for the Promotion of Radionuclide Technology). In addition to an inventory of the major applications of radionuclide technology, this General Program includes a comprehensive description of tasks relating to the central topics of raw materials, environment, technology and materials, health and nutrition, scientific developments of radionuclide technology. The 'General Program for the Advancement of the Radionuclide Technology' serves inter alia as a basis of evaluation in opinions on funding applications filed with the Federal Ministry for Research and Technology (BMFT) with respect to the provision of advanced techniques involving radionuclides for industrial application. (orig.) [de

78 FR 4848 - Social Media: Consumer Compliance Risk Management Guidance

Science.gov (United States)

2013-01-23

...: Consumer Compliance Risk Management Guidance AGENCY: Federal Financial Institutions Examination Council... Media: Consumer Compliance Risk Management Guidance'' (guidance). Upon completion of the guidance, and... management practices adequately address the consumer compliance and legal risks, as well as related risks...

33 CFR 385.5 - Guidance memoranda.

Science.gov (United States)

2010-07-01

... ability of the Corps of Engineers, the South Florida Water Management District, and other non-Federal... § 385.5 Guidance memoranda. (a) General. (1) Technical guidance for internal management of Corps of...) General format and content of Project Implementation Reports (§ 385.26(a)); (ii) Instructions for...

Laser Guidance Analysis Facility

Data.gov (United States)

Federal Laboratory Consortium — This facility, which provides for real time, closed loop evaluation of semi-active laser guidance hardware, has and continues to be instrumental in the development...

Existing ingestion guidance: Problems and recommendations

Energy Technology Data Exchange (ETDEWEB)

Mooney, Robert R; Ziegler, Gordon L; Peterson, Donald S [Environmental Radiation Section, Division of Radiation Protection, WA (United States)

1989-09-01

Washington State has been developing plans and procedures for responding to nuclear accidents since the early 1970s. A key part of this process has been formulating a method for calculating ingestion pathway concentration guides (CGs). Such a method must be both technically sound and easy to use. This process has been slow and frustrating. However, much technical headway has been made in recent years, and hopefully the experience of the State of Washington will provide useful insight to problems with the existing guidance. Several recommendations are offered on ways to deal with these problems. In January 1986, the state held an ingestion pathway exercise which required the determination of allowed concentrations of isotopes for various foods, based upon reactor source term and field data. Objectives of the exercise were not met because of the complexity of the necessary calculations. A major problem was that the allowed concentrations had to be computed for each isotope and each food group, given assumptions on the average diet. To solve problems identified during that exercise, Washington developed, by March 1986, partitioned CGs. These CGs apportioned doses from each food group for an assumed mix of radionuclides expected to result from a reactor accident. This effort was therefore in place just in time for actual use during the Chernobyl fallout episode in May 1986. This technique was refined and described in a later report and presented at the 1987 annual meeting of the Health Physics Society. Realizing the technical weaknesses which still existed and a need to simplify the numbers for decision makers, Washington State has been developing computer methods to quickly calculate, from an accident specific relative mix of isotopes, CGs which allow a single radionuclide concentration for all food groups. This latest approach allows constant CGs for different periods of time following the accident, instead of peak CGs, which are good only for a short time after the

Existing ingestion guidance: Problems and recommendations

International Nuclear Information System (INIS)

Mooney, Robert R.; Ziegler, Gordon L.; Peterson, Donald S.

1989-01-01

Washington State has been developing plans and procedures for responding to nuclear accidents since the early 1970s. A key part of this process has been formulating a method for calculating ingestion pathway concentration guides (CGs). Such a method must be both technically sound and easy to use. This process has been slow and frustrating. However, much technical headway has been made in recent years, and hopefully the experience of the State of Washington will provide useful insight to problems with the existing guidance. Several recommendations are offered on ways to deal with these problems. In January 1986, the state held an ingestion pathway exercise which required the determination of allowed concentrations of isotopes for various foods, based upon reactor source term and field data. Objectives of the exercise were not met because of the complexity of the necessary calculations. A major problem was that the allowed concentrations had to be computed for each isotope and each food group, given assumptions on the average diet. To solve problems identified during that exercise, Washington developed, by March 1986, partitioned CGs. These CGs apportioned doses from each food group for an assumed mix of radionuclides expected to result from a reactor accident. This effort was therefore in place just in time for actual use during the Chernobyl fallout episode in May 1986. This technique was refined and described in a later report and presented at the 1987 annual meeting of the Health Physics Society. Realizing the technical weaknesses which still existed and a need to simplify the numbers for decision makers, Washington State has been developing computer methods to quickly calculate, from an accident specific relative mix of isotopes, CGs which allow a single radionuclide concentration for all food groups. This latest approach allows constant CGs for different periods of time following the accident, instead of peak CGs, which are good only for a short time after the

75 FR 8412 - Office of New Reactors: Interim Staff Guidance on Assessing Ground Water Flow and Transport of...

Science.gov (United States)

2010-02-24

... NUCLEAR REGULATORY COMMISSION [NRC-2010-0047] Office of New Reactors: Interim Staff Guidance on Assessing Ground Water Flow and Transport of Accidental Radionuclide Releases; Solicitation of Public... ground water flow and transport of accidental radionuclide releases necessary to demonstrate compliance...

Analysis of costs for compliance with Federal Radiation Protection Guidance for Occupational Exposure. Volume 2: case study analysis of the impacts of proposed radiation protection guidance for workers

International Nuclear Information System (INIS)

1983-11-01

This report contains the writeups of case studies conducted in support of an effort to estimate costs and economic impacts of proposed Federal Radiation Protection Guidance for Occupational Exposures. The purpose of the case studies was to develop background information on representative organizations necessary to determine the impact of the proposed guidelines on selected industries. This information was used, together with other data, to estimate the aggregate costs of compliance with the proposed guidelines. The cost estimates are contained in a companion report

78 FR 67442 - Congestion Mitigation and Air Quality Improvement Program Interim Guidance

Science.gov (United States)

2013-11-12

...] Congestion Mitigation and Air Quality Improvement Program Interim Guidance AGENCY: Federal Highway... Comment. SUMMARY: The FHWA is issuing Interim Guidance on the Congestion Mitigation and Air Quality.../environment/air_quality/cmaq/policy_and_guidance/2008_guidance/ guidance/. DATES: This Interim Guidance is...

Assessment of radionuclide databases in CAP88 mainframe version 1.0 and Windows-based version 3.0.

Science.gov (United States)

LaBone, Elizabeth D; Farfán, Eduardo B; Lee, Patricia L; Jannik, G Timothy; Donnelly, Elizabeth H; Foley, Trevor Q

2009-09-01

In this study the radionuclide databases for two versions of the Clean Air Act Assessment Package-1988 (CAP88) computer model were assessed in detail. CAP88 estimates radiation dose and the risk of health effects to human populations from radionuclide emissions to air. This program is used by several U.S. Department of Energy (DOE) facilities to comply with National Emission Standards for Hazardous Air Pollutants regulations. CAP88 Mainframe, referred to as version 1.0 on the U.S. Environmental Protection Agency Web site (http://www.epa.gov/radiation/assessment/CAP88/), was the very first CAP88 version released in 1988. Some DOE facilities including the Savannah River Site still employ this version (1.0) while others use the more user-friendly personal computer Windows-based version 3.0 released in December 2007. Version 1.0 uses the program RADRISK based on International Commission on Radiological Protection Publication 30 as its radionuclide database. Version 3.0 uses half-life, dose, and risk factor values based on Federal Guidance Report 13. Differences in these values could cause different results for the same input exposure data (same scenario), depending on which version of CAP88 is used. Consequently, the differences between the two versions are being assessed in detail at Savannah River National Laboratory. The version 1.0 and 3.0 database files contain 496 and 838 radionuclides, respectively, and though one would expect the newer version to include all the 496 radionuclides, 35 radionuclides are listed in version 1.0 that are not included in version 3.0. The majority of these has either extremely short or long half-lives or is no longer in production; however, some of the short-lived radionuclides might produce progeny of great interest at DOE sites. In addition, 122 radionuclides were found to have different half-lives in the two versions, with 21 over 3 percent different and 12 over 10 percent different.

De Minimis Thresholds for Federal Building Metering Appropriateness

Energy Technology Data Exchange (ETDEWEB)

Henderson, Jordan W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-03-31

The U.S. Department of Energy (DOE) is required by statute and Presidential Memorandum to establish guidelines for agencies to meter their Federal buildings for energy (electricity, natural gas, and steam) and water. See 42 U.S.C. § 8253(e). DOE issued guidance in February 2006 on the installation of electric meters in Federal buildings. A recent update to the 2006 guidance accounts for more current metering practices within the Federal Government. The updated metering guidance specifies that all Federal buildings shall be considered “appropriate” for energy or water metering unless identified for potential exclusion. In developing the updated guidance to carry out the statue, Congress also directed DOE to (among other things) establish exclusions from the metering requirements based on the de minimis quantity of energy use of a Federal building, industrial process, or structure. This paper discusses the method used to identify de minimis values.

48 CFR 427.104 - General guidance.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false General guidance. 427.104... REQUIREMENTS PATENTS, DATA, AND COPYRIGHTS General 427.104 General guidance. As used in FAR part 27, the agency head or agency head designee is the Senior Procurement Executive, except under FAR 27.306(a) and (b...

Geochemistry and radionuclide migration

International Nuclear Information System (INIS)

Isherwood, D.

1978-01-01

Theoretically, the geochemical barrier can provide a major line of defense in protecting the biosphere from the hazards of nuclear waste. The most likely processes involved are easily identified. Preliminary investigations using computer modeling techniques suggest that retardation is an effective control on radionuclide concentrations. Ion exchange reactions slow radionuclide migration and allow more time for radioactive decay and dispersion. For some radionuclides, solubility alone may limit concentrations to less than the maximum permissible now considered acceptable by the Federal Government. The effectiveness of the geochemical barrier is ultimately related to the repository site characteristics. Theory alone tells us that geochemical controls will be most efficient in an environment that provides for maximum ion exchange and the precipitation of insoluble compounds. In site selection, consideration should be given to rock barriers with high ion exchange capacity that might also act as semi-permeable membranes. Also important in evaluating the site's potential for effective geochemical controls are the oxidation potentials, pH and salinity of the groundwater

Radioactivity: radionuclides in foods

International Nuclear Information System (INIS)

Simpson, R.E.; Baratta, E.J.; Jelinek, C.F.

1977-01-01

The results are summarized of the analysis for strontium-90, cesium-137, iodine-131, ruthenium-106, and potassium-40, a naturally occurring radionuclide, in samples of total diet and selected import commodities in the foods compliance program of the Food and Drug Administration. On the basis of the radionuclide intake guidelines established by the Federal Radiation Council (FRC), the low content of radionuclides found in the total diet samples for fiscal years 1973 and 1974 demonstrates the need for surveillance only at the present level. The low levels of radionuclides found in a limited number of edible imported commodities indicate that their contribution to the total diet would not increase the levels of these radionuclides above those recommended for only periodic surveillance by the FRC. The potassium levels, determined from potassium-40 activity, found in meats and fish agree with the value for normal muscle tissue for the reference man reported by the International Commission on Radiation Protection. Of the other commodities, nuts contained the highest levels, while sugar, beverages, and processed foods contained the lowest levels of potassium. Although cesium and potassium are chemical analogs with similar metabolic properties, because of their variable content in some leafy samples as a result of surface contamination, a correlation between cesium-137 levels and the cesium-137-to-potassium ratio was inconclusive

RIVER-RAD: A computer code for simulating the transport of radionuclides in rivers

International Nuclear Information System (INIS)

Hetrick, D.M.; McDowell-Boyer, L.M.; Sjoreen, A.L.; Thorne, D.J.; Patterson, M.R.

1992-11-01

A screening-level model, RIVER-RAD, has been developed to assess the potential fate of radionuclides released to rivers. The model is simplified in nature and is intended to provide guidance in determining the potential importance of the surface water pathway, relevant transport mechanisms, and key radionuclides in estimating radiological dose to man. The purpose of this report is to provide a description of the model and a user's manual for the FORTRAN computer code

76 FR 411 - Regulatory Guidance Concerning Electronic Signatures and Documents

Science.gov (United States)

2011-01-04

... guidance, including memoranda and letters, may no longer be relied upon to the extent they are inconsistent... Concerning Electronic Signatures and Documents AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of regulatory guidance. SUMMARY: FMCSA issues regulatory guidance concerning the...

75 FR 59094 - Federal Travel Regulation; Miscellaneous Amendments

Science.gov (United States)

2010-09-27

... references in a number of sections, by providing additional guidance for determining distance measurements... to carry senior Federal officials and non-Federal travelers. DATES: Effective Date: This final rule... concerning when travel on Government aircraft is not reported; adds additional guidance for determining...

Identification of technical guidance related to ground water monitoring

Energy Technology Data Exchange (ETDEWEB)

Vogelsberger, R.R.; Smith, E.D.; Broz, M.; Wright, J.C. Jr.

1987-05-01

Monitoring of ground water quality is a key element of ground water protection and is mandated by several federal and state laws concerned with water quality or waste management. Numerous regulatory guidance documents and technical reports discuss various aspects of ground water monitoring, but at present there is no single source of guidance on procedures and practices for ground water monitoring. This report is intended to assist US Department of Energy (DOE) officials and facility operating personnel in identifying sources of guidance for developing and implementing ground water monitoring programs that are technically sound and that comply with applicable regulations. Federal statutes and associated regulations were reviewed to identify requirements related to ground water monitoring, and over 160 documents on topics related to ground water monitoring were evaluated for their technical merit, their utility as guidance for regulatory compliance, and their relevance to DOE's needs. For each of 15 technical topics involved in ground water monitoring, the report presents (1) a review of federal regulatory requirements and representative state requirements, (2) brief descriptions of the contents and merits of available guidance documents and technical references, and (3) recommendations of the guidance documents or other technical resources that appear to be most appropriate for use in DOE's monitoring activities. The contents of the report are applicable to monitoring activities involving both radioactive and nonradioactive substances. The main sources of regulatory requirements considered in the report are the Atomic Energy Act (including the Uranium Mill Tailings Radiation Control Act), Resource Conservation and Recovery Act, Comprehensive Environmental Response, Compensation and Liability Act, Safe Drinking Water Act, Toxic Substances Control Act, and Federal Water Pollution Control Act.

Identification of technical guidance related to ground water monitoring

International Nuclear Information System (INIS)

Vogelsberger, R.R.; Smith, E.D.; Broz, M.; Wright, J.C. Jr.

1987-05-01

Monitoring of ground water quality is a key element of ground water protection and is mandated by several federal and state laws concerned with water quality or waste management. Numerous regulatory guidance documents and technical reports discuss various aspects of ground water monitoring, but at present there is no single source of guidance on procedures and practices for ground water monitoring. This report is intended to assist US Department of Energy (DOE) officials and facility operating personnel in identifying sources of guidance for developing and implementing ground water monitoring programs that are technically sound and that comply with applicable regulations. Federal statutes and associated regulations were reviewed to identify requirements related to ground water monitoring, and over 160 documents on topics related to ground water monitoring were evaluated for their technical merit, their utility as guidance for regulatory compliance, and their relevance to DOE's needs. For each of 15 technical topics involved in ground water monitoring, the report presents (1) a review of federal regulatory requirements and representative state requirements, (2) brief descriptions of the contents and merits of available guidance documents and technical references, and (3) recommendations of the guidance documents or other technical resources that appear to be most appropriate for use in DOE's monitoring activities. The contents of the report are applicable to monitoring activities involving both radioactive and nonradioactive substances. The main sources of regulatory requirements considered in the report are the Atomic Energy Act (including the Uranium Mill Tailings Radiation Control Act), Resource Conservation and Recovery Act, Comprehensive Environmental Response, Compensation and Liability Act, Safe Drinking Water Act, Toxic Substances Control Act, and Federal Water Pollution Control Act

Selected radionuclides important to low-level radioactive waste management

International Nuclear Information System (INIS)

1996-11-01

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

Selected radionuclides important to low-level radioactive waste management

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-11-01

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.

Radionuclide data bases available for bioaccumulation factors for freshwater biota

International Nuclear Information System (INIS)

Blaylock, B.G.

1982-01-01

Aquatic models currently in use for dose assessment simulate the transfer of radionuclides in aquatic environments and the transfer to man. In these models the assimilation of a radionuclide in aquatic biota is calculated by using a simple empirical relationship known as the bioaccumulation factor (BF) to represent the transfer of the radionuclide from water to organism. The purpose of this article is to review data bases that are available for BFs for freshwater biota and to identify the uncertainties associated with them. Data bases for raidoisotopes of Co, Cs, C, H, I, Pu, Ra, Ru, Sr, and U are reviewed. With the exception of ruthenium and carbon, the review is restricted to BFs determined for natural freshwater systems. Factors influencing the variability of BFs are identified, uncertainties associated with the validation of BFs are discussed, and some guidance is given for collecting data and measuring BFs

48 CFR 2452.237-73 - Conduct of Work and Technical Guidance.

Science.gov (United States)

2010-10-01

... conditions of the contract. (c) The GTR will issue technical guidance in writing or, if issued orally, he/she... Technical Guidance. 2452.237-73 Section 2452.237-73 Federal Acquisition Regulations System DEPARTMENT OF... Provisions and Clauses 2452.237-73 Conduct of Work and Technical Guidance. As prescribed in 2437.110(d...

Review of soil contamination guidance

International Nuclear Information System (INIS)

Mueller, M.A.; Kennedy, W.E. Jr.; Soldat, J.K.

1981-08-01

A review of existing and proposed radioactive soil contamination standards and guidance was conducted for United Nuclear Corporation (UNC), Office of Surplus Facilities Management. Information was obtained from both government agencies and other sources during a literature survey. The more applicable standards were reviewed, evaluated, and summarized. Information pertaining to soil contamination for both facility operation and facility decommissioning was obtained from a variety of sources. These sources included: the Code of Federal Regulations, regulatory guides, the Federal Register, topical reports written by various government agencies, topical reports written by national laboratories, and publications from the American National Standards Institute (ANSI). It was difficult to directly compare the standards and guidance obtained from these sources since each was intended for a specific situation and different units or bases were used. However, most of the information reviewed was consistent with the philosophy of maintaining exposures at levels as low as reasonably achievable

Regulatory systems-based licensing guidance documentation

International Nuclear Information System (INIS)

Delligatti, M.S.

1991-01-01

The US Nuclear Regulatory Commission (NRC) has developed a series of licensing guidance documents based on the regulatory requirements in Part 60 of Title 10 of the Code of Federal Regulations (10 CFR Part 60). This regulatory systems-based approach to licensing guidance documentation relies on the definition of the high-level waste repository in 10 CFR Part 60. A document which is important for the frame-work it gives to other programmatic licensing guidance is the Draft Regulatory Guide open-quotes Format and Content for the License Application for the High-Level Waste Repositoryclose quotes (FCRG). The FCRG describes a format and content acceptable to NRC for a high-level waste repository license application pursuant to the requirements of 10 CFR Part 60. Other licensing guidance documents will be compatible with the FCRG

PIV Logon Configuration Guidance

Energy Technology Data Exchange (ETDEWEB)

Lee, Glen Alan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-03-04

This document details the configurations and enhancements implemented to support the usage of federal Personal Identity Verification (PIV) Card for logon on unclassified networks. The guidance is a reference implementation of the configurations and enhancements deployed at the Los Alamos National Laboratory (LANL) by Network and Infrastructure Engineering – Core Services (NIE-CS).

Radionuclide Air Emissions Report for the Hanford Site Calendar Year 1999

International Nuclear Information System (INIS)

ROKKAN, D.J.

2000-01-01

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

Approach to DOE threshold guidance limits

International Nuclear Information System (INIS)

Shuman, R.D.; Wickham, L.E.

1984-01-01

The need for less restrictive criteria governing disposal of extremely low-level radioactive waste has long been recognized. The Low-Level Waste Management Program has been directed by the Department of Energy (DOE) to aid in the development of a threshold guidance limit for DOE low-level waste facilities. Project objectives are concernd with the definition of a threshold limit dose and pathway analysis of radionuclide transport within selected exposure scenarios at DOE sites. Results of the pathway analysis will be used to determine waste radionuclide concentration guidelines that meet the defined threshold limit dose. Methods of measurement and verification of concentration limits round out the project's goals. Work on defining a threshold limit dose is nearing completion. Pathway analysis of sanitary landfill operations at the Savannah River Plant and the Idaho National Engineering Laboratory is in progress using the DOSTOMAN computer code. Concentration limit calculations and determination of implementation procedures shall follow completion of the pathways work. 4 references

76 FR 50813 - Major Capital Investment Projects; Guidance on News Starts/Small Starts Policies and Procedures

Science.gov (United States)

2011-08-16

... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Major Capital Investment Projects; Guidance on News Starts/Small Starts Policies and Procedures AGENCY: Federal Transit Administration (FTA... Administration (FTA) to publish policy guidance on the New and Small Starts capital project review and evaluation...

75 FR 36471 - Seventh Meeting-RTCA Special Committee 220: Automatic Flight Guidance and Control

Science.gov (United States)

2010-06-25

... Committee 220: Automatic Flight Guidance and Control AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of RTCA Special Committee 220: Automatic Flight Guidance and Control meeting. SUMMARY: The... Committee 220: Automatic Flight Guidance and [[Page 36472

Targeted Radionuclide and Fluorescence Dual-modality Imaging of Cancer : Preclinical Advances and Clinical Translation

NARCIS (Netherlands)

Lutje, S.; Rijpkema, M.; Helfrich, W.; Oyen, W. J. G.; Boerman, O. C.

2014-01-01

In oncology, sensitive and reliable detection tumor tissue is crucial to prevent recurrences and to improve surgical outcome. Currently, extensive research is focused on the use of radionuclides as well as fluorophores to provide real-time guidance during surgery to aid the surgeon in the

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

International Nuclear Information System (INIS)

Peters, J.; Glucksberg, N.; Fogg, A.; Couture, B.

2006-01-01

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

Effects on radionuclide concentrations by cement/ground-water interactions in support of performance assessment of low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Krupka, K.M.; Serne, R.J.

1998-05-01

The US Nuclear Regulatory Commission is developing a technical position document that provides guidance regarding the performance assessment of low-level radioactive waste disposal facilities. This guidance considers the effects that the chemistry of the vault disposal system may have on radionuclide release. The geochemistry of pore waters buffered by cementitious materials in the disposal system will be different from the local ground water. Therefore, the cement-buffered environment needs to be considered within the source term calculations if credit is taken for solubility limits and/or sorption of dissolved radionuclides within disposal units. A literature review was conducted on methods to model pore-water compositions resulting from reactions with cement, experimental studies of cement/water systems, natural analogue studies of cement and concrete, and radionuclide solubilities experimentally determined in cement pore waters. Based on this review, geochemical modeling was used to calculate maximum concentrations for americium, neptunium, nickel, plutonium, radium, strontium, thorium, and uranium for pore-water compositions buffered by cement and local ground-water. Another literature review was completed on radionuclide sorption behavior onto fresh cement/concrete where the pore water pH will be greater than or equal 10. Based on this review, a database was developed of preferred minimum distribution coefficient values for these radionuclides in cement/concrete environments

Effects on radionuclide concentrations by cement/ground-water interactions in support of performance assessment of low-level radioactive waste disposal facilities

Energy Technology Data Exchange (ETDEWEB)

Krupka, K.M.; Serne, R.J. [Pacific Northwest National Lab., Richland, WA (United States)

1998-05-01

The US Nuclear Regulatory Commission is developing a technical position document that provides guidance regarding the performance assessment of low-level radioactive waste disposal facilities. This guidance considers the effects that the chemistry of the vault disposal system may have on radionuclide release. The geochemistry of pore waters buffered by cementitious materials in the disposal system will be different from the local ground water. Therefore, the cement-buffered environment needs to be considered within the source term calculations if credit is taken for solubility limits and/or sorption of dissolved radionuclides within disposal units. A literature review was conducted on methods to model pore-water compositions resulting from reactions with cement, experimental studies of cement/water systems, natural analogue studies of cement and concrete, and radionuclide solubilities experimentally determined in cement pore waters. Based on this review, geochemical modeling was used to calculate maximum concentrations for americium, neptunium, nickel, plutonium, radium, strontium, thorium, and uranium for pore-water compositions buffered by cement and local ground-water. Another literature review was completed on radionuclide sorption behavior onto fresh cement/concrete where the pore water pH will be greater than or equal 10. Based on this review, a database was developed of preferred minimum distribution coefficient values for these radionuclides in cement/concrete environments.

Federal environmental inspections handbook

International Nuclear Information System (INIS)

1991-10-01

This Federal Environmental Inspection Handbook has been prepared by the Department of Energy (DOE), Office of Environmental Guidance, RCRA/CERCLA Division (EH-231). It is designed to provide DOE personnel with an easily accessible compilation of the environmental inspection requirements under Federal environmental statutes which may impact DOE operations and activities. DOE personnel are reminded that this Handbook is intended to be used in concert with, and not as a substitute for, the Code of Federal Regulations (CFR). Federal Register (FR), and other applicable regulatory documents

The regulations for radionuclides and chemicals in the environment

International Nuclear Information System (INIS)

Kocher, D.C.

1991-01-01

This presentation detail information on current and proposed standards, recommendations, and guidances for limiting routine and accidental radiation exposures of the public. It also reviews certain laws and regulations intended primarily for limiting exposures of the public to non-radioactive hazardous materials. Limits on risk to the public embodied in laws and regulations are emphasized. It considers the only basis for comparing potential impacts from exposure to radionuclides and other hazardous materials

Pacific Northwest Laboratory facilities radionuclide inventory assessment CY 1992-1993

International Nuclear Information System (INIS)

Sula, M.J.; Jette, S.J.

1994-09-01

Assessments for evaluating compliance with airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAPs - U.S. Code of Federal Regulations, Title 40 Part 61, Subparts H and I) were performed for 33 buildings at the U.S. Department of Energy's (DOE) Pacific Northwest Laboratory on the Hanford Site, and for five buildings owned and operated by Battelle, Pacific Northwest Laboratories in Richland, Washington. The assessments were performed using building radionuclide inventory data obtained in 1992 and 1993. Results of the assessments are summarized in Table S.1 for DOE-PNL buildings and in Table S.2 for Battelle-owned buildings. Based on the radionuclide inventory assessments, four DOE-PNL buildings (one with two emission points) require continuous sampling for radionuclides per 40 CFR 61. None of the Battelle-owned buildings require continuous emission sampling

77 FR 10753 - Draft Guidance for Industry: Food and Drug Administration Records Access Authority Under the...

Science.gov (United States)

2012-02-23

...] Draft Guidance for Industry: Food and Drug Administration Records Access Authority Under the Federal... industry entitled ``FDA Records Access Authority Under Sections 414 and 704 of the Federal Food, Drug...). This updated draft guidance is intended to provide individuals in the human and animal food industries...

Radionuclide diagnostics in St. Petersburg: сurrent status and development challenges

Directory of Open Access Journals (Sweden)

I. A. Zvonova

2015-01-01

Full Text Available This work aims at radionuclide diagnostics analyses in the Russian Federation city of St. Petersburg over 2005–2014. The study covers trends and development challenges , availability of radionuclide diagnostics for population needs, exposure doses for patients.This work aims at radionuclide diagnostics analyses in the Russian Federation city of St. Petersburg over 2005–2014. The study covers trends and development challenges , availability of radionuclide diagnostics for population needs, exposure doses for patients.Materials and methods. The radionuclide diagnostics temporal and structural changes’ analysis was based on Federal state statistical observation forms No.3-DOZ for St. Petersburg and on the results of radionuclide diagnostics subdivision surveys with radiology physicians’ questionnaires on the amount and composition of conducted examinations, dosages of introduced radioactivity of radiopharmaceticals and patients’ doses.The results. Since the end of 1990s until 2012 the amount of radionuclide diagnostics procedures had been steadily reducing. 74000 procedures were conducted in 2005 and 35500 in 2012. The number of radionuclide diagnostics procedures per one thousand residents reduced from 16 to 7.2. Both indicators slightly grew in 2013. In 2014 the total number of radiodiagnostic proceduress amounted up to 42000 and 8.2 tests per 1000 residents. Since 2011 the diagnostic equipment was upgraded. Four medical institutions received SPECT (single photon emission computed tomography or SPECT/CT, two new PET ( positron emission tomographs – centers were set up, three medical institutions had acquired positron emission tomographs (PET and are conducting PET – diagnostics receiving radiofarmaceuticals from external PET – center. At the same time one a third of radiodiagnostic units still has been operating obsolete and depreciated equipment dating back to 1980–1990 .Inspection results indicated that St. Petersburg

Derived intervention levels for radionuclides in food

International Nuclear Information System (INIS)

1988-01-01

After the nuclear accident at Chernobyl in 1986, many countries were affected by widespread radioactive contamination. It became clear that the available guidance on dealing with the consequences of a nuclear accident was inappropriate for the long term and for areas far removed from the accident site. A particular concern was the safety of radioactively contaminated food and drinking-water in the ''far field'' region. The present guidelines, based on health protection principles, have been prepared by the World Health Organization in response to this concern. For various food categories, recommendations are made on levels of contamination by radionuclides at which corrective action might be justified to reduce the health risk to the population. The guidelines are based on accepted radiation dose criteria, on food consumption data from different parts of the world, and on dosimetric information for the relevant radionuclides. They are intended to assist in national decision-making in the event of another major nuclear accident. Refs, 1 fig., 14 tabs

75 FR 59326 - Eighth Meeting-RTCA Special Committee 220: Automatic Flight Guidance and Control

Science.gov (United States)

2010-09-27

... Committee 220: Automatic Flight Guidance and Control AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of RTCA Special Committee 220: Automatic Flight Guidance and Control meeting. SUMMARY: The... Special Committee 220: Automatic Flight Guidance and Control meeting. The agenda will include: Welcome...

76 FR 22163 - Tenth Meeting: RTCA Special Committee 220: Automatic Flight Guidance and Control

Science.gov (United States)

2011-04-20

... 220: Automatic Flight Guidance and Control AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of RTCA Special Committee 220 meeting: Automatic Flight Guidance and Control. SUMMARY: The FAA is... hereby given for a Special Committee 220, Automatic Flight Guidance and Control. Agenda Tuesday May 10...

76 FR 38742 - Eleventh Meeting: RTCA Special Committee 220: Automatic Flight Guidance and Control

Science.gov (United States)

2011-07-01

... Committee 220: Automatic Flight Guidance and Control AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of RTCA Special Committee 220 Meeting: Automatic Flight Guidance and Control. SUMMARY: The..., Automatic Flight Guidance and Control. Agenda Tuesday August 9-Thursday, August 11, 2011 Tuesday, August 9...

75 FR 15770 - Sixth Meeting-RTCA Special Committee 220: Automatic Flight Guidance and Control

Science.gov (United States)

2010-03-30

... 220: Automatic Flight Guidance and Control AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of RTCA Special Committee 220: Automatic Flight Guidance and Control meeting. SUMMARY: The FAA is... hereby given for a Special Committee 220: Automatic Flight Guidance and Control meeting. The agenda will...

75 FR 80886 - Ninth Meeting-RTCA Special Committee 220: Automatic Flight Guidance and Control

Science.gov (United States)

2010-12-23

... 220: Automatic Flight Guidance and Control AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of RTCA Special Committee 220: Automatic Flight Guidance and Control meeting. SUMMARY: The FAA is... for a Special Committee 220: Automatic Flight Guidance and Control meeting. The agenda will include...

German radionuclide exports and imports 1990

International Nuclear Information System (INIS)

Anon.

1991-01-01

The statistics compiled by the German Federal Office for Trade and Industry (Bundesamt fuer Wirtschaft) for the Federal Ministry for the Environment, Conservation of Nature, and Reactor Protection of imports and exports of radionuclides, irradiation samples and sealed emitters above 1850 GBq show a slight decline by 11.8%, on the basis of activity, in imports and a somewhat higher rise by 21.6% in exports in 1990. Imports returned to the level of 1988 after having experienced an extraordinary rise in 1989. Exports were slightly better than in the previous year, but still considerably below the average of the past five years. (orig.) [de

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

International Nuclear Information System (INIS)

Diediker, L.P.; Johnson, A.R.; Rhoads, K.; Klages, D.L.; Soldat, J.K.; Rokkan, D.J.

1993-06-01

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.''

Radionuclide Air Emissions Report for the Hanford Site Calendar Year 1999

Energy Technology Data Exchange (ETDEWEB)

ROKKAN, D.J.

2000-06-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-06-12

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 ProtectionAir Emissions. The EDE to the PNNL Site MEI due to routine emissions in 2011 from PNNL Site sources was 1.7E 05 mrem (1.7E-7 mSv) EDE. No nonroutine emissions occurred in 2011. The total radiological dose for 2011 to the MEI from all PNNL Site radionuclide emissions was more than 10,000 times smaller than the federal and state standard of 10 mrem/yr, to which the PNNL Site is in compliance.

Grants Management Guidance for Non-Profit Organizations

Science.gov (United States)

This guidance is intended to provide non-profit grant recipients with information to ensure that their organizations remain in compliance with the Code of Federal Regulations (CFR), Office of Management (OMB) cost principles, and the terms and conditions.

76 FR 50809 - Eleventh Meeting: RTCA Special Committee 220: Automatic Flight Guidance and Control

Science.gov (United States)

2011-08-16

... Committee 220: Automatic Flight Guidance and Control AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Correction of Notice of RTCA Special Committee 220 meeting: Automatic Flight Guidance and Control...: Automatic Flight Guidance and Control DATES: The meeting will be held September 13-15, 2011, from 9 a.m. to...

Draft federal GHG accounting and reporting : technical support document

Science.gov (United States)

2010-07-01

This is a technical support document (TSD) that accompanies the Federal Greenhouse Gas Accounting and Reporting Guidance (or Guidance). This document provides detailed information on the inventory reporting process and accepted calculation methodolog...

The Nuclear Data Commission and the Radionuclide Data Centre in Russia

International Nuclear Information System (INIS)

1994-12-01

The document includes two papers: 'The Work of the Nuclear Data Commission' and 'Radionuclide Data Centre', which describe the activities of these two organizations of the Russian Federation. A separate abstract was prepared for each paper

Radionuclide air emissions report for the Hanford Site

International Nuclear Information System (INIS)

Rokkan, D.J.; Diediker, L.P.; Manley, C.L.

1992-06-01

This report documents the radionuclide air emissions from the Hanford Site in 1991 and the resulting effective dose equivalent to any member of the public. The report is submitted in compliance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, ''National Emissions Standards for Hazardous Air Pollutants.''

Biological pathways of exposure and ecotoxicity values for uranium and associated radionuclides: Chapter D in Hydrological, geological, and biological site characterization of breccia pipe uranium deposits in Northern Arizona

Science.gov (United States)

Hinck, Jo E.; Linder, Greg L.; Finger, Susan E.; Little, Edward E.; Tillitt, Donald E.; Kuhne, Wendy

2010-01-01

plant’s or an animal’s life history and surrounding environment. Various species of plants, invertebrates, fishes, amphibians, reptiles, birds, and mammals found in the segregation areas that are considered species of concern by State and Federal agencies were included in the development of the site-specific food web. The utilization of subterranean habitats (burrows in uranium-rich areas, burrows in waste rock piles or reclaimed mining areas, mine tunnels) in the seasonally variable but consistently hot, arid environment is of particular concern in the segregation areas. Certain species of reptiles, amphibians, birds, and mammals in the segregation areas spend significant amounts of time in burrows where they can inhale or ingest uranium and other radionuclides through digging, eating, preening, and hibernating. Herbivores may also be exposed though the ingestion of radionuclides that have been aerially deposited on vegetation. Measured tissues concentrations of uranium and other radionuclides are not available for any species of concern in the segregation areas. The sensitivity of these animals to uranium exposure is unknown based on the existing scientific literature, and species-specific uranium presumptive effects levels were only available for two endangered fish species known to inhabit the segregation areas. Overall, the chemical toxicity data available for biological receptors of concern were limited, although chemical and radiation toxicity guidance values are available from several sources. However, caution should be used when directly applying these values to northern Arizona given the unique habitat and life history strategies of biological receptors in the segregation areas and the fact that some guidance values are based on models rather than empirical (laboratory or field) data. No chemical toxicity information based on empirical data is available for reptiles, birds, or wild mammals; therefore, the risks associated with uranium and other

Radionuclide air emission report for the Hanford Site Calendar Year 1993

International Nuclear Information System (INIS)

Diediker, L.P.; Curn, B.L.; Rhoads, K.; Damberg, E.G.; Soldat, J.K.; Jette, S.J.

1994-01-01

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

Guidance for performing preliminary assessments under CERCLA

Energy Technology Data Exchange (ETDEWEB)

NONE

1991-09-01

EPA headquarters and a national site assessment workgroup produced this guidance for Regional, State, and contractor staff who manage or perform preliminary assessments (PAs). EPA has focused this guidance on the types of sites and site conditions most commonly encountered. The PA approach described in this guidance is generally applicable to a wide variety of sites. However, because of the variability among sites, the amount of information available, and the level of investigative effort required, it is not possible to provide guidance that is equally applicable to all sites. PA investigators should recognize this and be aware that variation from this guidance may be necessary for some sites, particularly for PAs performed at Federal facilities, PAs conducted under EPA`s Environmental Priorities Initiative (EPI), and PAs at sites that have previously been extensively investigated by EPA or others. The purpose of this guidance is to provide instructions for conducting a PA and reporting results. This guidance discusses the information required to evaluate a site and how to obtain it, how to score a site, and reporting requirements. This document also provides guidelines and instruction on PA evaluation, scoring, and the use of standard PA scoresheets. The overall goal of this guidance is to assist PA investigators in conducting high-quality assessments that result in correct site screening or further action recommendations on a nationally consistent basis.

remedy for the inadequate representation of the guidance

African Journals Online (AJOL)

Elizabeth Egbochuku

comfortably and effectively within the accepted norms of the society” The planners of ... Guidance services in the Secondary Schools hence it's inclusion in the policy .... representatives from the Federal Ministry of Labour were sent to Bendel.

75 FR 78705 - Issuance of Exposure Drafts on Implementation Guidance on the Accounting for the Disposal of G-PP...

Science.gov (United States)

2010-12-16

... FEDERAL ACCOUNTING STANDARDS ADVISORY BOARD Issuance of Exposure Drafts on Implementation Guidance on the Accounting for the Disposal of G-PP&E and Implementation Guidance for Estimating the Historical Cost of G-PP&E AGENCY: Federal Accounting Standards Advisory Board. ACTION: Notice. Board Action...

Solid phase microextraction sampling of high explosive residues in the presence of radionuclides and radionuclide surrogate metals

International Nuclear Information System (INIS)

Duff, M.C.; Crump, S.L.; Ray, R.J.; Beals, D.; Cotham, W.E.; Mount, K.; Koons, R.D.; Leggitt, J.

2008-01-01

The Federal Bureau of Investigation (FBI) Laboratory currently does not have on site facilities for handling radioactive evidentiary materials and there are no established FBI methods or procedures for decontaminating high explosive (HE) evidence while maintaining evidentiary value. One experimental method for the isolation of HE residue involves using solid phase microextraction (SPME) fibers to remove residue of interest. Due to their high affinity for organics, SPME fibers should have little affinity for most metals. However, no studies have measured the affinity of radionuclides for SPME fibers. The focus of this research was to examine the affinity of dissolved radionuclide ( 239/240 Pu, 238 U, 237 Np, 85 Sr, 133 Ba, 137 Cs, 60 Co and 226 Ra) and stable radionuclide surrogate metals (Sr, Co, Ir, Re, Ni, Ba, Cs, Nb, Ru, and Nd) for SPME fibers at the exposure conditions that favor the uptake of HE residues. Our results from radiochemical and mass spectrometric analyses indicate these metals have little measurable affinity for these SPME fibers during conditions that are conducive to HE residue uptake with subsequent analysis by liquid or gas phase chromatography with mass spectrometric detection. (author)

Executive Order 13514: Federal Leadership in Environmental, Energy, and Economic Performance; Comprehensive Federal Fleet Management Handbook (Book)

Energy Technology Data Exchange (ETDEWEB)

Daley, R. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Ahdieh, N. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Bentley, J. [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2014-01-01

A comprehensive Federal Fleet Management Handbook that builds upon the "Guidance for Federal Agencies on E.O. 13514 Section 12-Federal Fleet Management" and provides information to help fleet managers select optimal greenhouse gas and petroleum reduction strategies for each location, meeting or exceeding related fleet requirements, acquiring vehicles to support these strategies while minimizing fleet size and vehicle miles traveled, and refining strategies based on agency performance.

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2000-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2001-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

2002-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Assessment of occupational exposure due to intakes of radionuclides. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Occupational exposure due to radioactive materials can occur as a result of various human activities. These include work associated with the different stages of the nuclear fuel cycle, the use of radioactive sources in medicine, scientific research, agriculture and industry, and occupations which involve the handling of materials containing enhanced concentrations of naturally occurring radionuclides. In order to control this exposure, it is necessary to be able to assess the magnitude of the doses involved. Three interrelated Safety Guides, prepared jointly by the IAEA and the International Labour Office (ILO), provide guidance on the application of the requirements of the Basic Safety Standards with respect to occupational exposure. Reference [3] gives general advice on the exposure conditions for which monitoring programmes should be set up to assess radiation doses arising from external radiation and from intakes of radionuclides by workers. More specific guidance on the assessment of doses from external sources of radiation can be found in Ref. [4] and the present Safety Guide deals with intakes of radioactive materials. Recommendations related to occupational radiation protection have also been developed by the International Commission on Radiological Protection (ICRP) [5]. These and other current recommendations of the ICRP [6] have been taken into account in preparing this Safety Guide. The purpose of this Safety Guide is to provide guidance for regulatory authorities on conducting assessments of intakes of radioactive material arising from occupational exposure. This Guide will also be useful to those concerned with the planning, management and operation of occupational monitoring programmes, and to those involved in the design of equipment for use in internal dosimetry and workplace monitoring

Sampling in forests for radionuclide analysis. General and practical guidance

Energy Technology Data Exchange (ETDEWEB)

Aro, Lasse (Finnish Forest Research Inst. (METLA) (Finland)); Plamboeck, Agneta H. (Swedish Defence Research Agency (FOI) (Sweden)); Rantavaara, Aino; Vetikko, Virve (Radiation and Nuclear Safety Authority (STUK) (Finland)); Straalberg, Elisabeth (Inst. Energy Technology (IFE) (Norway))

2009-01-15

The NKS project FOREST was established to prepare a guide for sampling in forest ecosystems for radionuclide analysis. The aim of this guide is to improve the reliability of datasets generated in future studies by promoting the use of consistent, recommended practices, thorough documentation of field sampling regimes and robust preparation of samples from the forest ecosystem. The guide covers general aims of sampling, the description of major compartments of the forest ecosystem and outlines key factors to consider when planning sampling campaigns for radioecological field studies in forests. Recommended and known sampling methods for various sample types are also compiled and presented. The guide focuses on sampling practices that are applicable in various types of boreal forests, robust descriptions of sampling sites, and documentation of the origin and details of individual samples. The guide is intended for scientists, students, forestry experts and technicians who appreciate the need to use sound sampling procedures in forest radioecological projects. The guide will hopefully encourage readers to participate in field studies and sampling campaigns, using robust techniques, thereby fostering competence in sampling. (au)

Sampling in forests for radionuclide analysis. General and practical guidance

International Nuclear Information System (INIS)

Aro, Lasse; Plamboeck, Agneta H.; Rantavaara, Aino; Vetikko, Virve; Straelberg, Elisabeth

2009-01-01

The NKS project FOREST was established to prepare a guide for sampling in forest ecosystems for radionuclide analysis. The aim of this guide is to improve the reliability of datasets generated in future studies by promoting the use of consistent, recommended practices, thorough documentation of field sampling regimes and robust preparation of samples from the forest ecosystem. The guide covers general aims of sampling, the description of major compartments of the forest ecosystem and outlines key factors to consider when planning sampling campaigns for radioecological field studies in forests. Recommended and known sampling methods for various sample types are also compiled and presented. The guide focuses on sampling practices that are applicable in various types of boreal forests, robust descriptions of sampling sites, and documentation of the origin and details of individual samples. The guide is intended for scientists, students, forestry experts and technicians who appreciate the need to use sound sampling procedures in forest radioecological projects. The guide will hopefully encourage readers to participate in field studies and sampling campaigns, using robust techniques, thereby fostering competence in sampling. (au)

RADIONUCLIDE AIR EMISSIONS REPORT FOR THE HANFORD SITE CY2003

International Nuclear Information System (INIS)

ROKKAN, D.J.

