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1

Radioactive Material Transportation Practices  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes standard transportation practices for Departmental programs to use in planning and executing offsite shipments of radioactive materials including radioactive waste. Does not cancel other directives.

2002-09-23T23:59:59.000Z

2

Radioactive Material Transportation Practices Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Manual establishes standard transportation practices for the Department of Energy, including National Nuclear Security Administration to use in planning and executing offsite shipments of radioactive materials and waste. The revision reflects ongoing collaboration of DOE and outside organizations on the transportation of radioactive material and waste. Cancels DOE M 460.2-1.

2008-06-04T23:59:59.000Z

3

Base Technology for Radioactive Material Transportation Packaging Systems  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish Department of Energy (DOE) policies and responsibilities for coordinating and planning base technology for radioactive material transportation packaging systems.

1992-07-08T23:59:59.000Z

4

Transporting radioactive materials: Q & A to your questions  

SciTech Connect (OSTI)

Over 2 million packages of radioactive materials are shipped each year in the United States. These shipments are carried by trucks, trains, ships, and airplanes every day just like other commodities. Compliance with Federal regulations ensures that radioactive materials are transported safely. Proper packaging is the key to safe shipment. Package designs for radioactive materials must protect the public and the environment even in case of an accident. As the level of radioactivity increases, packaging design requirements become more stringent. Radioactive materials have been shipped in this country for more than 40 years. As with other commodities, vehicles carrying these materials have been involved in accidents. However, no deaths or serious injuries have resulted from exposure to the radioactive contents of these shipments. People are concerned about how radioactive shipments might affect them and the environment. This booklet briefly answers some of the commonly asked questions about the transport of radioactive materials. More detailed information is available from the sources listed at the end of this booklet.

Not Available

1993-04-01T23:59:59.000Z

5

Romanian Experience for Enhancing Safety and Security in Transport of Radioactive Material - 12223  

SciTech Connect (OSTI)

The transport of Dangerous Goods-Class no.7 Radioactive Material (RAM), is an important part of the Romanian Radioactive Material Management. The overall aim of this activity is for enhancing operational safety and security measures during the transport of the radioactive materials, in order to ensure the protection of the people and the environment. The paper will present an overall of the safety and security measures recommended and implemented during transportation of RAM in Romania. Some aspects on the potential threat environment will be also approached with special referring to the low level radioactive material (waste) and NORM transportation either by road or by rail. A special attention is given to the assessment and evaluation of the possible radiological consequences due to RAM transportation. The paper is a part of the IAEA's Vienna Scientific Research Contract on the State Management of Nuclear Security Regime (Framework) concluded with the Institute for Nuclear Research, Romania, where the author is the CSI (Chief Scientific Investigator). The transport of RAM in Romania is a very sensible and complex problem taking into consideration the importance and the need of the security and safety for such activities. The Romanian Nuclear Regulatory Body set up strictly regulation and procedures according to the Recommendation of the IAEA Vienna and other international organizations. There were implemented the adequate regulation and procedures in order to keep the environmental impacts and the radiological consequences at the lower possible level and to assure the effectiveness of state nuclear security regime due to possible malicious acts in carrying out these activities including transport and the disposal site at the acceptable international levels. The levels of the estimated doses and risk expectation values for transport and disposal are within the acceptable limits provided by national and international regulations and recommendations but can increase, significantly during potential malicious acts. (authors)

Vieru, Gheorghe [Institute for Nuclear Research, P.O.BOX 78, 0300 PITESTI (Romania)

2012-07-01T23:59:59.000Z

6

Ontario Hydro`s transportation of radioactive material and emergency response plan  

SciTech Connect (OSTI)

Ontario Hydro has been transporting radioactive material for almost 30 years without any exposure to the public or release to the environment. However, there have been three accidents involving Hydro`s shipments of radioactive material. In addition to the quality packaging and shipping program, Ontario Hydro has an Emergency Response Plan and capability to deal with an accident involving a shipment of radioactive material. The Corporation`s ability to respond, to effectively control and contain the situation, site remediation, and to provide emergency public information in the event of a road accident minimizes the risk to the public and the environment. This emphasizes their commitment to worker safety, public safety and impact to the environment. Response capability is mandated under various legislation and regulations in Canada.