2004-01-01

This report documents radionuclide air emissions from the US Department of Energy (DOE) Hanford Site in 2003 and the resulting effective dose equivalent (EDE) to the maximally exposed individual (MEI) member of the public. The report has been prepared in accordance with the Code of Federal Regulations (CFR), Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants, Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities''; Washington Administrative Code (WAC) Chapter 246-247, ''Radiation Protection-Air Emissions''; 10 CFR 830.120, Quality Assurance; DOE Order 414.1B, Quality Assurance; NQA-1, Quality Assurance Requirements for Nuclear Facility Application; EPA QA/R-2, EPA Requirements for Quality Management Plans; and EPA QA/R-5, Requirements for Quality Assurance Project Plans. The federal regulations in Subpart H of 40 CFR 61 require the measurement and reporting of radionuclides emitted from DOE facilities and the resulting public dose from those emissions. A standard of 10 mrem/yr EDE is not to be exceeded. The EDE to the MEI due to routine and nonroutine emissions in 2003 from Hanford Site point sources was 0.022 mrem (0.00022 mSv), or 0.22 percent of the federal standard. The portions of the Hanford Site MEI dose attributable to individual point sources as listed in Section 2.0 are appropriate for use in demonstrating the compliance of abated stack emissions with applicable terms of the Hanford Site Air Operating Permit and of Notices of Construction. The state has adopted the 40 CFR 61 standard of 10 mrem/yr EDE into their regulations, yet further requires that the EDE to the MEI be calculated not only from point source emissions but also from diffuse and fugitive sources of emissions. WAC 246-247 also requires the reporting of radionuclide emissions from all Hanford Site sources during routine as well as nonroutine operations. The EDE from

78 FR 54949 - Major Project Financial Plan Guidance

Science.gov (United States)

2013-09-06

...'' (GA-090-751). That report recommended that Financial Plans include the cost of financing the project... Project Financial Plan Guidance AGENCY: Federal Highway Administration (FHWA), DOT. ACTION: Notice; Request for comments. SUMMARY: This notice requests comments on draft Major Project Financial Plan...

External dose-rate conversion factors of radionuclides for air submersion, ground surface contamination and water immersion based on the new ICRP dosimetric setting.

Science.gov (United States)

Yoo, Song Jae; Jang, Han-Ki; Lee, Jai-Ki; Noh, Siwan; Cho, Gyuseong

2013-01-01

For the assessment of external doses due to contaminated environment, the dose-rate conversion factors (DCFs) prescribed in Federal Guidance Report 12 (FGR 12) and FGR 13 have been widely used. Recently, there were significant changes in dosimetric models and parameters, which include the use of the Reference Male and Female Phantoms and the revised tissue weighting factors, as well as the updated decay data of radionuclides. In this study, the DCFs for effective and equivalent doses were calculated for three exposure settings: skyshine, groundshine and water immersion. Doses to the Reference Phantoms were calculated by Monte Carlo simulations with the MCNPX 2.7.0 radiation transport code for 26 mono-energy photons between 0.01 and 10 MeV. The transport calculations were performed for the source volume within the cut-off distances practically contributing to the dose rates, which were determined by a simplified calculation model. For small tissues for which the reduction of variances are difficult, the equivalent dose ratios to a larger tissue (with lower statistical errors) nearby were employed to make the calculation efficient. Empirical response functions relating photon energies, and the organ equivalent doses or the effective doses were then derived by the use of cubic-spline fitting of the resulting doses for 26 energy points. The DCFs for all radionuclides considered important were evaluated by combining the photon emission data of the radionuclide and the empirical response functions. Finally, contributions of accompanied beta particles to the skin equivalent doses and the effective doses were calculated separately and added to the DCFs. For radionuclides considered in this study, the new DCFs for the three exposure settings were within ±10 % when compared with DCFs in FGR 13.

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

Energy Technology Data Exchange (ETDEWEB)

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

1990-10-01

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.

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

International Nuclear Information System (INIS)

Carpenter, A.B.; Skone, S.S.; Rodenhizer, D.G.; Marusich, M.V.

1990-10-01

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

Radionuclide toxicity

International Nuclear Information System (INIS)

Galle, P.

1982-01-01

The aim of this symposium was to review the radionuclide toxicity problems. Five topics were discussed: (1) natural and artificial radionuclides (origin, presence or emission in the environment, human irradiation); (2) environmental behaviour of radionuclides and transfer to man; (3) metabolism and toxicity of radionuclides (radioiodine, strontium, rare gas released from nuclear power plants, ruthenium-activation metals, rare earths, tritium, carbon 14, plutonium, americium, curium and einsteinium, neptunium, californium, uranium) cancerogenous effects of radon 222 and of its danghter products; (4) comparison of the hazards of various types of energy; (5) human epidemiology of radionuclide toxicity (bone cancer induction by radium, lung cancer induction by radon daughter products, liver cancer and leukaemia following the use of Thorotrast, thyroid cancer; other site of cancer induction by radionuclides) [fr

Medical application of radionuclides and the resulting radiation exposure of parts of the population

International Nuclear Information System (INIS)

Keller, K.D.; Gloebel, B.; Andres, C.

1985-01-01

In a big hospital an investigation was made to find out to what extent the radionuclides used there contribute to the radiation exposure of the population living in the vicinity. The hospital used about 100 Ci of short-lived radionuclides a year. By applying the calculation basis stipulated by the Federal Ministry of the Interior, the radiation exposure was calculated for unfavourable cases. As a result, up to 30 mrem/a can theoretically be reached. (orig.) [de

75 FR 3959 - Fifth Meeting-RTCA Special Committee 220: Automatic Flight Guidance and Control

Science.gov (United States)

2010-01-25

... 220: Automatic Flight Guidance and Control AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of RTCA Special Committee 220: Automatic Flight Guidance and Control meeting. SUMMARY: The FAA is issuing this notice to advise the public of a meeting of RTCA Special Committee 220: Automatic Flight...

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

International Nuclear Information System (INIS)

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

1998-01-01

The present invention is a method of obtaining a radionuclide product selected from the group consisting of 223 Ra and 225 Ac, from a radionuclide ''cow'' of 227 Ac or 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 227 Ac, the at least one daughter radionuclide is a 227 Th and the product radionuclide is the 223 Ra and the first nitrate form ion exchange column passes the 227 Ac and retains the 227 Th. In another embodiment the radionuclide ''cow'' is the 229 Th, the at least one daughter radionuclide is a 225 Ra and said product radionuclide is the 225 Ac and the 225 Ac and nitrate form ion exchange column retains the 229 Th and passes the 225 Ra/Ac. 8 figs

Freedom to Tweet? Opportunities and Barriers for Federal Scientists on Social Media

Science.gov (United States)

Goldman, G. T.; Bailin, D.; Rogerson, P.; Renaud, A.; Halpern, M.; Grifo, F.

2013-12-01

The recent explosion of social media represents a fundamental shift in how scientists can share their work with the world, and federal scientists are taking advantage of these new tools. A 2009 report by the Chief Information Officers (CIO) Council--an interagency forum on federal information-technology management convened under the E-Government Act of 2002--recommends that all federal agencies develop a social media policy to address security concerns and provide guidance to employees on how they should identify themselves in these venues. In response to this report, and to the changing media landscape in general, many federal agencies have since developed polices to clarify how their employees may engage in social media. But how effective are such policies for federal scientists? Past analysis has looked at agency social media policies with an eye on performance metrics or on security and privacy of government information. Here, we assess the policies from a different angle: Do they provide sufficient guidance to government scientists and other technical experts? Do they adequately guide employees in a way that promotes responsible use while also affording them the freedom to use these tools to share their work? And how do different agencies compare? We analyzed policies, conducted a survey of federal scientists, and utilized Freedom of Information Act requests to assess how well federal policies and practices provide guidance and freedom for federal scientists using social media at 17 federal agencies. We found that some agencies have very thorough policies and practices that clearly guide and encourage their employees' use of social media outlets; while others provide minimal to no guidance to their scientists or discourage use of these tools. From this analysis, we identify opportunities for communication of federal science on social media, as well as barriers currently inhibiting federal scientists from using these tools. Finally, we offer recommendations for

Workshop on intakes of radionuclides: occupational and public exposure, Avignon, 15-18 September 1997

International Nuclear Information System (INIS)

Etherington, G.; Phipps, A.W.; Harrison, J.D.; Jones, D.G.; Stradling, G.N.

1998-01-01

This meeting was the fourth in this series of Workshops, previous meetings having been held in Versailles, France in 1988, in Elmau, Germany in 1991, and in Bath, UK in 1993. The Avignon meeting comes at a time of intense activity in internal dosimetry. The International Commission on Radiological Protection (ICRP) has recently completed development and publication of a series of physiologically based age-dependent biokinetic models for a range of important radionuclides. This followed the publication in 1994 of the new Human Respiratory Tract Model (HRTM). These models have now been used to determine the dose coefficients that are given in the EURATOM Directive and in the International Basic Safety Standards. A forthcoming ICRP publication will present predictions of the new models for bioassay quantities of interest, and will give revised guidance on the design and interpretation of internal dosimetry monitoring programmes. Another will give technical guidance on the use of the HRTM in practical situations. Looking further into the future, work on the development of a new age-dependent dosimetric model for the gastro-intestinal tract is now under way. With so many recent and forthcoming developments in modelling, it is not surprising that one of the unifying themes of the meeting was the impending need for internal dosimetry practitioners to be able to use the new models for assessments of doses in the workplace. The meeting's main sessions were organised under five headings: occupational exposure to radionuclides, public exposure to radionuclides, developments in modelling, physical dosimetry and treatment of accidental intakes

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

Science.gov (United States)

Bray, Lane A.; Ryan, Jack L.

1998-01-01

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.

Environmental restoration plans and activities in the Russian Federation

International Nuclear Information System (INIS)

Boldyrev, V.; Komarov, A.; Kuzin, R.; Shatalov, V.

1997-01-01

The report deals with the status of environmental restoration of uranium-contaminated sites and the methods to reduce radionuclides concentration in the solid and liquid wastes as well as their utilization potential. Attention is given to the waste utilization in agriculture and civil engineering construction. With this in view, the paper deals with waste water purification and applicable standards for natural radionuclides content in solid waste for utilization in construction activities. All works are carried out in accordance with the Special Complex Programme for environmental restoration of contaminated uranium mining and milling sites caused by the activities of the industries engaged in nuclear materials production for the Ministry of Atomic Energy of the Russian Federation. The Programme is an integral part of the Federal Programme ''Conversion of Russian Defense Industries in 1993-2000''. (author)

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-08-01

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.

Radionuclides in the ground at the Savannah River Plant

International Nuclear Information System (INIS)

Fenimore, J.W.; Horton, J.H. Jr.

1974-01-01

Savannah River Plant operations have dispersed radionuclides into the ground at more than 25 locations on the plant-site. At some sites decay and natural dispersal processes have reduced the concentration below detectable levels. Other sites will require continuous surveillance and restricted use. The purpose of this report is to tabulate the location of these sites and summarize the data collected from them so that these data will be readily available for future reference and guidance in evaluating and managing these sites. A description of each site and its condition during 1972 is attached. 1 fig

Radionuclide Air Emissions Report for the Hanford Site Calendar year 1998

Energy Technology Data Exchange (ETDEWEB)

DIEDIKER, L.P.

1999-06-15

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

Radionuclide trap

International Nuclear Information System (INIS)

McGuire, J.C.

1978-01-01

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

Glossary of CERCLA, RCRA and TSCA related terms and acronyms. Environmental Guidance

Energy Technology Data Exchange (ETDEWEB)

1993-10-01

This glossary contains CERCLA, RCRA and TSCA related terms that are most often encountered in the US Department of Energy (DOE) Environmental Restoration and Emergency Preparedness activities. Detailed definitions are included for key terms. The CERCLA definitions included in this glossary are taken from the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as amended and related federal rulemakings. The RCRA definitions included in this glossary are taken from the Resource Conservation and Recovery Act (RCRA) and related federal rulemakings. The TSCA definitions included in this glossary are taken from the Toxic Substances and Control Act (TSCA) and related federal rulemakings. Definitions related to TSCA are limited to those sections in the statute and regulations concerning PCBs and asbestos.Other sources for definitions include additional federal rulemakings, assorted guidance documents prepared by the US Environmental Protection Agency (EPA), guidance and informational documents prepared by the US Department of Energy (DOE), and DOE Orders. The source of each term is noted beside the term. Terms presented in this document reflect revised and new definitions published before July 1, 1993.

Bioavailability in ecological risk. Assessment for radionuclides

International Nuclear Information System (INIS)

Garnier-Laplace, J.; Gilbin, R.; Della-Vedova, C.; Adam, C.; Simon, O.; Denison, F.; Beaugelin, K.

2005-01-01

The guidance for performing Ecological Risk Assessments (ERA) in Europe has been published in 2003 in the EC's Technical Guidance Document. This document constitutes the official reference in which current water quality standards and risk assessment approach for metals/metalloids are still mainly based on total or dissolved concentrations. However, it has been recognized that accurate assessment of the bio-available metal fraction is crucial, even if the way to incorporate bioavailability into these procedures is still under discussion. The speciation of a pollutant in the exposure medium is the first factor that regulates its bioavailability and consequently its bioaccumulation and the induced biological effects. Therefore, within any ecological risk assessment, bioavailability has obvious implications: firstly in exposure analysis which aim is to determine Predicted Exposure Concentration (PEC); secondly in effect analysis while deriving the so-called Predicted No-Effect Concentrations (PNEC) as toxicity is often linked to the amount of the contaminant incorporated into the tissues of biota. Similarities between metals/metalloids and radionuclides are limited to the biogeochemical behaviour of the element considered and to the need to use bioavailability models. In addition, for radionuclides, emitted ionising radiations (type and energy) need to be taken into account for both exposure and effect analyses whilst performing dosimetric calculations appropriate to the exposure scenarios. A methodology for properly implementing bioavailability models is explained and illustrated for aqueous U(VI), starting from a comprehensive review of the thermodynamic data relevant to environmentally-realistic physico-chemical conditions. Then, the use of thermodynamic equilibrium modelling as a tool for interpreting the bioavailability of U(VI) is presented. Using a systematic approach, different bioavailability models of increasing complexity were tested to model U bio

Uptake of Radionuclide Metals by SPME Fibers

International Nuclear Information System (INIS)

Duff, M; S Crump, S; Robert Ray, R; Keisha Martin, K; Donna Beals, D

2006-08-01

The Federal Bureau of Investigation (FBI) Laboratory currently does not have on site facilities for handling radioactive evidentiary materials and there are no established FBI methods or procedures for decontaminating high explosive (HE) and fire debris (FD) evidence while maintaining evidentiary value. One experimental method for the isolation of HE and FD residue involves using solid phase microextraction or SPME fibers to remove residue of interest. Due to their high affinity for organics, SPME fibers should have little affinity for most metals. However, no studies have measured the affinity of radionuclides for SPME fibers. The focus of this research was to examine the affinity of dissolved radionuclide ( 239/240 Pu, 238 U, 237 Np, 85 Sr, 133 Ba, 137 Cs, 60 Co and 226 Ra) and stable radionuclide surrogate metals (Sr, Co, Ir, Re, Ni, Ba, Cs, Nb, Zr, Ru, and Nd) for SPME fibers at the exposure conditions that favor the uptake of HE and FD residues. Our results from radiochemical and mass spectrometric analyses indicate these metals have little measurable affinity for these SPME fibers during conditions that are conducive to HE and FD residue uptake with subsequent analysis by liquid or gas phase chromatography with mass spectrometric detection

77 FR 8751 - Guidance for Decommissioning Planning During Operations

Science.gov (United States)

2012-02-15

..., 40, 50, 70, and 72 [NRC-2011-0286] Guidance for Decommissioning Planning During Operations AGENCY... Guide, DG-4014, ``Decommissioning Planning During Operations'' in the Federal Register with a public... Guide DG-4014, ``Decommissioning Planning During Operations.'' This DG refers to NUREG-1757 Volume 3...

Radionuclide cisternography

International Nuclear Information System (INIS)

Song, H.H.

1980-01-01

The purpose of this thesis is to show that radionuclide cisternography makes an essential contribution to the investigation of cerebrospinal fluid (CSF) dynamics, especially for the investigation of hydrocephalus. The technical details of radionuclide cisternography are discussed, followed by a description of the normal and abnormal radionuclide cisternograms. The dynamics of CFS by means of radionuclide cisternography were examined in 188 patients in whom some kind of hydrocephalus was suspected. This study included findings of anomalies associated with hydrocephalus in a number of cases, such as nasal liquorrhea, hygromas, leptomeningeal or porencephalic cysts. The investigation substantiates the value of radionuclide cisternography in the diagnosis of disturbances of CSF flow. The retrograde flow of radiopharmaceutical into the ventricular system (ventricular reflux) is an abnormal phenomenon indicating the presence of communicating hydrocephalus. (Auth.)

Principles of effective USA federal fire management plans

Science.gov (United States)

Meyer, Marc D.; Roberts, Susan L.; Wills, Robin; Brooks, Matthew L.; Winford, Eric M.

2015-01-01

Federal fire management plans are essential implementation guides for the management of wildland fire on federal lands. Recent changes in federal fire policy implementation guidance and fire science information suggest the need for substantial changes in federal fire management plans of the United States. Federal land management agencies are also undergoing land management planning efforts that will initiate revision of fire management plans across the country. Using the southern Sierra Nevada as a case study, we briefly describe the underlying framework of fire management plans, assess their consistency with guiding principles based on current science information and federal policy guidance, and provide recommendations for the development of future fire management plans. Based on our review, we recommend that future fire management plans be: (1) consistent and compatible, (2) collaborative, (3) clear and comprehensive, (4) spatially and temporally scalable, (5) informed by the best available science, and (6) flexible and adaptive. In addition, we identify and describe several strategic guides or “tools” that can enhance these core principles and benefit future fire management plans in the following areas: planning and prioritization, science integration, climate change adaptation, partnerships, monitoring, education and communication, and applied fire management. These principles and tools are essential to successfully realize fire management goals and objectives in a rapidly changing world.

Radionuclides in domestic and imported foods in the United States, 1987-1992

International Nuclear Information System (INIS)

Cunningham, W.C.; Anderson, D.L.; Baratta, E.J.

1994-01-01

Findings from the U.S. Food and Drug Administration's Radionuclides in Foods program are summarized for foods collected between October 1, 1986, and September 30, 1992. Concentrations of radionuclide activity in the Total Diet Study and reactor-survey foods were in Range I or low in Range II of the surveillance and control recommendations of the Federal Radiation Council; no control actions were suggested. Dietary intake of 90 Sr continued the general decline observed since 1961. Approximately 2600 test portions of imported foods were analyzed for contamination associated with the Chernobyl nuclear accident. Concentrations of radionuclide activity were below limits of detection for the vast majority of the imported food test portions but were above the levels of concern for 23 portions. Since 1986, the fraction of imported food test portions having measurable amounts of contamination has steadily declined, as have the average concentrations of radionuclide activity; however, contamination is still occasionally found. Continued monitoring of both domestic and imported foods is planned. 17 refs., 2 figs., 2 tabs

78 FR 76297 - Social Media: Consumer Compliance Risk Management Guidance

Science.gov (United States)

2013-12-17

... encourage the application of uniform examination principles and standards by state and federal supervisory... marketing, providing incentives, facilitating applications for new accounts, inviting feedback from the... responsibilities. The revised Guidance clarifies and points to the longstanding principle that financial...

Criteria for Radionuclide Activity Concentrations for Food and Drinking Water

International Nuclear Information System (INIS)

2016-04-01

Requirements for the protection of people from the harmful consequences of exposure to ionizing radiation, for the safety of radiation sources and for the protection of the environment are established in IAEA Safety Standards Series No. GSR Part 3, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. GSR Part 3 requires that the regulatory body or other relevant authority establish specific reference levels for exposure due to radionuclides in commodities, including food and drinking water. The reference level is based on an annual effective dose to the representative person that generally does not exceed a value of about 1 mSv. International standards have been developed by the Food and Agriculture Organization of the United Nations/World Health Organization (FAO/WHO) Codex Alimentarius Commission for levels of radionuclides contained in food traded internationally that contains, or could potentially contain, radioactive substances as a consequence of a nuclear or radiological emergency. International standards have also been developed by the WHO for radionuclides contained in drinking water, other than in a nuclear or radiological emergency. These international standards provide guidance and criteria in terms of levels of individual radiation dose, levels of activity concentration of specific radionuclides, or both. The criteria derived in terms of levels of activity concentration in the various international standards differ owing to a number of factors and assumptions underlying the common objective of protecting public health in different circumstances. This publication considers the various international standards to be applied at the national level for the assessment of levels of radionuclides in food and in drinking water in different circumstances for the purposes of control, other than in a nuclear or radiological emergency. It collates and provides an overview of the different criteria used in assessing and

77 FR 13384 - Additional Guidance on Airfare/Air Tour Price Advertisements; Correction

Science.gov (United States)

2012-03-06

...The Department published a notice entitled ``Additional Guidance on Airfare/Air Tour Price Advertisements,'' in the Federal Register of February 27, 2012; the notice contained an incorrect address for the Department.

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

Energy Technology Data Exchange (ETDEWEB)

Mark Verdoorn; Tom Haney

2011-06-01

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

78 FR 9396 - Draft Guidance for Industry and Food and Drug Administration Staff; Civil Money Penalties for...

Science.gov (United States)

2013-02-08

...] Draft Guidance for Industry and Food and Drug Administration Staff; Civil Money Penalties for Tobacco... guidance for industry entitled ``Civil Money Penalties for Tobacco Retailers: Responses to Frequently Asked... civil money penalties for violations of regulations issued under the Federal Food, Drug, and Cosmetic...

78 FR 72900 - Guidance for Industry and Food and Drug Administration Staff; Civil Money Penalties for Tobacco...

Science.gov (United States)

2013-12-04

...] Guidance for Industry and Food and Drug Administration Staff; Civil Money Penalties for Tobacco Retailers... the guidance entitled ``Civil Money Penalties for Tobacco Retailers: Responses to Frequently Asked... issuance of civil money penalties for violations of regulations issued under the Federal Food, Drug, and...

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

International Nuclear Information System (INIS)

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

1996-12-01

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

77 FR 11550 - Draft Guidance for Industry on Notification to Food and Drug Administration of Issues That May...

Science.gov (United States)

2012-02-27

... proposed information collected is necessary for the proper performance of FDA's functions, including... the draft guidance for industry entitled: ``Planning for the Effects of High Absenteeism to Ensure Availability of Medically Necessary Drug Products'' (Absenteeism Draft Guidance) published in the Federal...

EARLY GUIDANCE FOR ASSIGNING DISTRIBUTION PARAMETERS TO GEOCHEMICAL INPUT TERMS TO STOCHASTIC TRANSPORT MODELS

International Nuclear Information System (INIS)

Kaplan, D; Margaret Millings, M

2006-01-01

Stochastic modeling is being used in the Performance Assessment program to provide a probabilistic estimate of the range of risk that buried waste may pose. The objective of this task was to provide early guidance for stochastic modelers for the selection of the range and distribution (e.g., normal, log-normal) of distribution coefficients (K d ) and solubility values (K sp ) to be used in modeling subsurface radionuclide transport in E- and Z-Area on the Savannah River Site (SRS). Due to the project's schedule, some modeling had to be started prior to collecting the necessary field and laboratory data needed to fully populate these models. For the interim, the project will rely on literature values and some statistical analyses of literature data as inputs. Based on statistical analyses of some literature sorption tests, the following early guidance was provided: (1) Set the range to an order of magnitude for radionuclides with K d values >1000 mL/g and to a factor of two for K d values of sp values -6 M and to a factor of two for K d values of >10 -6 M. This decision is based on the literature. (3) The distribution of K d values with a mean >1000 mL/g will be log-normally distributed. Those with a K d value <1000 mL/g will be assigned a normal distribution. This is based on statistical analysis of non-site-specific data. Results from on-going site-specific field/laboratory research involving E-Area sediments will supersede this guidance; these results are expected in 2007

ACHP |Partnering to Promote Heritage Tourism in Local Communities: Guidance

Science.gov (United States)

Publications Search skip specific nav links Home arrow Heritage Tourism arrow Partnering to Promote Heritage Tourism in Local Communities: Guidance for Federal Agencies Partnering to Promote Heritage Tourism in historic places. Such tourism - heritage tourism -can result in a variety of tangible and intangible

Speciation analysis of radionuclides

International Nuclear Information System (INIS)

Salbu, B.

2010-01-01

Full text: Naturally occurring and artificially produced radionuclides in the environment can be present in different physico-chemical forms (i. e. radionuclide species) varying in size (nominal molecular mass), charge properties and valence, oxidation state, structure and morphology, density, complexing ability etc. Low molecular mass (LMM) species are believed to be mobile and potentially bioavailable, while high molecular mass (HMM) species such as colloids, polymers, pseudocolloids and particles are considered inert. Due to time dependent transformation processes such as mobilization of radionuclide species from solid phases or interactions of mobile and reactive radionuclide species with components in soils and sediments, however, the original distribution of radionuclides deposited in ecosystems will change over time and influence the ecosystem behaviour. To assess the environmental impact from radionuclide contamination, information on radionuclide species deposited, interactions within affected ecosystems and the time-dependent distribution of radionuclide species influencing mobility and biological uptake is essential. The development of speciation techniques to characterize radionuclide species in waters, soils and sediments should therefore be essential for improving the prediction power of impact and risk assessment models. The present paper reviews fractionation techniques which should be utilised for radionuclide speciation purposes. (author)

Federal Standard: Beneficial Use of Dredged Material

Science.gov (United States)

The purpose of this document is to provide national guidance that explains the role of the Federal Standard in implementing beneficial uses of dredged material from U.S. Army Corps of Engineers’ new and maintenance navigation projects.

Quantitative radionuclide angiocardiography

International Nuclear Information System (INIS)

Scholz, P.M.; Rerych, S.K.; Moran, J.F.; Newman, G.E.; Douglas, J.M.; Sabiston, D.C. Jr.; Jones, R.H.

1980-01-01

This study introduces a new method for calculating actual left ventricular volumes and cardiac output from data recorded during a single transit of a radionuclide bolus through the heart, and describes in detail current radionuclide angiocardiography methodology. A group of 64 healthy adults with a wide age range were studied to define the normal range of hemodynamic parameters determined by the technique. Radionuclide angiocardiograms were performed in patients undergoing cardiac catherization to validate the measurements. In 33 patients studied by both techniques on the same day, a close correlation was documented for measurement of ejection fraction and end-diastolic volume. To validate the method of volumetric cardiac output calcuation, 33 simultaneous radionuclide and indocyanine green dye determinations of cardiac output were performed in 18 normal young adults. These independent comparisons of radionuclide measurements with two separate methods document that initial transit radionuclide angiocardiography accurately assesses left ventricular function

78 FR 14791 - Notice of Issuance of Exposure Draft on Implementation Guidance on General Property, Plant, and...

Science.gov (United States)

2013-03-07

... FEDERAL ACCOUNTING STANDARDS ADVISORY BOARD Notice of Issuance of Exposure Draft on Implementation Guidance on General Property, Plant, and Equipment Cost Accumulation, Assignment, and Allocation AGENCY...) has issued a Federal Financial Accounting Technical Release Exposure Draft entitled Implementation...

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-06-06

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-06-01

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

Pacific Northwest National Laboratory Campus Radionuclide Air Emissions Report for Calendar Year 2014

Energy Technology Data Exchange (ETDEWEB)

Snyder, Sandra F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Barnett, J. Matthew [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bisping, Lynn E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-06-01

This report documents radionuclide air emissions that result in the 2014 highest effective dose equivalent (EDE) to an offsite 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 Campus MEI due to routine major and minor point source emissions in 2014 from PNNL Campus sources is 2E 05 mrem (2E-07 mSv) EDE. The dose from all fugitive sources is 3E-6 mrem (3E-8 mSv) EDE. The dose from radon emissions is 1E-6 mrem (1E-8 mSv) EDE. No nonroutine emissions occurred in 2014. The total radiological dose for 2014 to the MEI from all PNNL Campus radionuclide emissions, including fugitive emissions and radon, is 3E-5 mrem (3E-7 mSv) EDE, or more than 100,000 times smaller than the federal and state standard of 10 mrem/yr, to which the PNNL Campus is in compliance.

Pacific Northwest National Laboratory Campus Radionuclide Air Emissions Report for Calendar Year 2015

Energy Technology Data Exchange (ETDEWEB)

Snyder, Sandra F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Barnett, J. Matthew [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bisping, Lynn E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2016-06-01

This report documents radionuclide air emissions that result in the 2015 highest effective dose equivalent (EDE) to an offsite 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 Campus MEI from routine major and minor point source emissions in 2015 from PNNL Campus sources is 2.6E-4 mrem (2.6E-6 mSv) EDE. The dose from all fugitive sources is 1.8E-6 mrem (1.8E-8 mSv) EDE. The dose from radon emissions is 4.4E-8 mrem (4.4E-10 mSv) EDE. No nonroutine emissions occurred in 2015. The total radiological dose to the MEI from all PNNL Campus radionuclide emissions, including fugitive emissions and radon, is 2.6E-4 mrem (2.6E-6 mSv) EDE, or more than 10,000 times less than the federal and state standard of 10 mrem/yr, with which the PNNL Campus is in compliance.

1986 imports and exports of radionuclides

International Nuclear Information System (INIS)

Anon.

1987-01-01

The statistics compiled by the German Federal Office for Industry (Bundesamt fuer Wirtschaft), on behalf of the Federal Ministry for the Environment, Protection of Nature, and Reactor Safety, of the imports and exports of radionuclides, irradiation samples, and sealed emitters of more than 1850 GBq show an enormous increase by 152.7% of imports (on the basis of activity) and a decline by 19.5% of exports. In the category of imports, some 98% of the total activity were made up of the H-3, Co-60, Mo-99, and Ir-192 nuclides. In the category of sealed emitters, the imports of Co-60 have trebled. In the exports category, more than 95% of the total activity were made up of the H-3, Mo-99, and Ir-192 nuclides. In the category of sealed emitters, exports of Cs-137 experienced a fourfold increase over the level of the previous year. (orig.) [de

Planning guidance for the Chemical Stockpile Emergency Preparedness Program

Energy Technology Data Exchange (ETDEWEB)

Shumpert, B.L.; Watson, A.P.; Sorensen, J.H. [and others

1995-02-01

This planning guide was developed under the direction of the U.S. Army and the Federal Emergency Management Agency (FEMA) which jointly coordinate and direct the development of the Chemical Stockpile Emergency Preparedness Program (CSEPP). It was produced to assist state, local, and Army installation planners in formulating and coordinating plans for chemical events that may occur at the chemical agent stockpile storage locations in the continental United States. This document provides broad planning guidance for use by both on-post and off-post agencies and organizations in the development of a coordinated plan for responding to chemical events. It contains checklists to assist in assuring that all important aspects are included in the plans and procedures developed at each Chemical Stockpile Disposal Program (CSDP) location. The checklists are supplemented by planning guidelines in the appendices which provide more detailed guidance regarding some issues. The planning guidance contained in this document will help ensure that adequate coordination between on-post and off-post planners occurs during the planning process. This planning guide broadly describes an adequate emergency planning base that assures that critical planning decisions will be made consistently at every chemical agent stockpile location. This planning guide includes material drawn from other documents developed by the FEMA, the Army, and other federal agencies with emergency preparedness program responsibilities. Some of this material has been developed specifically to meet the unique requirements of the CSEPP. In addition to this guidance, other location-specific documents, technical studies, and support studies should be used as needed to assist in the planning at each of the chemical agent stockpile locations to address the specific hazards and conditions at each location.

Features of DOE implementation of radiation protection guidance

International Nuclear Information System (INIS)

Jarrett, R.D.; Foulke, J.D.; Jones, C.R.

1991-01-01

In 1988 the Department of Energy became the first Federal agency to adopt the Presidential Guidance prepared by the Environmental Protection Agency, which incorporated the recommendations of the International Commission on Radiological Protection published in 1977. The most important provisions adopted are discussed in this paper. Two controversial issues are also discussed. Problem areas which gave rise to proposed revisions are explained

The Role of the Federal Standard in the Beneficial Use of Dredged Material

Science.gov (United States)

A guide for USACE Districts, other federal agencies, state agencies, local governments, and private interest groups. The Federal Standard Paper provides guidance on using dredged material as a resource to achieve environmental and economic benefits.

GUIDANCE COUNSELOR INSTITUTE FOR HEALTH CAREERS (JULY 7-22, 1966).

Science.gov (United States)

MORGAN, PHILIP W.

THE INSTITUTE, SPONSORED BY A FEDERATED CHARITY REPRESENTING 78 NONPROFIT VOLUNTARY HOSPITALS IN NEW YORK CITY, WAS ATTENDED BY 48 HIGH SCHOOL AND EMPLOYMENT SERVICE COUNSELORS. THE NEED FOR SUCH INSTITUTES WAS DOCUMENTED BY A PRE-INSTITUTE QUESTIONNAIRE TO LICENSED GUIDANCE COUNSELORS. TO EVALUATE THE INSTITUTE, THE PROFESSIONAL EXAMINATION…

Spectrometric control of radionuclides production parameters

International Nuclear Information System (INIS)

Zhuk, I.; Potarenko, A.; Yarochevich, O.; Hluboky, N.; Kerko, P.; Bogdanov, V.; Dyatel, N.

2006-01-01

Full text: A radioactive preparations and sources are widely used all over the world for scientific, industrial and medical purposes. These preparations in Belarus are planned to produce by the Joint Belarussian-Russian Closed Joint Stock Company 'Isotope technologies' (CJSC IT). The company was created in 1998 by two leading scientific centers-SSI 'Joint Institute of Power and Nuclear Research-Sosny' the National Academy of Sciences of Belarus and the State Center of Science of the Russian Federation 'Scientific research institute of nuclear reactors'. One of the mainstream directions in CJSC IT activities is production of radioactive preparations for the industrial and scientific application (such as 133 Ba, 109 Cd, 63 Ni, 60 Co) and for the medical purposes (such as 19 '2Ir, 60 Co). All radioactive preparations have a good export potential and adequate to modern technical and consumer requirements. X-γ spectrometric analysis of considered radioactive sources is one of the basic methods for quality control of radioactive sources. At present, we are developing x-γ spectrometric support of purification process from contaminating radionuclides of 109 Cd -γ preparation and 63 Ni - β preparation. Work on x-γ spectrometric quality control of 133 Ba preparation is carried out. The description of the used equipment is given. Techniques of contaminating radionuclides determination (contents ∼10 - '6 from activity of the basic radionuclide) are presented. Problems of the choice of geometry of measurements of sources with activity about 10 7 -10 9 Bq and possible sources of errors are discussed. (author)

Radionuclide fixation mechanisms in rocks

International Nuclear Information System (INIS)

Nakashima, S.

1991-01-01

In the safety evaluation of the radioactive waste disposal in geological environment, the mass balance equation for radionuclide migration is given. The sorption of radionuclides by geological formations is conventionally represented by the retardation of the radionuclides as compared with water movement. In order to quantify the sorption of radionuclides by rocks and sediments, the distribution ratio is used. In order to study quantitatively the long term behavior of waste radionuclides in geological environment, besides the distribution ratio concept in short term, slower radionuclide retention reaction involving mineral transformation should be considered. The development of microspectroscopic method for long term reaction path modeling, the behavior of iron during granite and water interaction, the reduction precipitation of radionuclides, radionuclide migration pathways, and the representative scheme of radionuclide migration and fixation in rocks are discussed. (K.I.)

Marine biogeochemistry of radionuclides

International Nuclear Information System (INIS)

Fowler, S.W.

1997-01-01

Radionuclides entering the ocean from runoff, fallout, or deliberate release rapidly become involved in marine biogeochemical cycles. Sources, sinks and transport of radionuclides and analogue elements are discussed with emphasis placed on how these elements interact with marine organisms. Water, food and sediments are the source terms from which marine biota acquire radionuclides. Uptake from water occurs by surface adsorption, absorption across body surfaces, or a combination of both. Radionuclides ingested with food are either assimilated into tissue or excreted. The relative importance of the food and water pathway in uptake varies with the radionuclide and the conditions under which exposure occurs. Evidence suggests that, compared to the water and food pathways, bioavailability of sediment-bound radionuclides is low. Bioaccumulation processes are controlled by many environmental and intrinsic factors including exposure time, physical-chemical form of the radionuclide, salinity, temperature, competitive effects with other elements, organism size, physiology, life cycle and feeding habits. Once accumulated, radionuclides are transported actively by vertical and horizontal movements of organisms and passively by release of biogenic products, e.g., soluble excreta, feces, molts and eggs. Through feeding activities, particles containing radionuclides are ''packaged'' into larger aggregates which are redistributed upon release. Most radionuclides are not irreversibly bound to such particles but are remineralized as they sink and/or decompose. In the pelagic zones, sinking aggregates can further scavenge particle-reactive elements thus removing them from the surface layers and transporting them to depth. Evidence from both radiotracer experiments and in situ sediment trap studies is presented which illustrates the importance of biological scavenging in controlling the distribution of radionuclides in the water column. (author)

75 FR 22601 - Draft Guidance for Industry and Food and Drug Administration Staff; User Fees for 513(g...

Science.gov (United States)

2010-04-29

...] Draft Guidance for Industry and Food and Drug Administration Staff; User Fees for 513(g); Requests for... the Internet. To receive ``Draft Guidance for Industry and Food and Drug Administration Staff; User... and Industry Procedures for Section 513(g) Requests for Information under the Federal Food, Drug, and...

Report on the intercomparison run and certified reference material IAEA-381. Radionuclides in Irish sea water

International Nuclear Information System (INIS)

Povinec, P.P.; Pham, M.K.; Ballestra, S.

1999-01-01

The accurate and precise determinations of radionuclide concentrations in marine samples are important aspects of marine radioactivity assessments and the use of radionuclides in studies of oceanographic processes. To address the problem of data quality, the IAEA Marine Environment Laboratory (MEL) in Monaco has conducted intercomparison exercises on radionuclides in marine samples for many years as part of its contribution to the IAEA's programme of Analytical Quality Control Services (AQCS). For this intercomparison exercise, the Federal Maritime and Hydrographic Agency, Hamburg, Germany (BSH) collected sea water from the Irish Sea in 1993. IAEA-MEL distributed sample aliquots during 1995-1996 for intercomparison of anthropogenic and natural radionuclides. About 80 laboratories world-wide were approached with a questionnaire for participation. Of these, only 43 accepted the invitation because of financial constraints (the participating laboratories were asked to pay transportation expenses). As the sample was collected in the Irish Sea, elevated levels of anthropogenic radionuclides were expected due to discharges from the Sellafield reprocessing plant. Participants were informed that the expected activities for anthropogenic radionuclides would be in the ranges: 90 Sr: 50-500 Bq/kg, 137 Cs: 100-1000 Bq/kg, 239+240 Pu: 1-50Bq/kg, 241 Am: 1-50Bq/kg. This report describes the results obtained from 28 laboratories on anthropogenic and natural radionuclide determinations in sea water

Web Usage Mining Analysis of Federated Search Tools for Egyptian Scholars

Science.gov (United States)

Mohamed, Khaled A.; Hassan, Ahmed

2008-01-01

Purpose: This paper aims to examine the behaviour of the Egyptian scholars while accessing electronic resources through two federated search tools. The main purpose of this article is to provide guidance for federated search tool technicians and support teams about user issues, including the need for training. Design/methodology/approach: Log…

Comparison of the Radionuclides Dispersion at the UAE Barakah Site with that at the ROK Shin-Kori Site - Comparison of the radionuclides dispersion in Barakah site with that in Shin-Kori site

Energy Technology Data Exchange (ETDEWEB)

Kim, Sung-yeop; Lee, Kun Jai; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of); Beeley, Philip A. [Khalifa University of Science, Technology and Research, P.O. Box 127788, Abu Dhabi (United Arab Emirates)

2014-07-01

In order to understand the characteristics of atmospheric dispersion of radionuclides in the desert environment of Barakah site in UAE, comparison research with the results of other environments could be an appropriate way to facilitate it. Shin-Kori site is the proper comparison target because same reactor type of APR1400 with that in Barakah site is under construction. Hypothetical accident scenario was considered and accident source term which had been developed in previous research has been applied as releasing source. After reviewing several computation codes, ADMS5 has been selected as an atmospheric dispersion modeling tool which is installing advanced Gaussian plum model and plentiful options. The climate data of both Barakah and Shin-Kori were acquired and the environments of both sites have been simulated considering wind speed, wind direction, temperature, humidity, ground surface roughness and etc. Near field final human doses on the maps have been schematised regarding statistical meteorological data of both sites and dose conversion factors from the publications of ICRP and federal guidance report of EPA. The results of this research are expected to enhance the understanding about differences between two environments which have same reactor type and to improve the comprehension of desert environment of Barakah site as well. Applying different dose conversion factors to Barakah site considering the desert biosphere could be further study to obtain more accurate results. (authors)

75 FR 22599 - Draft Guidance for Industry and Food and Drug Administration Staff; Food and Drug Administration...

Science.gov (United States)

2010-04-29

...] Draft Guidance for Industry and Food and Drug Administration Staff; Food and Drug Administration and Industry Procedures for Section 513(g) Requests for Information Under the Federal Food, Drug, and Cosmetic... and Industry Procedures for Section 513(g) Requests for Information Under the Federal Food, Drug, and...

Radionuclide generators

International Nuclear Information System (INIS)

Lambrecht, R.M.; Wollongong Univ.; Tomiyoshi, K.; Sekine, T.

1997-01-01

The present status and future directions of research and development on radionuclide generator technology are reported. The recent interest to develop double-neutron capture reactions for production of in vivo generators; neutron rich nuclides for radio-immunotherapeutic pharmaceuticals: and advances with ultra-short lived generators is highlighted. Emphasis is focused on: production of the parent radionuclide; the selection and the evaluation of support materials and eluents with respect to the resultant radiochemical yield of the daughter, and the breakthrough of the radionuclide parent: and, the uses of radionuclide generators in radiopharmaceutical chemistry, biomedical and industrial applications. The 62 Zn → 62 Cu, 66 Ni → 66 Cu, 103m Rh → 103 Rh, 188 W → 188 Re and the 225 Ac → 221 Fr → 213 Bi generators are predicted to be emphasized for future development. Coverage of the 99 Mo → 99m Tc generator was excluded, as it the subject of another review. The literature search ended June, 1996. (orig.)

International guidance on clearance criteria for application to materials containing radionuclides

International Nuclear Information System (INIS)

Linsley, G.

1999-01-01

The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources establish the conditions whereby radiation sources can be released from control. The essential principle behind this concept, termed clearance, is that the risks associated with the released source should be trivially small. The concept has been widely applied and practically applicable clearance levels have been derived for use in regulating the recycling and reuse of materials originating from the nuclear industry. Since materials released from controls may be traded between countries in the same way as any other material, it is necessary to have international agreements on acceptable levels of radioactivity in materials so as to provide a basis for regulating such movements. The International Atomic Energy Agency, in concert with other international bodies, has for many years been engaged in promoting discussions between its Member States in this subject area. International guidance has been produced and discussions are continuing towards reaching a full consensus on internationally accepted clearance levels. (author)

Activity measurements of {sup 18}F and {sup 90}Y with commercial radionuclide calibrators for nuclear medicine in Switzerland

Energy Technology Data Exchange (ETDEWEB)

Caffari, Yvan, E-mail: Yvan.Caffari@chuv.c [Institut de Radiophysique Appliquee, Grand-Pre 1, 1007 Lausanne (Switzerland); Spring, Philippe; Bailat, Claude; Nedjadi, Youcef; Bochud, Francois [Institut de Radiophysique Appliquee, Grand-Pre 1, 1007 Lausanne (Switzerland)

2010-07-15

The activity of radiopharmaceuticals in nuclear medicine is measured before patient injection with radionuclide calibrators. In Switzerland, the general requirements for quality controls are defined in a federal ordinance and a directive of the Federal Office of Metrology (METAS) which require each instrument to be verified. A set of three gamma sources (Co-57, Cs-137 and Co-60) is used to verify the response of radionuclide calibrators in the gamma energy range of their use. A beta source, a mixture of {sup 90}Sr and {sup 90}Y in secular equilibrium, is used as well. Manufacturers are responsible for the calibration factors. The main goal of the study was to monitor the validity of the calibration factors by using two sources: a {sup 90}Sr/{sup 90}Y source and a {sup 18}F source. The three types of commercial radionuclide calibrators tested do not have a calibration factor for the mixture but only for {sup 90}Y. Activity measurements of a {sup 90}Sr/{sup 90}Y source with the {sup 90}Y calibration factor are performed in order to correct for the extra-contribution of {sup 90}Sr. The value of the correction factor was found to be 1.113 whereas Monte Carlo simulations of the radionuclide calibrators estimate the correction factor to be 1.117. Measurements with {sup 18}F sources in a specific geometry are also performed. Since this radionuclide is widely used in Swiss hospitals equipped with PET and PET-CT, the metrology of the {sup 18}F is very important. The {sup 18}F response normalized to the {sup 137}Cs response shows that the difference with a reference value does not exceed 3% for the three types of radionuclide calibrators.

Radionuclides in terrestrial ecosystems

International Nuclear Information System (INIS)

Allen, S.E.; Horrill, A.D.; Howard, B.J.; Lowe, V.P.W.; Parkinson, J.A.

1983-07-01

The subject is discussed under the headings: concentration and spatial distribution of radionuclides in grazed and ungrazed saltmarshes; incorporation of radionuclides by sheep grazing on an estuarine saltmarsh; inland transfer of radionuclides by birds feeding in the estuaries and saltmarshes at Ravenglass; radionuclides in contrasting types of coastal pastures and taken up by individual plant species found in west Cumbria; procedures developed and used for the measurement of alpha and gamma emitters in environmental materials. (U.K.)

Radionuclide data

International Nuclear Information System (INIS)

Anon.

1992-01-01

Chapter 8 presents tables on selected alpha, beta, gamma and x-ray emitters by increasing energy; information on specific activity for selected radionuclides; naturally occurring radionuclides; the natural decay series; and the artificially produced neptunium series. A table of alpha emitters is listed by increasing atomic number and by energy. The table of β emitters presented is useful in identifying β emitters whose energies and possibly half-lives have been determined by standard laboratory techniques. It is also a handy guide to β-emitting isotopes for applications requiring specific half-lives and/or energies. Gamma rays for radionuclides of importance to radiological assessments and radiation protection are listed by increasing energy. The energies and branching ratios are important for radionuclide determinations with gamma spectrometry detectors. This section also presents a table of x-ray energies which are useful for radiochemical analyses. A number of nuclides emit x-rays as part of their decay scheme. These x-rays may be counted with Ar proportional counters, Ge planar or n-type Ge co-axial detectors, or thin crystal NaI(T1) scintillation counters. In both cases, spectral measurements can be made and both qualitative and quantitative information obtained on the sample. Nuclear decay data (energy and probability by radiation type) for more than one hundred radionuclides that are important to health physicists are presented in a schematic manner

Economic and technical assay of the application of radionuclide technology

International Nuclear Information System (INIS)

Emrich, F.G.

1976-05-01

The dynamically loaded components of combustion engines undergo wear during operation as a function of the operating points and the operating parameters selected. Radionuclide measurement methods developed in the Federal Republic of Germany in the LIT laboratory of Gesellschaft fuer Kernforschung allow to determine the wear of machine components during operation, contrary to conventional length measurement techniques. In the first part of this work the existing wear problems will be analyzed and investigations will be made into the capacities of conventional and radionuclide measurement methods. Based on this, a cost-benefit analysis system was developed for evaluation under technical and economical aspects of the use of different measurement methods allowing to solve detailed wear problems. This system furnishes results on the respective optimum wear measurement method relating to the actual problem and taking into account the relevant technical and economical boundary conditions. (orig.) [de

78 FR 17660 - Draft Guidance for E85 Flexible Fuel Vehicle Weighting Factor for Model Years 2016-2019 Vehicles...

Science.gov (United States)

2013-03-22

... ENVIRONMENTAL PROTECTION AGENCY [FRL-9792-9] Draft Guidance for E85 Flexible Fuel Vehicle... draft EPA guidance to auto manufacturers for weighting the greenhouse gas (GHG) emissions of a flexible... all federal government work days from 8:30 a.m. to 4:30 p.m.; generally, it is open Monday through...

NARAC: an emergency response resource for predicting the atmospheric dispersion and assessing the consequences of airborne radionuclides

International Nuclear Information System (INIS)

Bradley, Michael M.

2007-01-01

The National Atmospheric Release Advisory Center (NARAC) serves as a national resource for the United States, providing tools and services to quickly predict the environmental contamination and health effects caused by airborne radionuclides, and to provide scientifically based guidance to emergency managers for the protection of human life. NARAC's scientists have developed a diverse tool kit of numerical modeling capabilities to respond to different types of release events, distance scales (local, regional, continental, and global), and response times

RADBASE: A PC-based radionuclide data base for environmental site assessment

International Nuclear Information System (INIS)

Dundon, S.T.; Heger, A.S.

1992-01-01

A personal computer-based code, RADBASE, is being developed as a tool for reviewing environmental risk data. RADBASE has been designed to display the properties of radionuclides encountered in environmental restoration programs. The code contains five major features that display (a) physical properties, (b) pathways and toxicity data, (c) means of production and common uses, (d) federal radiation protection standards and action levels, and (e) bibliographic information. The benefits of the radionuclide data base contained in this code include time efficiency and update capability. This code separates itself from similar codes on the basis of its interactive data files, windows environment, and content. The user must only be equipped with basic information on a site and possess a minimum amount of user knowledge to operate and access additional data applicable to the constituents at the site

Radionuclide generators

International Nuclear Information System (INIS)

Lambrecht, R.M.

1983-01-01

The status of radionuclide generators for chemical research and applications related to the life sciences and biomedical research are reviewed. Emphasis is placed upon convenient, efficient and rapid separation of short-lived daughter radionuclides in a chemical form suitable for use without further chemical manipulation. The focus is on the production of the parent, the radiochemistry associated with processing the parent and daughter, the selection and the characteristic separation methods, and yields. Quality control considerations are briefly noted. The scope of this review includes selected references to applications of radionuclide generators in radiopharmaceutical chemistry, and the life sciences, particularly in diagnostic and therapeutic medicine. The 99 Mo-sup(99m)Tc generator was excluded. 202 references are cited. (orig.)

Russian Federation

International Nuclear Information System (INIS)

2001-01-01

In the Russian Federation (RF), management of radioactive wastes will be carried out within the framework of the Federal Target Program for management of radioactive wastes and used nuclear materials for the period 1996-2005. The agency within the RF responsible for this program is the Ministry of Russian Federation on Atomic Energy. Current radioactive waste disposal activities are focused on creating regional repositories for wastes generated by radiochemical production, nuclear reactors, science centers, and from other sources outside of the nuclear-fuel cycle (the latter wastes are managed by Scientific and Industrial Association, 'RADON'). Wastes of these types are in temporary storage, with the exception of non-fuel cycle wastes which are in long term storage managed by SAI 'RADON'. The criteria for segregating between underground or near-surface disposal of radioactive waste are based on the radiation fields and radionuclide composition of the wastes. The most progress in creating regional repositories has been made in the Northwest region of Russia. However, development of a detailed design has begun for a test facility in the Northeast for disposal of radioactive wastes generated in Murmansk and Arkhangelsk provinces. The feasibility study for construction of this facility is being evaluated by state monitoring organizations, the heads of administrations of the Arkhangelsk and Murmansk provinces, and Minatom of Russia

Environmental Baseline File for National Transportation

International Nuclear Information System (INIS)

1999-01-01

This Environmental Baseline File summarizes and consolidates information related to the national-level transportation of commercial spent nuclear fuel. Topics address include: shipments of commercial spent nuclear fuel based on mostly truck and mostly rail shipping scenarios; transportation routing for commercial spent nuclear fuel sites and DOE sites; radionuclide inventories for various shipping container capacities; transportation routing; populations along transportation routes; urbanized area population densities; the impacts of historical, reasonably foreseeable, and general transportation; state-level food transfer factors; Federal Guidance Report No. 11 and 12 radionuclide dose conversion factors; and national average atmospheric conditions

Environmental Baseline File National Transportation

International Nuclear Information System (INIS)

Harris, M.

1999-01-01

This Environmental Baseline File summarizes and consolidates information related to the national-level transportation of commercial spent nuclear fuel. Topics addressed include: shipments of commercial spent nuclear fuel based on mostly truck and mostly rail shipping scenarios; transportation routing for commercial spent nuclear fuel sites and DOE sites; radionuclide inventories for various shipping container capacities; transportation routing; populations along transportation routes; urbanized area population densities; the impacts of historical, reasonably foreseeable, and general transportation; state-level food transfer factors; Federal Guidance Report No. 11 and 12 radionuclide dose conversion factors; and national average atmospheric conditions

Radionuclides in radiation-induced bystander effect; may it share in radionuclide therapy?

Science.gov (United States)

Widel, M

2017-01-01

For many years in radiobiology and radiotherapy predominated the conviction that cellular DNA is the main target for ionizing radiation, however, the view has changed in the past 20 years. Nowadays, it is assumed that not only directed (targeted) radiation effect, but also an indirect (non-targeted) effect may contribute to the result of radiation treatment. Non-targeted effect is relatively well recognized after external beam irradiation in vitro and in vivo, and comprises such phenomena like radiation-induced bystander effect (RIBE), genomic instability, adaptive response and abscopal (out of field) effect. These stress-induced and molecular signaling mediated phenomena appear in non-targeted cells as variety responses resembling that observed in directly hit cells. Bystander effects can be both detrimental and beneficial in dependence on dose, dose-rate, cell type, genetic status and experimental condition. Less is known about radionuclide-induced non-targeted effects in radionuclide therapy, although, based on characteristics of the radionuclide radiation, on experiments in vitro utilizing classical and 3-D cell cultures, and preclinical study on animals it seems obvious that exposure to radionuclide is accompanied by various bystander effects, mostly damaging, less often protective. This review summarizes existing data on radionuclide induced bystander effects comprising radionuclides emitting beta- and alpha-particles and Auger electrons used in tumor radiotherapy and diagnostics. So far, separation of the direct effect of radionuclide decay from crossfire and bystander effects in clinical targeted radionuclide therapy is impossible because of the lack of methods to assess whether, and to what extent bystander effect is involved in human organism. Considerations on this topic are also included.

A Conceptual Framework for Allocation of Federally Stockpiled Ventilators During Large-Scale Public Health Emergencies.

Science.gov (United States)

Zaza, Stephanie; Koonin, Lisa M; Ajao, Adebola; Nystrom, Scott V; Branson, Richard; Patel, Anita; Bray, Bruce; Iademarco, Michael F

2016-01-01

Some types of public health emergencies could result in large numbers of patients with respiratory failure who need mechanical ventilation. Federal public health planning has included needs assessment and stockpiling of ventilators. However, additional federal guidance is needed to assist states in further allocating federally supplied ventilators to individual hospitals to ensure that ventilators are shipped to facilities where they can best be used during an emergency. A major consideration in planning is a hospital's ability to absorb additional ventilators, based on available space and staff expertise. A simple pro rata plan that does not take these factors into account might result in suboptimal use or unused scarce resources. This article proposes a conceptual framework that identifies the steps in planning and an important gap in federal guidance regarding the distribution of stockpiled mechanical ventilators during an emergency.

Guidance on the application of quality assurance for characterizing a low-level radioactive waste disposal site

International Nuclear Information System (INIS)

Pittiglio, C.L. Jr.; Starmer, R.J.; Hedges, D.

1990-10-01

This document provides the Nuclear Regulatory Commission's staff guidance to an applicant on meeting the quality control (QC) requirements of Title 10 of the Code of Federal Regulations, Part 61, Section 61.12 (10 CFR 61.12), for a low-level waste disposal facility. The QC requirements combined with the requirements for managerial controls and audits are the basis for developing a quality assurance (QA) program and for the guidance provided herein. QA guidance is specified for site characterization activities necessary to meet the performance objectives of 10 CFR Part 61 and to limit exposure to or the release of radioactivity. 1 tab

Radionuclide cardiography in medical practice

International Nuclear Information System (INIS)

Strangfeld, D.; Mohnike, W.; Schmidt, J.; Heine, H.; Correns, H.J.

1986-01-01

This publication is a compendium on all aspects of radionuclide diagnostics concerning cardiovascular system diseases. Starting with introductory remarks on the control of cardiovascular diseases the contribution of radionuclide cardiology to functional cardiovascular diagnostics as well as pathophysiological and pathobiochemical aspects of radiocardiography are outlined. Radiopharmaceuticals used in radiocardiography, physical and technical problems in application of radionuclides and their measuring techniques are discussed. In individual chapters radionuclide ventriculography, myocardial scintiscanning, circulatory diagnostics, radionuclide diagnostics of arterial hypertension, of thrombosis and in vitro diagnostics of thrombophilia are treated in the framework of clinical medicine

Metabolism of radionuclides in domestic animals

International Nuclear Information System (INIS)

Wirth, E.; Leising, C.

1986-01-01

The reactor accident at Chernobyl has shown that shortly after the contamination of the environment radionuclides can be found in animal products. The main contamination pathways of domestic animas are: uptake of radionuclides by foodstuffs; uptake of radionuclides by contaminated drinking water; uptake of radionuclides by inhalation; uptake of radionuclides through skin; uptake of radionuclides by ingestion of soil particles. Generally the uptake of radionuclides by food is the dominant exposure pathway. In rare cases the inhalation of radionuclides or the uptake by drinking water may be of importance. The metabolism of incorporated radionuclides is comparable to the respective metabolism of essential mass or trace elements or heavy metals. Radioisotopes of essential elements are for instance iron 55, manganese 54, cobalt 58 and cobalt 60. Other elements are typical antagonists to essential elements, e.g. strontium 90 is an antagonist to calcium or cesium 137 to potassium. Lead 210 and plutonium 239 behave similarly as heavy metals. Generally the knowledge of the metabolism of trace and mass elements, of antagonistic and synergistic elements and heavy metals can be applied to these radionuclides

Radionuclide scanning

International Nuclear Information System (INIS)

Shapiro, B.

1986-01-01

Radionuclide scanning is the production of images of normal and diseased tissues and organs by means of the gamma-ray emissions from radiopharmaceutical agents having specific distributions in the body. The gamma rays are detected at the body surface by a variety of instruments that convert the invisible rays into visible patterns representing the distribution of the radionuclide in the body. The patterns, or images, obtained can be interpreted to provide or to aid diagnoses, to follow the course of disease, and to monitor the management of various illnesses. Scanning is a sensitive technique, but its specificity may be low when interpreted alone. To be used most successfully, radionuclide scanning must be interpreted in conjunction with other techniques, such as bone radiographs with bone scans, chest radiographs with lung scans, and ultrasonic studies with thyroid scans. Interpretation is also enhanced by providing pertinent clinical information because the distribution of radiopharmaceutical agents can be altered by drugs and by various procedures besides physiologic and pathologic conditions. Discussion of the patient with the radionuclide scanning specialist prior to the study and review of the results with that specialist after the study are beneficial

Release criteria for patients having undergone radionuclide therapy and criteria for their crossing the state border of the Russian Federation

International Nuclear Information System (INIS)

Zvonova, I.; Balonov, M.; Golikov, V.

2011-01-01

By means of a conservative dosimetry model, the values of operational radiological criteria for patients released from hospital-residual activity in a body and dose rate near the patient's body-are substantiated based on the effective dose limit of 5 mSv for persons helping the patient or living with him and 1 mSv for other adults and children. Two sets of operative criteria for radionuclides 125 I, 131 I, 153 Sm and 188 Re used in Russia for radionuclide therapy were derived. Release criteria for 125 I well differ from such values in other countries because in this work absorption of 125 I low-energy photon radiation in the patient was taken into account. When a patient having undergone radionuclide therapy crosses the frontier of Russia, high-sensitivity devices for radiation control at the custom can detect the patient. A simplified radiological assessment of the patient was suggested aimed at provision of radiation safety for patient companions in transport. (authors)

Assessing radiation doses to the public from radionuclides in timber and wood products

International Nuclear Information System (INIS)

2003-10-01

In the event of a nuclear accident involving the release of radionuclides to the biosphere the radioactive contamination of forests can become a significant potential source of public radiation exposure. Two of these accidents - the Kyshtim accident, Urals, USSR (now Russian Federation) in 1957 and the Chernobyl accident, USSR (now Ukraine), in 1986 - resulted in significant contamination of thousands of square kilometres of forested areas with mixtures of radionuclides including long lived fission products such as 137 Cs and 90 Sr. Measurements and modelling of forest ecosystems after both accidents have shown that, following initial contamination, the activity concentration of long lived radionuclides in wood gradually increases over one to two decades and then slowly decreases in the subsequent period. The longevity of the contamination is due to the slow migration and persistent bioavailability of radionuclides in the forest soil profile, which results in long term transfer into wood through the root system of the trees. Another source of contamination is from global radioactive fallout after nuclear weapons tests, but the level of contamination is much lower than that from, for example, the Chernobyl accident. For instance, the level of 137 Cs in wood in Sweden is about 2-5 Bq kg -1 from global fallout. Global values are very similar to the Swedish levels. In contrast, the level of 137 Cs in Swedish wood due to Chernobyl is around 50 Bq kg -1 . Levels in wood from some contaminated areas located in countries of the Former Soviet Union (FSU) are about one to two orders of magnitude higher than this. The data on 137 Cs soil contamination within European territories, originating mainly from the Chernobyl accident, illustrate the scale of the problem. For comparison, residual 137 Cs soil deposition in Europe from global radioactive fallout was in the range 1-4 kBq m -2 . There is concern in several countries about the potential radiation exposure of people from

Drift-Scale Radionuclide Transport

International Nuclear Information System (INIS)

Houseworth, J.

2004-01-01

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

Analysis of radionuclides in airborne effluents from coal-fired power plants

Energy Technology Data Exchange (ETDEWEB)

Rosner, G.; Chatterjee, B.; Hoetzl, H.; Winkler, R.

1982-01-01

In order to assess the level of radioactivity emitted by coal-fired power plants in detail, specific activities of several radionuclides have been measured in samples from a coal-fired and a brown coal-fired plant in the Federal Republic of Germany. Samples measured included coal, brown coal, bottom ash, collected fly ash from the various electrostatic precipitator stages and sieve fractions of collected fly ash as well as samples of escaping fly ash taken from the exhaust stream, all taken simultaneously on three operating days. Nuclides measured were U-238, U-234, Th-232, Th-230, Th-228, Ra-226, Pb-210, Po-210 and K-40. Methods applied included (i) direct gamma spectrometry, (ii) radiochemical separation with subsequent alpha spectrometry and (iii) direct alpha spectrometry. Methods are described and discussed. Finally, annual emission rates of airborne radionuclides are calculated for both plants.

Analysis of radionuclides in airborne effluents from coal-fired power plants

International Nuclear Information System (INIS)

Rosner, G.; Chatterjee, B.; Hoetzl, H.; Winkler, R.

1982-01-01

In order to assess the level of radioactivity emitted by coal-fired power plants in detail, specific activities of several radionuclides have been measured in samples from a coal-fired and a brown coal-fired plant in the Federal Republic of Germany. Samples measured included coal, brown coal, bottom ash, collected fly ash from the various electrostatic precipitator stages and sieve fractions of collected fly ash as well as samples of escaping fly ash taken from the exhaust stream, all taken simultaneously on three operating days. Nuclides measured were U-238, U-234, Th-232, Th-230, Th-228, Ra-226, Pb-210, Po-210 and K-40. Methods applied included (i) direct gamma spectrometry, (ii) radiochemical separation with subsequent alpha spectrometry and (iii) direct alpha spectrometry. Methods are described and discussed. Finally, annual emission rates of airborne radionuclides are calculated for both plants. (orig.)

Chapter 2. Radionuclides in the biosphere

International Nuclear Information System (INIS)

Toelgyessy, J.; Harangozo, M.

2000-01-01

This is a chapter of textbook of radioecology for university students. In this chapter authors deal with role of radionuclides in the biosphere. Chapter consists of next parts: (1) Natural radionuclides in biosphere; (2) Man-made radionuclides in the biosphere; (3) Ecologically important radionuclides; (4) Natural background; (5) Radiotoxicity and (6) Paths of transfer of radionuclides from the source to human

Management of spent and disused sealed radiation sources in Russian Federation

International Nuclear Information System (INIS)

Sobolev, I.A.; Ojovan, M.I.; Karlina, O.K.; Arustamov, A.E.

2001-01-01

Full text: The system of management of spent and disused sealed radiation sources (SDSRS) in Russian Federation is based on centralised approach. This system involves 16 regional facilities of the system 'Radon' which provide safe management of SDSRS. The scientific and methodical guidance on activities of regional facilities 'Radon' carries out the Scientific and Industrial Association 'Radon', Moscow. Recently the Moscow SIA 'Radon' examined activities at regional facilities 'Radon' accordingly with the program approved by the State Supervision Authority of Russia (GAN). It was revealed that the main type of radioactive waste at these facilities comprises SDSRS. This is the case both on summarised quantity of accumulated radioactivity (more than 99%) and on general quantity of the containers with waste (more than 80%). The average radionuclide composition of the SDSRS accumulated at regional facilities 'Radon' is as follows: Cs-137 (40%), Co-60 (25%), Sr-90 (22%), Ir-192 (8%) and Tm-170 (4%). The content of other radionuclides in SDSRS is not more than 1%. At regional facilities 'Radon' SDSRS mainly are disposed of in bore hole type repositories. Nevertheless SDSRS are also stored in containers being placed into repositories for solid radioactive waste. SDSRS which contain long lived radionuclides are stored until the decision on their final disposal into a deep geological formation. So far as free (not conditioned) storage of SDSRS can not provide safe conditions for environment for a long time, it is necessary to immobilise sources additionally into a suitable matrix material. Supplemental sources inclusion in a lead (or lead based alloy) matrix using Moscow SIA 'Radon' mobile plant was carried out at five regional 'Radon' facilities as follows: Zagorsk branch of Moscow SIA 'Radon', Volgograd, Ekaterinburg, Nizhny Novgorod, and Ufa. More than 1 million Ci of SDSRS are stored at present time in conditioned form in bore hole repositories. In 1998-1999 the Moscow

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

Energy Technology Data Exchange (ETDEWEB)

Mark Verdoorn; Tom Haney

2012-06-01

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

75 FR 77954 - Transfer of Federally Assisted Facility

Science.gov (United States)

2010-12-14

.... seq., permits the Administrator of the Federal Transit Administration (FTA) to authorize a recipient... land sit within a secure Public Works Yard and any other acquiring agency would need access to use this...) provides guidance on the transfer of capital assets. Specifically, if a recipient of FTA assistance decides...

1991 annual report of the Karlsruhe Federal Food Research Institute

International Nuclear Information System (INIS)

1992-01-01

The Federal Food Research Institute does research in the field of nutrition, food and household sciences as well as in related special fields. Among its working priorities are the determination of foreign matter and radionuclides in food as well as food preservation by means of irradiation including dosimetry. The results of those priorities are represented. (orig./MG) [de

Geomorphological applications of environmental radionuclides

International Nuclear Information System (INIS)

Quine, T.A.; Walling, D.

1998-01-01

Geomorphologists have shown increasing interest in environmental radionuclides since pioneering studies by Ritchie and McHenry in the USA and Campbell, Longmore and Loughran in Australia. Environmental radionuclides have attracted this interest because they provide geomorphologists with the means to trace sediment movement within the landscape. They, therefore, facilitate investigation of subjects at the core of geomorphology, namely the rates and patterns of landscape change. Most attention has been focussed on the artificial radionuclide caesium-137 ( 137 Cs) but more recently potential applications of the natural radionuclides lead-210 ( 210 Pb) and beryllium-7( 7 Be) have been investigated (Walling et al., 1995; Wallbrink and Murray, 1996a, 1996b). The origin, characteristics and applications of these radionuclides are summarised. These radionuclides are of value as sediment tracers because of three important characteristics: a strong affinity for sediment; a global distribution and the possibility of measurement at low concentration. Geomorphological applications of environmental radionuclides provide unique access to detailed qualitative data concerning landscape change over a range of timescales

Foodstuffs, radionuclides, monitoring

International Nuclear Information System (INIS)

Denisikov, A.I.

2000-01-01

Radionuclide contamination of water and food stuffs as a result of the Chernobyl accident and permissible contents of 90 Sr and 137 Cs are considered in brief. A method of radiation monitoring of food stuffs and water for the radionuclides mentioned is suggested. The method permits employment of the simplest and cheapest radiometric equipment for analysis, whole the high degree of radionuclide concentration using fiber sorbents permits using the instrumentation without expensive shields against external radiation. A description of ion-exchange unit for radiation monitoring of liquid samples of food stuffs or water, is provided [ru

Generator for radionuclide

International Nuclear Information System (INIS)

Weisner, P.S.; Forrest, T.R.F.

1985-01-01

This invention provides a radionuclide generator of the kind in which a parent radionuclide, adsorbed on a column of particulate material, generates a daughter radionuclide which is periodically removed from the column. This invention is particularly concerned with technetium generators using single collection vials. The generator comprises a column, a first reservoir for the eluent, a second reservoir to contain the volume of eluent required for a single elution, and means connecting the first reservoir to the second reservoir and the second reservoir to the column. Such a generator is particularly suitable for operation by vacuum elution

Process for encapsulating radionuclides

International Nuclear Information System (INIS)

Brownell, L.E.; Isaacson, R.E.

1976-01-01

Radionuclides are immobilized in virtually an insoluble form by reacting at a temperature of at least 90 0 C as an aqueous alkaline mixture having a solution pH of at least 10, containing a source of silicon, the radionuclide waste, and a metal cation. The molar ratio of silicon to the metal cation is on the order of unity to produce a gel from which complex metalosilicates crystallize to entrap the radionuclides within the resultant condensed crystal lattice. The product is a silicious stone-like material which is virtually insoluble and nonleachable in alkaline or neutral environment. One embodiment provides for the formation of the complex metalo-silicates, such as synthetic pollucite, by gel formation with subsequent calcination to the solid product; another embodiment utilizes a hydrothermal process, either above ground or deep within basalt caverns, at greater than atmospheric pressures and a temperature between 90 and 500 0 C to form complex metalo-silicates, such as strontium aluminosilicate. Another embodiment provides for the formation of complex metalo-silicates, such as synthetic pollucite, by slurrying an alkaline mixture of bentonite or kaolinite with a source of silicon and the radionuclide waste in salt form. In each of the embodiments a mobile system is achieved whereby the metalo-silicate constituents reorient into a condensed crystal lattice forming a cage structure with the condensed metalo-silicate lattice which completely surrounds the radionuclide and traps the radionuclide therein; thus rendering the radionuclide virtually insoluble

Sustainable Federal Fleets: Deploying Electric Vehicles and Electric Vehicle Supply Equipment

Energy Technology Data Exchange (ETDEWEB)

2017-01-01

The U.S. Department of Energy (DOE) Federal Energy Management Program (FEMP) helps federal agencies reduce petroleum consumption and increase alternative fuel use through its resources for Sustainable Federal Fleets. To assist agencies with the transition to plug-in electric vehicles (PEVs), including battery electric vehicles (BEVs) and plug-in hybrid electric vehicles (PHEVs), FEMP offers technical guidance on electric vehicle supply equipment (EVSE) installations and site-specific planning through partnerships with the National Renewable Energy Laboratory's (NREL's) EVSE Tiger Teams.

Radionuclide transfer from mother to embryo

International Nuclear Information System (INIS)

Toader, M.; Vasilache, R.A.; Scridon, R.; Toader, M.L.

1998-01-01

The transfer of radionuclides from mother to embryo is still a matter of high interest. Therefore, the relation was investigated between the amount of radionuclides in the embryo and the dietary intake of the mother, this for two scenarios: a recurrent intake of variable amounts of radionuclides, and a long-term intake of a relatively constant amount of radionuclides, the radionuclide being 137 Cs. In the first case, the amount of radionuclides present in the embryo increases with the age of the embryo and with the intake of the mother. In the second case, no correlation could be found between the age of the embryo and its radioactive content; only the correlation between the intake of the mother and the radionuclide content of the embryo remained. (A.K.)

Quality assurance guidance for a low-level radioactive waste disposal facility

International Nuclear Information System (INIS)

Pittiglio, C.L. Jr.; Hedges, D.

1991-04-01

This document provides guidance to an applicant on meeting the quality control (QC) requirements of 10 CFR 61.12(j) for a low-level radioactive waste (LLRW) disposal facility. The QC requirements, plus audits and managerial controls requirements, establish the need for developing a quality assurance (QA) program and the guidance provided herein. The criteria developed for this document are similar to the criteria developed for Appendix B to Title 10 of the Code of Federal Regulations (10 CFR) Part 50. Although Appendix B is not a regulatory requirement for an LLRW disposal facility, the criteria that were developed for 10 CFR Part 50 are basic to any QA program. This document establishes QA guidance for the design, construction, and operation of those structures, engineered or natural systems, and components whose function is required to meet the performance objectives of Subpart C of 10 CFR Part 61 and to limit exposure to or release of radioactivity. 7 refs

76 FR 21755 - Guidance to Federal Financial Assistance Recipients Regarding Title VI Prohibition Against...

Science.gov (United States)

2011-04-18

... urged to develop a systemic process for determining which documents to translate. DHS disagrees with one... obligation under 6 CFR part 21 and 44 CFR 7.5(b) to enforce the non-discriminatory requirements of Title VI... other component offices, will enforce and monitor efforts. As noted in the Guidance, the DHS Office for...

Radionuclide diagnosis of emergency states

International Nuclear Information System (INIS)

Ishmukhametov, A.I.

1985-01-01

Solution of emergency state radionuclide diagnostics from the technical point of view is provided by the application of the mobile quick-operating equipment in combination with computers, by the use of radionuclides with acceptable for emergency medicine characteristics and by development of radionuclide investigation data propcessing express-method. Medical developments include the study of acute disease and injury radioisotope semiotics, different indication diagnostic value determining, comparison of the results, obtained during radionuclide investigation, with clinicolaboratory and instrumental data, separation of methodical complex series

Anthropogenic radionuclides in the environment

Energy Technology Data Exchange (ETDEWEB)

Hu, Q; Weng, J; Wang, J

2007-11-15

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.

Radionuclide daughter inventory generator code: DIG

International Nuclear Information System (INIS)

Fields, D.E.; Sharp, R.D.

1985-09-01

The Daughter Inventory Generator (DIG) code accepts a tabulation of radionuclide initially present in a waste stream, specified as amounts present either by mass or by activity, and produces a tabulation of radionuclides present after a user-specified elapsed time. This resultant radionuclide inventory characterizes wastes that have undergone daughter ingrowth during subsequent processes, such as leaching and transport, and includes daughter radionuclides that should be considered in these subsequent processes or for inclusion in a pollutant source term. Output of the DIG code also summarizes radionuclide decay constants. The DIG code was developed specifically to assist the user of the PRESTO-II methodology and code in preparing data sets and accounting for possible daughter ingrowth in wastes buried in shallow-land disposal areas. The DIG code is also useful in preparing data sets for the PRESTO-EPA code. Daughter ingrowth in buried radionuclides and in radionuclides that have been leached from the wastes and are undergoing hydrologic transport are considered, and the quantities of daughter radionuclide are calculated. Radionuclide decay constants generated by DIG and included in the DIG output are required in the PRESTO-II code input data set. The DIG accesses some subroutines written for use with the CRRIS system and accesses files containing radionuclide data compiled by D.C. Kocher. 11 refs

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

Energy Technology Data Exchange (ETDEWEB)

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

1981-01-01

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.

75 FR 75628 - Final Guidance for Federal Departments and Agencies on Establishing, Applying, and Revising...

Science.gov (United States)

2010-12-06

... guidance. Comments that raised policy or substantive concerns are grouped into thematic issues and... expedite the environmental review process for proposals that normally do not require additional analysis... clarity and transparency for proposed projects that could be categorically excluded from further analysis...

History of medical radionuclide production.

Science.gov (United States)

Ice, R D

1995-11-01

Radionuclide production for medical use originally was incidental to isotope discoveries by physicists and chemists. Once the available radionuclides were identified they were evaluated for potential medical use. Hevesy first used 32P in 1935 to study phosphorous metabolism in rats. Since that time, the development of cyclotrons, linear accelerators, and nuclear reactors have produced hundreds of radionuclides for potential medical use. The history of medical radionuclide production represents an evolutionary, interdisciplinary development of applied nuclear technology. Today the technology is represented by a mature industry and provides medical benefits to millions of patients annually.

National Emission Standards for Hazardous Air Pollutants. Calendar Year 2013 INL Report for Radionuclides [2014

Energy Technology Data Exchange (ETDEWEB)

Verdoorn, Mark; Haney, Tom

2014-06-01

This report documents the calendar year 2013 radionuclide air emissions and resulting effective dose equivalent to the maximally exposed individual member of the public from operations at the Department of Energy’s Idaho National Laboratory Site. This report was prepared in accordance with the Code of Federal Regulations, Title 40, ''Protection of the Environment,'' Part 61, ''National Emission Standards for Hazardous Air Pollutants,'' Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.'' The effective dose equivalent to the maximally exposed individual member of the public was 3.02 E-02 mrem per year, 0.30 percent of the 10 mrem standard.

National Emission Standards for Hazardous Air Pollutants. Calendar Year 2012 INL Report for Radionuclides (2013)

Energy Technology Data Exchange (ETDEWEB)

Verdoorn, Mark; Haney, Tom

2013-06-01

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

Transfer of fallout radionuclides derived from Fukushima NPP accident: 1 year study on transfer of radionuclides through hydrological processes

Science.gov (United States)

Onda, Yuichi; Kato, Hiroaki; Patin, Jeremy; Yoshimura, Kazuya; Tsujimura, Maki; Wakahara, Taeko; Fukushima, Takehiko

2013-04-01

Previous experiences such as Chernobyl Nuclear Power Plant accident have confirmed that fallout radionuclides on the ground surface migrate through natural environment including soils and rivers. Therefore, in order to estimate future changes in radionuclide deposition, migration process of radionuclides in forests, soils, ground water, rivers should be monitored. However, such comprehensive studies on migration through forests, soils, ground water and rivers have not been conducted so far. Here, we present the following comprehensive investigation was conducted to confirm migration of radionuclides through natural environment including soils and rivers. 1)Study on depth distribution of radiocaesium in soils within forests, fields, and grassland 2)Confirmation of radionuclide distribution and investigation on migration in forests 3)Study on radionuclide migration due to soil erosion under different land use 4)Measurement of radionuclides entrained from natural environment including forests and soils 5)Investigation on radionuclide migration through soil water, ground water, stream water, spring water under different land use 6)Study on paddy-to-river transfer of radionuclides through suspended sediments 7)Study on river-to-ocean transfer of radionuclides via suspended sediments 8)Confirmation of radionuclide deposition in ponds and reservoirs

75 FR 80287 - Environmental Protection Agency Implementation of OMB Guidance on Drug-Free Workplace Requirements

Science.gov (United States)

2010-12-22

... of omnibus drug legislation on November 18, 1988. Federal agencies issued an interim final common...; FRL- 9242-2] Environmental Protection Agency Implementation of OMB Guidance on Drug-Free Workplace... Protection Agency is removing its regulation implementing the Governmentwide common rule on drug-free...

Evaluation of the endocrine activity of 2,4,6-tribromophenol, benzanthrone and benzophenone-2 based on Appendix 7.8-5 of REACH guidance document

DEFF Research Database (Denmark)

Duis, Karen; Holbech, Henrik; Velasco-Santamaría, Yohana M.

Within a project funded by the German Federal Environment Agency, the practicability of Appendix 7.8-5 of REACH guidance document R.7b was evaluated using three case study substances. Shortcomings in the guidance were identified. An assessment of potential endocrine activity in aquatic vertebrates...

Assessing radiation doses to the public from radionuclides in timber and wood products

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-10-01

In the event of a nuclear accident involving the release of radionuclides to the biosphere the radioactive contamination of forests can become a significant potential source of public radiation exposure. Two of these accidents - the Kyshtim accident, Urals, USSR (now Russian Federation) in 1957 and the Chernobyl accident, USSR (now Ukraine), in 1986 - resulted in significant contamination of thousands of square kilometres of forested areas with mixtures of radionuclides including long lived fission products such as {sup 137}Cs and {sup 90}Sr. Measurements and modelling of forest ecosystems after both accidents have shown that, following initial contamination, the activity concentration of long lived radionuclides in wood gradually increases over one to two decades and then slowly decreases in the subsequent period. The longevity of the contamination is due to the slow migration and persistent bioavailability of radionuclides in the forest soil profile, which results in long term transfer into wood through the root system of the trees. Another source of contamination is from global radioactive fallout after nuclear weapons tests, but the level of contamination is much lower than that from, for example, the Chernobyl accident. For instance, the level of {sup 137}Cs in wood in Sweden is about 2-5 Bq kg{sup -1} from global fallout. Global values are very similar to the Swedish levels. In contrast, the level of {sup 137}Cs in Swedish wood due to Chernobyl is around 50 Bq kg{sup -1}. Levels in wood from some contaminated areas located in countries of the Former Soviet Union (FSU) are about one to two orders of magnitude higher than this. The data on {sup 137}Cs soil contamination within European territories, originating mainly from the Chernobyl accident, illustrate the scale of the problem. For comparison, residual {sup 137}Cs soil deposition in Europe from global radioactive fallout was in the range 1-4 kBq m{sup -2}. There is concern in several countries about the

Conditions and processes affecting radionuclide transport

Science.gov (United States)

Simmons, Ardyth M.; Neymark, Leonid A.

2012-01-01

Characteristics of host rocks, secondary minerals, and fluids would affect the transport of radionuclides from a previously proposed repository at Yucca Mountain, Nevada. Minerals in the Yucca Mountain tuffs that are important for retarding radionuclides include clinoptilolite and mordenite (zeolites), clay minerals, and iron and manganese oxides and hydroxides. Water compositions along flow paths beneath Yucca Mountain are controlled by dissolution reactions, silica and calcite precipitation, and ion-exchange reactions. Radionuclide concentrations along flow paths from a repository could be limited by (1) low waste-form dissolution rates, (2) low radionuclide solubility, and (3) radionuclide sorption onto geological media.

Radionuclide Activity Concentrations in Spas of Argentina

International Nuclear Information System (INIS)

Gnoni, G.; Czerniczyniec, M.; Palacios, M.

2011-01-01

Geothermal waters have been used on a large scale for bathing, drinking and medical purposes. These waters often have a very high mineral content because solubility increases with temperature. Ground waters are in close contact with soil and rocks containing radium. Once formed by decay from radium, radon gas (Rn-222) may diffuse through rocks pores and geological discontinuities and may dissolve in these waters. Radon and other natural radionuclides are transported to the surface where radon can easily diffuse into the atmosphere. Then it may be possible to find out significant radon levels at places like geothermal spas. In this work the most important natural radionuclide activity concentrations in different thermal spas of Argentina were measured to characterize waters and to evaluate the exposure of workers and members of the public. Three passive methods were used to measure radon in air. One of them is an screening method based on the radon adsorption on activated charcoal. The other two methods are time integrated ones, CR-39 or Makrofol tracks detectors, which can be exposed between two and three months. To characterize waters other natural radionuclides have been also measured. Uranium concentration was measured by fluorimetry. Ra-226 and Pb-210 measurements were performed by radiochemical methods and liquid scintillation. The results obtained were compared with the guidelines values recommended by WHO and EPA for drinking waters and, in the case of radon in air, the results were compared with values established by BSS-115. In order to assess worker doses, the higher value measured for radon in air and real scenario data were taken into account. Moreover, in situ dose rate measurements were also performed and then compared with natural background values. In relation with water characterization, almost all values obtained for the geothermal waters analyzed were below the corresponding guidance levels. Taking into account the highest value measured of radon

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

Energy Technology Data Exchange (ETDEWEB)

Hiergesell, R.; Phifer, M.

2014-04-29

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

76 FR 50433 - Regulatory Guidance: Applicability of the Federal Motor Carrier Safety Regulations to Operators...

Science.gov (United States)

2011-08-15

... operating under share-cropping agreements are common or contract carriers; and third, whether FMCSA should.... FMCSA is issuing guidance that farmers operating under share-cropping or similar arrangements are not... farmer, the Agency sought as much public involvement and comment as possible on these issues. It is worth...

Lessons learned from the second Federal Radiology Emergency Response Plan Field Exercise (FFE-2)

International Nuclear Information System (INIS)

Adler, M.V.; Gant, K.S.; Weiss, B.H.; Wolff, W.F.; Adler, V.

1988-01-01

The FFE-2, held in 1987 at the Zion Nuclear Power Station, provided a large-scale, multiagency, field test of the Federal Radiological Emergency Response Plan (FRERP). The FRERP provided workable guidance for coordinating the federal response efforts and effectively supplementing the states' resources. Needs for more training for responders and clarification in portions of the response were identified

75 FR 52857 - National Endowment for the Humanities Implementation of OMB Guidance on Drug-Free Workplace...

Science.gov (United States)

2010-08-30

... Endowment for the Humanities Implementation of OMB Guidance on Drug-Free Workplace Requirements AGENCY... the Governmentwide common rule on drug-free workplace requirements for financial assistance, currently... Federal regulations on drug-free workplace requirements for financial assistance. These changes constitute...

Radionuclides in air, water, and biota

International Nuclear Information System (INIS)

Seymour, A.H.; Nelson, V.A.

1977-01-01

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 radionuclides by gamma spectrometry. Selected samples were also analyzed for tritium, 55 Fe, and 90 Sr. The objectives were to search for and identify radionuclides of Amchitka origin in the samples and to contribute to the general knowledge of the distribution of radionuclides in the environment. The studies showed that there has been no escape of radionuclides from the underground sites of the three nuclear detonations at Amchitka Island except for trace quantities of radionuclides, principally tritium, in water and soil gas samples from the immediate vicinity of the surface ground zero for the 1965 event. Two naturally occurring radionuclides, 40 K and 7 Be, were the most abundant radionuclides in the samples, usually by a factor of 10 or more, except for 137 Cs in lichen samples. All levels were well below applicable Radiation Protction Guides, often being near the statistical limit of detection

Phytoremediation of radionuclides: an emerging alternative

International Nuclear Information System (INIS)

Singh, Shraddha

2013-01-01

Proliferation of nuclear power industry, nuclear weapon testing, dismantling of existing nuclear weapons and occasional accidents have contributed to an enhancement in the level of radionuclides in the environment. The radionuclides due to their long half life and transfer through the food chain effect adversely to normal biological systems. Hence, it is essential to effectively remove the radionuclides from contaminated soils and solutions. Phytoremediation - the use of plants for remediation of toxic metals and radionuclides has been recognized as an aesthetically pleasing, low cost and environment friendly in situ method. Phytoremediation is an umbrella term which covers several plant based approaches. Plants have shown the potential of remediation of these radionuclides from spiked solutions, low level nuclear waste and soil. Various aspects of phytoremediation as well as potential of various plants for remediation of radionuclides will be discussed here. (author)

Radionuclide migration test using undisturbed aerated soil

International Nuclear Information System (INIS)

Yamamoto, Tadatoshi; Ohtsuka, Yoshiro; Ogawa, Hiromichi; Wadachi, Yoshiki

1988-01-01

As one of the most important part of safety assessment on the shallow land disposal of lowlevel radioactive waste, the radionuclide migration was studied using undisturbed soil samples, in order to evaluate an exact radionuclide migration in an aerated soil layer. Soil samples used in the migration test were coastal sand and loamy soil which form typical surface soil layers in Japan. The aqueous solution containing 60 CoCl 2 , 85 SrCl 2 and 137 CsCl was fed into the soil column and concentration of each radionuclide both in effluent and in soil was measured. Large amount of radionuclides was adsorbed on the surface of soil column and small amount of radionuclides moved deep into the soil column. Difference in the radionuclide profile was observed in the low concentration portion particularly. It is that some fractions of 60 Co and 137 Cs are stable in non-ionic form and move downward through the soil column together with water. The radionuclide distribution in the surface of soil column can be fairly predicted with a conventional migration equation for ionic radionuclides. As a result of radionuclide adsorption, both aerated soil layers of coastal sand and loamy soil have large barrier ability on the radionuclide migration through the ground. (author)

The development and revision of the Federal Radiological Emergency Response Plan

International Nuclear Information System (INIS)

Gant, K.S.; Adler, M.V.; Wolff, W.F.