Karmali, N. [Ontario Hydro, Toronto, Ontario (Canada). Nuclear Operations Branch

1993-12-31T23:59:59.000Z

7

Regulatory compliance in the design of packages used to transport radioactive materials  

SciTech Connect (OSTI)

Shipments of radioactive materials within the regulatory jurisdiction of the US Department of Energy (DOE) must meet the package design requirements contained in Title 10 of the Code of Federal Regulations, Part 71, and DOE Order 5480.3. These regulations do not provide design criteria requirements, but only detail the approval standards, structural performance criteria, and package integrity requirements that must be met during transport. The DOE recommended design criterion for high-level Category I radioactive packagings is Section III, Division 1, of the ASME Boiler and Pressure Vessel Code. However, alternative design criteria may be used if all the design requirements are satisfied. The purpose of this paper is to review alternatives to the Code criteria and discuss their applicability to the design of containment vessels in packages for high-level radioactive materials. Issues such as design qualification by physical testing, the use of scale models, and problems encountered using a non-ASME design approach are addressed.

Raske, D.T.

1993-06-01T23:59:59.000Z

8

Property Valuation and Radioactive Materials Transportation: A Legal, Economic and Public Perception Analysis  

SciTech Connect (OSTI)

The shipment of transuranic (TRU) radioactive waste to the Waste Isolation Pilot Plant (WIPP) in New Mexico raised a serious socioeconomic issue - the potential devaluation of property values due to the transportation of TRU waste from generator sites to the disposal facility. In 1992, the New Mexico Supreme Court held in City of Santa Fe v. Komis that a loss in value from public perception of risk was compensable. This issue has become an extremely important one for the development of the Yucca Mountain repository in Nevada for disposal of spent nuclear fuel and high-level radioactive waste. Much research has been conducted about the potential impacts of transportation of spent fuel and radioactive waste. This paper examines the pertinent studies conducted since the Komis case. It examines how the public debate on radioactive materials transportation continues and is now focused on transportation of high-level waste and spent nuclear fuel to the proposed Yucca Mountain repository. Finally, the paper suggests a path forward DOE can take to address this issue.

Holm, J. A.; Thrower, A. W.; Widmayer, D. A.; Portner, W.

2003-02-26T23:59:59.000Z

9

A Review of Removable Surface Contamination on Radioactive Materials Transportation Containers  

SciTech Connect (OSTI)

This report contains the results of a study sponsored by the U.S. Nuclear Regulatory Commission (NRC) of removable surface contamination on radioactive materials transportation containers. The purpose of the study is to provide information to the NRC during their review of existing regulations. Data was obtained from both industry and literature on three major topics: 1) radiation doses, 2) economic costs, and 3) contamination frequencies. Containers for four categories of radioactive materials are considered including radiopharmaceuticals, industrial sources, nuclear fuel cycle materials, and low-level radioactive waste. Assumptions made in this study use current information to obtain realistic yet conservative estimates of radiation dose and economic costs. Collective and individual radiation doses are presented for each container category on a per container basis. Total doses, to workers and the public, are also presented for spent fuel cask and low-level waste drum decontamination. Estimates of the additional economic costs incurred by lowering current limits by factors of 10 and 100 are presented. Current contamination levels for each category of container are estimated from the data collected. The information contained in this report is designed to be useful to the NRC in preparing their recommendations for new regulations.

Kennedy, Jr, W. E.; Watson, E. C.; Murphy, D. W.; Harrer, B. J.; Harty, R.; Aldrich, J. M.

1981-05-01T23:59:59.000Z

10

Knowledge Management Initiatives Used to Maintain Regulatory Expertise in Transportation and Storage of Radioactive Materials - 12177  

SciTech Connect (OSTI)

The U.S. Nuclear Regulatory Commission (NRC) was established in 1974 with the mission to license and regulate the civilian use of nuclear materials for commercial, industrial, academic, and medical uses in order to protect public health and safety, and the environment, and promote the common defense and security. Currently, approximately half (?49%) of the workforce at the NRC has been with the Agency for less than six years. As part of the Agency's mission, the NRC has partial responsibility for the oversight of the transportation and storage of radioactive materials. The NRC has experienced a significant level of expertise leaving the Agency due to staff attrition. Factors that contribute to this attrition include retirement of the experienced nuclear workforce and mobility of staff within or outside the Agency. Several knowledge management (KM) initiatives have been implemented within the Agency, with one of them including the formation of a Division of Spent Fuel Storage and Transportation (SFST) KM team. The team, which was formed in the fall of 2008, facilitates capturing, transferring, and documenting regulatory knowledge for staff to effectively perform their safety oversight of transportation and storage of radioactive materials, regulated under Title 10 of the Code of Federal Regulations (10 CFR) Part 71 and Part 72. In terms of KM, the SFST goal is to share critical information among the staff to reduce the impact from staff's mobility and attrition. KM strategies in place to achieve this goal are: (1) development of communities of practice (CoP) (SFST Qualification Journal and the Packaging and Storing Radioactive Material) in the on-line NRC Knowledge Center (NKC); (2) implementation of a SFST seminar program where the seminars are recorded and placed in the Agency's repository, Agency-wide Documents Access and Management System (ADAMS); (3) meeting of technical discipline group programs to share knowledge within specialty areas; (4) development of written guidance to capture 'administrative and technical' knowledge (e.g., office instructions (OIs), generic communications (e.g., bulletins, generic letters, regulatory issue summary), standard review plans (SRPs), interim staff guidance (ISGs)); (5) use of mentoring strategies for experienced staff to train new staff members; (6) use of Microsoft SharePoint portals in capturing, transferring, and documenting knowledge for staff across the Division from Division management and administrative assistants to the project managers, inspectors, and technical reviewers; and (7) development and implementation of a Division KM Plan. A discussion and description of the successes and challenges of implementing these KM strategies at the NRC/SFST will be provided. (authors)

Lindsay, Haile; Garcia-Santos, Norma; Saverot, Pierre; Day, Neil; Gambone Rodriguez, Kimberly; Cruz, Luis; Sotomayor-Rivera, Alexis; Vechioli, Lucieann; Vera, John; Pstrak, David [United States Nuclear Regulatory Commission, Mail Stop EBB-03D-02M, 6003 Executive Boulevard, Rockville, MD 20852 (United States)

2012-07-01T23:59:59.000Z

11

Radioactive Materials License Commitments  

E-Print Network [OSTI]

Radioactive Materials License Commitments for The University of Texas at Austin May 2009 July 2009 in the use of radioactive materials. In July 1963, the State of Texas granted The University of Texas at Austin a broad radioactive materials license for research, development and instruction. While this means

12

Radioactive material (RAM) transportation accident and incident experience in the U.S.A. (1971--1997)  

SciTech Connect (OSTI)

The Radioactive Materials Incident Report (RMIR) database was developed in 1981 at the Transportation Technology Center of Sandia National Laboratories to support its research and development activities for the US Department of Energy (DOE). This database contains information about radioactive materials transportation incidents that have occurred in the US since 1971. These data were drawn from the US Department of Transportation`s (DOT) Hazardous Materials Incident Report system, from Nuclear Regulatory Commission (NRC) files, and from various agencies including state radiological control offices. Support for the RMIR data base is funded by the National Transportation Program (EM-70) of the US Department of Energy. Transportation events in RMIR are classified in one of the following ways: as a transportation accident, as a handling accident, or as a reported incident. This presentation will provide definitions for these classifications and give examples of each. The primary objective of this presentation is to provide information on nuclear materials transportation accident incident events in the US for the period 1971--1997. Among the areas to be examined are: transportation accidents by mode, package response during accidents and an examination of accidents where release of contents has occurred.

McClure, J.D.; Yoshimura, H.R.; Fagan, H.F. [Sandia National Labs., Albuquerque, NM (United States). Transportation Systems Analysis Dept.; Thomas, T. [Dept. of Energy National Transportation Program (United States)

1997-11-01T23:59:59.000Z

13

PATRAM '92: 10th international symposium on the packaging and transportation of radioactive materials [Papers presented by Sandia National Laboratories  

SciTech Connect (OSTI)

This document provides the papers presented by Sandia Laboratories at PATRAM '92, the tenth International symposium on the Packaging and Transportation of Radioactive Materials held September 13--18, 1992 in Yokohama City, Japan. Individual papers have been cataloged separately. (FL)

none,

1992-01-01T23:59:59.000Z

14

Waste management facilities cost information for transportation of radioactive and hazardous materials  

SciTech Connect (OSTI)

This report contains cost information on the U.S. Department of Energy (DOE) Complex waste streams that will be addressed by DOE in the programmatic environmental impact statement (PEIS) project. It describes the results of the task commissioned by DOE to develop cost information for transportation of radioactive and hazardous waste. It contains transportation costs for most types of DOE waste streams: low-level waste (LLW), mixed low-level waste (MLLW), alpha LLW and alpha MLLW, Greater-Than-Class C (GTCC) LLW and DOE equivalent waste, transuranic (TRU) waste, spent nuclear fuel (SNF), and hazardous waste. Unit rates for transportation of contact-handled (<200 mrem/hr contact dose) and remote-handled (>200 mrem/hr contact dose) radioactive waste are estimated. Land transportation of radioactive and hazardous waste is subject to regulations promulgated by DOE, the U.S. Department of Transportation (DOT), the U.S. Nuclear Regulatory Commission (NRC), and state and local agencies. The cost estimates in this report assume compliance with applicable regulations.