1989-01-01

Since 1985, federal agencies have been using the Federal Radiological Emergency Response Plan (FRERP) in exercises and real events. This experience and the development of other emergency response guidance (e.g., National System for Emergency Coordination) are fueling current efforts to review and revise the FRERP to reflect what the agencies have learned since the FRERP was published. Revision efforts are concentrating on clarifying the plan and addressing deficiencies. No major changes are expected in the general structure of the federal response nor should states need to revise their plans because of these modifications. 5 refs

Radionuclides in food

International Nuclear Information System (INIS)

Fernandez Gomez, Isis Maria

2008-01-01

The sources of the presence of radionuclides in food are presented: natural radiation and artificial radiation. The transfer of radionuclides through food chains, intakes of radionuclides to the body with its partners effective doses and typical consumption of basic foods of a rural adult population are exposed as main topics. Also the radiation doses from natural sources and exposure to man by ingestion of contaminated food with radionuclides of artificial origin are shown. The contribution of the food ingestion to the man exposure depends on: characteristics of radionuclide, natural conditions, farming practices and eating habits of the population. The principal international organizations in charge of setting guide levels for radionuclides in food are mentioned: standards, rules and the monitoring. It establishes that a guide is necessary for the food monitoring; the alone CODEX ALIMENTARIUS is applicable to emergency situations and the generic action levels proposed by the CODEX not satisfy all needs (no guiding international levels for planned or existing situations such as NORM). There are handled mainly socio-economic and political aspects. Among the actions to be taken are: to assure a public comprehensive information over the risk evaluation in food; to reinforce the collaboration among the different international organizations (WHO, IAEA, ICRP, EC) in relation with the food of set; to give follow-up to the control of the drinkable water and NORM's presence in the food. In addition, it is possible to create the necessary mechanisms to reduce the number of irrelevant measures and bureaucratic useless steps (certificates); to promote the exchange between the different institutions involved in the topic of the food, with relation to the acquired experiences and learned lessons. Likewise, it might examine the possibility of a multidisciplinary approximation (radioactive and not radioactive pollutants); to elaborate a technical guide to assure the

Initial Radionuclide Inventories

Energy Technology Data Exchange (ETDEWEB)

H. Miller

2004-09-19

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

Sequim Site Radionuclide Air Emissions Report for Calendar Year 2012

Energy Technology Data Exchange (ETDEWEB)

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

2013-04-01

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

Determination of alpha radionuclides in fish

International Nuclear Information System (INIS)

Pernicka, L.; Matel, L.; Rosskopfova, O.

2001-01-01

In atmospheric water, external water and undercurrent the occurrence of radionuclides is usual. It is an important factor of quality of the environment. Plants ingest radionuclides from water and with they everyone. And it arises radioactivity infest food-chain. Radiotoxicity of this radionuclides is very deer sometimes. The sensitive radiochemical procedures for their determination are necessarily important. The poster presents the combined procedure used at our laboratory for determination of alpha radionuclides in biological samples. (authors)

Statistical methods for determination of background levels for naturally occuring radionuclides in soil at a RCRA facility

International Nuclear Information System (INIS)

Guha, S.; Taylor, J.H.

1996-01-01

It is critical that summary statistics on background data, or background levels, be computed based on standardized and defensible statistical methods because background levels are frequently used in subsequent analyses and comparisons performed by separate analysts over time. The final background for naturally occurring radionuclide concentrations in soil at a RCRA facility, and the associated statistical methods used to estimate these concentrations, are presented. The primary objective is to describe, via a case study, the statistical methods used to estimate 95% upper tolerance limits (UTL) on radionuclide background soil data sets. A 95% UTL on background samples can be used as a screening level concentration in the absence of definitive soil cleanup criteria for naturally occurring radionuclides. The statistical methods are based exclusively on EPA guidance. This paper includes an introduction, a discussion of the analytical results for the radionuclides and a detailed description of the statistical analyses leading to the determination of 95% UTLs. Soil concentrations reported are based on validated data. Data sets are categorized as surficial soil; samples collected at depths from zero to one-half foot; and deep soil, samples collected from 3 to 5 feet. These data sets were tested for statistical outliers and underlying distributions were determined by using the chi-squared test for goodness-of-fit. UTLs for the data sets were then computed based on the percentage of non-detects and the appropriate best-fit distribution (lognormal, normal, or non-parametric). For data sets containing greater than approximately 50% nondetects, nonparametric UTLs were computed

Radionuclide usage survey 1979-80

International Nuclear Information System (INIS)

Woods, M.J.

1980-08-01

Details of a survey by the Life Sciences Working Group of the International Committee for Radionuclide Metrology (ICRM) on radionuclide usage by medical physicists in 11 countries are presented. The results indicate that the radionuclide which will be of most significance in the future will be F-18, Fe-52, Ga-67, Ga-68, Kr-81m, Tc-99m, In-111, I-123, Xe-127 and Tl-201, (U.K.)

Career guidance in communities

DEFF Research Database (Denmark)

Thomsen, Rie

for the development of a critically reflexive career guidance practice. The considerations are organised around seven elements. 1. Creating opportunity, structure and access 2. Entering a community and increasing visibility 3. Providing guidance in communities 4. Exploring potentials in guidance situations 5...... in career guidance practices as well as in the lives of the people in the communities. This paper falls into two parts: The first part considers the collective as the starting point for the development of meaningful career guidance activities. Based on previous research on career guidance in communities......The aim of this paper is to inspire practitioners and professionals to leave their offices to bring career guidance into communities that might not identify with career guidance in the first instance. By making the effort to engage with communities, practitioners may bring about a critical change...

Radionuclides: Accumulation and Transport in Plants.

Science.gov (United States)

Gupta, D K; Chatterjee, S; Datta, S; Voronina, A V; Walther, C

Application of radioactive elements or radionuclides for anthropogenic use is a widespread phenomenon nowadays. Radionuclides undergo radioactive decays releasing ionizing radiation like gamma ray(s) and/or alpha or beta particles that can displace electrons in the living matter (like in DNA) and disturb its function. Radionuclides are highly hazardous pollutants of considerable impact on the environment, food chain and human health. Cleaning up of the contaminated environment through plants is a promising technology where the rhizosphere may play an important role. Plants belonging to the families of Brassicaceae, Papilionaceae, Caryophyllaceae, Poaceae, and Asteraceae are most important in this respect and offer the largest potential for heavy metal phytoremediation. Plants like Lactuca sativa L., Silybum marianum Gaertn., Centaurea cyanus L., Carthamus tinctorius L., Helianthus annuus and H. tuberosus are also important plants for heavy metal phytoremediation. However, transfer factors (TF) of radionuclide from soil/water to plant ([Radionuclide]plant/[Radionuclide]soil) vary widely in different plants. Rhizosphere, rhizobacteria and varied metal transporters like NRAMP, ZIP families CDF, ATPases (HMAs) family like P1B-ATPases, are involved in the radio-phytoremediation processes. This review will discuss recent advancements and potential application of plants for radionuclide removal from the environment.

International Scavenging for First Responder Guidance and Tools: IAEA Products

Energy Technology Data Exchange (ETDEWEB)

Stern, W. [Brookhaven National Lab. (BNL), Upton, NY (United States); Berthelot, L. [Brookhaven National Lab. (BNL), Upton, NY (United States); Bachner, K. [Brookhaven National Lab. (BNL), Upton, NY (United States)

2017-05-05

In fiscal years (FY) 2016 and 2017, with support from the U.S. Department of Homeland Security (DHS), Brookhaven National Laboratory (BNL) examined the International Atomic Energy Agency (IAEA) radiological emergency response and preparedness products (guidance and tools) to determine which of these products could be useful to U.S. first responders. The IAEA Incident and Emergency Centre (IEC), which is responsible for emergency preparedness and response, offers a range of tools and guidance documents for responders in recognizing, responding to, and recovering from radiation emergencies and incidents. In order to implement this project, BNL obtained all potentially relevant tools and products produced by the IAEA IEC and analyzed these materials to determine their relevance to first responders in the U.S. Subsequently, BNL organized and hosted a workshop at DHS National Urban Security Technology Laboratory (NUSTL) for U.S. first responders to examine and evaluate IAEA products to consider their applicability to the United States. This report documents and describes the First Responder Product Evaluation Workshop, and provides recommendations on potential steps the U.S. federal government could take to make IAEA guidance and tools useful to U.S. responders.

76 FR 62312 - Multi-Agency Informational Meeting Concerning Compliance With the Federal Select Agent Program...

Science.gov (United States)

2011-10-07

... interested individuals to obtain specific regulatory guidance and information on standards concerning biosafety and biosecurity issues related to the Federal Select Agent Program. CDC, APHIS, and CJIS...

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

Science.gov (United States)

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

1999-03-23

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

Proposed radioactive liquid effluent monitoring requirements at the Savannah River Site

International Nuclear Information System (INIS)

Jannik, G.T.; Carlton, W.H.; Blunt, B.C.

1994-01-01

Clear regulatory guidance exists for structuring a radiological air monitoring program, however, there is no parallel guidance for radiological liquid monitoring. For Department of Energy (DOE) facilities, there are no existing applicable federal regulations, DOE orders, or DOE guidance documents that specify at what levels continuous monitoring, continuous sampling, or periodic confirmatory measurements of radioactive liquid effluents must be made. In order to bridge this gap and to technically justify and document liquid effluent monitoring decisions at DOE's Savannah River Site, Westinghouse Savannah River Company has proposed that a graded, dose-based approach be established, in conjunction with limits on facility radionuclide inventories, to determine the monitoring and sampling criteria to be applied at each potential liquid radioactive effluent point. The graded approach would be similar to--and a conservative extension of--the existing, agreed-upon SRS/EPA-IV airborne effluent monitoring approach documented in WSRC's NESHAP Quality Assurance Project Plan. The limits on facility radionuclide inventories are based on--and are a conservative extension of--the 10 CFR 834, 10 CFR 20, and SCR 61-63 annual limits on discharges to sanitary sewers. Used in conjunction with each other, the recommended source category criteria levels and facility radionuclide inventories would allow for the best utilization of resources and provide consistent, technically justifiable determinations of radioactive liquid effluent monitoring requirements

A Guide to Federal Regulation; Understanding the FCC Rules.

Science.gov (United States)

Cable Television Information Center, Washington, DC.

While it is apparent that the Federal Communications Commission (FCC) has given a great deal of thought to the regulation of cable systems, the basic success or failure of cable as a communications service will depend on local development. Relatively little guidance has been provided to local franchising authorities for selecting among applicants,…

Radionuclide transport processes in terrestrial ecosystems

International Nuclear Information System (INIS)

Whicker, F.W.

1983-01-01

Some major principles and the status of knowledge concerning the transport of radionuclides through terrestrial ecosystems are reviewed. Fundamental processes which control the flow of radionuclides between ecosystem components such as air, soil, plants, and animals are described, with emphasis on deposition, resuspension, plant uptake, ingestion, and assimilation. Properties of radionuclides, organisms, and ecosystems are examined in relation to their influence on the accumulation of radioactive materials by plants and animals. The effects of the physicochemical nature of the radionuclide; morphology, physiology, and behavior of the organism; and soil, nutrient, and trophic characteristics of the ecosystem are highlighted. Observations in natural ecosystems on radionuclides such as 137 Cs, 90 Sr, 131 I, 3 H, and 239 Pu are used to illustrate current concepts. An assessment of the degree to which the processes controlling radionuclide behavior are understood and of our ability to simulate and predict such behavior with computerized models is offered. Finally, brief comments are made on research needs

Radionuclide Sensors for Water Monitoring

International Nuclear Information System (INIS)

Grate, Jay W.; Egorov, Oleg B.; DeVol, Timothy A.

2004-01-01

Radionuclide contamination in the soil and groundwater at U.S. Department of Energy (DOE) sites is a severe problem that requires monitoring and remediation. Radionuclide measurement techniques are needed to monitor surface waters, groundwater, and process waters. Typically, water samples are collected and transported to an analytical laboratory, where costly radiochemical analyses are performed. To date, there has been very little development of selective radionuclide sensors for alpha- and beta-emitting radionuclides such as 90Sr, 99Tc, and various actinides of interest. The objective of this project is to investigate novel sensor concepts and materials for sensitive and selective determination of beta- and alpha-emitting radionuclide contaminants in water. To meet the requirements for loW--level, isotope-specific detection, the proposed sensors are based on radiometric detection. As a means to address the fundamental challenge of the short ranges of beta and alpha particle s in water, our overall approach is based on localization of preconcentration/separation chemistries directly on or within the active area of a radioactivity detector. Automated microfluidics is used for sample manipulation and sensor regeneration or renewal. The outcome of these investigations will be the knowledge necessary to choose appropriate chemistries for selective preconcentration of radionuclides from environmental samples, new materials that combine chemical selectivity with scintillating properties, new materials that add chemical selectivity to solid-state diode detectors, new preconcentrating column sensors, and improved instrumentation and signal processing for selective radionuclide sensors. New knowledge will provide the basis for designing effective probes and instrumentation for field and in situ measurements

Radionuclides in terrestrial ecosystems

International Nuclear Information System (INIS)

Bocock, K.L.

1981-01-01

This report summarizes information on the distribution and movement of radionuclides in semi-natural terrestrial ecosystems in north-west England with particular emphasis on inputs to, and outputs from ecosystems; on plant and soil aspects; and on radionuclides in fallout and in discharges by the nuclear industry. (author)

75 FR 39133 - Institute of Museum and Library Services Implementation of OMB Guidance on Drug-Free Workplace...

Science.gov (United States)

2010-07-08

... of Museum and Library Services Implementation of OMB Guidance on Drug-Free Workplace Requirements... regulation implementing the Governmentwide common rule on drug-free workplace requirements for financial... the CFR all Federal regulations on drug-free workplace requirements for financial assistance. These...

Artificial radionuclides in soil, flora and fauna

International Nuclear Information System (INIS)

Marej, A.N.

1984-01-01

Sources and ways of soil contamination by radionuclides, as well as the main regularities of radionuclide behaviour in soils, are discussed. Ways of radionuclide uptake by plants are discussed in detail, since radionuclide contamination of vegetation, and agricultural plants and pastures in particular, is one of the main factors, determining sanitary value of environmental contamination by radioactive substances

Marine Sciences Laboratory Radionuclide Air Emissions Report for Calendar Year 2014

Energy Technology Data Exchange (ETDEWEB)

Snyder, Sandra F.; Barnett, J. Matthew

2015-05-04

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.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 Protection–Air Emissions.'' The EDE to the MSL MEI due to routine operations in 2014 was 9E-05 mrem (9E-07 mSv). No non-routine emissions occurred in 2014. The MSL is in compliance with the federal and state 10 mrem/yr standard.

Marine Sciences Laboratory Radionuclide Air Emissions Report for Calendar Year 2013

Energy Technology Data Exchange (ETDEWEB)

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

2014-05-01

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 Protection–Air 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.

Environmental behaviour of radionuclides and transfer to man

International Nuclear Information System (INIS)

Smith, H.

1982-01-01

The environmental behaviour of the radionuclides making the major contribution to man's irradiation through diet is described. The following stages are emphasized: transfer of radionuclides to plants; transfer of radionuclides to animals; metabolism of inhaled or ingested radionuclides in animals providing food for man; transfer of radionuclides through the aquatic environment; application of food chain models. (43 references)

Radioactivity measurement of primordial radionuclides in and dose evaluation from marble and glazed tiles used as covering building materials in Turkey

International Nuclear Information System (INIS)

Turhan, S.; Varinlioglu, A.

2012-01-01

Measurements of the natural radioactivity arising from primordial radionuclides ( 226 Ra, 232 Th and 40 K) in marble and glazed tile samples used covering building materials in Turkey were carried out by gamma-ray spectrometer with a high purity germanium detector. The mean activity concentrations of the 226 Ra, 232 Th and 40 K in marble and glazed tile samples were found as 8.2, 5.5 and 58.1 Bq kg -1 and 81.2, 65.4 and 450.1 Bq kg -1 , respectively. The radiation doses received by occupants of buildings in which the sample marble and glazed tiles might be used are estimated using measured activity concentrations of constituent primordial radionuclides and dose conversion factors evaluated by the European Commission from models of tile use. Results obtained are presented for each radionuclide, analysed and compared with relevant national and international legislation, guidance and report, and with the results obtained from other studies. Results show that the use of such decorative building materials in the construction of domestic homes or workplaces in Turkey is unlikely to lead to any significant radiation exposure to the occupants. (authors)

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

International Nuclear Information System (INIS)

Kaplan, D; Roberts, Kimberly; Serkiz, Steven; Siegfried, Matthew

2008-01-01

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 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 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 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 d values differed from previous SRS K d values measured with reducing grout (Kaplan and Coates 2007). These values also supported a previous finding that K 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 d values be used in future PAs, except Np(V) and Pu(IV) K 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

Application of discrete ordinates and Monte Carlo methods to transport of photons from environmental sources

International Nuclear Information System (INIS)

Ryman, J.C.; Eckerman, K.F.; Shultis, J.K.; Faw, R.E.; Dillman, L.T.

1996-01-01

Federal Guidance Report No. 12 tabulates dose coefficients for external exposure to photons and electrons emitted by radionuclides distributed in air, water, and soil. Although the dose coefficients of this report are based on previously developed dosimetric methodologies, they are derived from new, detailed calculations of energy and angular distributions of the radiations incident on the body and the transport of these radiations within the body. Effort was devoted to expanding the information available for assessment of radiation dose from radionuclides distributed on or below the surface of the ground. A companion paper (External Exposure to Radionuclides in Air, Water, and Soil) discusses the significance of the new tabulations of coefficients and provides detiled comparisons to previously published values. This paper discusses details of the photon transport calculations

Inverse problem in radionuclide transport

International Nuclear Information System (INIS)

Yu, C.

1988-01-01

The disposal of radioactive waste must comply with the performance objectives set forth in 10 CFR 61 for low-level waste (LLW) and 10 CFR 60 for high-level waste (HLW). To determine probable compliance, the proposed disposal system can be modeled to predict its performance. One of the difficulties encountered in such a study is modeling the migration of radionuclides through a complex geologic medium for the long term. Although many radionuclide transport models exist in the literature, the accuracy of the model prediction is highly dependent on the model parameters used. The problem of using known parameters in a radionuclide transport model to predict radionuclide concentrations is a direct problem (DP); whereas the reverse of DP, i.e., the parameter identification problem of determining model parameters from known radionuclide concentrations, is called the inverse problem (IP). In this study, a procedure to solve IP is tested, using the regression technique. Several nonlinear regression programs are examined, and the best one is recommended. 13 refs., 1 tab

Radionuclide Retention in Concrete Wasteforms

Energy Technology Data Exchange (ETDEWEB)

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

2012-09-24

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.

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

International Nuclear Information System (INIS)

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

1982-12-01

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 ( 137 Cs, 90 Sr, 239 240 Pu, and 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

Local IRBs vs. federal agencies: shifting dynamics, systems, and relationships.

Science.gov (United States)

Klitzman, Robert L

2012-07-01

How IRBs relate to federal agencies, and the implications of these relationships, have received little, if any, systematic study. I interviewed 46 IRB chairs, directors, administrators, and members, contacting the leadership of 60 U.S. IRBs (every fourth one in the list of the top 240 institutions by NIH funding), interviewing IRB leaders from 34 (response rate=55%). IRBs describe complex direct and indirect relationships with federal agencies that affect IRBs through audits, guidance documents, and other communications, and can generate problems and challenges. Researchers often blame IRBs for frustrations, but IRBs often serve as the "local face" of federal regulations and agencies and are "stuck in the middle." These data have critical implications for policy, practice, and research.

77 FR 14473 - Final Guidance on Improving the Process for Preparing Efficient and Timely Environmental Reviews...

Science.gov (United States)

2012-03-12

..., economic, and social aspirations and is a cornerstone of our Nation's efforts to protect the environment... direct interaction with the public. Earlier CEQ guidance has emphasized the importance of public... Federal involvement that trigger NEPA requirements). \\38\\ 40 CFR 1507.3(b)(1). All agencies are required...

Modeling Radionuclide Decay Chain Migration Using HYDROGEOCHEM

Science.gov (United States)

Lin, T. C.; Tsai, C. H.; Lai, K. H.; Chen, J. S.

2014-12-01

Nuclear technology has been employed for energy production for several decades. Although people receive many benefits from nuclear energy, there are inevitably environmental pollutions as well as human health threats posed by the radioactive materials releases from nuclear waste disposed in geological repositories or accidental releases of radionuclides from nuclear facilities. Theoretical studies have been undertaken to understand the transport of radionuclides in subsurface environments because that the radionuclide transport in groundwater is one of the main pathway in exposure scenarios for the intake of radionuclides. The radionuclide transport in groundwater can be predicted using analytical solution as well as numerical models. In this study, we simulate the transport of the radionuclide decay chain using HYDROGEOCHEM. The simulated results are verified against the analytical solution available in the literature. Excellent agreements between the numerical simulation and the analytical are observed for a wide spectrum of concentration. HYDROGECHEM is a useful tool assessing the ecological and environmental impact of the accidental radionuclide releases such as the Fukushima nuclear disaster where multiple radionuclides leaked through the reactor, subsequently contaminating the local groundwater and ocean seawater in the vicinity of the nuclear plant.

2 CFR 182.120 - Are any of my Federal assistance awards exempt from this part?

Science.gov (United States)

2010-01-01

... GOVERNMENTWIDE GUIDANCE FOR GRANTS AND AGREEMENTS Reserved GOVERNMENTWIDE REQUIREMENTS FOR DRUG-FREE WORKPLACE (FINANCIAL ASSISTANCE) Purpose and Coverage § 182.120 Are any of my Federal assistance awards exempt from...

Measurement of radionuclides in waste packages

Science.gov (United States)

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

1984-09-12

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.

Remedial design and remedial action guidance for the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

1993-10-01

The US Department of Energy, Idaho Operations Office (DOE-ID), the US Environmental Protection Agency, Region X (EPA), and the Idaho Department of Health and Welfare (IDHW) have developed this guidance on the remedial design and remedial action (RD/RA) process. This guidance is applicable to activities conducted under the Idaho National Engineering Laboratory (INEL) Federal Facility Agreement and Consent Order (FFA/CO) and Action Plan. The INEL FFA/CO and Action Plan provides the framework for performing environmental restoration according to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The guidance is intended for use by the DOE-ID, the EPA, and the IDHW Waste Area Group (WAG) managers and others involved in the planning and implementation of CERCLA environmental restoration activities. The scope of the guidance includes the RD/RA strategy for INEL environmental restoration projects and the approach to development and review of RD/RA documentation. Chapter 2 discusses the general process, roles and responsibilities, and other elements that define the RD/RA strategy. Chapters 3 through 7 describe the RD/RA documents identified in the FFA/CO and Action Plan. Chapter 8 provides examples of how this guidance can be applied to restoration projects. Appendices are included that provide excerpts from the FFA/CO pertinent to RD/RA (Appendix A), a applicable US Department of Energy (DOE) orders (Appendix B), and an EPA Engineering ''Data Gaps in Remedial Design'' (Appendix C)

Speciation of radionuclides in the environment

International Nuclear Information System (INIS)

Gunten, H.R. von; Benes, P.

1994-02-01

Methods for the determination of the speciation of radionuclides in aerosols, in aquatic solutions, in sediments, soils and rocks are reviewed. At present, most of the results about speciation are deduced from model calculations, model experiments, and separation of species (forms) of radionuclides, e.g., by sequential extraction procedures. Methods of direct determination of speciation of radionuclides (e.g. by laser induced spectroscopy) are in general not yet sensitive enough for a measurement of the very low concentrations of radionuclides in the environment. The methodological part of this paper is followed by a review of the very abundant literature about speciation of important radionuclides in the environment, i.e. in the atmosphere, hydrosphere and lithosphere. The review does not include the biosphere. Literature up to spring 1993 is included (with a few more recent additions). (author)

Radionuclide transport in a single fissure

International Nuclear Information System (INIS)

Eriksen, T.E.

1983-01-01

Radionuclide migration have been studied in natural fissures orieted parallel to the axis of granite drill cores. A short pulse of the radionuclides solution was injected at one end of the fissure and the temporal change in radionuclide concentration of the eluate measured. After several hundred fissure volumes water had been pumped through the fissure following the radionuclide pulse the activity distribution on the fissure surfaces was measured. From the retardation of 152 Eu, 235 Np and 237 Pu it is concluded that these radionuclides are transported in the oxidation states Eu(III), Pu(IV) and Np(V). The distribution coefficients K sub (d) calculated from flow and activity distribution data on the basis of geometric surface area/volume ratios are of the same order as published K sub (d) values obtained from batch equilibrium experiments. (Author)

Measurement of anthropogenic radionuclides in the atmosphere with a radionuclide monitoring network for nuclear tests

International Nuclear Information System (INIS)

Yonezawa, Chushiro; Yamamoto, Yoichi

2011-01-01

A worldwide radionuclide monitoring network for nuclear tests has detected the anthropogenic radioactive materials released in the atmosphere due to the accident of the Fukushima Daiichi Nuclear Power Plant impacted by the Great East Japan Earthquake on March 11, 2011. After four months have passed since the accident occurred, most overseas stations do not detect the radionuclides of Fukushima origin any more. The Takasaki station in Japan, however, is still detecting them every day. This paper describes radionuclide monitoring stations and the network of them as part of the International Monitoring System (IMS) in the Comprehensive Nuclear Test Ban Treaty (CTBT), as well as the measurement results of radionuclide particulates and radioactive isotopes of xenon released from the Fukushima Daiichi Nuclear Power Plant with the monitoring network. (J.P.N.)

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

International Nuclear Information System (INIS)

Spasennykh, M.Yu.; Apps, J.A.

1995-05-01

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

A vector Wiener filter for dual-radionuclide imaging

International Nuclear Information System (INIS)

Links, J.M.; Prince, J.L.; Gupta, S.N.

1996-01-01

The routine use of a single radionuclide for patient imaging in nuclear medicine can be complemented by studies employing two tracers to examine two different processes in a single organ, most frequently by simultaneous imaging of both radionuclides in two different energy windows. In addition, simultaneous transmission/emission imaging with dual-radionuclides has been described, with one radionuclide used for the transmission study and a second for the emission study. There is thus currently considerable interest in dual-radionuclide imaging. A major problem with all dual-radionuclide imaging is the crosstalk between the two radionuclides. Such crosstalk frequently occurs, because scattered radiation from the higher energy radionuclide is detected in the lower energy window, and because the lower energy radionuclide may have higher energy emissions which are detected in the higher energy window. The authors have previously described the use of Fourier-based restoration filtering in single photon emission computed tomography (SPECT) and positron emission tomography (PET) to improve quantitative accuracy by designing a Wiener or other Fourier filter to partially restore the loss of contrast due to scatter and finite spatial resolution effects. The authors describe here the derivation and initial validation of an extension of such filtering for dual-radionuclide imaging that simultaneously (1) improves contrast in each radionuclide's direct image, (2) reduces image noise, and (3) reduces the crosstalk contribution from the other radionuclide. This filter is based on a vector version of the Wiener filter, which is shown to be superior [in the minimum mean square error (MMSE) sense] to the sequential application of separate crosstalk and restoration filters

76 FR 10205 - Department of Homeland Security Implementation of OMB Guidance on Drug-Free Workplace Requirements

Science.gov (United States)

2011-02-24

... Flexibility Act, 5 U.S.C. 605(b), as amended by the Small Business Regulatory Enforcement and Fairness Act of... Guidance on Drug-Free Workplace Requirements AGENCY: Department of Homeland Security (DHS). ACTION: Final... consolidate all Federal regulations on drug-free workplace requirements for financial assistance into one...

Monitoring and assessment of individual doses of occupationally exposed workers due to intake of radionuclides

International Nuclear Information System (INIS)

Alexander, O. A.

2014-04-01

Monitoring and estimation of individual intakes of radionuclides can be complex. Doses of intakes cannot be measured directly, however must be assessed from the monitoring data of the individual. The individual monitoring data includes whole body counting, excretion analysis (urine or faecal). In the estimation of these data requires that the assessor makes assumptions about the exposure scenario, including the pattern and mode of radionuclide intake. Also physicochemical characteristics of the material involved and the period of time between exposure and measurement. This project report seeks to provide some underlying guidance on monitoring programmes and data interpretation using case study. In this present study the committed effective dose (CED) 1.20mSv exceeded the recording level (i.e. 1mSv) however it was below the investigation level (i.e. 2mSv). The present study recommends that as an essential part in internal dosimetry, specialists be capable of recognizing conditions warranting follow-up bioassay and dose evaluation. Personnel should be familiar with the relevant internal dosimetry literature and the recommendations of national and international scientific organizations with regard to internal dose. (au)

Radionuclides in Canada goose eggs

International Nuclear Information System (INIS)

Rickard, W.H.; Sweany, H.A.

1975-01-01

Low levels of radionuclides were measured in Canada goose eggs taken from deserted nests from Columbia River islands on the Energy Research and Development Administration's Hanford Reservation. Potassium-40, a naturally occurring radionuclide, was the most abundant radionuclide measured in egg contents and egg shell. Strontium-90 was incorporated into egg shells and cesium-137 into inner egg contents. Manganese-54, cobalt-60, and zinc-65 were more abundant in inner egg contents than in egg shell. Cerium-144 was detected in egg shell but not in inner shell

Radionuclide adsorption distribution coefficients measured in Hanford sediments for the low level waste performance assessment project

International Nuclear Information System (INIS)

Kaplan, D.I.; Serne, R.J.; Owen, A.T.

1996-08-01

Preliminary modeling efforts for the Hanford Site's Low Level Waste-Performance Assessment (LLW PA) identified 129 I, 237 Np, 79 Se, 99 Tc, and 234 , 235 , 238 U as posing the greatest potential health hazard. It was also determined that the outcome of these simulations was very sensitive to the parameter describing the extent to which radionuclides sorb to the subsurface matrix, i.e., the distribution coefficient (K d ). The distribution coefficient is a ratio of the radionuclide concentration associated with the solid phase to that in the liquid phase. The objectives of this study were to (1) measure iodine, neptunium, technetium, and uranium K d values using laboratory conditions similar to those expected at the LLW PA disposal site, and (2) evaluate the effect of selected environmental parameters, such as pH, ionic strength, moisture concentration, and radio nuclide concentration, on K d values of selected radionuclides. It is the intent of these studies to develop technically defensible K d values for the PA. The approach taken throughout these studies was to measure the key radio nuclide K d values as a function of several environmental parameters likely to affect their values. Such an approach provides technical defensibility by identifying the mechanisms responsible for trends in K d values. Additionally, such studies provide valuable guidance regarding the range of K d values likely to be encountered in the proposed disposal site

Sensors and Automated Analyzers for Radionuclides

International Nuclear Information System (INIS)

Grate, Jay W.; Egorov, Oleg B.

2003-01-01

The production of nuclear weapons materials has generated large quantities of nuclear waste and significant environmental contamination. We have developed new, rapid, automated methods for determination of radionuclides using sequential injection methodologies to automate extraction chromatographic separations, with on-line flow-through scintillation counting for real time detection. This work has progressed in two main areas: radionuclide sensors for water monitoring and automated radiochemical analyzers for monitoring nuclear waste processing operations. Radionuclide sensors have been developed that collect and concentrate radionuclides in preconcentrating minicolumns with dual functionality: chemical selectivity for radionuclide capture and scintillation for signal output. These sensors can detect pertechnetate to below regulatory levels and have been engineered into a prototype for field testing. A fully automated process monitor has been developed for total technetium in nuclear waste streams. This instrument performs sample acidification, speciation adjustment, separation and detection in fifteen minutes or less

Radionuclide deposition control

International Nuclear Information System (INIS)

1980-01-01

A method is described for controlling the deposition, on to the surfaces of reactor components, of the radionuclides manganese-54, cobalt-58 and cobalt-60 from a liquid stream containing the radionuclides. The method consists of disposing a getter material (nickel) in the liquid stream, and a non-getter material (tantalum, tungsten or molybdenum) as a coating on the surfaces where deposition is not desired. The process is described with special reference to its use in the coolant circuit in sodium cooled fast breeder reactors. (U.K.)

Guidance Oriented Acquisition of Learning Skills (Project GOALS). Final Evaluation Report, 1992-93. OREA Report.

Science.gov (United States)

Musante, Patricia

Guidance Oriented Acquisition of Learning Skills (Project GOALS) was a federally-funded project in three Brooklyn (New York) high schools in its fourth year of operation in 1992-93. It served 312 limited-English-proficient and 57 English-proficient students through instruction in English as a Second Language (ESL), native language arts (NLA) in…

Coastal nonpoint pollution control program: Program development and approval guidance

International Nuclear Information System (INIS)

1993-01-01

The document, developed by NOAA and EPA, contains guidance for states in developing and implementing their coastal nonpoint pollutant source programs. It describes the requirements that must be met, including: the geographic scope of the program; the pollutant sources to be addressed; the types of management measures used; the establishment of critical areas; technical assistance, public participation, and administrative coordination; and, the process for program submission and Federal approval. The document also contains the criteria by which NOAA and EPA will review the states' submissions

Radionuclide transfer

International Nuclear Information System (INIS)

Gerber, G.B.

1993-01-01

The research project described here had the aim to obtain further information on the transfer of nuclides during pregnancy and lactation. The tests were carried out in mini-pigs and rats receiving unchanging doses of radionuclides with the food. The following findings were revealed for the elements examined: Fe, Se, Cs and Zn were characterized by very high transfer levels in the mother, infant and foetus. A substantial uptake by the mother alone was observed for Co, Ag and Mn. The uptake by the foetus and infant here was 1 to 10 times lower. A preferential concentration in certain tissues was seen for Sr and Tc; the thyroid levels of Tc were about equally high in mothers and infants, while Sr showed less accumulation in the maternal bone. The lanthanide group of substances (Ce, Eu and Gd as well as Y and Ru) were only taken up to a very limited extent. The uptake of the examined radionuclides (Fe, Co, Ag, Ce) with the food ingested was found here to be ten times greater in rats as compared to mini-pigs. This showed that great caution must be observed, if the behaviour of radionuclides in man is extrapolated from relevant data obtained in rodents. (orig./MG) [de

Radionuclides in the study of marine processes

International Nuclear Information System (INIS)

Kershaw, P.J.; Woodhead, D.S.

1991-01-01

For many years, the radioactive properties of the naturally occurring radionuclides have been used to determine their distributions in the marine environment and, more generally, to gain an understanding of the dynamic processes which control their behaviour in attaining these distributions. More recently the inputs from human activities of both natural and artificial (i.e. man-made) radionuclides have provided additional opportunities for the study of marine processes on local, regional and global scales. The primary objective of the symposium is to provide a forum for an open discussion of the insights concerning processes in the marine environment which can be gained from studies of radionuclide behaviour. Papers have been grouped within the following principal themes; the uses of radionuclides as tracers of water transport; scavenging and particulate transport processes in the oceans as deduced from radionuclide behaviour; processes in the seabed and radionuclides in biological systems. (Author)

Chemical speciation of radionuclides migrating in groundwaters

International Nuclear Information System (INIS)

Robertson, D.; Schilk, A.; Abel, K.; Lepel, E.; Thomas, C.; Pratt, S.; Cooper, E.; Hartwig, P.; Killey, R.

1994-04-01

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., 60 Co and 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

The 3D cadastre prototype and pilot in the Russian Federation

NARCIS (Netherlands)

Vandysheva, N.; Sapelnikov, S.; Van Oosterom, P.J.M.; De Vries, M.E.; Spiering, B.; Wouters, R.; Hoogeveen, A.; Penkov, V.

2012-01-01

This paper presents the developed prototype and the planned pilot of the on-going project on 3D cadastre modelling in the Russian Federation. The aim of this project is to provide guidance in the development of 3D Cadastral registration and to create favourable legal and institutional conditions for

75 FR 18500 - Guidance on Improving EPA Review of Appalachian Surface Coal Mining Operations under the Clean...

Science.gov (United States)

2010-04-12

..., Monday through Friday, excluding legal holidays. The telephone number for the Public Reading Room is (202... recognizes the importance of this guidance to its Federal and state partners, to the regulated community, and... of Appalachian Surface Coal Mining Operations under the Clean Water Act, National Environmental...

Mobility and Bioavailability of Radionuclides in Soils

International Nuclear Information System (INIS)

Iurian, A.; Olufemi Phaneuf, M.; Mabit, L.

2016-01-01

It is crucial to understand the behavior of radionuclides in the environment, their potential mobility and bioavailability related to long-term persistence, radiological hazards, and impact on human health. Such key information is used to develop strategies that support policy decisions. The environmental behavior of radionuclides depends on ecosystem characteristics. A given soil’s capacity to immobilize radionuclides has been proved to be the main factor responsible for their resulting activity concentrations in plants. The mobility and bioavailability of radionuclides in soils is complex, depending on clay-sized soil fraction, clay mineralogy, organic matter, cation exchange capacity, pH and quantities of competing cations. Moreover, plant species have different behaviors regarding radionuclide absorption depending on soil and plan characteristics

Radionuclides deposition over Antarctica

International Nuclear Information System (INIS)

Pourchet, M.; Magand, O.; Frezzotti, M.; Ekaykin, A.; Winther, J.-G.

2003-01-01

A detailed and comprehensive map of the distribution patterns for both natural and artificial radionuclides over Antarctica has been established. This work integrates the results of several decades of international programs focusing on the analysis of natural and artificial radionuclides in snow and ice cores from this polar region. The mean value (37±20 Bq m -2 ) of 241 Pu total deposition over 28 stations is determined from the gamma emissions of its daughter 241 Am, presenting a long half-life (432.7 yrs). Detailed profiles and distributions of 241 Pu in ice cores make it possible to clearly distinguish between the atmospheric thermonuclear tests of the fifties and sixties. Strong relationships are also found between radionuclide data ( 137 Cs with respect to 241 Pu and 210 Pb with respect to 137 Cs), make it possible to estimate the total deposition or natural fluxes of these radionuclides. Total deposition of 137 Cs over Antarctica is estimated at 760 TBq, based on results from the 90-180 deg. East sector. Given the irregular distribution of sampling sites, more ice cores and snow samples must be analyzed in other sectors of Antarctica to check the validity of this figure

Radionuclides in the food chain

International Nuclear Information System (INIS)

Harley, J.H.; Schmidt, G.D.

1988-01-01

Radionuclides in the Food Chain reviews past experience in meeting the challenge of radionuclide contamination of foodstuffs and water sources and, in the wake of the reactor accidents at Chernobyl and Three Mile Island, presents current concepts and programs relating to measurement, surveillance, effects, risk management, evaluation guidelines, and control and regulatory activities. This volume, based on a symposium sponsored by the International Life Sciences Institute in association with the International Institute for Applied Systems Analysis, which brought together both radiation experts and food industry policymakers, examines such vital topics as structural problems in large-scale crisis-managment systems; dose assessment from man-made sources; international recommendations on radiation protection; airborne contamination, as well as aquatic and soilborne radionuclides; food-chain contamination from testing nuclear devices; long-term health effects of radionuclides in food and water supplies; and use of mathematical models in risk assessment and management. (orig.)

Hanford Site radionuclide national emission standards for hazardous air pollutants unregistered stack (power exhaust) source assessment

International Nuclear Information System (INIS)

Davis, W.E.

1994-01-01

On February 3, 1993, the US Department of Energy, Richland Operations Office received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency, Region 10. The Compliance Order requires the Richland Operations Office to evaluate all radionuclide emission points at the Hanford Site to determine which are subject to continuous emission measurement requirements in 40 Code of Federal Regulations (CFR) 61, Subpart H, and to continuously measure radionuclide emissions in accordance with 40 CFR 61.93. This evaluation provides an assessment of the 39 unregistered stacks, under Westinghouse Hanford Company's management, and their potential radionuclide emissions, i.e., emissions with no control devices in place. The evaluation also determined if the effective dose equivalent from any of these stack emissions exceeded 0.1 mrem/yr, which will require the stack to have continuous monitoring. The result of this assessment identified three stacks, 107-N, 296-P-26 and 296-P-28, as having potential emissions that would cause an effective dose equivalent greater than 0.1 mrem/yr. These stacks, as noted by 40 CFR 61.93, would require continuous monitoring

Hanford Site radionuclide national emission standards for hazardous air pollutants unregistered stack (power exhaust) source assessment

Energy Technology Data Exchange (ETDEWEB)

Davis, W.E.

1994-08-04

On February 3, 1993, the US Department of Energy, Richland Operations Office received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency, Region 10. The Compliance Order requires the Richland Operations Office to evaluate all radionuclide emission points at the Hanford Site to determine which are subject to continuous emission measurement requirements in 40 Code of Federal Regulations (CFR) 61, Subpart H, and to continuously measure radionuclide emissions in accordance with 40 CFR 61.93. This evaluation provides an assessment of the 39 unregistered stacks, under Westinghouse Hanford Company`s management, and their potential radionuclide emissions, i.e., emissions with no control devices in place. The evaluation also determined if the effective dose equivalent from any of these stack emissions exceeded 0.1 mrem/yr, which will require the stack to have continuous monitoring. The result of this assessment identified three stacks, 107-N, 296-P-26 and 296-P-28, as having potential emissions that would cause an effective dose equivalent greater than 0.1 mrem/yr. These stacks, as noted by 40 CFR 61.93, would require continuous monitoring.

Idaho radionuclide exposure study: Literature review

International Nuclear Information System (INIS)

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

1987-10-01

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 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

75 FR 71564 - Defense Federal Acquisition Regulation Supplement; Contractor Insurance/Pension Review (DFARS...

Science.gov (United States)

2010-11-24

... Federal Acquisition Regulation Supplement; Contractor Insurance/Pension Review (DFARS Case 2009-D025... conducting a Contractor Insurance/Pension Review from Procedures, Guidance, and Information (PGI) to the... This final rule relocates requirements for Contractor Insurance/ Pension Review to DFARS 242.7302 from...

Some parameters of radionuclide kinetics

International Nuclear Information System (INIS)

Prokof'ev, O.N.; Smirnov, V.A.; Belen'kij, E.I.

1978-01-01

Numerical values of the rates of radionuclide absorption into, and elimination from, bovine organs were determined. Kinetic rate constants of radionuclides such as 89 Sr, 99 Mo, 131 I, 132 Tl, and 140 Be were calculated. The calculations were done for muscle, liver, and kidney

Radionuclide - Soil Organic Matter Interactions

DEFF Research Database (Denmark)

Carlsen, Lars

1985-01-01

Interactions between soil organic matter, i.e. humic and fulvic acids, and radionuclides of primary interest to shallow land burial of low activity solid waste have been reviewed and to some extent studied experimentally. The radionuclides considered in the present study comprise cesium, strontium...

Radionuclide transport in a single fissure

International Nuclear Information System (INIS)

Eriksen, T.E.

1984-01-01

Radionuclide migration has been studied in natural fissures running parallel to the axes of granitic drill cores. A short pulse of radionuclide solution was injected at one end of the fissure and the temporal change in radionuclide concentration of the eluate measured. At the end of each experiment the fissure was opened and the radionuclide distribution on the fissure surfaces measured. The retardation of 241 Am(III) at pH 8.2 as well as the variation in 235 Np(V) retardation with pH are found to be in good agreement with K d-values obtained in batch experiments. The reduction of (TcO - 4 ) to Tc(IV) leads as expected to increasing retardation.(author)

Radionuclide migration in water reservoirs

International Nuclear Information System (INIS)

Rodionova, L.F.