Feizollahi, F.; Shropshire, D.; Burton, D.

1995-06-01T23:59:59.000Z

15

Radiation Machines and Radioactive Materials (Iowa)  

Broader source: Energy.gov [DOE]

These chapters describe general provisions and regulatory requirements; registration, licensure, and transportation of radioactive materials; and exposure standards for radiation protection.

16

Radiation Sources and Radioactive Materials (Connecticut)  

Broader source: Energy.gov [DOE]

These regulations apply to persons who receive, transfer, possess, manufacture, use, store, handle, transport or dispose of radioactive materials and/or sources of ionizing radiation. Some...

17

Radioactive waste material melter apparatus  

DOE Patents [OSTI]

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another.

Newman, Darrell F. (Richland, WA); Ross, Wayne A. (Richland, WA)

1990-01-01T23:59:59.000Z

18

Radioactive waste material melter apparatus  

DOE Patents [OSTI]

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs.

Newman, D.F.; Ross, W.A.

1990-04-24T23:59:59.000Z

19

Helpful links for materials transport, safety, etc.  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Helpful links for materials transport, safety, etc. relating to experiment safety at the APS. Internal Reference Material: Transporting Hazardous Materials "Natural" radioactivity...

20

DOE Partnerships with States, Tribes and Other Federal Programs Help Responders Prepare for Challenges Involving Transport of Radioactive Materials  

SciTech Connect (OSTI)

DOE Partnerships with States, Tribes and Other Federal Programs Help Responders Prepare for Challenges Involving Transport of Radioactive Materials Implementing adequate institutional programs and validating preparedness for emergency response to radiological transportation incidents along or near U.S. Department of Energy (DOE) shipping corridors poses unique challenges to transportation operations management. Delayed or insufficient attention to State and Tribal preparedness needs may significantly impact the transportation operations schedule and budget. The DOE Transportation Emergency Preparedness Program (TEPP) has successfully used a cooperative planning process to develop strong partnerships with States, Tribes, Federal agencies and other national programs to support responder preparedness across the United States. DOE TEPP has found that building solid partnerships with key emergency response agencies ensures responders have access to the planning, training, technical expertise and assistance necessary to safely, efficiently and effectively respond to a radiological transportation accident. Through the efforts of TEPP over the past fifteen years, partnerships have resulted in States and Tribal Nations either using significant portions of the TEPP planning resources in their programs and/or adopting the Modular Emergency Response Radiological Transportation Training (MERRTT) program into their hazardous material training curriculums to prepare their fire departments, law enforcement, hazardous materials response teams, emergency management officials, public information officers and emergency medical technicians for responding to transportation incidents involving radioactive materials. In addition, through strong partnerships with Federal Agencies and other national programs TEPP provided technical expertise to support a variety of radiological response initiatives and assisted several programs with integration of the nationally recognized MERRTT program into other training venues, thus ensuring consistency of radiological response curriculums delivered to responders. This presentation will provide an overview of the steps to achieve coordination, to avoid redundancy, and to highlight several of the successful partnerships TEPP has formed with States, Tribes, Federal agencies and other national programs. Events, accident scenarios, and training where TEPP was proven to be integral in building the radiological response capabilities for first responders to actual radiological incidents are also highlighted. Participants will gain an appreciation for the collaborative efforts States and Tribes are engaging in with the DOE to ensure that responders all along the DOE transportation corridors are adequately prepared to respond to shipments of radioactive materials through their communities.