1983-01-01

Toxicity degree and radiation effect of different radionuclides depend on multiple factors, whose interaction can strengthen or weaken the effects through the mechanism of nuclide accumulation by hydrobiontes. Stage of development of an aquatic organism, its age, mass and sex as well as lifetime and residence time of the organism in the given medium are of importance. The radionuclide build up depends on illumination, locale of the bioobject residence, on the residence nature. The concentration of radionuclides in aquatic organisms and bionts survival depend on a season, temperature of the residence medium, as well as salinity and mineral composition of water influence

Radionuclide Air Emissions Report for 2012

Energy Technology Data Exchange (ETDEWEB)

Wahl, Linnea [Ernest Orlando Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States)

2013-05-01

Berkeley Lab operates facilities where radionuclides are produced, handled, store d, and potentially emitted . These facilities are subject to the EPA radioactive air emission regulations in 40 CFR 61, Subpart H (EPA 1989a). Radionuclides may be emitted from stacks or vents on buildings where radionuclide production or use is authorized or they may be emitted as diffuse sources. In 2012, all Berkeley Lab sources were minor sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.001 mSv/yr]) . These minor sources include d about 140 stack sources and no diffuse sources . T here were no unplanned airborne radionuclide emissions from Berkeley Lab operations . Emissions from minor sources were measured by sampling or monitoring or were calculated based on quantities used, received for use, or produced during the year. Using measured and calculated emissions, and building- specific and common parameters, Laboratory personnel applied the EPA -approved computer code s, CAP88-PC and COMPLY , to calculate doses to the maximally exposed individual (MEI) at any offsite point where there is a residence, school, business, or office. Because radionuclides are used at three noncontiguous locations (the main site, Berkeley West Bio center, and Joint BioEnergy Institute), three different MEIs were identified.

Radionuclide techniques in studies of cardiac performance and circulatory changes during antihypertensive treatment

International Nuclear Information System (INIS)

Falch, D.K.

A non-invasive radionuclide technique to determine variables in the systematic and pulmonary circulation useful in out- patient studies is described. Indium 113m chloride was chosen as the tracer, and iodine 125 iothalamate may be used for simultaneous determination of the glomerular filtration rate. The counting geometry is discussed at some length. The errors of the method and its reproducability seem to be acceptable. The method was tested on two groups of healthy subjects, one of which was composed of well-trained athletes, and two groups of patients, one with chronic cardiac insufficiency, the other with primary hypertension. Tables are presented giving hemodynamic data for these groups. It is concluded that the technique gives some useful data, but that further refinement and supplementation is necessary to obtain a guidance in drug therapy. (JIW)

76 FR 24479 - EPA and Army Corps of Engineers Guidance Regarding Identification of Waters Protected by the...

Science.gov (United States)

2011-05-02

... Waters Protected by the Clean Water Act AGENCY: Environmental Protection Agency (EPA); and U.S. Army... will identify waters protected by the Federal Water Pollution Control Act Amendments of 1972 (Clean... guidance the number of waters identified as protected by the Clean Water Act will increase compared to...

Background information on sources of low-level radionuclide emissions to air

International Nuclear Information System (INIS)

Corbit, C.D.; Herrington, W.N.; Higby, D.P.; Stout, L.A.; Corley, J.P.

1983-09-01

This report provides a general description and reported emissions for eight low-level radioactive source categories, including facilties that are licensed by the Nuclear Regulatory Commission (NRC) and Agreement States, and non-Department of Energy (DOE) federal facilities. The eight categories of low-level radioactive source facilities covered by this report are: research and test reactors, accelerators, the radiopharmaceutical industry, source manufacturers, medical facilities, laboratories, naval shipyards, and low-level commercial waste disposal sites. Under each category five elements are addressed: a general description, a facility and process description, the emission control systems, a site description, and the radionuclides released to air (from routine operations)

Background information on sources of low-level radionuclide emissions to air

Energy Technology Data Exchange (ETDEWEB)

Corbit, C.D.; Herrington, W.N.; Higby, D.P.; Stout, L.A.; Corley, J.P.

1983-09-01

This report provides a general description and reported emissions for eight low-level radioactive source categories, including facilties that are licensed by the Nuclear Regulatory Commission (NRC) and Agreement States, and non-Department of Energy (DOE) federal facilities. The eight categories of low-level radioactive source facilities covered by this report are: research and test reactors, accelerators, the radiopharmaceutical industry, source manufacturers, medical facilities, laboratories, naval shipyards, and low-level commercial waste disposal sites. Under each category five elements are addressed: a general description, a facility and process description, the emission control systems, a site description, and the radionuclides released to air (from routine operations).

Radionuclide supply of the progeny via mother's milk

International Nuclear Information System (INIS)

Ovcharenko, E.P.

1982-01-01

While examining transition of radioactive substances from material organism to milk and then radionuclide administration with milk to progeny, a number of relationships had been revealed. They are similar to those discovered by the author during his study on transplacental radionuclide kinetics. The quantity of transition through placental and milk barriers of group 2 Periodical system radionuclides is inversally proportional to radionuclide mass number. There is evidence for the increase of radionuclide transition per different kinds of animal progeny mass unit during pregnancy as well as during lactation [ru

Radionuclide Retention in Concrete Wasteforms

Energy Technology Data Exchange (ETDEWEB)

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

2011-09-30

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

Graphic Turbulence Guidance

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — Forecast turbulence hazards identified by the Graphical Turbulence Guidance algorithm. The Graphical Turbulence Guidance product depicts mid-level and upper-level...

Water, soil, crops and radionuclides. Studies on the behavior of radionuclides in the terrestrial environments

International Nuclear Information System (INIS)

Uchida, Shigeo

2008-01-01

In order to predict the migration of artificially-produced radionuclides into a human body and its radiation dose rates of human body and to decrease the exposed radiation doses of human body, the behavior of radionuclides in the environment must be elucidated. In National Institute of Radiological Sciences (NIRS), the environmental radioecological research group of Nakaminato Laboratory for Marine Radioecology has progressed the survey and research on the behavior of artificially-produced radionuclides in the terrestrial environment. This article describes the research results (the radioactivity of water, soil, and crops) made so far at Nakaminato Laboratory for Marine Radioecology. (M.H.)

Abscess detection with radionuclides

International Nuclear Information System (INIS)

Alavi, J.B.

1988-01-01

Radionuclide studies may aid in the diagnosis and localization of intra-abdominal infections. Despite the introduction of new radiographic and ultrasound methods, there are several clinical situations in which radionuclide scans have proved useful. Those include detection of postoperative intra-abdominal abscess, evaluation of liver abscess, differentiation between pancreatic pseudocyst or abscess, evaluation of fever of unknown origin, and evaluation of inflammatory bowel disease. Each clinical situation is discussed separately here

Natural and Synthetic Barriers to Immobilize Radionuclides

International Nuclear Information System (INIS)

Um, W.

2011-01-01

The experiments of weathering of glass waste form and the reacted sediments with simulated glass leachates show that radionuclide sequestration can be significantly enhanced by promoting the formation of secondary precipitates. In addition, synthetic phosphate-bearing nanoporous material exhibits high stability at temperature and has a very high K d value for U(VI) removal. Both natural and synthetic barrier materials can be used as additional efficient adsorbents for retarding transport of radionuclides for various contaminated waste streams and waste forms present at U. S. Department of Energy clean-up sites and the proposed geologic radioactive waste disposal facility. In the radioactive waste repository facility, natural or synthetic materials are planned to be used as a barrier material to immobilize and retard radionuclide release. The getter material can be used to selectively scavenge the radionuclide of interest from a liquid waste stream and subsequently incorporate the loaded getters in a cementitious or various monolithic waste forms. Also, the getter material is to reduce the release of radionuclides from monolithic waste forms. Also, the getter material is to reduce the release of radionuclides from monolithic waste forms. Also, the getter material is to reduce the release of radionuclides form monolithic waste forms by being emplaced as a backfill barrier material around the wastes or waste form to minimize the potential around the wastes or waste form to minimize the potential hazard of leached radioactive wastes. The barrier material should be highly efficient to sequester radionuclides and possess physical and chemical stability for long-term exposure to severe weathering conditions. Because potential leaching of radionuclides depends on various environmental and weathering conditions of the near-field repository, the barrier materials must be durable and not disintegrate under a range of moisture, temperature, pressure, radiation, Eh, ph. and

Therapy for incorporated radionuclides: scope and need

International Nuclear Information System (INIS)

Smith, V.H.

1981-03-01

In the United States the recent termination of funding for research on therapy for incorporated radionuclides has virtually halted progress on improved or new agents and procedures for removing radioactivity from the body. Research was eliminated, but is still needed on new removal agents, improved delivery system, in vitro test systems, and the toxicology of treatments. For many radionuclides, no adequate therapy exists. The relationship between radionuclide removal and reduction in cancer risk is still unanswered. Without proper research support, needed improvements in the treatment for incorporated radionuclides in the US are uncertain

Hydroponic phytoremediation of heavy metals and radionuclides

International Nuclear Information System (INIS)

Hartong, J.; Szpak, J.; Hamric, T.; Cutright, T.

1998-01-01

It is estimated that the Departments of Defense, Energy, and Agriculture will spend up to 300 billion federal dollars on environmental remediation during the next century. Current remediation processes can be expensive, non-aesthetic, and non-versatile. Therefore, the need exists for more innovative and cost effective solutions. Phytoremediation, the use of vegetation for the remediation of contaminated sediments, soils, and ground water, is an emerging technology for treating several categories of persistent, toxic contaminants. Although effective, phytoremediation is still in a developmental stage, and therefore is not a widely accepted technology by regulatory agencies and public groups. Research is currently being conducted to validate the processes effectiveness as well as increase regulatory and community acceptance. This research will focus on the ability of plants to treat an aquifer contaminated with heavy metals and radionuclides. Specifically, the effectiveness of hydroponically grown dwarf sunflowers and mustard seed will be investigated

Hydroponic phytoremediation of heavy metals and radionuclides

Energy Technology Data Exchange (ETDEWEB)

Hartong, J; Szpak, J; Hamric, T; Cutright, T

1998-07-01

It is estimated that the Departments of Defense, Energy, and Agriculture will spend up to 300 billion federal dollars on environmental remediation during the next century. Current remediation processes can be expensive, non-aesthetic, and non-versatile. Therefore, the need exists for more innovative and cost effective solutions. Phytoremediation, the use of vegetation for the remediation of contaminated sediments, soils, and ground water, is an emerging technology for treating several categories of persistent, toxic contaminants. Although effective, phytoremediation is still in a developmental stage, and therefore is not a widely accepted technology by regulatory agencies and public groups. Research is currently being conducted to validate the processes effectiveness as well as increase regulatory and community acceptance. This research will focus on the ability of plants to treat an aquifer contaminated with heavy metals and radionuclides. Specifically, the effectiveness of hydroponically grown dwarf sunflowers and mustard seed will be investigated.

Modeling the dynamics of radionuclide concentration in food after an accident in tropical areas

International Nuclear Information System (INIS)

Vinhas, Denise M.; Rochedo, Elaine R.R.; Wasserman, Maria Angelica; Conti, Luiz Fernando C.

2005-01-01

Following an accidental release of radionuclides to the atmosphere that leads to the contamination of large areas, a detailed and fast methodology to assess the prognosis of public exposure is needed, in order to estimate radiological consequences as a base to propose and optimize decisions related to the protection of the public. The German model ECOSYS has been chosen to integrate the SIEM - Integrated Emergency System, developed by IRD/CNEN to assess the doses to the public at the short, medium and long term after an accidental contamination of rural areas. The use of such a model demands a considerable effort in adapting the scenarios to fit the specific conditions of the location where it is to be applied, in particular considering the differences on climate, environmental characteristics, agricultural calendar and practices, along with population diet. The area selected as reference to start this adaptation process is the 50 km radius area surrounding the Brazilian nuclear power plants, at Angra dos Reis County, in Rio de Janeiro State. Radionuclides included in this study were 137 Cs, 90 Sr and 131 I. This work describes the methodology used to select scenarios and describes the results related to the dynamics of the predicted concentration of radionuclides in different kinds of vegetable foods. It also discusses the relevance of criteria, parameter values and site specific aspects that are to be considered in performing assessments of public exposure. The work provides guidance to the need of radioecological research and on the database needed to perform the simulations, in order to improve the adequacy of the estimates to actual Brazilian scenarios. (author)

Phytoremediation of soils contaminated with radionuclides

International Nuclear Information System (INIS)

Yamaguchi, Isamu

2004-01-01

Aiming at efficient phytoremediation of soils contaminated with radionuclides, we examined the effect of soil microbes on the uptake ability of plants using the multitracer technique to find that tomato rhizofungi in Fusarium spp. can stimulate the uptake of 85 Sr and 137 Cs by the plants. The synergic effect of a nonpathogenic strain of F. oxysporum on the uptake of radionuclides by plants proved to be enhanced by introducing a phytochelatin synthase gene into the fungus. Since soil contamination by radionuclides is still an unsolved problem in many parts of the world. Studies on phytoremediation of polluted soil environment will be important for developing effective strategies and devising adequate techniques to reduce human risks caused by food contamination of radionuclides. (author)

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-01-07

In 2010 a Composite Analysis (CA) of the U.S. Department of Energy’s (DOE’s) 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. DOE’s 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

Implementation of IAEA Code of Conduct and Guidance – Exporting State Perspective

International Nuclear Information System (INIS)

Hayes, T.

2010-01-01

Canadian Nuclear Safety Commission (CNSC) is a federal agency reporting to Parliament through Natural Resources Minister It Regulates all nuclear facilities and activities to protect the health, safety and security of persons and the environment, assure that Canada meets its international commitments and obligations on the peaceful use of nuclear energy by Implementation of the IAEA Code and Guidance. There were 99 States committed to the IAEA Code of Conduct (as of July 2010) while 59 States committed to the IAEA Guidance on Import and Export (as of July 2010) Use of risk-informed regulatory processes to optimize resource allocation and decision-making. Canadian Nuclear Safety Commission Control of Radioactive Sources. As such, the Canadian Government is a strong proponent of the establishment and maintenance of an effective, efficient and harmonized international regime for ensuring the safety and security of such sources

Non-cable vehicle guidance

Energy Technology Data Exchange (ETDEWEB)

Daugela, G.C.; Willott, A.M.; Chopiuk, R.G.; Thornton, S.E.

1988-06-01

The purpose is to determine the most promising driverless mine vehicle guidance systems that are not dependent on buried cables, and to plan their development. The project is presented in two phases: a preliminary study and literature review to determine whether suitable technologies exist to justify further work; and an in-depth assessment and selection of technologies for vehicle guidance. A large number of guidance elements are involved in a completely automated vehicle. The technologies that hold the best potential for development of guidance systems for mine vehicles are ultrasonics, radar, lasers, dead reckoning, and guidance algorithms. The best approach to adaptation of these technologies is on a step by step basis. Guidance modules that are complete in themselves and are designed to be integrated with other modules can provide short term benefits. Two modules are selected for development: the dragline operations monitor and automated machine control for optimized mining (AMCOM). 99 refs., 20 figs., 40 tabs.

Radionuclide Retention in Concrete Waste Forms

Energy Technology Data Exchange (ETDEWEB)

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

2010-09-30

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

Remediation of radionuclide pollutants through biosorption - an overview

Energy Technology Data Exchange (ETDEWEB)

Das, Nilanjana [Environmental Biotechnology Division, School of Biosciences and Technology, VIT University, Vellore (India)

2012-01-15

The development of nuclear science and technology has led to the increase of nuclear wastes containing radionuclides to be released and disposed in the environment. Pollution caused by radionuclides is a serious problem throughout the world. To solve the problem, substantial research efforts have been directed worldwide to adopt sustainable technologies for the treatment of radionuclide containing wastes. Biosorption represents a technological innovation as well as a cost effective excellent remediation technology for cleaning up radionuclides from aqueous environment. A variety of biomaterials viz. algae, fungi, bacteria, plant biomass, etc. have been reported for radionuclide remediation with encouraging results. This paper reviews the achievements and current status of radionuclide remediation through biosorption which will provide insights into this research frontier. (Copyright copyright 2012 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

Radionuclide injury to the lung

International Nuclear Information System (INIS)

Dagle, G.E.; Sanders, C.L.

1984-01-01

Radionuclide injury to the lung has been studied in rats, hamsters, dogs, mice and baboons. Exposure of the lung to high dose levels of radionuclides produces a spectrum of progressively more severe functional and morphological changes, ranging from radiation pneumonitis and fibrosis to lung tumors. These changes are somewhat similar for different species. Their severity can be related to the absorbed radiation dose (measured in rads) produced by alpha, beta or gamma radiation emanating from various deposited radionuclides. The chemicophysical forms of radionuclides and spatial-temporal factors are also important variables. As with other forms of injury to the lung, repair attempts are highlighted by fibrosis and proliferation of pulmonary epithelium. Lung tumors are the principal late effect observed in experimental animals following pulmonary deposition of radionuclides at dose levels that do not result in early deaths from radiation pneumonitis or fibrosis. The predominant lung tumors described have been of epithelial origin and have been classified, in decreasing frequency of occurrence, as adenocarcinoma, bronchioloalveolar carcinoma, epidermoid carcinomas and combined epidermoid and adenocarcinoma. Mesothelioma and fibrosarcoma have been observed in rats, but less commonly in other species. Hemangiosarcomas were frequently observed in dogs exposed to beta-gamma emitters, and occasionally in rats exposed to alpha emitters. These morphologic changes in the lungs of experimental animals were reviewed and issues relevant to the prediction of human hazards discussed. 88 references

The vertical distribution of radionuclides in a Ribble Estuary saltmarsh: transport and deposition of radionuclides

International Nuclear Information System (INIS)

Brown, J.E.; McDonald, P.; Parker, A.; Rae, J.E.

1999-01-01

Routine discharges of low-level liquid radioactive waste by British Nuclear Fuels plc (BNFL) at Sellafield and Springfields have resulted in enhanced levels of radionuclides in sediments of the Ribble Estuary, NW England, UK. Variations in radionuclide concentrations ( 137 Cs, 230 Th, and 239240 Pu) with depth in a mature saltmarsh core were analysed in order to investigate historical discharge trends and waste-dispersal mechanisms. Core samples from Longton/Hutton Marsh were analysed by gamma-spectrometry and α-spectrometry for radionuclides and by laser granulometry to establish grain-size variations with depth. Distinct subsurface maxima were present for 137 Cs and 239240 Pu with activities as high as 4500 Bq kg -1 for 137 Cs and 600 Bq kg -1 for 239240 Pu. Thorium-230 exhibited complex activity profiles with depth, specific activities ranging between 200 and 2400 Bq kg -1 . The vertical distributions of Sellafield-derived radionuclides ( 137 Cs and 239240 Pu) in mature saltmarsh deposits reflect the time-integrated discharge pattern from Sellafield, implying a transport mechanism that has involved the mixing of sediment labelled with radioactivity from recent discharges and sediment labelled from historical discharge events before deposition. A mechanism involving the transport of contaminated silt therefore seems to dominate. The vertical distribution of Springfields-derived 230 Th in the same areas reflects the annual gross-α discharge pattern from BNFL Springfields. In contrast to the Sellafield-derived radionuclides, a fairly rapid transport mechanism from source to sink is implied, with little or no time for mixing with radionuclides discharged years earlier. (Copyright (c) 1999 Elsevier Science B.V., Amsterdam. All rights reserved.)

Up-to-date concentrations of long-lived artificial radionuclides in the Tom and Ob rivers in the area influenced by discharges from Siberian chemical combine

International Nuclear Information System (INIS)

Nikitin, A.I.; Kryshev, I.I.; Bashkirov, N.I.; Valetova, N.K.; Dunaev, G.E.; Kabanov, A.I.; Katrich, I.Yu; Krutovsky, A.O.; Nikitin, V.A.; Petrenko, G.I.; Polukhina, A.M.; Selivanova, G.V.; Shkuro, V.N.

2012-01-01

The Siberian Chemical Combine (SCC) is located in Seversk (formerly known as Tomsk-7) in the Tomsk Region of the Russian Federation. The main contribution of radionuclides in the SCC process water discharged into the Tom River was from the single-pass reactors, now removed from service (the last SCC reactor was shutdown on June 5, 2008). The data on the concentrations of 90 Sr, 137 Cs, 239,240 Pu and other artificial radionuclides in water, bottom sediments and flood-plain soils of the Tom and Ob rivers from Tomsk to the confluence of the rivers, are presented and discussed. The results of measurements carried out after shutdown of the last SCC single-pass reactor indicated no radiologically significant consequences of SCC activities for the studied water environment compartments. Contemporary activity concentrations of long-lived artificial radionuclides 3 H, 90 Sr, 137 Cs and 239,240 Pu in river water were below the intervention levels established by current regulations of the Russian Federation for these radionuclides. The results of 3 H analysis in water from the Tom and Samuska rivers demonstrated no inflow of contaminated formation water to surface water from the sites where liquid radioactive wastes of the SCC were injected below the surface. However, the density of flood-plain soil contamination by long-lived 137 Cs in the area influenced by SCC liquid discharges was higher than regional technogenic background. There were local flood-plain areas contaminated not only by 137 Cs, but also other gamma-emitters, such as 60 Co and 152 Eu.

PACE and the Federal Housing Finance Agency (FHFA)

Energy Technology Data Exchange (ETDEWEB)

Zimring, Mark; Fuller, Merrian

2010-03-17

The FHFA regulates Fannie Mae, Freddie Mac, and the 12 Federal Home Loan Banks (the government-sponsored enterprises - GSEs). On June 18, 2009, James B. Lockhart III, then Director of FHFA, released a letter expressing concern about the negative impact of energy loan tax assessment programs (ELTAPs) - also known as Property Assessed Clean Energy (PACE) programs - on both the housing finance system and homeowner program participants. Subsequently, a number of PACE proponents responded to the concerns laid out in the FHFA letter. In early Fall 2009, word circulated that FHFA was planning to follow its June letter with guidance to other agencies, possibly including Fannie Mae and Freddie Mac, discouraging them from buying loans on properties subject to PACE-type assessment liens. This triggered a second round of stakeholder letters, several of which were addressed to President Obama. On October 18, 2009, the White House, in what some believe was an attempt to obviate the need for FHFA guidance, released a Policy Framework for PACE Financing Programs that outlined best practices guidance for homeowner and lender protection. As of February 2010, FHFA and the GSEs have agreed to monitor PACE programs and work with stakeholders and the Administration to consider additional guidance beyond the Policy Framework and to collect more information on PACE program efficacy and risks. A summary of the communications timeline and highlights of the communications are provided.

Interpretation of biological-rate coefficients derived from radionuclide content, radionuclide concentration and specific activity experiments

International Nuclear Information System (INIS)

Vanderploeg, H.A.; Booth, R.S.

1976-01-01

Rigorous expressions are derived for the biological-rate coefficients (BRCs) determined from time-dependent measurements of three different dependent variables of radionuclide tracer experiments. These variables, which apply to a single organism, are radionuclide content, radionuclide concentration and specific activity. The BRCs derived from these variables have different mathematical expressions and, for high growth rates, their numerical values can be quite different. The precise mathematical expressions for the BRCs are presented here to aid modelers in selecting the correct parameters for their models and to aid experiments in interpreting their results. The usefulness of these three variables in quantifying elemental uptakes and losses by organisms is discussed. (U.K.)

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

Energy Technology Data Exchange (ETDEWEB)

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

2008-10-30

understand the limits of these data. They do not provide insight into how radionuclides cured and immobilized in Saltstone will leach from the Saltstone. However they do provide insight into how radionuclides once released into porewater will interact with Saltstone or vault concrete. The use of these site-specific data would greatly improve the pedigree of the input data for the Saltstone performance assessment. Additionally, these studies provided important guidance and technical justification for the conceptual geochemical model to be used in the Saltstone performance assessment.

Research on sorption behavior of radionuclides under shallow land environment. Mechanism and standard methodologies for measurement of distribution coefficients of radionuclides

International Nuclear Information System (INIS)

Sakamoto, Yoshiaki; Tanaka, Tadao; Takebe, Shinichi; Nagao, Seiya; Ogawa, Hiromichi; Komiya, Tomokazu; Hagiwara, Shigeru

2001-01-01

This study consists of two categories' research works. One is research on sorption mechanism of radionuclides with long half-life, which are Technetium-99, TRU elements and U series radionuclides, on soil and rocks, including a development of database of distribution coefficients of radionuclides. The database on the distribution coefficients of radionuclides with information about measurement conditions, such as shaking method, soil characteristics and solution composition, has been already opened to the public (JAERI-DATABASE 20001003). Another study is investigation on a standard methodology of the distribution coefficient of radionuclide on soils, rocks and engineering materials in Japan. (author)

Radionuclides in the environment: Risks and opportunities

International Nuclear Information System (INIS)

Elzerman, A.W.

1993-01-01

Environmental chemistry plays a critical role in the open-quotes nuclear ageclose quotes. It makes a vital contribution to understanding of the sources, fate and effects of radionuclides in the environment, both man-made and natural. Risk assessment of radionuclides in the environment relies heavily on the tools of environmental chemistry. On the other hand, radionuclides provide unique opportunities to exploit in environmental chemistry investigations due to their well-defined sources, traceability in environmental processes, analytical sensitivities, and open-quotes built-inclose quotes radioactive decay open-quotes clocksclose quotes. In some cases naturally present radionuclides are utilized, while in others tracers are deliberately added or have already been added by the nuclear fuel cycle or nuclear testing. Several examples in each of these categories are discussed to spotlight the current status of environmental chemistry and radionuclides in the environment as an example application

75 FR 28253 - Federal Management Regulation (FMR); Notice of GSA Bulletin FMR B-26

Science.gov (United States)

2010-05-20

... responsibility to provide guidance to agencies on property management accountability systems. This bulletin is... agencies maintain adequate inventory controls and accountability systems for property under their control... General and other executive agencies to develop accounting systems for Federal property. The term ``system...

EBS Radionuclide Transport Abstraction

International Nuclear Information System (INIS)

Schreiner, R.

2001-01-01

The purpose of this work is to develop the Engineered Barrier System (EBS) radionuclide transport abstraction model, as directed by a written development plan (CRWMS M and O 1999a). This abstraction is the conceptual model that will be used to determine the rate of release of radionuclides from the EBS to the unsaturated zone (UZ) in the total system performance assessment-license application (TSPA-LA). In particular, this model will be used to quantify the time-dependent radionuclide releases from a failed waste package (WP) and their subsequent transport through the EBS to the emplacement drift wall/UZ interface. The development of this conceptual model will allow Performance Assessment Operations (PAO) and its Engineered Barrier Performance Department to provide a more detailed and complete EBS flow and transport abstraction. The results from this conceptual model will allow PA0 to address portions of the key technical issues (KTIs) presented in three NRC Issue Resolution Status Reports (IRSRs): (1) the Evolution of the Near-Field Environment (ENFE), Revision 2 (NRC 1999a), (2) the Container Life and Source Term (CLST), Revision 2 (NRC 1999b), and (3) the Thermal Effects on Flow (TEF), Revision 1 (NRC 1998). The conceptual model for flow and transport in the EBS will be referred to as the ''EBS RT Abstraction'' in this analysis/modeling report (AMR). The scope of this abstraction and report is limited to flow and transport processes. More specifically, this AMR does not discuss elements of the TSPA-SR and TSPA-LA that relate to the EBS but are discussed in other AMRs. These elements include corrosion processes, radionuclide solubility limits, waste form dissolution rates and concentrations of colloidal particles that are generally represented as boundary conditions or input parameters for the EBS RT Abstraction. In effect, this AMR provides the algorithms for transporting radionuclides using the flow geometry and radionuclide concentrations determined by other

Radionuclide carrier

International Nuclear Information System (INIS)

Hartman, F.A.; Kretschmar, H.C.; Tofe, A.J.

1978-01-01

A physiologically acceptable particulate radionuclide carrier is described. It comprises a modified anionic starch derivative with 0.1% to 1.5% by weight of a reducing agent and 1 to 20% by weight of anionic substituents

Chapter 13. Radionuclides in medicine

International Nuclear Information System (INIS)

Toelgyessy, J.; Harangozo, M.

2000-01-01

This is a chapter of textbook of radioecology for university students. In this chapter authors deal with problems connected with using of radionuclides in medicine. Methods of treatment with using of radionuclides are reviewed. Chapter consists of next parts: (1) Remotion of thyroid gland; (2) Treatment of cerebrally tumour in nuclear reactor; (3) Artificial heart

Naturally occurring radionuclides in food

International Nuclear Information System (INIS)

Djujic, I.

1995-01-01

The naturally occurring radionuclides are the major source of radiation exposure to humans. The principal way of natural radiation exposure is the inhalation of 222 Rn decay products (about 85% of the total). The remainder is equally divided between internally deposited radionuclides, cosmic and terrestrial sources. In the present study, the content of 40 K, 210 Pb, 226 Ra, 230 Th, 232 Th and 238 U in representative food samples (milk, pork, beef, potatoes, wheat and corn flour) and samples of different food items that do not represent entire national production but provide interesting additional data for approximative calculation of naturally occurring radionuclide intake is presented. Daily weight of food eaten, participation of food groups, as well as daily intake by food of mentioned naturally occurring radionuclides in the Serbian diet was obtained on the base of house hold budget surveys. The result obtained for daily intake estimates in mBq for Serbian population are 78.1 ( 40 K), 38.2( 210 Pb), 52.3( 226 Ra), 2.0( 230 Th) and 12.5( 238 U). (author)

Radionuclide Sensors for Subsurface Water Monitoring. Final report

International Nuclear Information System (INIS)

Timothy DeVol

2006-01-01

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 monitored 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

Uptake by plants of radionuclides from FUSRAP waste materials

International Nuclear Information System (INIS)

Knight, M.J.

1983-04-01

Radionuclides from FUSRAP wastes potentially may be taken up by plants during remedial action activities and permanent near-surface burial of contaminated materials. In order to better understand the propensity of radionuclides to accumulate in plant tissue, soil and plant factors influencing the uptake and accumulation of radionuclides by plants are reviewed. In addition, data describing the uptake of the principal radionuclides present in FUSRAP wastes (uranium-238, thorium-230, radium-226, lead-210, and polonium-210) are summarized. All five radionuclides can accumulate in plant root tissue to some extent, and there is potential for the translocation and accumulation of these radionuclides in plant shoot tissue. Of these five radionuclides, radium-226 appears to have the greatest potential for translocation and accumulation in plant shoot tissue. 28 references, 1 figure, 3 tables

Uptake by plants of radionuclides from FUSRAP waste materials

Energy Technology Data Exchange (ETDEWEB)

Knight, M.J.

1983-04-01

Radionuclides from FUSRAP wastes potentially may be taken up by plants during remedial action activities and permanent near-surface burial of contaminated materials. In order to better understand the propensity of radionuclides to accumulate in plant tissue, soil and plant factors influencing the uptake and accumulation of radionuclides by plants are reviewed. In addition, data describing the uptake of the principal radionuclides present in FUSRAP wastes (uranium-238, thorium-230, radium-226, lead-210, and polonium-210) are summarized. All five radionuclides can accumulate in plant root tissue to some extent, and there is potential for the translocation and accumulation of these radionuclides in plant shoot tissue. Of these five radionuclides, radium-226 appears to have the greatest potential for translocation and accumulation in plant shoot tissue. 28 references, 1 figure, 3 tables.

Determination of natural occurring radionuclides concentrations

International Nuclear Information System (INIS)

Stajic, J.; Markovic, V.; Krstic, D.; Nikezic, D.

2011-01-01

Tobacco smoke contains certain concentrations of naturally occurring radionuclides from radioactive chains of uranium and thorium - 214 Pb, 214 Bi, 228 Ac, 208 Tl, 226 Ra, 232 Th and 40 K. Inhaling of tobacco smoke leads to internal exposure of man. In order to estimate absorbed dose of irradiation it is necessary to determine concentrations of radionuclides present in the tobacco leaves. In this paper specific activities of naturally occurring radionuclides were measured in tobacco samples from cigarettes which are used in Serbia. [sr

Manual of bioassay procedures for radionuclides

International Nuclear Information System (INIS)

Pleskach, S.; Petkau, A.

1986-06-01

A monitoring program is described by which atomic radiation workers ar monitored for internal contamination with radionuclides in the workplace. The program involves analytical procedures for measuring alpha, beta and gamma activity in biological specimens, usually urine. Radionuclides are identified by their characteristic radiation using liquid scintillation counting, and alpha, beta and gamma spectrometry. Examples of calculating the minimum detectable activity for specific radionuclides are given and used to derive call-in-criteria in accordance with which the different groups of workers are monitored each month

78 FR 41852 - Hours of Service for Commercial Motor Vehicle Drivers; Regulatory Guidance Concerning Off-Duty Time

Science.gov (United States)

2013-07-12

... provided: 1. The driver is relieved of all duty and responsibility for the care and custody of the vehicle... Service for Commercial Motor Vehicle Drivers; Regulatory Guidance Concerning Off-Duty Time AGENCY: Federal... motor vehicle (CMV) driver to record meal and other routine stops made during a work shift as off-duty...

Radionuclides in ground-level air

International Nuclear Information System (INIS)

Sinkko, K.

1987-01-01

In the air surveillance programme the concentrations of artificial radionuclides are monitored in the air close to the ground to obtain the necessary basic data for estimating the exposure of the Finnish population to fall-out radionuclides and also to detect atmospheric traces of radioactive materials caused by their use or production. Airborne dust is collected on filters with high-volume air samplers and the concentrations of gamma-emitting radionuclides in the air are evaluated. In the first quarter of 1986 only long-lived cesium, caused by earlier atmospheric nuclear explosions was detected. The concentrations of cesium were very low. In January and March a small amount of short-lived, fresh fission and activation products were also observed

77 FR 14811 - Draft Guidance for Industry on Direct-to-Consumer Television Advertisements-the Food and Drug...

Science.gov (United States)

2012-03-13

...The Food and Drug Administration (FDA) is announcing the availability of a draft guidance for industry entitled ``Direct-to- Consumer Television Advertisements--FDAAA DTC Television Ad Pre- Dissemination Review Program.'' This draft guidance is intended to assist sponsors of human prescription drug products, including biological drug products, who are subject to the pre-dissemination review of television advertisements (TV ads) provision of the Federal Food, Drug, and Cosmetic Act (the FD&C Act). (The term ``pre- dissemination review'' is used throughout the guidance to refer to review under the FD&C Act, which is entitled ``Prereview of Television Advertisements.'') The draft guidance describes which TV ads FDA intends to make subject to this provision, explains how FDA will notify sponsors that an ad is subject to review under this provision, and describes the general and center-specific procedures sponsors should follow to submit their TV ads to FDA for pre-dissemination review in compliance with the FD&C Act. These proposed TV ads will be subject to a 45-calendar day review clock by FDA.

Measurements for modeling radionuclide transfer in the aquatic environment

International Nuclear Information System (INIS)

Kahn, B.

1976-01-01

Analytical methods for measuring radionuclides in the aquatic environment are discussed for samples of fresh water and seawater, fish and shellfish, biota such as algae, plankton, seaweed, and aquatic plants, and sediment. Consideration is given to radionuclide collection and concentration, sample preservation, radiochemical and instrumental analysis, and quality assurance. Major problems are the very low environmental levels of the radionuclides of interest, simultaneous occurrence of radionuclides in several chemical and physical forms and the numerous factors that affect radionuclide levels in and transfers among media. Some radionuclides of importance in liquid effluents from nuclear power stations are listed, and sources of radiochemical analytical methods are recommended

Statistical analysis of fallout radionuclides transfer to paddy-field rice

International Nuclear Information System (INIS)

Takahashi, T.; Morisawa, S.; Inoue, Y.

1996-01-01

Radionuclides released from nuclear facilities to atmosphere are transported through various pathways in biosphere and cause human exposure. Among these radionuclides transfer pathways, an ingestion of crops containing radionuclides is one of the dominant pathway for human exposure. For the safety assessment of nuclear facilities, it is important to understand the behavior of radionuclides in agricultural environment and to describe them in a mathematical model. In this paper, a statistical model is proposed for estimating the concentration of fallout radionuclides in paddy-field rice, the staple food for Japanese people. For describing behavior of fallout radionuclides in a paddy-field, a dynamic model and a statistical model have been proposed respectively. The model used in this study has been developed assuming that the amount of radionuclides transfer to brown rice (hulled rice) or polished rice through direct deposition of airborne radionuclides (the direct deposition pathway) and root uptake from a paddy soil (the root uptake pathway) are proportional to the deposition flux of radionuclides and concentration of radionuclides in paddy soil respectively. That is, the model has two independent variables; the deposition flux of radionuclides and the concentration of radionuclides in the paddy soil, and has single dependent variable; the concentration of radionuclides in brown rice or polished rice. The regression analysis is applied by using environmental monitoring data. Then the distribution of radionuclides between rice-bran (skin part of rice crop) and polished rice (core part) through both the direct deposition pathway and the root uptake pathway are evaluated by the model. (author)

Accumulation of radionuclides by lichen symbionts

Energy Technology Data Exchange (ETDEWEB)

Nifontova, M G; Kulikov, N V [AN SSSR, Sverdlovsk. Inst. Ehkologii Rastenij i Zhivotnykh

1983-01-01

The aim of investigation is the quantitative estimation of ability and role of separate symbionts in the accumulation of radionuclides. As investigation volumes, durably cultivated green lichen alga Trebouxia erici and lichen fungi extracted from Cladonia rangiferina, Parmelia caperata and Acarospora fuscata are used. The accumulation of radioactive isotopes with fungi and seaweeds is estimated according to accumulation coefficients (AC) which are the ratio of radiation concentration in plants and agarized medium. Radionuclide content (/sup 90/Sr and /sup 137/Cs) is determined radiometrically. A special series of experiments is done to investigate radionuclide accumulation dependences with lichen seaweed and fungi on light conditions. It is shown that both symbionts of lichen-seaweed and fungus take part in the accumulation of radionuclide from outer medium (atmospheric fall-out and soil). However fungus component constituting the base of structural organization of thallus provides the greater part of radionuclides accumulated by the plant. Along with this the violation of viability of seaweed symbionts particularly in the case of light deficiency brings about the reduction of /sup 137/Cs sorption by seaweeds and tells on the total content of radiocesium in plant thallus.

The rocky flats controversy on radionuclide soil action levels

International Nuclear Information System (INIS)

Earle, T.C.

2004-01-01

This report describes how stakeholder involvement processes led to the successful resolution of a dispute over radionuclide soil action levels at the Rocky Flats Site near Denver, Colorado. During the Cold War Era, Rocky Flats, a plutonium fabrication plant, was part of the American government's multi-site nuclear weapons production facilities. Although the Rocky Flats plant had significant positive effects on the local economy, it became a target of public protest due to concerns over both public safety in the area surrounding the site and global nuclear proliferation. In the late 1980's, local safety concerns led to investigations by state and federal agencies. In 1992, with the Cold War ended, the Department of Energy decided to decommission the Rocky Flats site and to begin the long process of decontamination. (author)

Targeted Radionuclide Therapy

Directory of Open Access Journals (Sweden)

David Cheng

2011-10-01

Full Text Available Targeted radiotherapy is an evolving and promising modality of cancer treatment. The killing of cancer cells is achieved with the use of biological vectors and appropriate radionuclides. Among the many advantages of this approach are its selectiveness in delivering the radiation to the target, relatively less severe and infrequent side effects, and the possibility of assessing the uptake by the tumor prior to the therapy. Several different radiopharmaceuticals are currently being used by various administration routes and targeting mechanisms. This article aims to briefly review the current status of targeted radiotherapy as well as to outline the advantages and disadvantages of radionuclides used for this purpose.

Targeted Radionuclide Therapy

Energy Technology Data Exchange (ETDEWEB)

Ersahin, Devrim, E-mail: devrimersahin@yahoo.com; Doddamane, Indukala; Cheng, David [Department of Diagnostic Radiology, School of Medicine, Yale University, 333 Cedar St., New Haven, CT 06520 (United States)

2011-10-11

Targeted radiotherapy is an evolving and promising modality of cancer treatment. The killing of cancer cells is achieved with the use of biological vectors and appropriate radionuclides. Among the many advantages of this approach are its selectiveness in delivering the radiation to the target, relatively less severe and infrequent side effects, and the possibility of assessing the uptake by the tumor prior to the therapy. Several different radiopharmaceuticals are currently being used by various administration routes and targeting mechanisms. This article aims to briefly review the current status of targeted radiotherapy as well as to outline the advantages and disadvantages of radionuclides used for this purpose.

Radionuclides in foods

International Nuclear Information System (INIS)

1994-01-01

This report contains data on the levels of radionuclides in the UK foodchain. Most data derive from monitoring programmes that exist around nuclear sites, and in some cases date back to the 1960s. Some comparative data from site operator and government-run programmes are included. Data from monitoring undertaken after the Chernobyl accident are summarised. General monitoring of the foodchain for both artificial and natural radionuclides, and the results of relevant government-sponsored research are also described. The report includes basic information on radioactivity in the environment, radiation protection standards and describes what measures are taken to routinely monitor the foodchain and assess public risk. (Author)

Targeted Radionuclide Therapy

International Nuclear Information System (INIS)

Ersahin, Devrim; Doddamane, Indukala; Cheng, David

2011-01-01

Targeted radiotherapy is an evolving and promising modality of cancer treatment. The killing of cancer cells is achieved with the use of biological vectors and appropriate radionuclides. Among the many advantages of this approach are its selectiveness in delivering the radiation to the target, relatively less severe and infrequent side effects, and the possibility of assessing the uptake by the tumor prior to the therapy. Several different radiopharmaceuticals are currently being used by various administration routes and targeting mechanisms. This article aims to briefly review the current status of targeted radiotherapy as well as to outline the advantages and disadvantages of radionuclides used for this purpose

Radionuclides in house dust

Energy Technology Data Exchange (ETDEWEB)

Fry, F A; Green, N; Dodd, N J; Hammond, D J

1985-04-01

Discharges of radionuclides from the British Nuclear Fuel plc (BNFL) reprocessing plant at Sellafield in Cumbria have led to elevated concentrations radionuclides in the local environment. The major routes of exposure of the public are kept under review by the appropriate authorising Government departments and monitoring is carried out both by the departments and by BNFL itself. Recently, there has been increasing public concern about general environmental contamination resulting from the discharges and, in particular, about possible exposure of members of the public by routes not previously investigated in detail. One such postulated route of exposure that has attracted the interest of the public, the press and Parliament arises from the presence of radionuclides within houses. In view of this obvious and widespread concern, the Board has undertaken a sampling programme in a few communities in Cumbria to assess the radiological significance of this source of exposure. From the results of our study, we conclude that, although radionuclides originating rom the BNFL site can be detected in house dust, this source of contamination is a negligible route of exposure for members of the public in West Cumbria. This report presents the results of the Board's study of house dust in twenty homes in Cumbria during the spring and summer of 1984. A more intensive investigation is being carried out by Imperial College. (author)

Radionuclide accumulation peculiarities demonstrated by vegetable varieties

International Nuclear Information System (INIS)

Kruk, A.V.; Goncharenko, G.G.; Kilchevsky, A.V.

2004-01-01

This study focused on ecological and genetic aspects of radionuclide accumulation demonstrated by a number of vegetable varieties. The researches resulted in determining the cabbage varieties which were characterised by the minimal level of radionuclide accumulation. It was shown that the above varieties manifested the relation between radionuclide accumulation and morphobiological characteristics such as vegetation period duration and yield criteria. The study specified the genotypes with high ecological stability as regards to radionuclide accumulation: 'Beloruskaya 85' cabbage and 'Dokhodny' tomato showed the best response to Cs 137, while 'Beloruskaya 85', 'Rusinovka', 'Amager 611' cabbage varieties and 'Sprint' tomato showed the minimal level of Sr 90 accumulation. (authors)

75 FR 27552 - Guidance for Federal Land Management in the Chesapeake Bay Watershed

Science.gov (United States)

2010-05-17

... will allow the federal government to lead the way in protecting the Bay and its watershed with the most effective tools and practices available to reduce water pollution from a variety of nonpoint sources... describe ``proven cost-effective tools and practices that reduce water pollution'' that are appropriate to...

2008 LANL radionuclide air emissions report

Energy Technology Data Exchange (ETDEWEB)

Fuehne, David P.

2009-06-01

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

2010 LANL radionuclide air emissions report /

Energy Technology Data Exchange (ETDEWEB)

Fuehne, David P.

2011-06-01

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

Preparation of porous materials for radionuclides capture

International Nuclear Information System (INIS)

Bajzikova, Anna; Smrcek, Stanislav; Kozempel, Jan; Vlk, Martin; Barta, Jan

2015-01-01

Porous materials showing promise for radionuclide capture from water at contaminated sites were prepared. Nanoporous materials (size of pores 1-100 nm) and some polymers are well suited to this purpose owing their affinity for selected radionuclides. Nanoporous metal oxides and silica gel with styrene-divinylbenzene-TODGA-modified surface were prepared, characterized and tested for radionuclide ( 227 Ac, 227 Th, 223 Ra) capture efficiency. (orig.)

Federal Energy Savings Performance Contracts: Frequently Asked Questions on the Scope of 42 U.S.C. § 8287 et seq.

Energy Technology Data Exchange (ETDEWEB)

None, None

2016-12-21

Document provides clarification and guidance on issues commonly raised regarding the scope of 42 U.S.C. § 8287 et seq. It is a supplement to the Federal Energy Management Program's extensive collection of materials that are available to assist federal agencies execute successful energy savings performance contract (ESPC) projects.

Radionuclide Data Centre. Tasks and problems of obtaining the most reliable values of the nuclear physics characteristics of radionuclides and radiation physics parameters of radionuclide sources

International Nuclear Information System (INIS)

Chechev, V.P.

1994-01-01

Information is provided on the establishment of the Radionuclide Data Centre under the V.G. Khlopin Radium Institute. Its functions and areas of activity are discussed. The paper focuses on the procedure of obtaining the evaluated values of the decay and radiative characteristics of the widely used radionuclides. (author)

The uptake of radionuclides from the soil

International Nuclear Information System (INIS)

Steffens, W.; Fuehr, F.; Mittelstaedt, W.

1980-01-01

Radioactive materials, fission products of fuels used and corrosion nuclides are transferred in small amounts through waste gases and waste liquids of nuclear plants to the environment. They are deposited on plants and soil, are subjected there to nuclide-specific distribution patterns, can be enriched in the soil over years, are taken up from plants via the roots and hence get into the food chains and contribute to the radiation burden to man. The annual radiation burden via food absorption is determined by calculation models. These models take into account the uptake of radionuclides via the plant roots by nuclide-specific transfer factors. Close-to-practice tests with representative soils of the Federal Republic of Germany enable the fluctuation of these transfer factors to be determined and hence contribute to the conservative assessment of the ingestion burden via the soil/plant transfer for the operation of nuclear power plants or reprocessing plants. (orig.) [de

Human dose pathways of radionuclides in forests

International Nuclear Information System (INIS)

Rantavaara, A.

2009-01-01

Forest soil, understorey vegetation and trees are all sources of radionuclides and human radiation doses after contaminating atmospheric deposition. People are exposed to radiation externally from sources outside the body and internally via ingestion and inhalation of radionuclides. Understorey vegetation contributes to ingestion doses through berries, herbs, wild honey, mushrooms and game meat; also trees provide feed to terrestrial birds and big game. During stay in forests people are subject to external radiation from forest floor and overstorey, and they may inhale airborne radioactive aerosol or gaseous radionuclides in ground level air. In the early phase of contamination also resuspended radionuclides may add to the internal dose of people via inhalation. People in Nordic countries are most exposed to radiation via ingestion of radionuclides in wild foods. The distribution of radionuclides in forests is changed by environmental processes, and thereby also the significance of various dose pathways to humans will change with time. External exposure is received in living environment from contaminated stemwood used as building timber and for manufacturing of furniture and other wood products. The aim of this paper is to outline the significance of various human dose pathways of radionuclides in forests considering the public and workers in forestry and production of bioenergy. Examples on effective doses are given based on two historical events, atmospheric nuclear weapon tests (mostly in 1950's and in 1960's) and the Chernobyl nuclear power plant accident in 1986. (au)

Healthcare organizations and the Internet: impact on federal tax exemption.

Science.gov (United States)

Woods, LaVerne; Osborne, Michele

2002-01-01

Tax-exempt healthcare organizations have turned to the Internet as a powerful tool in communicating with the public, medical staff, and patients. Activities as diverse as providing links to the Web sites of other organizations, selling goods and services, soliciting contributions, and hosting forums on the Internet raise unresolved questions concerning the impact of Internet use on such organizations' tax-exempt status. The Internal Revenue Service has provided no guidance to date regarding the manner in which a nonprofit organizations' use of the Internet may affect its tax-exempt status or subject it to federal income tax on some sources of funds. This article suggests analytical approaches for applying existing law in the Internet context and identifies areas that are ripe for additional guidance.

Marine Sciences Laboratory Radionuclide Air Emissions Report for Calendar Year 2015

Energy Technology Data Exchange (ETDEWEB)

Snyder, Sandra F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Barnett, J. Matthew [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2016-05-05

The U.S. Department of Energy Office of Science (DOE-SC) Pacific Northwest Site Office has oversight and stewardship duties associated with the Pacific Northwest National Laboratory Marine Sciences Laboratory located on Battelle Land – Sequim. This report is prepared to document compliance with the 40 CFR Part 61, Subpart H, “National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities” and Washington Administrative Code . The EDE to the MSL MEI due to routine operations in 2015 was 1.1E-04 mrem (1.1E-06 mSv). No non-routine emissions occurred in 2015. The MSL is in compliance with the federal and state 10 mrem/yr standard.

Radionuclides in house dust

CERN Document Server

Fry, F A; Green, N; Hammond, D J

1985-01-01

Discharges of radionuclides from the British Nuclear Fuel plc (BNFL) reprocessing plant at Sellafield in Cumbria have led to elevated concentrations radionuclides in the local environment. The major routes of exposure of the public are kept under review by the appropriate Government departments and monitoring is carried out both by the departments and by BNFL itself. Recently, there has been increasing public concern about general environmental contamination resulting from the discharges and, in particular, about possible exposure of members of the public by routes not previously investigated in detail. One such postulated route of exposure that has attracted the interest of the public, the press and Parliament arises from the presence of radionuclides within houses. In view of this obvious and widespread concern, the Board has undertaken a sampling programme in a few communities in Cumbria to assess the radiological significance of this source of exposure. From the results of our study, we conclude that, alt...

DKPRO: A radionuclide decay and reprocessing code

International Nuclear Information System (INIS)

Wootan, D.; Schmittroth, F.A.

1997-01-01

The DKPRO code solves the general problem of modeling complex nuclear wastes streams using ORIGEN2 radionuclide production files. There is a continuing need for estimates of Hanford radionuclides. Physical measurements are one basis; calculational estimates, the approach represented here, are another. Given a known nuclear fuel history, it is relatively straightforward to calculate radionuclide inventories with codes such as the widely-used Oak Ridge National Laboratory code ORIGEN2

Radionuclide-migration model for buried waste at the Savannah River Plant

International Nuclear Information System (INIS)

King, C.M.; Root, R.W. Jr.

1982-01-01

Solid waste has been buried at the Savannah River Plant burial ground since 1953. The solid waste is contaminated with alpha-emitting transuranium (TRU) nuclides, with beta-gamma-emitting activation and fission products, and with tritium. To provide guidance for the current use and eventual permanent retirement of the burial site from active service, a radionuclide environmental transport model has been used to project the potential influence on man if the burial site were occupied after decommissioning. The model used to simulate nuclide migration includes the various hydrological, animal, vegetative, atmospheric, and terrestrial pathways in estimating dose to man as a function of time. Specific scenarios include a four-person home farm on the 195-acre burial ground. Key input to the model includes site-specific nuclide migration rates through soil, nuclide distribution coefficients, and site topography. Coupled with literature data on plant and animal concentration factors, transfer coefficients reflecting migration routes are input to a set of linear differential equations for subsequent matrix solution. Output from the model is the nuclide-specific decayed curie intake by man. To discern principal migration routes, model-compartment inventories with time can also be displayed. Dose projections subsequently account for organ concentrations in man for the nuclide of interest. Radionuclide migration has been examined in depth with the dose-to-man model. Movement by vegetative pathways is the primary route for potential dose to man for short-lived isotopes. Hydrological routes provide a secondary scheme for long-lived nuclides. Details of model methodology are reviewed

Transfer of radionuclides into human milk

International Nuclear Information System (INIS)

Steiner, M.; Wirth, E.

1998-01-01

Up until now the potential radiation exposure to breast-fed babies due to contaminated human milk has not been taken into account, when deriving international limit values and reference levels for radionuclides in foodstuffs, in air at monitored work places or for exposures in the medical field. It was the aim of the research project 'Transfer of radionuclides into human milk' to quantify the transfer of incorporated radionuclides into mother's milk, and develop simple models to estimate the radiation exposure of babies through the ingestion of human milk. The study focused on considerations of the radiation exposure due to the ingestion of contaminated foodstuffs by the mother, the inhalation of radionuclides at monitored work places, and the administration of radiopharmaceuticals to breast-feeding mothers. The blocking of infant thyroid glands by stable iodine in the case of accidental releases of radioiodine was considered as well. (orig.) [de

Biogeochemical cycles of Chernobyl-born radionuclides in the contaminated forest ecosystems: long-term dynamics of the migration processes

Science.gov (United States)

Shcheglov, Alexey; Tsvetnova, Ol'ga; Klyashtorin, Alexey

2013-04-01

1986 (less than two months after the accident) and have been continued up to now, focused on the most common forest ecosystems scattered over the contaminated areas of Russian Federation and Ukraine. A comprehensive analysis of the 137Cs and 90Sr biogeochemical fluxes shows that downward radionuclide fluxes (those directed from tree crowns to the soil) dominated over the upward fluxes (from the soil to forest vegetation) in the first years after the accident. Currently, the biological cycle in the contaminated ecosystems is a main factor impeding further vertical migration of long-lived radionuclides from upper soil layers to the ground water. The role of biota as a retardation factor depends on landscape type as well. In accumulative landscapes (with positive material balance), biota plays leading role in radionuclide retardation, while in eluvial landscapes (with the negative balance) soil absorbing complex serves as the dominant barrier for radionuclides leaching down the soil profile. The manifestation of both soil- and biota-driven factors depends on the radionuclide chemical speciation in the initial fallout. The latter factor is most important for 137Cs, yet less manifested for 90Sr. Among the biota components, fungi and forest vegetation are of particular importance for 137Cs and 90Sr accumulation, respectively. In summary, biogeochemical cycles of 137Cs and 90Sr in the investigated forest ecosystems serve as main factors impeding the radionuclide migration from the fallout to ground water. Larger-scale landscape factors determine the radionuclide flux intensity in the biogeochemical cycles and affect the radionuclide spatial variability in the contaminated biota components.

Radionuclide migration in crystalline rock fractures

International Nuclear Information System (INIS)

Hoelttae, P.

2002-01-01

Crystalline rock has been considered as a host medium for the repository of high radioactive spent nuclear fuel in Finland. The geosphere will act as an ultimate barrier retarding the migration of radionuclides to the biosphere if they are released through the technical barriers. Radionuclide transport is assumed to take place along watercarrying fractures, and retardation will occur both in the fracture and within the rock matrix. To be able to predict the transport and retardation of radionuclides in rock fractures and rock matrices, it is essential to understand the different phenomena involved. Matrix diffusion has been indicated to be an important mechanism, which will retard the transport of radionuclides in rock fractures. Both dispersion and matrix diffusion are processes, which can have similar influences on solute breakthrough curves in fractured crystalline rock. In this work, the migration of radionuclides in crystalline rock fractures was studied by means of laboratory scale column methods. The purpose of the research was to gain a better understanding of various phenomena - particularly matrix diffusion - affecting the transport and retardation behaviour of radionuclides in fracture flow. Interaction between radionuclides and the rock matrix was measured in order to test the compatibility of experimental retardation parameters and transport models used in assessing the safety of underground repositories for spent nuclear fuel. Rock samples of mica gneiss and of unaltered, moderately altered and strongly altered tonalite represented different rock features and porosities offering the possibility to determine experimental boundary limit values for parameters describing both the transport and retardation of radionuclides and rock matrix properties. The dominant matrix diffusion behaviour was demonstrated in porous ceramic column and gas diffusion experiments. Demonstration of the effects of matrix diffusion in crystalline rock fracture succeeded for the

ORNL's DCAL software package

International Nuclear Information System (INIS)

Eckerman, K.F.

2007-01-01

Oak Ridge National Laboratory has released its Dose and Risk Calculation software, DCAL. DCAL, developed with the support of the U.S. Environmental Protection Agency, consists of a series of computational modules, driven in either an interactive or a batch mode for computation of dose and risk coefficients from intakes of radionuclides or exposure to radionuclides in environmental media. The software package includes extensive libraries of biokinetic and dosimetric data that represent the current state of the art. The software has unique capability for addressing intakes of radionuclides by non-adults. DCAL runs as 32-bit extended DOS and console applications under Windows 98/NT/2000/XP. It is intended for users familiar with the basic elements of computational radiation dosimetry. Components of DCAL have been used to prepare U.S. Environmental Protection Agency's Federal Guidance Reports 12 and 13 and several publications of the International Commission on Radiological Protection. (author)

Information by the Federal Government. Report of the Federal Governement on 'Environmental radioactivity and radiation load in 1975'

International Nuclear Information System (INIS)

1977-01-01

The report on environmental radioactivity and radiation load, to be published annually by the Federal government, contains data on artificial exposure from nuclear facilities, data on the application of radioactive substances and ionizing rays in research and technology, on occupational activities, medical application and special occurrences. Not only the annual release of radioactive substances from nuclear fcilities is presented but also data on the maximum permissible radiation exposures and the average gonadal exposure within the vicinity of plants. Furthermore, data is presented on the influence of X-ray investigations on the genetically significant dose as well as on the proportion in percent of the various radionuclides when applied in nuclear medicine. (ORU) [de

Gastroesophageal reflux in children: radionuclide gastroesophagography

International Nuclear Information System (INIS)

Blumhagen, J.D.; Rudd, T.G.; Christie, D.L.

1980-01-01

Sixty-five symptomatic infants and children underwent radionuclide gastroesophagography, acid reflux testing, and barium esophagography with water-siphon testing to evaluate the clinical efficacy of the scintigraphic technique in detecting gastroesophageal reflux. After ingesting /sup 99m/Tc sulfur colloid in fruit juice, patients rested beneath the gamma camera for 30 to 60 min while esophageal activity was monitored continuously. By using the acid reflux test as a standard of comparison, the senstivity of radionuclide gastroesophagography was 75%. Because of its physiologic nature, low radiation exposure, and convenience, radionuclide gastroesophagography warrants further evaluation as a screening test for gastroesophageal reflux

Soil - plant experimental radionuclide transfer factors

International Nuclear Information System (INIS)

Dobrin, R.I.; Dulama, C.N.; Toma, Al.

2006-01-01

Some experimental research was performed in our institute to assess site specific soil-plant transfer factors. A full characterization of an experimental site was done both from pedo-chemical and radiological point of view. Afterwards, a certain number of culture plants were grown on this site and the evolution of their radionuclide burden was then recorded. Using some soil amendments one performed a parallel experiment and the radionuclide root uptake was evaluated and recorded. Hence, transfer parameters were calculated and some conclusions were drawn concerning the influence of site specific conditions on the root uptake of radionuclides. (authors)

Biota-sediment accumulation factors for radionuclides and sediment associated biota of the Ottawa River

Energy Technology Data Exchange (ETDEWEB)

Rowan, D.; Silke, R.; Carr, J., E-mail: rowand@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

2013-12-15

As Ottawa River contamination is historical and resides in sediment, ecological risk and trophic transfer depend on linkages between sediment and biota. One of the ways in which this linkage is quantified is through the use of the biota sediment accumulation factor (BSAF). In this study, we present the first field estimates of BSAF for a number of radionuclides. The strongest and most consistent BSAFs were those for {sup 137}Cs in deposit feeding taxa, suggesting that sediment concentrations rather than dissolved concentrations drive uptake. For crayfish and unionid bivalves that do not feed on sediment, biota radionuclide concentrations were not related to sediment concentrations, but rather reflected concentrations in water. BSAFs would not be appropriate for these non-deposit feeding biota. BSAFs for {sup 137}Cs were not significantly different among deposit feeding taxa, suggesting similar processes for ingestion, assimilation and elimination. These data also show that the concentration factor approach used for guidance would have led to spurious results in this study for deposit feeding benthic invertebrates. Concentrations of {sup 137}Cs in Hexagenia downstream of the CRL process outfall range by about 2-orders of magnitude, in comparison to relatively uniform water concentrations. The concentration factor approach would have predicted a single value downstream of CRL, underestimating exposure to Hexagenia by almost 2-orders of magnitude at sites close to the CRL process outfall. (author)

Sources of anthropogenic radionuclides in the environment: a review

International Nuclear Information System (INIS)

Hu Qinhong; Weng Jianqing; Wang Jinsheng

2010-01-01

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 on sources of anthropogenic radionuclides in the environment, as well as a brief discussion of salient geochemical behavior of important radionuclides. We first discuss the following major anthropogenic sources and current developments that have lead, or could potentially contribute, to the radionuclide contamination of the environment: (1) nuclear weapons program; (2) nuclear weapons testing; (3) nuclear power plants; (4) uranium mining and milling; (5) commercial fuel reprocessing; (6) geological repository of high-level nuclear wastes that include radionuclides might be released in the future, and (7) nuclear accidents. Then, we briefly summarize the inventory of radionuclides 99 Tc and 129 I, as well as geochemical behavior for radionuclides 99 Tc, 129 I, and 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.

Dissecting Attending Surgeons' Operating Room Guidance: Factors That Affect Guidance Decision Making.

Science.gov (United States)

Chen, Xiaodong Phoenix; Williams, Reed G; Smink, Douglas S

2015-01-01

The amount of guidance provided by the attending surgeon in the operating room (OR) is a key element in developing residents' autonomy. The purpose of this study is to explore factors that affect attending surgeons' decision making regarding OR guidance provided to the resident. We used video-stimulated recall interviews (VSRI) throughout this 2-phase study. In Phase 1, 3 attending surgeons were invited to review separately 30 to 45 minute video segments of their prerecorded surgical operations to explore factors that influenced their OR guidance decision making. In Phase 2, 3 attending surgeons were observed and documented in the OR (4 operations, 341min). Each operating surgeon reviewed their videotaped surgical performance within 5 days of the operation to reflect on factors that affected their decision making during the targeted guidance events. All VSRI were recorded. Thematic analysis and manual coding were used to synthesize and analyze data from VSRI transcripts, OR observation documents, and field notes. A total of 255 minutes of VSRI involving 6 surgeons and 7 surgical operations from 5 different procedures were conducted. A total of 13 guidance decision-making influence factors from 4 categories were identified (Cohen's κ = 0.674): Setting (case schedule and patient morbidity), content (procedure attributes and case progress), resident (current competency level, trustworthiness, self-confidence, and personal traits), and attending surgeon (level of experience, level of comfort, preferred surgical technique, OR training philosophy, and responsibility as surgeon). A total of 5 factors (case schedule, patient morbidity, procedure attributes, resident current competency level, and trustworthiness) influenced attending surgeons' pre-OR guidance plans. "OR training philosophy" and "responsibility as surgeon" were anchor factors that affected attending surgeons' OR guidance decision-making patterns. Surgeons' OR guidance decision making is a dynamic process

Transuranic radionuclides dispersed into the aquatic environment, a bibliography

Energy Technology Data Exchange (ETDEWEB)

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

1994-04-01

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.

Radionuclide characterization of environmental air around nuclear facilities

International Nuclear Information System (INIS)

Gede Sutresna Wijaya; Anung Muharini

2015-01-01

Air is an important environmental component in human life. Presence of air pollutants or contaminants will have a negative impact on human health. According to the existence of a nuclear facility in Yogyakarta, the characterization of radionuclides in the air is absolutely necessary to ensure the safety of people and the environment and also to supervise the safe operation of the facility. In this research the characterization of radionuclides in the air was carried through the air sampling by using High Volume Air Sampler equipped with filter TFA 2133, followed by analysis using combination of a gamma and alpha spectrometers. The concentration of radioactivity in the air fluctuates depending on the time and duration of sampling. Characterization of gamma emitting radionuclides in the air is dominated by radon progeny radionuclides such as 214 Pb, 214 Bi with activity 20.09 ± 1.23 until 32.91 ± 4.87 Bq/m 3 and 31.22 ± 1.76 until 44.25 ± 4.91 Bq/m 3 . Alpha emitter radionuclide was dominated by 214 Po (7.69 MeV) which is also radon progeny and a primordial radionuclides. It can be concluded that the presence of radionuclides in the environmental air not as a product resulting from the operation of nuclear facilities in Yogyakarta. (author)

Raising the Profile of Career Guidance: Educational and Vocational Guidance Practitioner

Science.gov (United States)

Hiebert, Bryan

2009-01-01

In 2007 the International Association for Educational and Vocational Guidance (IAEVG) launched the Educational and Vocational Guidance Practitioner credential (EVGP) as one means of formally acknowledging the knowledge, skills, and personal attributes that practitioners need in order to provide quality career development services to clients. This…

An overview of BORIS: Bioavailability of Radionuclides in Soils

International Nuclear Information System (INIS)

Tamponnet, C.; Martin-Garin, A.; Gonze, M.-A.; Parekh, N.; Vallejo, R.; Sauras-Yera, T.; Casadesus, J.; Plassard, C.; Staunton, S.; Norden, M.; Avila, R.; Shaw, G.

2008-01-01

The ability to predict the consequences of an accidental release of radionuclides relies mainly on the level of understanding of the mechanisms involved in radionuclide interactions with different components of agricultural and natural ecosystems and their formalisation into predictive models. Numerous studies and databases on contaminated agricultural and natural areas have been obtained, but their use to enhance our prediction ability has been largely limited by their unresolved variability. Such variability seems to stem from incomplete knowledge about radionuclide interactions with the soil matrix, soil moisture, and biological elements in the soil and additional pollutants, which may be found in such soils. In the 5th European Framework Programme entitled Bioavailability of Radionuclides in Soils (BORIS), we investigated the role of the abiotic (soil components and soil structure) and biological elements (organic compounds, plants, mycorrhiza, and microbes) in radionuclide sorption/desorption in soils and radionuclide uptake/release by plants. Because of the importance of their radioisotopes, the bioavailability of three elements, caesium, strontium, and technetium has been followed. The role of one additional non-radioactive pollutant (copper) has been scrutinised in some cases. Role of microorganisms (e.g., K d for caesium and strontium in organic soils is much greater in the presence of microorganisms than in their absence), plant physiology (e.g., changes in plant physiology affect radionuclide uptake by plants), and the presence of mycorrhizal fungi (e.g., interferes with the uptake of radionuclides by plants) have been demonstrated. Knowledge acquired from these experiments has been incorporated into two mechanistic models CHEMFAST and BIORUR, specifically modelling radionuclide sorption/desorption from soil matrices and radionuclide uptake by/release from plants. These mechanistic models have been incorporated into an assessment model to enhance its

An overview of BORIS: Bioavailability of Radionuclides in Soils

Energy Technology Data Exchange (ETDEWEB)

Tamponnet, C. [Institute of Radioprotection and Nuclear Safety, DEI/SECRE, CADARACHE, B.P. 1, 13108 Saint-Paul-lez-Durance, Cedex (France)], E-mail: christian.tamponnet@irsn.fr; Martin-Garin, A.; Gonze, M.-A. [Institute of Radioprotection and Nuclear Safety, DEI/SECRE, CADARACHE, B.P. 1, 13108 Saint-Paul-lez-Durance, Cedex (France); Parekh, N. [Center for Ecology and Hydrology, Lancaster Environment Centre, Lancaster University, Lancaster LA1 4YQ (United Kingdom); Vallejo, R.; Sauras-Yera, T.; Casadesus, J. [Department of Plant Biology, University of Barcelona, 08028 Barcelona (Spain); Plassard, C.; Staunton, S. [INRA, UMR Rhizosphere and Symbiosis, Place Viala, 34060 Montpellier (France); Norden, M. [Swedish Radiation Protection Institute, 171 16 Stockholm (Sweden); Avila, R. [Facilia AB, Valsgaerdevaegen 12, 168 53 Bromma, Stockholm (Sweden); Shaw, G. [Division of Agricultural and Environmental Sciences University Park, Nottingham NG7 2RD (United Kingdom)

2008-05-15

The ability to predict the consequences of an accidental release of radionuclides relies mainly on the level of understanding of the mechanisms involved in radionuclide interactions with different components of agricultural and natural ecosystems and their formalisation into predictive models. Numerous studies and databases on contaminated agricultural and natural areas have been obtained, but their use to enhance our prediction ability has been largely limited by their unresolved variability. Such variability seems to stem from incomplete knowledge about radionuclide interactions with the soil matrix, soil moisture, and biological elements in the soil and additional pollutants, which may be found in such soils. In the 5th European Framework Programme entitled Bioavailability of Radionuclides in Soils (BORIS), we investigated the role of the abiotic (soil components and soil structure) and biological elements (organic compounds, plants, mycorrhiza, and microbes) in radionuclide sorption/desorption in soils and radionuclide uptake/release by plants. Because of the importance of their radioisotopes, the bioavailability of three elements, caesium, strontium, and technetium has been followed. The role of one additional non-radioactive pollutant (copper) has been scrutinised in some cases. Role of microorganisms (e.g., K{sub d} for caesium and strontium in organic soils is much greater in the presence of microorganisms than in their absence), plant physiology (e.g., changes in plant physiology affect radionuclide uptake by plants), and the presence of mycorrhizal fungi (e.g., interferes with the uptake of radionuclides by plants) have been demonstrated. Knowledge acquired from these experiments has been incorporated into two mechanistic models CHEMFAST and BIORUR, specifically modelling radionuclide sorption/desorption from soil matrices and radionuclide uptake by/release from plants. These mechanistic models have been incorporated into an assessment model to enhance

A basic toxicity classification of radionuclides

International Nuclear Information System (INIS)

1963-01-01

In the course of its work in the field of health and safety the International Atomic Energy Agency has often met the practical requirement for grading radionuclides in order of their relative radiotoxicities. This need was particularly evident when the Agency's Basic Safety Standards for the protection of health against ionizing radiation were in preparation, when it was necessary to exempt quantities of radionuclides from inclusion in the norms. A basic toxicity grading might be of help to laboratories in meeting some of their requirements in problems related to waste management as well as for the design of experimental facilities. It should also serve as a basis for the development of safety criteria for laboratory equipment and procedures for handling and transporting various quantities and kinds of radionuclides. The purpose of the present Report is to make a toxicity grading of the radionuclides according to the risk of biological injury which they may cause when they have become incorporated in the human body. 4 refs, 4 tabs

A basic toxicity classification of radionuclides

Energy Technology Data Exchange (ETDEWEB)

1963-04-01

In the course of its work in the field of health and safety the International Atomic Energy Agency has often met the practical requirement for grading radionuclides in order of their relative radiotoxicities. This need was particularly evident when the Agency's Basic Safety Standards for the protection of health against ionizing radiation were in preparation, when it was necessary to exempt quantities of radionuclides from inclusion in the norms. A basic toxicity grading might be of help to laboratories in meeting some of their requirements in problems related to waste management as well as for the design of experimental facilities. It should also serve as a basis for the development of safety criteria for laboratory equipment and procedures for handling and transporting various quantities and kinds of radionuclides. The purpose of the present Report is to make a toxicity grading of the radionuclides according to the risk of biological injury which they may cause when they have become incorporated in the human body. 4 refs, 4 tabs.

Method of preparing radionuclide doses

International Nuclear Information System (INIS)

Kuperus, J.H.

1987-01-01

A method is described of preparing aliquot dosea of a tracer material useful in diagnostic nuclear medicine comprising: storing discrete quantities of a lyophilized radionuclide carrier in separate tubular containers from which air and moisture is excluded, selecting from the tubular containers a container in which is stored a carrier appropriate for a nuclear diagnostic test to be performed, interposing the selected container between the needle and the barrel of a hypodermic syringe, and drawing a predetermined amount of a liquid containing a radionuclide tracer in known concentration into the hypodermic syringe barrel through the hypodermic needle and through the selected container to dissolve the discrete quantity of lyophilized carrier therein to combine the carrier with the radionuclide tracer to form an aliquot dose of nuclear diagnostic tracer material, as needed

Transfer parameters of radionuclides in the marine environment

International Nuclear Information System (INIS)

1996-03-01

To increase the accuracy of estimation of exposure dose by radionuclides in the marine, the informations of environmental parameter data in the marine were collected, arranged and discussed. The informations were discussed by 'a sectional committee of marine suspended solids and sediment'. The following problems were investigated and the studies were recorded in this report, clear explanation about the distribution factor (kd), the estimation method of kd, the fluctuating factor of kd data (properties of suspension and sediment, differences among the experimental methods), the physical and chemical behavior of radionuclides, sediment of radionuclides by means of sorption to the suspended particles in the marine, sorption of radionuclides into the marine soil (sediment), re-eluent of radionuclides sorpted in the marine soil (sediment), and relation between marine organism and marine suspended materials and sediment. (S.Y.)

Modeling the dynamics of radionuclide concentration in animal derived products after an accident in tropical areas

International Nuclear Information System (INIS)

Vinhas, Denise M.; Rochedo, Elaine R.R.; Wasserman, Maria A.V.; Conti, Luiz F.C.

2005-01-01

Following an accidental release of radionuclides to the atmosphere with the contamination of large areas, a detailed and fast methodology to assess the prognosis of public exposure is needed to estimate radiological consequences and optimize decisions to the protection of the public. The German model ECOSYS has been chosen to integrate the SIEM - Integrated Emergency System, developed by IRD/CNEN to assess the doses to the public after an accidental contamination of rural areas. The use the model demands a considerable effort in adapting scenarios to fit the specific conditions of a location, considering the differences related to climate, environmental characteristics, agricultural calendar and practices, along with population diet. The area selected to start this adaptation considers the characteristics of the 50 km radius area surrounding the nuclear power plants at Angra dos Reis, Rio de Janeiro. At a first stage, the concentration on vegetal food products has been studied. This work describes the methodology used to select scenarios and presents results of the dynamics of the predicted concentration of radionuclides in different kinds of animal derived food products. The work provides guidance to the need of radioecological research needed to improve the adequacy of the estimates to actual Brazilian scenarios. (author)

Production of medical short-lived radionuclides in Canada

International Nuclear Information System (INIS)

Wiebe, L.I.

1985-01-01

The production of radionuclides for medical and biomedical research in Canada has been reviewed with respect to the national geographic and demographic characteristics which influence their use. The types of facilities available for the production of short-lived radionuclides have been summarized, and a tabulation of the radionuclides that are produced has been presented. In broad terms production facilities can be classified as belonging to one of two groups, nuclear reactor or charged-particle accelerators. The charged-particle accelerators produce the more neutron-deficient and (because of the resultant decay properties) the more useful radionuclides for medical application. The nuclear reactor facilities for radionuclide production range in size and capacity from the high-flux research reactors of AECL to the six SLOWPOKE reactors, five of which are located on university campuses across the country. The McMaster University reactor is used to produce curie quantities of fluorine-18 weekly. Millicurie amounts of a large number of radionuclides, most of which have half-lives ranging from 2 to 50 hr, are produced in the low-flux reactors, in support of basic medical research

Simulation of radionuclide transport in U.S. agriculture

International Nuclear Information System (INIS)

Sharp, R.D.; Baes, C.F. III.

1982-01-01

Because of the recent concern about the impact of energy technologies on man and related health effects, there has emerged a need for models to calculate or predict the effects of radionuclides on man. A general overview is presented of a model that calculates the ingrowth of radionuclides into man's food chain. The FORTRAN IV computer program TERRA, Transport of Environmentally Released Radionuclides in Agriculture, simulates the build-up of radionuclides in soil, four plant food compartments, in meat and milk from beef, and in the livestock food compartments that cause radionuclide build-up in milk and meat from beef. A large data set of spatially oriented parameters has been developed in conjunction with TERRA. This direct-access data set is called SITE, Specific Information on the Terrestrial Environment, and contains 35 parameters for each of 3525 half-degree longitude-latitude cells which define the lower 48 states. TERRA and SITE are used together as a package for determining radionuclide concentrations in man's food anywhere within the conterminous 48 states due to atmospheric releases

Assessment of the important radionuclides in nuclear waste

International Nuclear Information System (INIS)

Kerrisk, J.F.

1985-10-01

The relative importance of the various radionuclides contained in nuclear waste has been assessed by consideration of (1) the quantity of each radionuclide present, (2) the Environmental Protection Agency's release limits for radionuclides, (3) how retardation processes such as solubility and sorption affect radionuclie transport, and (4) the physical and chemical forms of radionuclides in the waste. Three types of waste were reviewed: spent fuel, high-level waste, and defense high-level waste. Conditions specific to the Nevada Nuclear Waste Storage Investigations project potential site at Yucca Mountain were used to describe radionuclide transport. The actinides Am, Pu, Np, and U were identified as the waste elements for which solubility and sorption data were most urgently needed. Other important waste elements were identified as Sr, Cs, C, Ni, Zr, Tc, Th, Ra, and Sn. Under some conditions, radionuclides of three elements (C, Tc, and I) may have high solubility and negligible sorption. The potential for transport of some waste elements (C and I) in the gas phase must also be evaluated for the Yucca Mountain Site. 12 refs., 17 tabs

76 FR 17617 - Multi-Agency Informational Meeting Concerning Compliance With the Federal Select Agent Program...

Science.gov (United States)

2011-03-30

... assessments, biosafety requirements, and security measures. DATES: The meeting will be held on May 10, 2011...) and other interested individuals to obtain specific regulatory guidance and information on standards concerning biosafety and biosecurity issues related to the Federal Select Agent Program. CDC, APHIS, and FBI...

Radionuclide Retention in Concrete Wasteforms - FY13

Energy Technology Data Exchange (ETDEWEB)

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

2013-10-15

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.

Guidance for evidence-informed policies about health systems: rationale for and challenges of guidance development.

Directory of Open Access Journals (Sweden)

Xavier Bosch-Capblanch

Full Text Available In the first paper in a three-part series on health systems guidance, Xavier Bosch-Capblanch and colleagues examine how guidance is currently formulated in low- and middle-income countries, and the challenges to developing such guidance.

21 CFR 892.1390 - Radionuclide rebreathing system.

Science.gov (United States)

2010-04-01

... gaseous or volatile radionuclide or a radionuclide-labeled aerosol and permit it to be respired by the patient during nuclear medicine ventilatory tests (testing process of exchange between the lungs and the...

Monitoring radionuclides in subsurface drinking water sources near unconventional drilling operations: a pilot study

International Nuclear Information System (INIS)

Nelson, Andrew W.; Knight, Andrew W.; Eitrheim, Eric S.; Schultz, Michael K.

2015-01-01

Unconventional drilling (the combination of hydraulic fracturing and horizontal drilling) to extract oil and natural gas is expanding rapidly around the world. The rate of expansion challenges scientists and regulators to assess the risks of the new technologies on drinking water resources. One concern is the potential for subsurface drinking water resource contamination by naturally occurring radioactive materials co-extracted during unconventional drilling activities. Given the rate of expansion, opportunities to test drinking water resources in the pre- and post-fracturing setting are rare. This pilot study investigated the levels of natural uranium, lead-210, and polonium-210 in private drinking wells within 2000 m of a large-volume hydraulic fracturing operation – before and approximately one-year following the fracturing activities. Observed radionuclide concentrations in well waters tested did not exceed maximum contaminant levels recommended by state and federal agencies. No statistically-significant differences in radionuclide concentrations were observed in well-water samples collected before and after the hydraulic fracturing activities. Expanded monitoring of private drinking wells before and after hydraulic fracturing activities is needed to develop understanding of the potential for drinking water resource contamination from unconventional drilling and gas extraction activities. - Highlights: • Natural radionuclides in ground water near unconventional drilling operations were investigated. • Natural uranium ( nat U), lead-210 ( 210 Pb), and polonium-210 ( 210 Po) levels are described. • No statistically significant increases in natural radioactivity post-drilling were observed

Naturally occurring radionuclides in agricultural products: An overview

International Nuclear Information System (INIS)

Hanlon, E.A.

1994-01-01

Low levels of naturally occurring radionuclides exist in phosphatic clays, a by-product of phosphatic mining and beneficiation processes. Concerns about these radionuclides entering the human food chain were an immediate research priority before the phosphate clays could be reclaimed for intensive agricultural purposes. Efforts included the assembly of a large body of data from both sons and plants, part of which were produced by the Polk County (Florida) Mined Lands Agricultural Research/Demonstration Project MLAR/DP. Additional detailed studies involving dairy and beef cattle (Bos taurus) were conducted by researchers working with the MLAR/DP. A national symposium was conducted in which data concerning the MLAR/DP work and other research projects also dealing with naturally occurring radionuclides in agriculture could be discussed. The symposium included invited review papers dealing with the identification of radionuclide geological origins, the geochemistry and movement of radionuclides within the environment, mechanisms of plant uptake, entry points into the food chain, and evaluation of dose and risk assessment to the consumer of low levels of radionuclides. The risk to human health of an individual obtaining 0.1 of his or her dietary intake from crops produced on phosphatic clays increased by 1 in 5 x 10 6 /yr above a control individual consuming no food grown on phosphatic clays. Leaf tissues were found to be generally higher than fruit, grain, or root tissues. The natural range in radionuclide content among various food types was greater than the difference in radionuclides content between the same food produced on phosphatic clays vs. natural soils. 19 refs

Migration of radionuclides through a river system

Energy Technology Data Exchange (ETDEWEB)

Matsunaga, Takeshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1999-03-01

Migration behavior of several atmospherically-derived radionuclides in a river watershed was studied. A main interest was in their relocation from the ground soil of the watershed to a downstream region through a river. Studied radionuclides are: {sup 137}Cs generated by weapon tests in the atmosphere; {sup 210}Pb and {sup 7}Be of naturally occurring radionuclides; {sup 137}Cs, {sup 90}Sr, {sup 239,240}Pu and {sup 241}Am released by the Chernobyl nuclear power plant accident. Dominance of the form in suspended solid in river water (particulate form) was qualified for the radionuclides in the Kuji river watershed. An importance of discharge in flooding was also confirmed. A historical budget analysis for weapon test derived {sup 137}Cs was presented for the Hi-i river watershed and its accompanied lake sediment (Lake Shinji). The work afforded a scheme of a fate of {sup 137}Cs after falling on the ground soil and on the lake surface. Several controlling factors, which can influence on the chemical form of radionuclides discharged to a river, were also investigated in the vicinity of the Chernobyl nuclear power plant. A special attention was paid on the association of the radionuclides with dissolved species in water. Preferential association of Pu and Am isotopes to a large molecular size of dissolved matrices, probably of humic substances, was suggested. (author)

Measuring Integrated Socioemotional Guidance at School: Factor Structure and Reliability of the Socioemotional Guidance Questionnaire (SEG-Q)

Science.gov (United States)

Jacobs, Karen; Struyf, Elke

2013-01-01

Socioemotional guidance of students has recently become an integral part of education, however no instrument exists to measure integrated socioemotional guidance. This study therefore examines the factor structure and reliability of the Socioemotional Guidance Questionnaire. Psychometric properties of the Socioemotional Guidance Questionnaire and…

Graphical Turbulence Guidance - Composite

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — Forecast turbulence hazards identified by the Graphical Turbulence Guidance algorithm. The Graphical Turbulence Guidance product depicts mid-level and upper-level...

Mathematical simulation of sediment and radionuclide transport in estuaries

International Nuclear Information System (INIS)

Onishi, Y.; Trent, D.S.

1982-11-01

The finite element model LFESCOT (Flow, Energy, Salinity, Sediment and Contaminant Transport Model) was synthesized under this study to simulate radionuclide transport in estuaries to obtain accurate radionuclide distributions which are affected by these factors: time variance, three-dimensional flow, temperature, salinity, and sediments. Because sediment transport and radionuclide adsorption/desorption depend strongly on sizes or types of sediments, FLESCOT simulates sediment and a sediment-sorbed radionuclide for the total of three sediment-size fractions (or sediment types) of both cohesive and noncohesive sediments. It also calculates changes of estuarine bed conditions, including bed elevation changes due to sediment erosion/deposition, and three-dimensional distributions of three bed sediment sizes and sediment-sorbed radionuclides within the bed. Although the model was synthesized for radionuclide transport, it is general enough to also handle other contaminants such as heavy metals, pesticides, or toxic chemicals. The model was checked for its capability for flow, water surface elevation change, salinity, sediment and radionuclide transport under various simple conditions first, confirming the general validity of the model's computational schemes. These tests also revealed that FLESCOT can use large aspect ratios of computational cells, which are necessary in handling long estuarine study areas. After these simple tests, FLESCOT was applied to the Hudson River estuary between Chelsea and the mouth of the river to examine how well the model can predict radionuclide transport through simulating tidally influenced three-dimensional flow, salinity, sediment and radionuclide movements with their interactions

Online estimation of radionuclide transportation in water environment

International Nuclear Information System (INIS)

Yi-Jing Zhang; Li-Sheng Hu

2017-01-01

Transportation evaluation of the radionuclide waste discharged from nuclear power plants is an essential licensing issue, especially for inland sites. Basically, the dynamics of radionuclide transportation are nonlinear and time-varying. Motivated by its time-consuming computation, the work proposed an online estimation method for the radionuclide waste in water surface. After extracting the nonlinearity of factors influencing radionuclide transportation, the method utilizes transfer function and generalized autoregressive conditional heteroskedasticity models to perform deterministic and probabilistic estimations. It turns out that, the resulting predictions show high accuracy and can optimize the online discharge management of radioactive waste for nuclear power plants. (author)

78 FR 48175 - Retrospective Review of Draft Guidance Documents Issued Before 2010; Withdrawal of Guidances

Science.gov (United States)

2013-08-07

... guidances (number 19 through 22), contact the Office of Pharmaceutical Science in CDER. 23. ``Qualifying for... to the pharmaceutical industry. In most cases, FDA has developed other guidances and resources to... guidances: 1. ``Manufacturing, Processing, or Holding Active Pharmaceutical Ingredients''--issued April 1998...

Radionuclide examinations

International Nuclear Information System (INIS)

Lentle, B.C.

1989-01-01

This paper reports on radionuclide examinations of the pancreas. The pancreas, situated retroperitonally high in the epigastrium, was a particularly difficult organ to image noninvasively before ultrasonography and computed tomography (CT) became available. Indeed the organ still remains difficult to examine in some patients, a fact reflected in the variety of methods available to evaluate pancreatic morphology. It is something of a paradox that the pancreas is metabolically active and physiologically important but that its examination by radionuclide methods has virtually ceased to have any role in day-to-day clinical practice. To some extent this is caused by the tendency of the pancreas's commonest gross diseases emdash carcinoma and pancreatitis, for example emdash to result in nonfunction of the entire organ. Disorders of pancreatic endocrine function have generally not required imaging methods for diagnosis, although an understanding of diabetes mellitus and its nosology has been advanced by radioimmunoassay of plasma insulin concentrations

Radionuclides in terrestrial ecosystems

International Nuclear Information System (INIS)

Howard, B.J.; Kennedy, V.H.; Nelson, A.

1983-06-01

A bibliographical database has been developed to provide quick access to research and background literature in the field of radioecology. This is a development of an earlier database described by Nelson (Bocock 1981). ITE's particular fields of interest have led to a subject bias in the bibliography towards studies in Cumbria, especially those concerned with radionuclides originating from the reprocessing plant at Sellafield, and towards ecological research studies that are complementary to radionuclide studies. Other subjects covered, include the chemistry of radionuclides, budgets and transfers within ecosystems and techniques for the analysis of environmental samples. ITE's research objectives have led to the establishment of a specialized database which is intended to complement rather than compete with the large international databases made available by suppliers such as IRS-DIALTECH or DIALOG. Currently the database holds about 1900 references which are stored on a 2 1/2 megabyte hard disk on a Digital PDP11/34 computer operating under a time shared system. The references follow a standard format. (author)

Contextual cueing improves attentional guidance, even when guidance is supposedly optimal.

Science.gov (United States)

Harris, Anthony M; Remington, Roger W

2017-05-01

Visual search through previously encountered contexts typically produces reduced reaction times compared with search through novel contexts. This contextual cueing benefit is well established, but there is debate regarding its underlying mechanisms. Eye-tracking studies have consistently shown reduced number of fixations with repetition, supporting improvements in attentional guidance as the source of contextual cueing. However, contextual cueing benefits have been shown in conditions in which attentional guidance should already be optimal-namely, when attention is captured to the target location by an abrupt onset, or under pop-out conditions. These results have been used to argue for a response-related account of contextual cueing. Here, we combine eye tracking with response time to examine the mechanisms behind contextual cueing in spatially cued and pop-out conditions. Three experiments find consistent response time benefits with repetition, which appear to be driven almost entirely by a reduction in number of fixations, supporting improved attentional guidance as the mechanism behind contextual cueing. No differences were observed in the time between fixating the target and responding-our proxy for response related processes. Furthermore, the correlation between contextual cueing magnitude and the reduction in number of fixations on repeated contexts approaches 1. These results argue strongly that attentional guidance is facilitated by familiar search contexts, even when guidance is near-optimal. (PsycINFO Database Record (c) 2017 APA, all rights reserved).

Dose assessment from potential radionuclide emissions from stacks on the Hanford Site

International Nuclear Information System (INIS)

Davis, W.E.; Barnett, J.M.

1995-04-01

On February 3, 1993, the US Department of Energy, Richland Operations Office (RL), received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency (EPA), Region 10. The Compliance Order required RL to (1) evaluate all radionuclide emission points at the Hanford Site to determine which points are subject to the continuous emission sampling requirements of Title 40, Code of Federal Regulations, Part 61 (40 CFR 61), Subpart H, and (2) continuously sample radionuclide emissions in accordance with requirements in 40 CFR 61.93. The Information Request required RL to provide a written Compliance Plan to meet the requirements of the Compliance Order. A Compliance Plan was submitted to EPA, Region 10, on April 30, 1993. The Compliance Plan specified that a dose assessment would be performed for 84 Westinghouse Hanford Company (WHC) stacks registered with the Washington State Department of Health on the Hanford Site. Any stack identified in the assessment as having potential emissions to cause an effective dose equivalent (EDE) to a maximum exposed individual (MEI) greater than 0.1 mrem y -1 must have a compliant sampling system. In addition, a Federal Facility Compliance Agreement (FFCA) was signed on. February 7, 1994. The FFCA required that all unregistered stacks on the Hanford Site be assessed. This requirement increased the number of stacks to be assessed to 123 stacks. Six methods for performing the assessments are described. An initial assessment using only the HEPA filtration factor for back calculations identified 32 stacks that would have emissions which would cause an EDE to the MEI greater than 0.1 mrem y -1 . When the other methods were applied the number was reduced to 20 stacks. The paper discusses reasons for these overestimates

The fate and importance of radionuclides produced in nuclear events

Energy Technology Data Exchange (ETDEWEB)

Shore, B; Anspaugh, L; Chertok, R; Gofman, J; Harrison, F; Heft, R; Koranda, J; Ng, Y; Phelps, P; Potter, G; Tamplin, A [Lawrence Radiation Laboratory, University of California, Livermore, CA (United States)

1969-07-01

Some of the major program at the Bio-Medical Division concerned with the fate and importance of the fission products, the radionuclides induced in the device materials, the radionuclides induced in the environment surrounding the device, and the tritium produced in Plowshare cratering events will be discussed. These programs include (1) critical unknowns in predicting organ and body burdens from radionuclides produced in cratering events; (2) the analysis with a high-resolution solid state gamma ray spectrometer of radionuclides in complex biological and environmental samples; (3) the characterization of radioactive particles from cratering detonation; (4) the biological availability to beagles, pigs and goats of radionuclides in Plowshare debris; (5) the biological availability to aquatic animals of radionuclides in Plowshare and other nuclear debris and the biological turnover of critical nuclides in specific aquatic animals; (6) the biological availability of Plowshare and other nuclear debris radionuclides to dairy cows and the transplacental transport of debris radionuclides in the dairy cow; (7) the persistence and behavior of radionuclides, particularly tritium, at sites of Plowshare and other nuclear detonations; and (8) somatic effects of Low Dose Radiation: Chromosome studies. (author)

The fate and importance of radionuclides produced in nuclear events

International Nuclear Information System (INIS)

Shore, B.; Anspaugh, L.; Chertok, R.; Gofman, J.; Harrison, F.; Heft, R.; Koranda, J.; Ng, Y.; Phelps, P.; Potter, G.; Tamplin, A.

1969-01-01

Some of the major program at the Bio-Medical Division concerned with the fate and importance of the fission products, the radionuclides induced in the device materials, the radionuclides induced in the environment surrounding the device, and the tritium produced in Plowshare cratering events will be discussed. These programs include (1) critical unknowns in predicting organ and body burdens from radionuclides produced in cratering events; (2) the analysis with a high-resolution solid state gamma ray spectrometer of radionuclides in complex biological and environmental samples; (3) the characterization of radioactive particles from cratering detonation; (4) the biological availability to beagles, pigs and goats of radionuclides in Plowshare debris; (5) the biological availability to aquatic animals of radionuclides in Plowshare and other nuclear debris and the biological turnover of critical nuclides in specific aquatic animals; (6) the biological availability of Plowshare and other nuclear debris radionuclides to dairy cows and the transplacental transport of debris radionuclides in the dairy cow; (7) the persistence and behavior of radionuclides, particularly tritium, at sites of Plowshare and other nuclear detonations; and (8) somatic effects of Low Dose Radiation: Chromosome studies. (author)

Migration of radionuclides in geologic media: Fundamental research needs

International Nuclear Information System (INIS)

Reed, D.T.; Zachara, J.M.; Wildung, R.E.; Wobber, F.J.

1990-01-01

An assessment of the fundamental research needs in understanding and predicting the migration of radionuclides in the subsurface is provided. Emphasis is on the following three technical areas: (1) aqueous speciation of radionuclides, (2) the interaction of radionuclides with substrates, and (3) intermediate-scale interaction studies. This research relates to important issues associated with environmental restoration and remediation of DOE sites contaminated with mixed radionuclide-organic wastes. 64 refs., 1 fig., 1 tab

Radiopharmaceuticals and other compounds labelled with short-lived radionuclides

CERN Document Server

Welch, Michael J

2013-01-01

Radiopharmaceuticals and Other Compounds Labelled with Short-Lived Radionuclides covers through both review and contributed articles the potential applications and developments in labeling with short-lived radionuclides whose use is restricted to institutions with accelerators. The book discusses the current and potential use of generator-produced radionuclides as well as other short-lived radionuclides, and the problems of quality control of such labeled compounds. The book is useful to nuclear medicine physicians.

Radionuclides incorporation in activated natural nanotubes

International Nuclear Information System (INIS)

Silva, Jose Parra

2016-01-01

Natural palygorskite nanotubes show suitable physical and chemical properties and characteristics to be use as potential nanosorbent and immobilization matrix for the concentration and solidification of radionuclides present in nuclear wastes. In the development process of materials with sorption properties for the incorporation and subsequent immobilization of radionuclides, the most important steps are related with the generation of active sites simultaneously to the increase of the specific surface area and suitable heat treatment to producing the structural folding. This study evaluated the determining parameters and conditions for the activation process of the natural palygorskite nanotubes aiming at the sorption of radionuclides in the nanotubes structure and subsequent evaluation of the parameters involve in the structural folding by heat treatments. The optimized results about the maximum sorption capacity of nickel in activated natural nanotubes show that these structures are apt and suitable for incorporation of radionuclides similar to nickel. By this study is verified that the optimization of the acid activation process is fundamental to improve the sorption capacities for specifics radionuclides by activated natural nanotubes. Acid activation condition optimized maintaining structural integrity was able to remove around 33.3 wt.% of magnesium cations, equivalent to 6.30·10 -4 g·mol -1 , increasing in 42.8% the specific surface area and incorporating the same molar concentration of nickel present in the liquid radioactive waste at 80 min. (author)

100 Years of radionuclide metrology

International Nuclear Information System (INIS)

Judge, S.M.; Arnold, D.; Chauvenet, B.; Collé, R.; De Felice, P.; García-Toraño, E.; Wätjen, U.

2014-01-01

The discipline of radionuclide metrology at national standards institutes started in 1913 with the certification by Curie, Rutherford and Meyer of the first primary standards of radium. In early years, radium was a valuable commodity and the aim of the standards was largely to facilitate trade. The focus later changed to providing standards for the new wide range of radionuclides, so that radioactivity could be used for healthcare and industrial applications while minimising the risk to patients, workers and the environment. National measurement institutes responded to the changing demands by developing new techniques for realising primary standards of radioactivity. Looking ahead, there are likely to be demands for standards for new radionuclides used in nuclear medicine, an expansion of the scope of the field into quantitative imaging to facilitate accurate patient dosimetry for nuclear medicine, and an increasing need for accurate standards for radioactive waste management and nuclear forensics. - Highlights: • The driving forces for the development of radionuclide metrology. • Radium standards to facilitate trade of this valuable commodity in the early years. • After 1950, focus changes to healthcare and industrial applications. • National Measurement Institutes develop new techniques, standards, and disseminate the best practice in measurement. • Challenges in nuclear medicine, radioactive waste management and nuclear forensics

Underground radionuclide migration at the Nevada Test Site

International Nuclear Information System (INIS)

Nimz, G.J.; Thompson, J.L.

1992-01-01

This document reviews results from a number of studies concerning underground migration of radionuclides from nuclear test cavities at the Nevada Test Site (NTS). Discussed are all cases known to the Department of Energy's Hydrology and Radionuclide Migration Program where radionuclides have been detected outside of the immediate vicinity of nuclear test cavities that are identifiable as the-source of the nuclides, as well as cases where radionuclides might have been expected and were intentionally sought but not fixed. There are nine locations where source-identifiable radionuclide migration has been detected, one where migration was purposely induced by pumping, and three where migration might be expected but was not found. In five of the nine cases of non-induced migration, the inferred migration mechanism is prompt fracture injection during detonation. In the other four cases, the inferred migration mechanism is water movement. In only a few of the reviewed cases can the actual migration mechanism be stated with confidence, and the attempt has been made to indicate the level of confidence for each case. References are cited where more information may be obtained. As an aid to future study, this document concludes with a brief discussion of the aspects of radionuclide migration that, as the present review indicates, are not yet understood. A course of action is suggested that would produce a better understanding of the phenomenon of radionuclide migration

75 FR 69089 - Guidance for Industry and Food and Drug Administration Staff; Class II Special Controls Guidance...

Science.gov (United States)

2010-11-10

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-D-0514] Guidance for Industry and Food and Drug Administration Staff; Class II Special Controls Guidance Document... Administration (FDA) is announcing the availability of the guidance entitled ``Class II Special Controls Guidance...

76 FR 29251 - Guidance for Industry and Food and Drug Administration Staff; Class II Special Controls; Guidance...

Science.gov (United States)

2011-05-20

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2006-D-0094] Guidance for Industry and Food and Drug Administration Staff; Class II Special Controls; Guidance Document... of the guidance entitled ``Guidance for Industry and Food and Drug Administration Staff; Class II...

National Geospatial Data Asset Lifecycle Baseline Maturity Assessment for the Federal Geographic Data Committee

Science.gov (United States)

Peltz-Lewis, L. A.; Blake-Coleman, W.; Johnston, J.; DeLoatch, I. B.

2014-12-01

The Federal Geographic Data Committee (FGDC) is designing a portfolio management process for 193 geospatial datasets contained within the 16 topical National Spatial Data Infrastructure themes managed under OMB Circular A-16 "Coordination of Geographic Information and Related Spatial Data Activities." The 193 datasets are designated as National Geospatial Data Assets (NGDA) because of their significance in implementing to the missions of multiple levels of government, partners and stakeholders. As a starting point, the data managers of these NGDAs will conduct a baseline maturity assessment of the dataset(s) for which they are responsible. The maturity is measured against benchmarks related to each of the seven stages of the data lifecycle management framework promulgated within the OMB Circular A-16 Supplemental Guidance issued by OMB in November 2010. This framework was developed by the interagency Lifecycle Management Work Group (LMWG), consisting of 16 Federal agencies, under the 2004 Presidential Initiative the Geospatial Line of Business,using OMB Circular A-130" Management of Federal Information Resources" as guidance The seven lifecycle stages are: Define, Inventory/Evaluate, Obtain, Access, Maintain, Use/Evaluate, and Archive. This paper will focus on the Lifecycle Baseline Maturity Assessment, and efforts to integration the FGDC approach with other data maturity assessments.

2 CFR 182.125 - Does this part affect the Federal contracts that I receive?

Science.gov (United States)

2010-01-01

... GOVERNMENTWIDE GUIDANCE FOR GRANTS AND AGREEMENTS Reserved GOVERNMENTWIDE REQUIREMENTS FOR DRUG-FREE WORKPLACE (FINANCIAL ASSISTANCE) Purpose and Coverage § 182.125 Does this part affect the Federal contracts that I... violation of the requirements of this part, as described in § 182.510(c). However, this part does not apply...

Evaluation of strategies for monitoring and sampling airborne radionuclides in the workplace

International Nuclear Information System (INIS)

Boecker, B.B.; Hoover, M.D.; Newton, G.J.; Guilmette, R.A.; Scott, B.R.

1994-01-01

Protection of workers from intakes of airborne radioactive materials is receiving increased attention as part of the overall emphasis on minimisation of occupational radiation exposures. Because current guidance of the International Commission on Radiological Protection on protection from airborne radionuclides is based on annual limits on intake, ALI, and average annual air concentrations derived from these ALIs, increased effort is being devoted to monitoring exposure levels, directly or indirectly, in the workplace. Possible approaches include the use of fixed air samplers, continuous air monitors, and personal air samplers worn by individual workers. Periodic bioassay of these workers of whole-body counting, chest counting, or excreta analyses can provide useful information on the adequacy with which the above approaches are monitoring the workplace. Because each approach requires a major commitment of institutional resources, it is important that the overall monitoring plan reflect the relative value of these different approaches for the facility and processes being monitored. (Author)

21 CFR 892.5700 - Remote controlled radionuclide applicator system.

Science.gov (United States)

2010-04-01

... radionuclide applicator system. (a) Identification. A remote controlled radionuclide applicator system is an... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Remote controlled radionuclide applicator system... include patient and equipment supports, component parts, treatment planning computer programs, and...

The contamination of the oceans by anthropogenic radionuclides

International Nuclear Information System (INIS)

Figueira, Rubens C.L.; Cunha, Ieda I.L.

1998-01-01

Several hundreds of artificial of artificial radionuclides are produced as the result of human activities, such as the applications of nuclear reactors and particle accelerators, testing of nuclear weapons and nuclear accidents. Many of these radionuclides are short-lived and decay quickly after their production, but some of them are longer-lived and are released into the environment. From the radiological point of view the most important radionuclides are cesium-137, strontium-90 and plutonium-239, due to their chemical and nuclear characteristics. The two first radioisotopes present long half life (30 and 28 years), high fission yields and chemical behaviour similar to potassium and calcium, respectively. No stable element exists for plutonium-239, that presents high radiotoxity, longh half-life (24000 years) and some marine organisms accumulate plutonium at high levels. The radionuclides introduced into marine environment undergo various physical, chemical and biological processes taking place in the sea. These processes may be due to physical, dispersion or complicated chemical and biological interactions of the radionuclides with inorganic and organic suspend matter, variety of living organism, bottom sediments, etc. The behaviour of radionuclides in the sea depends primarily on their chemical properties, but it may also be influenced by properties of interacting matrices and other environmental factors. The major route of radiation exposure of man to artificial radionuclides occuring in the marine environment is through ingestion of radiologically contamined marine organisms. This paper summarizes the main sources of contamination in the marine environment and presents an overview covering the oceanic distribution of anthropogenic radionuclides in the FAO regions. A great number of measurements of artificial radioclides have been carried out on various marine environmental samples in different oceans over the world, being cesium-137 the most widely measured

Radionuclide examination in rheumatology

International Nuclear Information System (INIS)

Streda, A.; Kolar, J.; Valesova, M.

1984-01-01

On the basis of twenty years of experience with the use of radionuclides in bone and articular rheumatic diseases indications for such examinations are summed up. The main advantage of the use of radionuclide methods is that they bring forward early diagnosis of tissue reconstruction which can thus be detected at the stage of microstructural changes. They also provide earlier and more reliable detection of the degree of the pathological process than is provided by X-ray examination. In some cases scintiscan may also be found useful as a method for following up the results of treatment of rheumatic diseases. (author)

Solubility limited radionuclide transport through geologic media

International Nuclear Information System (INIS)

Muraoka, Susumu; Iwamoto, Fumio; Pigford, T.H.

1980-11-01

Prior analyses for the migration of radionuclides neglect solubility limits of resolved radionuclide in geologic media. But actually some of the actinides may appear in chemical forms of very low solubility. In the present report we have proposed the migration model with no decay parents in which concentration of radionuclide is limited in concentration of solubility in ground water. In addition, the analytical solutions of the space-time-dependent concentration are presented in the case of step release, band release and exponential release. (author)

Methodology of ABNT ISO/IEC GUIA 25 implantation in the laboratories of radionuclides analysis in environmental samples of the Analysis Division/CNEN

International Nuclear Information System (INIS)

Oliveira, Josue Peter de

1997-07-01

The ISO/EEC Guide 25: 1993 Standard G eneral requirements for the competence of calibration and testing laboratories . Is published in Brazil by Brazilian Association for Technical Standards (ABNT) as ABNT ISO/DEC GUIA 25 and establishes general requirements a laboratory must demonstrate to meet, in order to be recognized as having technical competence (accreditation) to carry out specifics calibration or testing. Therefore, the accredited laboratory starts, respectively, taking part from the Brazilian Calibration Network (RBC) or from the Brazilian Testing Laboratories Network (RBLE) . The Environmental Radioanalysis Division (DIAMB) from Environmental Radiological Protection Department (DEPRA) from Institute of Radiation Protection and Dosimetry (IRD) from Brazilian National Nuclear Energy Commission (CNEN) is a laboratory responsible for analyzing radionuclides deriving for the samples from DEPRA's Surveillance Program, research and servings, due to an eventual radionuclide contamination in environment, foods and others raw materials for human consumption; including for importation and exportation products certification purposes. For all these reasons, DIAMB needs its formal recognition for carrying out radionuclides analysis in environmental samples. This work aims to provide a methodology in order to guide a laboratory which has the intention to implement a accreditation process. It also describes policies to meet the requirements related to the Standard, guidance needed to specification of some steps and also comments some points from the Standard in order to become easier all the accreditation process comprehension. (author)

Radionuclide determination of right and left ventricular stroke volumes

Energy Technology Data Exchange (ETDEWEB)

Shen, Wei Feng; Roubin, G S; Choong, C Y.P.; Harris, P J; Flether, P J; Kelly, D T; Uren, R F; Hutton, B F

1985-03-01

The relationship between radionuclide and thermodilution measurement of stroke volumes (SV) was investigated in 30 patients without valvular regurgitation or intracardiac shunt (group A) at rest and during exercise. Both attenuated radionuclide right ventricular (RV) and left ventricular (LV) SV measurements correlated well with the SV determined by the thermodilution method (r = 0.87 and r = 0.93, all P < 0.001). The reliability of the radionuclide method to estimate SV was evaluated prospectively in two additional groups of patients. In 11 patients without valvular regurgitation or intracardiac shunt (group B) the radionuclide RVSV and LVSV closely approximated to thermodilution SV at rest and during exercise. In 15 patients with aortic regurgitation (group C) the radionuclide stroke volume ratio correlated well with the angiographic regurgitant fraction. Thus, both RVSV and LVSV and the severity of aortic regurgitation can be reliably measured with gated radionuclide ventriculography.

Methods for determining radionuclide retardation factors: status report

International Nuclear Information System (INIS)

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

1980-04-01

This report identifies a number of mechanisms that retard radionuclide migration, and describes the static and dynamic methods that are used to study such retardation phenomena. Both static and dynamic methods are needed for reliable safety assessments of underground nuclear-waste repositories. This report also evaluates the extent to which the two methods may be used to diagnose radionuclide migration through various types of geologic media, among them unconsolidated, crushed, intact, and fractured rocks. Adsorption is one mechanism that can control radionuclide concentrations in solution and therefore impede radionuclide migration. Other mechanisms that control a solution's radionuclide concentration and radionuclide migration are precipitation of hydroxides and oxides, oxidation-reduction reactions, and the formation of minerals that might include the radionuclide as a structural element. The retardation mechanisms mentioned above are controlled by such factors as surface area, cation exchange capacity, solution pH, chemical composition of the rock and of the solution, oxidation-reduction potential, and radionuclide concentration. Rocks and ground waters used in determining retardation factors should represent the expected equilibrium conditions in the geologic system under investigation. Static test methods can be used to rapidly screen the effects of the factors mentioned above. Dynamic (or column) testing, is needed to assess the effects of hydrodynamics and the interaction of hydrodynamics with the other important parameters. This paper proposes both a standard method for conducting batch Kd determinations, and a standard format for organizing and reporting data. Dynamic testing methods are not presently developed to the point that a standard methodology can be proposed. Normal procedures are outlined for column experimentation and the data that are needed to analyze a column experiment are identified

Federal Research Opportunities: DOE, DOD, and HHS Need Better Guidance for Participant Activities

Science.gov (United States)

2016-01-01

contract with DOE and the Economy Act of 1932, as amended. In addition, we examined documents developed by ORAU and used by DOE, DOD, and HHS to set forth...energy and climate change policy and analyses in the international economy , and building efficiencies. Environmental Protection Agency Climate...biomarkers for environmental contaminants. Federal Bureau of Investigation Juvenile prostitution and child abduction, causes of postmortem hair root

Research progess on treatment of cancer with targeted radionuclide therapy

International Nuclear Information System (INIS)

Luo Jiawen; Zhang Caixia

2008-01-01

The new development and situation of targeted radionuclide therapy in oncology is described, which include radioimmunotherapy, peptide receptor radionuclide therapy, gene therapy and radionuclide labled chemotherapeutics therapy. The application research on labled carrier of those therapy is emphasized. Meanwhile, the research progess of indomethacin and its combined with targeted radionuclide therapy is also described. (authors)

Radionuclide cisternographic findings in patients with spontaneous intracranial hypotension

International Nuclear Information System (INIS)

Jung, Dong Jin; Kim, Jae Seung; Ryu, Jin Sook; Shin, Jung Woo; Im, Joo Hyuk; Lee, Myoung Chong; Jung, Sung Joo; Moon, Dae Hyuk; Lee, Hee Kyung

1998-01-01

Radionuclide cisternography may be helpful in understanding pathophysiology of postural headache and low CSF pressure in patients with spontaneous intracranial hypotension. The purpose of this study was to characterize radionuclide cisternogrpahic findings of spontaneous intracranial hypotension. The study population consists of 15 patients with spontaneous intracranial hypotension. Diagnosis was based on their clinical symptoms and results of lumbar puncture. All patients underwent radionuclide cisternography following injection of 111 to 222 MBq of Tc-99m DTPA into the lumbar subarachnoid space. Sequential images were obtained between 1/2 hour and 24 hour after the injection of Tc-99m DTPA. Radioactivity of the bladder, soft tissue uptake, migration of radionuclide in the subarachnoid space, and extradural leakage of radionuclide were evaluated according to the scan time. Radionuclide cisternogram showed delayed migration of radionuclide into the cerebral convexity (14/15), increased soft tissue uptake (11/15), and early visualization of bladder activity at 30 min (6/10) and 2 hr (13/13). Cisternography also demonstrated leakage site of CSF in 4 cases and 2 of these were depicted at 30min. Epidural blood patch was done in 11 patients and headache was improved in all cases. The characteristics findings of spontaneous intracranial hypotension were delayed migration of radionuclide and early visualization of the soft tissue and bladder activity. These scintigraphic findings suggest that CSF leakage rather than increased CSF absorption or decreased production may be the main pathophysiology of spontaneous intracranial hypotension. Early and multiple imaging including the bladder and soft tissue is required to observe the entire dynamics of radionuclide migration

Fire fighting in a radionuclide laboratory

International Nuclear Information System (INIS)

Wenzel, H.

1991-01-01

A fire-brigade was called to a laboratory which held a handling licence for the radionuclides C-14, T, P-32, Se-75, Mo-99, and S-35. The fire-brigade was unaware of a release of radionuclides. Therefore they used respiratory equipment, and all persons present were subsequently examined for contamination. (DG) [de

Permissible annual depositions and radionuclide concentrations in air

International Nuclear Information System (INIS)

Belyaev, V.A.; Golovko, M.Yu.

1993-01-01

It is established that it necessary to take into account the other ways of radionuclide intake apart from the inhalation one when determining the standards for radionuclide contamination of the atmospheric air. Whereby it is proposed to standardize annual depositions rather than permissible concentration in the atmospheric air for the ways related to radionuclide releases on the ground surface, which is explained by ambiguity of their dry deposition rate from the air. Formulae and results of calculation of standard characteristics are presented. The permissible radionuclide depositions, related to the intake through food chains are calculated with account for diet diversity, agroclimatic and phenological parameters in different regions of the country

Understanding Radionuclide Interactions with Layered Materials

Science.gov (United States)

Wang, Y.

2015-12-01

Layered materials play an important role in nuclear waste management and environmental cleanup. Better understanding of radionuclide interactions with those materials is critical for engineering high-performance materials for various applications. This presentation will provide an overview on radionuclide interactions with two general categories of layered materials - cationic clays and anionic clays - from a perspective of nanopore confinement. Nanopores are widely present in layered materials, either as the interlayers or as inter-particle space. Nanopore confinement can significantly modify chemical reactions in those materials. This effect may cause the preferential enrichment of radionuclides in nanopores and therefore directly impact the mobility of the radionuclides. This effect also implies that conventional sorption measurements using disaggregated samples may not represent chemical conditions in actual systems. The control of material structures on ion exchange, surface complexation, and diffusion in layered materials will be systematically examined, and the related modeling approaches will be discussed. This work was performed at Sandia National Laboratories, which is a multiprogram laboratory operated by Sandia Corporation, a Lockheed-Martin Company, for the DOE under contract DE-AC04-94AL8500.

Radionuclide transport in a single fissure

International Nuclear Information System (INIS)

Eriksen, T.E.

1988-12-01

The study of radionuclide migration through rock is currently of great interest due to its relevance to the possible escape paths into the biosphere of radionuclides released from high level radioactive wastes burried in deep geological repositories. While water will provide the vehicle for transportation, interaction with geological material may greatly influence the radionuclide movement relative that of water. A flow system for laboratory studies of radionuclide transport in natural fissures in granitic rock under reducing conditions is described. The system based on the use of synthetic ground water equilibrated with granitic rock in a well sealed system, allow experiments to be carried out at -240 mV reduction potential. In flow experiments with technetium the retardation was found to be dependent on the method used for reducing TcO 4 - . The preparation of the tracer solutions is crucial, as some of the redox-reactions may be very slow. The dynamics of the Tc(VII) reduction and also speciation need to be carried out in separate experiments. (4 illustrations, 5 tables)

Radionuclide therapy practice and facilities in Europe

International Nuclear Information System (INIS)

Hoefnagel, C.A.; Clarke, S.E.M.; Fischer, M.; Chatal, J.F.; Lewington, V.J.; Nilsson, S.; Troncone, L.; Vieira, M.R.

1999-01-01

Using a questionnaire the EANM Task Group Radionuclide Therapy in 1993 collected data on the current practice of radionuclide therapy in European countries. Subsequently, at the request of the EANM Executive Committee, the EANM Radionuclide Therapy Committee has made an inventory of the distribution of facilities for radionuclide therapy and undertaken an assessment of the total number of patients treated throughout Europe and of the types of treatment provides, with the aim of supporting the development of policy to adjust the available capacity to the needs by the year 2000. For this purpose, a second, more detailed questionnaire was sent out the members and national advisors of the Committee (see below), who gathered the data for each country that was a member of the EANM at the time. It is concluded that a wide bariation in therapy practice exists across Europe, particularly in the utilisation of radionuclide therapy, the requirement and availability of proper isolation facilities and the background training of those undertaking therapy. More uniform guidelines and legislation are required, although changes in legislation may have a significant impact in some countries. Although there is wide variation in the therapies used in each country, one the whole it appears that there is an underutilisation of nuclear medicine as a therapeutic modality. A rapidly increasing role may be expected, in particular for oncological indications requiring high-dose radionuclide treatment. Therefore there is an urgent need for a greater number of isolation beds in dedicated centers throughout Europe

The art of translating nutritional science into dietary guidance: history and evolution of the Dietary Guidelines for Americans.

Science.gov (United States)

Watts, Mary Lee; Hager, Mary H; Toner, Cheryl D; Weber, Jennifer A

2011-07-01

The United States government has published official Dietary Guidelines for Americans (DGA) since 1980 and has recently released the 2010 version. Serving as a foundational cornerstone for federal nutrition policy, the DGA embrace current nutritional science and translate it into practical guidance to enhance the overall health of Americans. This article reviews the history and process for developing the DGA, including the incorporation of sophisticated and systematic techniques for reviewing emerging evidence. It also explores issues related to implementation of the guidelines through federal policy, the food supply, and consumer knowledge and behavior. © 2011 International Life Sciences Institute.

Surface diffusion of sorbed radionuclides

International Nuclear Information System (INIS)

Berry, J.A.; Bond, K.A.

1991-01-01

Surface diffusion has in the past been invoked to explain rates of radionuclide migration which were greater than those predicted. Results were generally open to interpretation but the possible existence of surface diffusion, whereby sorbed radionuclides could potentially migrate at much enhanced rates, necessitated investigation. In this work through-diffusion experiments have shown that although surface diffusion does exist for some nuclides, the magnitude of the phenomenon is not sufficient to affect repository safety assessment modelling. (author)

DNA damage induced by radionuclide internal irradiation

International Nuclear Information System (INIS)

Cui Fengmei; Zhao Jingyong; Hong Chengjiao; Lao Qinhua; Wang Liuyi; Yang Shuqin

2004-01-01

Objective: To study the DNA damage of peripheral blood mononuclear cell (PBMC) in rats exposed to radionuclide internal irradiation. Methods: The radionuclides were injected into the rats and single cell get electrophoresis (SCGE) was performed to detect the length of DNA migration in the rat PBMC. Results: DNA migration in the rat PBMC increased with accumulative dose or dose-rate. It showed good relationship of dose vs. response and of dose-rate vs. response, both relationship could be described as linear models. Conclusion: Radionuclide internal irradiation could cause DNA damage in rat PBMC. (authors)

Radionuclide Basics: Iodine

Science.gov (United States)

... Centers Radiation Protection Contact Us Share Radionuclide Basics: Iodine Iodine (chemical symbol I) is a chemical element. ... in the environment Iodine sources Iodine and health Iodine in the Environment All 37 isotopes of iodine ...

78 FR 7282 - Reform of Federal Policies Relating to Grants and Cooperative Agreements; Cost Principles and...

Science.gov (United States)

2013-02-01

... II Reform of Federal Policies Relating to Grants and Cooperative Agreements; Cost Principles and... further review, the Cost Principles for Hospitals at 45 CFR Part 74, Appendix E. The proposal consolidates... instructed the OMB Director to ``review and where appropriate revise guidance concerning cost principles...

40 CFR 141.66 - Maximum contaminant levels for radionuclides.

Science.gov (United States)

2010-07-01

... beta particle and photon radioactivity from man-made radionuclides in drinking water must not produce.../year). (2) Except for the radionuclides listed in table A, the concentration of man-made radionuclides... may make this technology too complex for small surface water systems. e Removal efficiencies can vary...

Radionuclide migration at sites of temporary storage of SNF and RW in North-West Russia - Contribution to regulatory development

International Nuclear Information System (INIS)

Sneve, M.K.; Shandala, N.K.; Orlova, E.I.; Titov, A.V.; Kochetkov, O.A.; Smith, G.M.; Barraclough, I.M.

2007-01-01

Two technical bases of the Northern Fleet were created in the Russian northwest in the 1960s at Andreeva in the Kola Bay and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, performing receipt and storage of radioactive waste and spent nuclear fuel. No further stored material was received after 1985. These technical bases have since been re-categorised as sites of temporary storage. It is necessary to note that, during the storage of RW and SNF, certain conditions arose which resulted in failure of the storage barrier system, resulting in release of radionuclides. Remediation activities at the site focus on reduction of major risks associated with most hazardous radioactive source terms. In addition, the long term management of the sites includes consideration of how to remediate contaminated areas, not only because they affect continuing work at the site, but also because this work will influence final radiological status of the sites. The optimum approach to remediation will be affected by how quickly radionuclides could move, both during the remediation works and, so far as any residual activity is concerned, after the works are completed. Present investigations reported here are directed to determination of sorption-desorption parameters of radionuclides in the studied areas, which will affect their underground migration, with the purpose of accounting for regional peculiarities in optimization process of the STSs remediation. The work is being carried out by the TSO State Research Centre - Institute of Biophysics, of Russian Federation, with assistance from western experts. The work forms part of a regulatory collaboration programme on-going between the Norwegian Radiation Protection Authority and the Federal Medical-Biological Agency which is designed to support the development of norms and standards to be applied in the remediation of these sites of temporary storage. (author)

78 FR 68819 - Final NOAA Procedures for Government-to-Government Consultation With Federally Recognized Indian...

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2013-11-15

... implications'' are defined in section 1 of E.O. 13175. This Handbook provides guidance to Regional Offices and... has defined the term ``policies with tribal implications.'' It is not within the [[Page 68821... Native Corporation and Federally recognized Indian tribe may conflict or coincide. The essence of the...

Choice of radionuclide for antibody labelling: new perspectives

International Nuclear Information System (INIS)

Hazra, D.K.; Dass, S.

1983-01-01

The expanding horizons of labelled antibody techniques in diagnostic imaging or assay, therapy and research and the availabilities of monoclonal antibodies is resulting in a demand for suitable radionuclides as antibody labels. An outline is given of the different criteria for choosing an appropriate radionuclide for labelling an antibody depending on its particular field of use. The requirements of procedures for firmly linking radionuclides to antibodies are also given. (U.K.)

Emissions of the corrosion radionuclides in an atmosphere

International Nuclear Information System (INIS)

Vardanyan, M.

2010-01-01

In area of Armenian nuclear power plant location, in atmospheric air in majority of cases log two technogenic radionuclides: l 37 C s and 9 0 S r. Presence of these radionuclides basically is caused by global fall out (consequences of tests of the nuclear weapon and Chernobyl NPP accident), whose contribution to the contents of these radionuclides in atmosphere is incomparably greater, than emissions from the NPP. However there are some cases when in an atmosphere are registered the technogenic radionuclides, caused by emissions from NPP. In the present work such case is considered. Gas-aerosol releases of NPP in the atmosphere are carefully purified by means of various high-efficiency filters and gas-cleaning systems. Nevertheless, one should forecast and measure, the possible impact of these releases on the environment in the regions surrounding the NPP. Radioactive releases of the Armenian NPP (ANPP) contain the set of radionuclides characteristic for NPPs of this type. They may be divided into three groups: 1 31 I , 1 37 C s, 1 34 C s, 9 0 S r and 8 9 S r fission fragments, isotopes of noble gases krypton and xenon and other radionuclides; corrosion originated radionuclides: 6 0 C o, 1 10m A g, 5 4 M n, 5 l C r and others; activation products of the heat-transfer agent itself. It should be noted that the amount of radioactive materials released in the environment by the ANPP during the whole period of its operation was much lower than the admissible quantities specified in the corresponding legal documents (RSN, NPPSP) acting in Armenia, which are practically identical to the internationally accepted norms. The amounts of releases and their radionuclides composition for the ANPP are given

Stochastic analysis of radionuclide migration in saturated-unsaturated soils

International Nuclear Information System (INIS)

Kawanishi, Moto

1988-01-01

In Japan, LLRW (low level radioactive wastes) generated from nuclear power plants shall be started to store concentrically in the Shimokita site from 1990, and those could be transformed into land disposal if the positive safety is confirmed. Therefore, it is hoped that the safety assessment method shall be successed for the land disposal of LLRW. In this study, a stochastic model to analyze the radionuclide migration in saturated-unsaturated soils was constructed. The principal results are summarized as follows. 1) We presented a generalized idea for the modeling of the radionuclide migration in saturated-unsaturated soils as an advective-dispersion phenomena followed by the decay of radionuclides and those adsorption/desorption in soils. 2) Based on the radionuclide migration model mentioned above, we developed a stochastic analysis model on radionuclide migration in saturated-unsaturated soils. 3) From the comparison between the simulated results and the exact solution on a few simple one-dimensional advective-dispersion problems of radionuclides, the good validity of this model was confirmed. 4) From the comparison between the simulated results by this model and the experimental results of radionuclide migration in a one-dimensional unsaturated soil column with rainfall, the good applicability was shown. 5) As the stochastic model such as this has several advantages that it is easily able to represent the image of physical phenomena and has basically no numerical dissipation, this model should be more applicable to the analysis of the complicated radionuclide migration in saturated-unsaturated soils. (author)

Preparation of Radiopharmaceuticals Labeled with Metal Radionuclides

Energy Technology Data Exchange (ETDEWEB)

Welch, M.J.

2012-02-16

The overall goal of this project was to develop methods for the production of metal-based radionuclides, to develop metal-based radiopharmaceuticals and in a limited number of cases, to translate these agents to the clinical situation. Initial work concentrated on the application of the radionuclides of Cu, Cu-60, Cu-61 and Cu-64, as well as application of Ga-68 radiopharmaceuticals. Initially Cu-64 was produced at the Missouri University Research Reactor and experiments carried out at Washington University. A limited number of studies were carried out utilizing Cu-62, a generator produced radionuclide produced by Mallinckrodt Inc. (now Covidien). In these studies, copper-62-labeled pyruvaldehyde Bis(N{sup 4}-methylthiosemicarbazonato)-copper(II) was studied as an agent for cerebral myocardial perfusion. A remote system for the production of this radiopharmaceutical was developed and a limited number of patient studies carried out with this agent. Various other copper radiopharmaceuticals were investigated, these included copper labeled blood imaging agents as well as Cu-64 labeled antibodies. Cu-64 labeled antibodies targeting colon cancer were translated to the human situation. Cu-64 was also used to label peptides (Cu-64 octriatide) and this is one of the first applications of a peptide radiolabeled with a positron emitting metal radionuclide. Investigations were then pursued on the preparation of the copper radionuclides on a small biomedical cyclotron. A system for the production of high specific activity Cu-64 was developed and initially the Cu-64 was utilized to study the hypoxic imaging agent Cu-64 ATSM. Utilizing the same target system, other positron emitting metal radionuclides were produced, these were Y-86 and Ga-66. Radiopharmaceuticals were labeled utilizing both of these radionuclides. Many studies were carried out in animal models on the uptake of Cu-ATSM in hypoxic tissue. The hypothesis is that Cu-ATSM retention in vivo is dependent upon the

Radionuclide transfer onto ground surface in surface water flow, 1

International Nuclear Information System (INIS)

Mukai, Masayuki; Takebe, Shinichi; Komiya, Tomokazu; Kamiyama, Hideo

1991-07-01

Radionuclides migration in ground surface water flow is considered to be one of the important path way in the scenario for environmental migration of radionuclides leaked from low level radioactive waste repository. Simulating the slightly sloped surface on which contaminated solution is flowing downward, testing for radionuclide migration on ground surface had been started. As it's first step, an experiment was carried out under the condition of restricted infiltration in order to elucidate the adsorption behavior of radionuclides onto the loamy soil surface in related with hydraulic conditions. Radionuclides concentration change in effluent solution with time and a concentration distribution of radionuclides adsorbed on the ground surface were obtained from several experimental conditions combining the rate and the duration time of the water flow. The radionuclides concentration in the effluent solution was nearly constant during each experimental period, and was reduced under the condition of lower flow rate. The surface distribution of radionuclides concentration showed two distinctive regions. The one was near the inlet vessel where the concentration was promptly reducing, and the other was following the former where the concentration was nearly constant. The characteristic surface distribution of radionuclides concentration can be explained by a two dimensional diffusion model with a first order adsorption reaction, based on the advection of flow rate distribution in perpendicular direction. (author)

Extreme radionuclide accumulation on alpine glaciers in cryoconites

International Nuclear Information System (INIS)

Lettner, H.; Wilflinger, T.; Hubmer, A.K.; Bossew, P.

2008-01-01

Full text: Under environmental conditions when radionuclide fallout will not be diluted by media like soil or water, radionuclides deposited may accumulate to unusual high activities. On glacier surfaces conditions as such exist for aerosols and airborne dust deposited with anthropogenic and natural radionuclides attached on their surfaces. In the course of agglomeration processes initiated by melting and redistribution, these particles may concentrate in small depressions, ice pockets, ablation edges etc. and form substances called cryoconites ('ice dust'). As there is no other matrix than the original aerosol particles, cryoconites are a sink for radionuclides and airborne pollutants and their activity levels are among the highest produced by natural processes observed in environmental media. 137 Cs activities found on glaciers in the Austrian alps are between 255 and 136.000 Bq/kg and predominantly derived from Chernobyl, but also from global fallout. Further anthropogenic radionuclides detected are 134 Cs, 90 Sr, 238,239+240 Pu, 241 Am, 125 Sb, 154 Eu, 60 Co and 207 Bi. In combination with the naturally occurring radionuclides 7 Be and 210 Pb and isotopic ratios such as 134 Cs/ 137 Cs, identification and discrimination of the sources, the nuclear weapon tests and the Chernobyl fallout, can be carried out. (author)

Radionuclide X-ray fluorescence analysis

International Nuclear Information System (INIS)

Cechak, T.

1994-01-01

The author's achievements in the title field are summarized and discussed. The following topics are dealt with: (i) principles of radionuclide X-ray fluorescence analysis; (ii) mathematical methods in X-ray fluorescence analysis; (iii) Ross differential filters; (iv) application of radionuclide X-ray fluorescence analysis in the coal industry (with emphasis on the determination of the ash content, sulfur content, and arsenic content of coal); and (v) evaluation of the X-ray fluorescence analyzer from the radiological safety point of view. (P.A.)

Radionuclide generators for biomedical applications

International Nuclear Information System (INIS)

Finn, R.D.; Molinski, V.J.; Hupf, H.B.; Kramer, H.

1983-10-01

This document reviews the chemical literature of those radionuclide generators that have gained or appear to possess utility in medical imaging. The text represents a conscientious effort to peruse the scientific literature through 1980. The intent of this work is to provide a reference point for the investigator who is interested in the development of a particular generator system and the refinements which have been reported. Moreover, the incorporation of the particular daughter radionuclide into a suitable radiodiagnostic agent is presented

2014 LANL Radionuclide Air Emissions Report

Energy Technology Data Exchange (ETDEWEB)

Fuehne, David Patrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-07-21

This report describes the emissions of airborne radionuclides from operations at Los Alamos National Laboratory (LANL) for calendar year 2014, and the resulting off-site dose from these emissions. This document fulfills the requirements established by the National Emissions Standards for Hazardous Air Pollutants in 40 CFR 61, Subpart H – Emissions of Radionuclides other than Radon from Department of Energy Facilities, commonly referred to as the Radionuclide NESHAP or Rad-NESHAP. Compliance with this regulation and preparation of this document is the responsibility of LANL’s RadNESHAP compliance program, which is part of the Environmental Protection Division. The information in this report is required under the Clean Air Act and is being submitted to the U.S. Environmental Protection Agency (EPA) Region 6.

Inventories of selected radionuclides in the oceans

International Nuclear Information System (INIS)

1988-10-01

In March 1984 an ad hoc Review Committee composed of senior experts in the marine radioactivity field made recommendations that ''the Monaco Laboratory should be engaged in compiling and evaluating the input of radionuclides into the marine environment''. The Committee recommended that work should commence on selected radionuclides, viz., 14 C, caesium isotopes, plutonium isotopes, 210 Po and 210 Pb followed by 226 Ra. Depending on the radionuclides involved the assistance of competent experts from outside as well as inside the IAEA was sought. The present document is a product of the work carried out within the framework of the above-mentioned task and contains reports on 14 C, 90 Sr, 137 Cs, 238 Pu, 239+240 Pu, 210 Pb, 210 Po and 226 Ra. Although the estimation of the inventory in the marine environment and related input and output fluxes, is the same for all radionuclides concerned, different approaches were followed to achieve this objective. These approaches depended on the geochemical characteristics of the radionuclides and the availability of data for different times and locations. For regions where data were lacking, extrapolation on the basis of specific assumptions has often been necessary. As the work was initiated during the pre-Chernobyl period, the radionuclides derived from the Chernobyl incident were not, in general, considered. Since the work for preparing the forthcoming report of the UNSCEAR is scheduled to be completed by 1991, it is hoped that the information contained in this volume will be beneficial. Refs, figs and tabs

New radionuclide generator systems for use in nuclear medicine

International Nuclear Information System (INIS)

Atcher, R.W.

1979-01-01

A current emphasis in nuclear medicine is to better match the physical lifetime of the radionuclides used in vivo for diagnosis and treatment to the biological lifetime of the diagnostic procedure or to minimize radiation dose to areas other than those to be treated. In many cases the biological lifetime is on the order of minutes. Since the direct production of radionuclides with half lives of minutes requires the user to be near a suitable reactor or accelerator, this study was undertaken to produce short-lived radionuclides indirectly. If a long-lived radionuclide decays into a short-lived radionuclide, quick separation of the daughter activity from the parent enables the user to have a short-lived daughter while freeing him from the constraint of proximity to a cyclotron. Systems where a short-lived daughter is separated from a long-lived parent are called radionuclide generators. Two generator systems were developed for use in nuclear medicine, one in diagnostic work and the other for therapeutic work. The yield and breakthrough characteristics were within the limits required to minimize unnecessary radiation exposure in patients. Two parent radionuclides were produced using 4 He beams available from medium energy cyclotrons. The yield was high enough to produce generators that would be useful in clinical applications

Development of a transportable system for radionuclide analysis

International Nuclear Information System (INIS)

Cunningham, W.C.; Anderson, D.L.; Lamont, W.H.; South, P.K.; Rury, M.A.; Beachley, G.M.; Ondov, J.M.

2008-01-01

Transportable radioanalytical systems were assembled and tested for quantitative determination of γ-emitting radionuclides and screening of β- emitting radionuclides. Standard operating procedures (SOPs), including instructions for assembly, disassembly, operation, sample collection and analysis, and all other procedures needed, were developed. Foods, as well as National Institute of Standards and Technology, International Atomic Energy Agency, and in-house Reference Materials were analyzed. An SOP for γ-emitting radionuclides was successfully tested at 3 locations. (author)

Hydrology/Radionuclide Migration Program and related research activities

International Nuclear Information System (INIS)

Jones, M.A.

1992-02-01

This report presents the results of technical studies conducted under the Hydrology/Radionuclide Migration Program (HRMP) at the Nevada Test Site (NTS) for the period of October 1, 1985 through September 30, 1986. The HRMP was initiated in 1973 as the Radionuclide Migration Program to study and better understand the hydrologic systems of the NTS and potential movement and rates of movement of radionuclides and other contaminants injected into these systems by underground nuclear testing

77 FR 72920 - Federal Housing Administration (FHA) Section 232 Healthcare Mortgage Insurance Program: Partial...

Science.gov (United States)

2012-12-07

... 202-708- 0599 (this is not a toll-free number). Persons with hearing or speech impairments may access... freedom of choice for the public. As this rule will include guidance for PPCs in the Code of Federal...-402-3055 (this is not a toll-free number). Individuals with speech or hearing impairments may access...

National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions Calendar Year 2009

International Nuclear Information System (INIS)

2010-01-01

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office operates the Nevada Test Site (NTS) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NTS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NTS 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 NTS. After nuclear testing ended in 1992, NTS 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 were also emitted to air at the NLVF, an NTS 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 facility to 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation not related to NTS activities. Unrelated doses could come from naturally occurring radioactive elements or from sources such as medically or commercially used radionuclides. The NTS demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations. This method was approved by the U.S. Environmental Protection Agency for use on the NTS in 2001 and has been the sole method used since 2005. Six locations on the NTS 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

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

International Nuclear Information System (INIS)

2011-01-01

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

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

International Nuclear Information System (INIS)

2012-01-01

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

78 FR 12759 - Draft Guidance for Industry on Attachment to Guidance on Antiviral Product Development-Conducting...

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2013-02-25

...; formerly 2005D-0183] Draft Guidance for Industry on Attachment to Guidance on Antiviral Product Development... guidance to the Division of Drug Information, Center for Drug Evaluation and Research, Food and Drug... 20852. FOR FURTHER INFORMATION CONTACT: Lisa K. Naeger, Center for Drug Evaluation and Research, Food...

Utilization of E-Counseling in Career Information Dissemination Among Undergraduates of Federal Universities in South East Nigeria

Directory of Open Access Journals (Sweden)

Joachim Chinweike Omeje

2016-06-01

Full Text Available This descriptive survey study was designed to find out the utilization of e-counseling in career information dissemination among the undergraduates of the federal universities in South East Nigeria. Three research questions and three null hypotheses guided the study. The population of the study consisted of 36 guidance counselors and 64,997 undergraduates of the federal universities in South East Nigeria. The sample consisted of 1,036 participants. This is made up of all the 36 guidance counselors in the federal universities in South East Nigeria, and 1,000 undergraduates randomly selected from the various universities. In each university, 200 undergraduates made up of 100 males and 100 females were randomly selected using balloting by replacement. All the guidance counselors were used due to smallness in number. The instrument for data collection was the E-Counselling Career Information Dissemination Questionnaire (E-CCIDQ. The reliability of the instrument was established using Cronbach’s alpha statistical analysis, and reliability indices of .91, .85, and .84 were obtained for the three clusters. Data for the research questions were answered using percentage, mean, and standard deviation, while the null hypotheses were analyzed using t test statistics tested at the .05 level of significance. The research findings revealed that the universities in South East of Nigeria have e-counseling facilities and the students are very aware of e-counseling opportunities in the universities. Also, the counselors and undergraduates to a high extent utilize e-counseling in career information dissemination. Based on findings, discussions and some recommendations were made.

EBS Radionuclide Transport Abstraction

International Nuclear Information System (INIS)

J.D. Schreiber

2005-01-01

The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in ''Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration'' (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system performance assessment for the license application (TSPA-LA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ). The EBS RT Abstraction conceptual model consists of two main components: a flow model and a transport model. Both models are developed mathematically from first principles in order to show explicitly what assumptions, simplifications, and approximations are incorporated into the models used in the TSPA-LA. The flow model defines the pathways for water flow in the EBS and specifies how the flow rate is computed in each pathway. Input to this model includes the seepage flux into a drift. The seepage flux is potentially split by the drip shield, with some (or all) of the flux being diverted by the drip shield and some passing through breaches in the drip shield that might result from corrosion or seismic damage. The flux through drip shield breaches is potentially split by the waste package, with some (or all) of the flux being diverted by the waste package and some passing through waste package breaches that might result from corrosion or seismic damage. Neither the drip shield nor the waste package survives an igneous intrusion, so the flux splitting submodel is not used in the igneous scenario class. The flow model is validated in an independent model validation technical review. The drip shield and waste package flux splitting algorithms are developed and validated using experimental data. The transport model considers

EBS Radionuclide Transport Abstraction

Energy Technology Data Exchange (ETDEWEB)

J.D. Schreiber

2005-08-25

The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in ''Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration'' (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system performance assessment for the license application (TSPA-LA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ). The EBS RT Abstraction conceptual model consists of two main components: a flow model and a transport model. Both models are developed mathematically from first principles in order to show explicitly what assumptions, simplifications, and approximations are incorporated into the models used in the TSPA-LA. The flow model defines the pathways for water flow in the EBS and specifies how the flow rate is computed in each pathway. Input to this model includes the seepage flux into a drift. The seepage flux is potentially split by the drip shield, with some (or all) of the flux being diverted by the drip shield and some passing through breaches in the drip shield that might result from corrosion or seismic damage. The flux through drip shield breaches is potentially split by the waste package, with some (or all) of the flux being diverted by the waste package and some passing through waste package breaches that might result from corrosion or seismic damage. Neither the drip shield nor the waste package survives an igneous intrusion, so the flux splitting submodel is not used in the igneous scenario class. The flow model is validated in an independent model validation technical review. The drip shield and waste package flux splitting algorithms are developed and validated using experimental data. The transport

EBS Radionuclide Transport Abstraction

Energy Technology Data Exchange (ETDEWEB)

J. Prouty

2006-07-14

The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system performance assessment (TSPA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ). The EBS RT Abstraction conceptual model consists of two main components: a flow model and a transport model. Both models are developed mathematically from first principles in order to show explicitly what assumptions, simplifications, and approximations are incorporated into the models used in the TSPA. The flow model defines the pathways for water flow in the EBS and specifies how the flow rate is computed in each pathway. Input to this model includes the seepage flux into a drift. The seepage flux is potentially split by the drip shield, with some (or all) of the flux being diverted by the drip shield and some passing through breaches in the drip shield that might result from corrosion or seismic damage. The flux through drip shield breaches is potentially split by the waste package, with some (or all) of the flux being diverted by the waste package and some passing through waste package breaches that might result from corrosion or seismic damage. Neither the drip shield nor the waste package survives an igneous intrusion, so the flux splitting submodel is not used in the igneous scenario class. The flow model is validated in an independent model validation technical review. The drip shield and waste package flux splitting algorithms are developed and validated using experimental data. The transport model considers advective transport and diffusive transport

EBS Radionuclide Transport Abstraction

International Nuclear Information System (INIS)

J. Prouty

2006-01-01

The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system performance assessment (TSPA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ). The EBS RT Abstraction conceptual model consists of two main components: a flow model and a transport model. Both models are developed mathematically from first principles in order to show explicitly what assumptions, simplifications, and approximations are incorporated into the models used in the TSPA. The flow model defines the pathways for water flow in the EBS and specifies how the flow rate is computed in each pathway. Input to this model includes the seepage flux into a drift. The seepage flux is potentially split by the drip shield, with some (or all) of the flux being diverted by the drip shield and some passing through breaches in the drip shield that might result from corrosion or seismic damage. The flux through drip shield breaches is potentially split by the waste package, with some (or all) of the flux being diverted by the waste package and some passing through waste package breaches that might result from corrosion or seismic damage. Neither the drip shield nor the waste package survives an igneous intrusion, so the flux splitting submodel is not used in the igneous scenario class. The flow model is validated in an independent model validation technical review. The drip shield and waste package flux splitting algorithms are developed and validated using experimental data. The transport model considers advective transport and diffusive transport

Quality control for radionuclide determinations in the Saxon state laboratories for environmental radioactivity by intercomparison and comparative measurements

International Nuclear Information System (INIS)

Knobus, B.

2001-01-01

Quality control for radionuclide analysis is necessary and essential for the quality assurance of the measuring results executing the measuring programmes of surveillance of the radioactivity in the environment and from installations. Acts, ordinances and guidelines require the participation in intercomparisons for authorized institutions detecting the demanded quality of measurements (e.g. trueness, reproducibility) for Federal Authorities. These are mainly those intercomparisons which are prepared, practised and evaluated by the federal laboratories. Comparative measurements are generally organized and executed by the state laboratory itself with a few participants for special measuring tasks. In this paper are described and discussed extend and special results of those intercomparisons and comparative measurements of the Saxon state laboratories for environmental radioactivity from 1992 until 2000. If necessary, there are following improvements for quality assurance. (orig.) [de

Improving global laboratory capabilities for emergency radionuclide bioassay

International Nuclear Information System (INIS)

Li, C.; Jourdain, J.; Kramer, G. H.

2012-01-01

During a radiological or nuclear emergency, first-responders and the general public may be internally contaminated with the radionuclide(s) involved. A timely radionuclide bioassay provides important information about contamination, for subsequent dose assessment and medical management. Both technical and operational gaps are discussed in this paper. As many people may need to be assessed in a short period of time, any single laboratory may find its capabilities insufficient. Laboratories from other regions or other countries may be called upon for assistance. This paper proposes a road-map to improve global capabilities in emergency radionuclide bioassay, suggesting a phased approach for establishing a global laboratory network. Existing international collaboration platforms could provide the base on which to build such a network. (authors)

Radionuclide techniques for brain imaging

International Nuclear Information System (INIS)

Cowan, R.J.; Moody, D.M.

1984-01-01

Over the past decade, many of the prime indications for radionuclide brain scanning have become instead indications for CCT, and nuclear medicine studies of the brain have assumed more of a complementary, supportive role. However, there is great promise for improvement in central nervous system radionuclide applications with advances anticipated in both radiopharmaceuticals and instrumentation. Nuclear medicine is continuing to function as a powerful research tool and, in the relatively near future, may regain its role as a major clinical test of the central nervous system

Relating β+ radionuclides' properties by order theory

International Nuclear Information System (INIS)

Quintero, N.Y.; Guillermo Restrepo; Cohen, I.M.; Universidad Tecnologica Nacional, Buenos Aires

2013-01-01

We studied 27 β + radionuclides taking into account some of their variants encoding information of their production, such as integral yield, threshold energy and energy of projectiles used to generate them; these radionuclides are of current use in clinical diagnostic imaging by positron emission tomography (PET). The study was conducted based on physical, physico-chemical, nuclear, dosimetric and quantum properties, which characterise the β + radionuclides selected, with the aim of finding meaningful relationships among them. In order to accomplish this objective the mathematical methodology known as formal concept analysis was employed. We obtained a set of logical assertions (rules) classified as implications and associations, for the set of β + radionuclides considered. Some of them show that low mass defect is related to high and medium values of maximum β + energy, and with even parity and low mean lives; all these parameters are associated to the dose received by a patient subjected to a PET analysis. (author)

Metabolic transformation of radionuclides in marine organisms

International Nuclear Information System (INIS)

Koyanagi, Taku

1987-01-01

Physico-chemical form of radionuclides is one of the important factors governing the concentration by marine organisms, whereas biological activities affect the existing states of radionuclides especially in coastal waters. Radioiodine in the form of iodate which is predominant species in seawater is reduced to iodide ion by biological activities and concentration factor of iodide is an order of magnitude higher than those of iodate. Extremely high accumulation of transition elements, actinides, or natural radionuclides in branchial heart of octopus is explained by the fuction of adenochrome, a glandular pigment in the organ as a natural complexing agent, and similar metal-binding proteins with relatively low molecular weight have been found in various marine invertebrates. High accumulation of some elements also found in mollusk kidney is considered to be caused by the intracellular concretions composed of calcium phosphate. All these biological processes suggest the significance of further investigations on metabolic transformation of radionuclides in marine organisms. (author)

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

Energy Technology Data Exchange (ETDEWEB)

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

2011-07-29

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

The main trends in clinical use of radionuclides in oncology

International Nuclear Information System (INIS)

Agranat, V.Z.

1979-01-01

The main trends of using radionuclide methods in clinical oncology are shown. Two main aspects of using radionuclide methods are pointed out: radionuclide investigation of the primary tumour as ''local'' manifestation of the cancer disease, radionuclide investigation of the body ''response'' to the tumour process. Each of the aspects of the problem is briefly considered on some examples. Examples of positive scintigraphy of tumours are given. It is shown that tumorotropic properties of some radionuclides make possible using visualization methods realizing the differential diagnosis of some tumours. Considered are direct and indirect signs which allow determining the presence of metastases and testifying to the tumour process spread

Radionuclide concentrations in white sturgeon from the Columbia River

International Nuclear Information System (INIS)

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

1993-11-01

The objectives of this study were to (1) review and summarize historical data on radionuclide concentrations in white sturgeon from the Columbia River, (2) determine present-day radionuclide tissue burdens from different locations in the Columbia River, and (3) compare historical data with current data. We first reviewed and summarized the historical literature on radionuclide concentrations in white sturgeon from the Hanford Reach. Field studies were then conducted to evaluate the relationship among sample locations, age/length of white sturgeon, and present radionuclide tissue burdens. Results and comparisons are discussed in the remainder of this report

Radionuclide Therapies in Molecular Imaging and Precision Medicine.

Science.gov (United States)

Kendi, A Tuba; Moncayo, Valeria M; Nye, Jonathon A; Galt, James R; Halkar, Raghuveer; Schuster, David M

2017-01-01

This article reviews recent advances and applications of radionuclide therapy. Individualized precision medicine, new treatments, and the evolving role of radionuclide therapy are discussed. Copyright © 2016 Elsevier Inc. All rights reserved.

Natural and anthropogenic radionuclide activity concentrations in the New Zealand diet.

Science.gov (United States)

Pearson, Andrew J; Gaw, Sally; Hermanspahn, Nikolaus; Glover, Chris N

2016-01-01

To support New Zealand's food safety monitoring regime, a survey was undertaken to establish radionuclide activity concentrations across the New Zealand diet. This survey was undertaken to better understand the radioactivity content of the modern diet and also to assess the suitability of the current use of milk as a sentinel for dietary radionuclide trends. Thirteen radionuclides were analysed in 40 common food commodities, including animal products, fruits, vegetables, cereal grains and seafood. Activity was detected for (137)Caesium, (90)Strontium and (131)Iodine. No other anthropogenic radionuclides were detected. Activity concentrations of the three natural radionuclides of Uranium and the daughter radionuclide (210)Polonium were detected in the majority of food sampled, with a large variation in magnitude. The maximum activity concentrations were detected in shellfish for all these radionuclides. Based on the established activity concentrations and ranges, the New Zealand diet contains activity concentrations of anthropogenic radionuclides far below the Codex Alimentarius guideline levels. Activity concentrations obtained for milk support its continued use as a sentinel for monitoring fallout radionuclides in terrestrial agriculture. The significant levels of natural and anthropogenic radionuclide activity concentrations detected in finfish and molluscs support undertaking further research to identify a suitable sentinel for New Zealand seafood monitoring. Copyright © 2015 The Authors. Published by Elsevier Ltd.. All rights reserved.

CRRIS, Health Risk Assessment from Atmospheric Releases of Radionuclides

International Nuclear Information System (INIS)

1999-01-01

1 - Description of program or function: CRRIS consists of eight fully integrated computer codes which calculate environmental transport of atmospheric releases of radionuclides and resulting doses and health risks to individuals or populations. Each code may be used alone for various assessment applications. Because of its modular structure, CRRIS allows assessments to be tailored to the user's needs. Radionuclides are handled by CRRIS either in terms of the released radionuclides or the exposure radionuclides which consist of both the released nuclides and decay products that build up during environmental transport. Atmospheric dispersion calculations are performed by the ANEMOS computer code for distances less than 100 km and the RETADD-II computer code regional-scale distances. Both codes estimate annual-average air concentrations and ground deposition rates by location. SUMIT will translate and scale multiple ANEMOS runs onto a master grid. TERRA reads radionuclide air concentrations and deposition rates to estimate concentrations of radionuclides in food and surface soil. Radiologic decay and ingrowth, soil leaching, and transport through the food chain are included in the calculations. MLSOIL computes an effective radionuclide ground-surface concentration to be used in computing external health effects. The five-layer model of radionuclide transport through soil in MLSOIL provides an alternative to the single-layer model used in TERRA. DFSOIL computes dose factors used in MLSOIL to compute doses from the five soil layers and from the ground surface. ANDROS reads environmental concentrations of radionuclides computed by the other CRRIS codes and produces tables of doses and risks to individuals or populations from atmospheric releases of radionuclides. 2 - Method of solution: SUMIT performs geometric interpolation. TERRA and MLSOIL are terrestrial transport compartment models. DFSOIL computes soil-layer-specific dose factors based on the point-kernel method

The behaviour of radionuclides in soil

International Nuclear Information System (INIS)

Bunzl, K.

1987-01-01

Radionuclides in soil are of natural as well as of artificial origin. Their migration in the soil and their availability for ecological processes depend considerably on the extent at which they are sorbed. The methods for the determination of the vertical rate of migration are described. For most radionuclides this transport is very slow (a few cm per year). Cs-137 is of especial interest. It is sorbed strongly by most soils and, as a consequence, its root uptake is small. However, as a result of the sorption, this radionuclide is eluted from the root zone only very slowly and its thus available for the root uptake for many years. The Cs-137 concentrations in plants to be expected in the coming years as a result of the fallout from Chernobyl are small. (orig.) [de

Transport of radionuclides in the biosphere

International Nuclear Information System (INIS)

Bundi, A.

1983-10-01

The dispersion of radionuclides in the biosphere and their uptake by man via various nutritional pathways is studied using a compartment model. The sample environment is the area of the lower Limmat and Aare valleys. General considerations of the compartmental description of the biosphere are made. The problem of the description of surface features, in particular soil, sediment and water, is studied in detail using the code BIOPATH. This study is intended to be an example of how a model of the biosphere could be constructed. It is shown that this is a reasonable model to calculate the spreading of radionuclides in the biosphere and that it indicates the relative significance of individual compartments, pathways and radionuclides. Calculated values of dose committment, however, should not be used as reference data for safety analyses. (Auth.)

Bone stress: a radionuclide imaging perspective

International Nuclear Information System (INIS)

Roub, L.W.; Gumerman, L.W.; Hanley, E.N. Jr.; Clark, M.W.; Goodman, M.; Herbert, D.L.

1979-01-01

Thirty-five college athletes with lower leg pain underwent radiography and radionuclide studies to rule out a stress fracture. Their asymptomatic extremities and 13 pain-free athletes served as controls. Four main patterns were observed: (a) sharply marginated scintigraphic abnormalities and positive radiographs; (b) sharply marginated scintigraphic abnormalities and negatives radiographs; (c) ill-defined scintigraphic abnormalities and negative radiographs; and (d) negative radionuclide images and negative radiographs. Since the patients with the first two patterns were otherwise identical medically, the authors feel that this scintigraphic appearance is characterisic of bone stress in the appropriate clinical setting, regardless of the radiographic findings. A schema is proposed to explain the occurrence of positive radionuclide images and negative radiographs in the same patient, using a broad conceptual approach to the problem of bone stress

Radionuclide migration in groundwater. Annual progress report for 1982

International Nuclear Information System (INIS)

Robertson, D.E.; Toste, A.P.; Abel, K.H.; Brodzinski, R.L.

1984-01-01

Research has continued at a low-level waste disposal facility to characterize the physicochemical species of radionuclides migrating in groundwater. This facility consists of an unlined basin and connecting trench which receives effluent water containing low levels of a wide variety of fission and activation products and trace amounts of transuranic radionuclides. The effluent water percolates through the soil and a small fraction of it emerges at seepage springs located some 260 meters from the trench. The disposal basin and trench are very efficient in retaining most of the radionuclides, but trace amounts of a number of radionuclides existing in mobile chemical forms migrate in the groundwater from the trench to the springs. This facility provides the opportunity for characterizing the rates and mechanisms of radionuclide migration in groundwaters, identifying retardation processes, and validating geochemical models. 13 references, 25 figures, 23 tables

Proceedings of the public meeting to address a proposed federal radiation research agenda. Volume I. Issue papers

International Nuclear Information System (INIS)

1980-03-01

Separate abstracts were prepared for 11 of the 12 invited issue papers and for 3 of the 13 documents received from the public at large in the preparation of an agenda for federally sponsored and conducted research into the biological effects of ionizing radiation. One issue paper previously input to the data base deals with the potential for significant human exposure from environmentally dispersed radionuclides

Field surveying of radionuclide contamination in forests

International Nuclear Information System (INIS)

Turunen, J.; Rantavaara, A.; Ammann, M.

2009-01-01

Field measurements of radionuclides after an accidental contamination of forests assume the capacity for identification of a number of nuclides in varying source geometries. The continuous redistribution of radionuclides in forests through natural processes implies a decrease of prevailing surface contamination of trees and an increase in activity density on the ground. Portable gamma spectrometers have long been based on Na(I) detectors which, due to their low energy resolution, are not the tool for analysis of contamination from accidental releases of fission and activation products in the first days or weeks after a deposition. Data of airborne radionuclides from the Chernobyl accident in April 1986 were used for demonstration of initial and later distribution of radionuclides as sources of air Kerma in forests. Forest model (FDMF, PV. 6.0) of the RODOS system was used for the assessment of time-dependent Kerma rate from different forest compartments. The results show the fast reduction of activities of short-lived nuclides and their contributions to the Kerma rate in the first weeks and months. The results also give an estimate for the time needed until a gamma spectrometer with a low energy resolution would give useful information about long-lived radioactivity on the forest floor. An example is given on a portable high resolution semiconductor spectrometer that has suitable characteristics for field surveying also during occurrence of a great number of radionuclides contributing to the gamma spectrum. The needs for further research of a recently deposited radionuclide contamination on forest vegetation and soil, and the efforts for improvement of portable radiation meters and their use in management planning and radioecological research on contaminated forests are discussed. (au)

Exchange of certain radionuclides between environment and freshwater algae

International Nuclear Information System (INIS)

Marchyulenene, E. D.P.

1978-01-01

Data on the dynamics and levels of accumulation of strontium, cesium, cerium and ruthenium radionuclides by Charophyta and Cladophora fresh-water algae are presented. An attempt has been made to investigate some processes that accompany the accumulation of radionuclides by plants. Under experimental conditions, the intensity and levels of radionuclide accumulation can be presented in the following order: 144 Ce> 106 Ru> 90 Sr> 137 Cs. The dynamics of radionuclide accumulation varied greatly with the radionuclide and the algae species studied. The 144 Ce accumulation coefficients (AC) in the course of experiment (from 3 hours to 16 days) increased 8-, 9-, 23.4-, 27-, 14.3- and 20.4-fold for Cladophora glomerata, Nitella syncarpa, Nitellopsis obtusa, Chara vulgaris, Ch. rudis, and Ch. aspera, respectively. In the case of 106 Ru, AC for C.glomerata, N. syncarapa, Ch. vulgaris and Ch. rudis increased 34-, 18-,24- and 23-fold, respectively. In all algae species studied the equilibrium of radionuclide accumulation was attained after 2-4 days of experiment. Levels of accumulated 90 Sr and 137 Cs in most species depended on the season while that of 144 Cs and 106 Ru remained constant throughout the vegetation period. The levels of radionuclide elimination, like the accumulation levels, are shown to depend on both isotopes and algae species

Exposure to radionuclides in smoke from vegetation fires

International Nuclear Information System (INIS)

Carvalho, Fernando P.; Oliveira, João M.; Malta, Margarida

2014-01-01

Naturally occurring radionuclides of uranium, thorium, radium, lead and polonium were determined in bushes and trees and in the smoke from summer forest fires. Activity concentrations of radionuclides in smoke particles were much enriched when compared to original vegetation. Polonium-210 ( 210 Po) in smoke was measured in concentrations much higher than all other radionuclides, reaching 7255 ± 285 Bq kg −1 , mostly associated with the smaller size smoke particles ( 210 Po in surface air near forest fires displayed volume concentrations up to 70 mBq m −3 , while in smoke-free air 210 Po concentration was about 30 μBq m −3 . The estimated absorbed radiation dose to an adult member of the public or a firefighter exposed for 24 h to inhalation of smoke near forest fires could exceed 5 μSv per day, i.e, more than 2000 times above the radiation dose from background radioactivity in surface air, and also higher than the radiation dose from 210 Po inhalation in a chronic cigarette smoker. It is concluded that prolonged exposure to smoke allows for enhanced inhalation of radionuclides associated with smoke particles. Due to high radiotoxicity of alpha emitting radionuclides, and in particular of 210 Po, the protection of respiratory tract of fire fighters is strongly recommended. - Highlights: • Natural radionuclides in vegetation are in low concentrations. • Forest fires release natural radionuclides from vegetation and concentrate them in inhalable ash particles. • Prolonged inhalation of smoke from forest fires gives rise enhanced radiation exposure of lungs especially due to polonium. • Respiratory protection of fire fighters and members of public is highly recommended for radioprotection reasons

Development of threshold guidance: National Low-Level Radioactive Waste Management Program

International Nuclear Information System (INIS)

1986-09-01

The current study has been conducted to provide DOE with a technical basis for the development of threshold guidance. The objective of the study was to develop the necessary background information and recommendations to assist the DOE in implementing the threshold limit concept for the disposal of DOE wastes at DOE facilities. The nature of low-level radioactive waste (LLW) varies greatly in both form and radionuclide content. While some low-level waste streams can contain substantial quantities of radioactive constituents, a potentially significant fraction of low-level waste is contaminated either very slightly or not at all. There is a strong likelihood that managing wastes with extremely low levels of radioactivity as nonradioactive waste would pose no significant safety problems and could result in substantial cost savings relative to its handling as LLW. Since all materials, including waste products, contain some radioactivity, it is necessary to distinguish between those wastes that would require disposal as LLW and those that have sufficiently low levels of radiological content to be managed according to their nonradiological properties. 131 refs., 9 figs., 24 tabs

Consequence ranking of radionuclides in Hanford tank waste

International Nuclear Information System (INIS)

Schmittroth, F.A.; De Lorenzo, T.H.

1995-09-01

Radionuclides in the Hanford tank waste are ranked relative to their consequences for the Low-Level Tank Waste program. The ranking identifies key radionuclides where further study is merited. In addition to potential consequences for intrude and drinking-water scenarios supporting low-level waste activities, a ranking based on shielding criteria is provided. The radionuclide production inventories are based on a new and independent ORIGEN2 calculation representing the operation of all Hanford single-pass reactors and the N Reactor

Colloid-facilitated radionuclide transport: a regulatory perspective

Science.gov (United States)

Dam, W. L.; Pickett, D. A.; Codell, R. B.; Nicholson, T. J.

2001-12-01

What hydrogeologic-geochemical-microbial conditions and processes affect migration of radionuclides sorbed onto microparticles or native colloid-sized radionuclide particles? The U.S. Nuclear Regulatory Commission (NRC) is responsible for protecting public health, safety, and the environment at numerous nuclear facilities including a potential high-level nuclear waste disposal site. To fulfill these obligations, NRC needs to understand the mechanisms controlling radionuclide release and transport and their importance to performance. The current focus of NRC staff reviews and technical interactions dealing with colloid-facilitated transport relates to the potential nuclear-waste repository at Yucca Mountain, Nevada. NRC staff performed bounding calculations to quantify radionuclide releases available for ground-water transport to potential receptors from a Yucca Mountain repository. Preliminary analyses suggest insignificant doses of plutonium and americium colloids could be derived from spent nuclear fuel. Using surface complexation models, NRC staff found that colloids can potentially lower actinide retardation factors by up to several orders of magnitude. Performance assessment calculations, in which colloidal transport of plutonium and americium was simulated by assuming no sorption or matrix diffusion, indicated no effect of colloids on human dose within the 10,000 year compliance period due largely to long waste-package lifetimes. NRC staff have identified information gaps and developed technical agreements with the U.S. Department of Energy (DOE) to ensure sufficient information will be presented in any potential future Yucca Mountain license application. DOE has agreed to identify which radionuclides could be transported via colloids, incorporate uncertainties in colloid formation, release and transport parameters, and conceptual models, and address the applicability of field data using synthetic microspheres as colloid analogs. NRC is currently

The uptake of radionuclides by plants

International Nuclear Information System (INIS)

Cawse, P.A.; Turner, G.S.

1982-02-01

A review of the literature, since 1970, on the research into the uptake of radionuclides by plants, with references to earlier soil and plant studies on the fate of nuclear weapons fallout. Experimental data on the uptake of plutonium isotopes, americium 241, cesium 137, radium 226, curium 244 and neptunium 237 and details of the chemical form of the radionuclide, soil type and plant growth period are tabulated. (U.K.)

Report on the intercomparison run IAEA-156 radionuclides in clover

International Nuclear Information System (INIS)

Strachnov, V.; Valkovic, V.; Dekner, R.

1991-01-01

This report contains the results of the intercomparison IAEA-156 on the determination of radionuclides in clover. Initially participants were requested to determine the levels of 134 Cs, 137 Cs, 40 K, 90 Sr and invited to provide data for other radionuclides. The participants included 46 laboratories located in 25 countries, and statistical evaluation of their data yield recommended values for these four radionuclides. Additional radionuclides reported were 210 Pb, 239 Pu and 125 Sb; however, insufficient data exists to statistically determine recommended values for these radionuclides. The following are the recommended values, with confidence intervals, for the most frequently measured radionuclides (reference date: 1 August 1986): 134 Cs 132.1 Bq/kg (126.4-137.7); 137 Cs 264 Bq/kg (254-274); 40 K 657 Bq/kg (637-676); 90 Sr 14.8 Bq/kg (13.4-16.3). Figs and tabs

Criteria of reference radionuclides for safety analysis of spent fuel waste disposal

International Nuclear Information System (INIS)

Suryanto

1998-01-01

Study on the criteria for reference radionuclides selection for assessment on spent fuel disposal have done. The reference radionuclides in this study means radionuclides are predicted to contribute of the most radiological effect for man if spent fuel waste are discharged on deep geology formation. The research was done by investigate critically of parameters were used on evaluation a kind of radionuclide. Especially, this research study of parameter which relevant disposal case and or spent fuel waste on deep geology formation . The research assumed that spent fuel discharged on deep geology by depth 500-1000 meters from surface of the land. The migration scenario Radionuclides from waste form to man was assumed particularly for normal release in which Radionuclides discharge from waste form in a series thorough container, buffer, geological, rock, to fracture(fault) and move together with ground water go to biosphere and than go into human body. On this scenario, the parameter such as radionuclides inventory, half life, heat generation, hazard index based on maximum permissible concentration (MPC) or annual limit on intake (ALI) was developed as criteria of reference radionuclides selection. The research concluded that radionuclides inventory, half live, heat generated, hazard index base on MPC or ALI can be used as criteria for selection of reference Radionuclide. The research obtained that the main radionuclides are predicted give the most radiological effect to human are as Cs-137, Sr-90, I-129, Am-243, Cm-244, Pu-238, Pu-239, Pu-240. The radionuclides reasonable to be used as reference radionuclides in safety analysis at spent fuel disposal. (author)

Radionuclides in marine organisms

International Nuclear Information System (INIS)

Honda, Teruyuki

2001-01-01

The concentration and accumulation of radionuclides in marine organisms were explained in this paper. Secular change of the radioactivity concentration of 137 Cs in seaweed in coastal area of Japan showed more than 5Bq/kg-fresh in the first half of 1960, but decreased less than 1 Bq/kg-fresh after then and attained to less than 0.1 Bq/kg-fresh in 1990s. However, the value increased a while in 1986, which indicated the effect of Chernobyl accident. The accident increased 137 Cs of shellfish near Japan. The concentration of 239+240 Pu was the lowest value in muscles of fish, but increased from 1.7 to 42.3 mBq/kg wet wt in seaweed in 1999. 99 Tc concentration of seaweed showed from 100 to 1000 times as much as that of seawater. Radionuclides in the Irish Sea are originated from Sellafield reprocessing plant. The concentration factors of macro-algae and surface water fish (IAEA,1985) were shown. Analytical results of U in 61 kinds of marine organs showed that the concentration was different in the part of organ. The higher concentration of U was observed in hard tissue of fish. The concentration factor was different between chemical substances with the same radionuclides. (S.Y.)

Development of radionuclide parameter database on internal contamination in nuclear emergencies

International Nuclear Information System (INIS)

Zhao Li; Xu Cuihua; Li Wenhong; Su Xu

2010-01-01

Objective: To develop a radionuclide parameter database on internal contamination in nuclear emergencies. Methods: By researching the radionuclides composition discharged from different nuclear emergencies, the radionuclide parameters were achieved on physical decay, absorption and metabolism in the body from ICRP publications and some other publications. The database on internal contamination for nuclear incidents was developed by using MS Visual Studio 2005 C and MS Access programming language. Results: The radionuclide parameter database on internal contamination in nuclear emergency was established. Conclusions: The database may be very convenient for searching radionuclides and radionuclide parameter data discharged from different nuclear emergencies, which would be helpful to the monitoring and assessment and assessment of internal contamination in nuclear emergencies. (authors)

Report on the intercomparison run IAEA-321 radionuclides in milk powder

International Nuclear Information System (INIS)

Strachnov, V.; Burns, K.; Dekner, R.

1990-01-01

This report contains the results of the intercomparison IAEA-321 on the determination of radionuclides in milk powder. Initially participants were requested to determine the levels of 134 Cs, 137 Cs, 40 K, 90 Sr and invited to provide data for other radionuclides. The participants included 61 laboratories located in 29 countries, and statistical evaluation of their data yield recommended values for these four radionuclides. Additional radionuclides reported were 226 Ra and 232 Th, however insufficient data exists to statistically determine recommended values for these radionuclides. The recommended values for radionuclide determination are: 134 Cs: 15.5 Bq/kg; 137 Cs: 72.6 Bq/Kg; 40 K: 552 Bq/kg; 90 Sr: 3.3 Bq/kg. Tabs

New best estimates for radionuclide solid-liquid distribution coefficients in soils. Part 3: miscellany of radionuclides (Cd, Co, Ni, Zn, I, Se, Sb, Pu, Am, and others)

International Nuclear Information System (INIS)

Gil-Garcia, C.; Tagami, K.; Uchida, S.; Rigol, A.; Vidal, M.

2009-01-01

New best estimates for the solid-liquid distribution coefficient (K d ) for a set of radionuclides are proposed, based on a selective data search and subsequent calculation of geometric means. The K d best estimates are calculated for soils grouped according to the texture and organic matter content. For a limited number of radionuclides this is extended to consider soil cofactors affecting soil-radionuclide interaction, such as pH, organic matter content, and radionuclide chemical speciation. Correlations between main soil properties and radionuclide K d are examined to complete the information derived from the best estimates with a rough prediction of K d based on soil parameters. Although there are still gaps for many radionuclides, new data from recent studies improve the calculation of K d best estimates for a number of radionuclides, such as selenium, antimony, and iodine.

A random walk model to simulate the atmospheric dispersion of radionuclide

Science.gov (United States)

Zhuo, Jun; Huang, Liuxing; Niu, Shengli; Xie, Honggang; Kuang, Feihong

2018-01-01

To investigate the atmospheric dispersion of radionuclide in large-medium scale, a numerical simulation method based on random walk model for radionuclide atmospheric dispersion was established in the paper. The route of radionuclide migration and concentration distribution of radionuclide can be calculated out by using the method with the real-time or historical meteorological fields. In the simulation, a plume of radionuclide is treated as a lot of particles independent of each other. The particles move randomly by the fluctuations of turbulence, and disperse, so as to enlarge the volume of the plume and dilute the concentration of radionuclide. The dispersion of the plume over time is described by the variance of the particles. Through statistical analysis, the relationships between variance of the particles and radionuclide dispersion characteristics can be derived. The main mechanisms considered in the physical model are: (1) advection of radionuclide by mean air motion, (2) mixing of radionuclide by atmospheric turbulence, (3) dry and wet deposition, (4) disintegration. A code named RADES was developed according the method. And then, the European Tracer Experiment (ETEX) in 1994 is simulated by the RADES and FLEXPART codes, the simulation results of the concentration distribution of tracer are in good agreement with the experimental data.

Correlation Water Velocity and TSS with Natural Radionuclides Activity

International Nuclear Information System (INIS)

Tri Harningsih; Muzakky; Agus Taftazani

2007-01-01

Correlation water velocity and TSS with natural radionuclides activity has been studied. For that purpose, the study is to correlation water velocity and TSS with radionuclides on water and sediment samples in alongside river Code Yogyakarta. This research selected radionuclides, for examples Ra-226, Pb-212, Ac- 228, and K-40. Election of this radionuclides to spread over gamma gross composition alongside river of Code. Gamma gross influenced by water velocity and TSS, so that require to correct between water velocity and TSS to radionuclides. Sampling water and sediment conducted when dry season of August, 2006 at 11 locations, start from Boyong Bridge until Pacar Bridge. Result of analysis showed that water velocity range from 8-1070 L/dt and TSS range from 2.81 E-06 - 8.02 E-04 mg/L. The accumulation of radionuclides in water samples non correction water velocity for Ra-226: 0.302-2.861 Bq/L, Pb-212: 0.400-3.390 Bq/L, Ac- 228: 0.0029-0.0047 Bq/L and K-40: 0.780-9.178 Bq/L. The accumulation of radionuclide in water samples correction water velocity for Ra-226: 1.112-70.454 Bq/L, Pb-212: 0.850-77.113 Bq/L, Ac-228: 0.7187- 60.859 Bq/L and K-40: 2.420-208.8 Bq/L. While distribution of radionuclide in sediment for the Ra-226: 0.0012-0.0211 Bq/kg, Pb-212: 0.0017-0.0371 Bq/kg, Ac-228: 0.0021-0.0073 Bq/kg and K-40: 0.0006-0.0084 Bq/kg. (author)

Removal of radionuclides from liquid streams by reverse osmosis

International Nuclear Information System (INIS)

Deshmukh, U.A.; Ramachandhran, V.; Misra, B.M.

1987-01-01

Separation of radionuclides in trace concentrations by cellulose acetate membranes has been under investigation in this laboratory, and the behaviour of some important radionuclides such as 137 Cs and 90 Sr under reverse osmosis has been reported earlier. The present work deals with a few other typical radionuclides such as 60 Co, 103 Ru and 131 I which are not fully amenable to conventional methods for their removal. Separation of these radionuclides from liquid streams by the reverse osmosis process was studied using a small reverse osmosis test cell. Various parameters like membrane porosity, applied pressure and feed activity levels were investigated. Cellulose acetate membranes offer reasonable separation of 60 Co, 103 Ru and 131 I radionuclides, indicating the potential of reverse osmosis for treatment of effluents containing these radioisotopes. The percent separation is found to be in the order of Co > Ru > I. The percent radioactive separation improves with increases in feed activity. The performance data are explained in terms of solution-diffusion mechanism. It appears that the separation of radionuclides is not governed by diffusion alone, but by the interaction of solutes with the membranes. (author)

Quality in career guidance: The Danish case

DEFF Research Database (Denmark)

Plant, Peter

2011-01-01

Quality assurance systems are introduced in career guidance to monitor, control and develop guidance interventions. The Danish case represents at centrally driven, top-down approach......Quality assurance systems are introduced in career guidance to monitor, control and develop guidance interventions. The Danish case represents at centrally driven, top-down approach...

Separation of radionuclides from water by magnesium oxide adsorption

International Nuclear Information System (INIS)

Tseng, Chia-Lian; Lo, Jem-Mau; Yeh, Si-Jung

1987-01-01

Adsorption by magnesium oxide of more than forty radionuclides in respective ionic species in water was observed. Generally, the radionuclides in di-valent and/or multi-valent cations are favorably adsorbed by magnesium oxide; but not for the those in mono-valent cations. In addition, the adsorption by magnesium oxide was not effective to most of the radionuclides in negative ionic species. From the observations, the adsorption mechanism is more prominently by the ion exchange of the di- or multi-valent cation species with the hydrous magnesium oxide. Separation of the radionuclides related to the corrosion products possibly produced in a nuclear power plant from natural seawater was attempted by the magnesium oxide adsorption method. It should be emphasized that the adsorption method was found to be practical for separating radionuclides from a large quantity of natural seawater with high recovery and high reproducibility. (author)

Mechanisms of radionuclide transition in natural environment

International Nuclear Information System (INIS)

Pacyna, J.

1974-01-01

Mechanisms of radionuclide transition in various elements of the environment have been dealt with in an ecological aspect. The knowledge of the radionuclide propagation tracks will make possible to ascertain precisely causes and effects of the radiation and to reduce the contamination value. Particular attention has been paid to test methods. (author)