Marsha Keister

2001-02-01T23:59:59.000Z

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


21

Definition of Small Gram Quantity Contents for Type B Radioactive Material Transportation Packages: Activity-Based Content Limitations  

SciTech Connect (OSTI)

Since the 1960's, the Department of Transportation Specification (DOT Spec) 6M packages have been used extensively for transportation of Type B quantities of radioactive materials between Department of Energy (DOE) facilities, laboratories, and productions sites. However, due to the advancement of packaging technology, the aging of the 6M packages, and variability in the quality of the packages, the DOT implemented a phased elimination of the 6M specification packages (and other DOT Spec packages) in favor of packages certified to meet federal performance requirements. DOT issued the final rule in the Federal Register on October 1, 2004 requiring that use of the DOT Specification 6M be discontinued as of October 1, 2008. A main driver for the change was the fact that the 6M specification packagings were not supported by a Safety Analysis Report for Packaging (SARP) that was compliant with Title 10 of the Code of Federal Regulations part 71 (10 CFR 71). Therefore, materials that would have historically been shipped in 6M packages are being identified as contents in Type B (and sometimes Type A fissile) package applications and addenda that are to be certified under the requirements of 10 CFR 71. The requirements in 10 CFR 71 include that the Safety Analysis Report for Packaging (SARP) must identify the maximum radioactivity of radioactive constituents and maximum quantities of fissile constituents (10 CFR 71.33(b)(1) and 10 CFR 71.33(b)(2)), and that the application (i.e., SARP submittal or SARP addendum) demonstrates that the external dose rate (due to the maximum radioactivity of radioactive constituents and maximum quantities of fissile constituents) on the surface of the packaging (i.e., package and contents) not exceed 200 mrem/hr (10 CFR 71.35(a), 10 CFR 71.47(a)). It has been proposed that a 'Small Gram Quantity' of radioactive material be defined, such that, when loaded in a transportation package, the dose rates at external points of an unshielded packaging not exceed the regulatory limits prescribed by 10 CFR 71 for non-exclusive shipments. The mass of each radioisotope presented in this paper is limited by the radiation dose rate on the external surface of the package, which per the regulatory limit should not exceed 200 mrem/hr. The results presented are a compendium of allowable masses of a variety of different isotopes (with varying impurity levels of beryllium in some of the actinide isotopes) that, when loaded in an unshielded packaging, do not result in an external dose rate on the surface of the package that exceeds 190 mrem/hr (190 mrem/hr was chosen to provide 5% conservatism relative to the regulatory limit). These mass limits define the term 'Small Gram Quantity' (SGQ) contents in the context of radioactive material transportation packages. The term SGQ is isotope-specific and pertains to contents in radioactive material transportation packages that do not require shielding and still satisfy the external dose rate requirements. Since these calculated mass limits are for contents without shielding, they are conservative for packaging materials that provide some limited shielding or if the contents are placed into a shielded package. The isotopes presented in this paper were chosen as the isotopes that Department of Energy (DOE) sites most likely need to ship. Other more rarely shipped isotopes, along with industrial and medical isotopes, are planned to be included in subsequent extensions of this work.

Sitaraman, S; Kim, S; Biswas, D; Hafner, R; Anderson, B

2010-10-27T23:59:59.000Z

22

Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multimodal transportation network  

SciTech Connect (OSTI)

Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, and focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

23

Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multi-modal transportation network  

SciTech Connect (OSTI)

Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, all focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

2010-10-28T23:59:59.000Z

24

Fate and transport processes controlling the migration of hazardous and radioactive materials from the Area 5 Radioactive Waste Management Site (RWMS)  

SciTech Connect (OSTI)

Desert vadose zones have been considered as suitable environments for the safe and long-term isolation of hazardous wastes. Low precipitation, high evapotranspiration and thick unsaturated alluvial deposits commonly found in deserts make them attractive as waste disposal sites. The fate and transport of any contaminant in the subsurface is ultimately determined by the operating retention and transformation processes in the system and the end result of the interactions among them. Retention (sorption) and transformation are the two major processes that affect the amount of a contaminant present and available for transport. Retention processes do not affect the total amount of a contaminant in the soil system, but rather decrease or eliminate the amount available for transport at a given point in time. Sorption reactions retard the contaminant migration. Permanent binding of solute by the sorbent is also possible. These processes and their interactions are controlled by the nature of the hazardous waste, the properties of the porous media and the geochemical and environmental conditions (temperature, moisture and vegetation). The present study summarizes the available data and investigates the fate and transport processes that govern the migration of contaminants from the Radioactive Waste Management Site (RWMS) in Area 5 of the Nevada Test Site (NTS). While the site is currently used only for low-level radioactive waste disposal, past practices have included burial of material now considered hazardous. Fundamentals of chemical and biological transformation processes are discussed subsequently, followed by a discussion of relevant results.

Estrella, R.

1994-10-01T23:59:59.000Z

25

Container for radioactive materials  

DOE Patents [OSTI]

A container is claimed for housing a plurality of canister assemblies containing radioactive material. The several canister assemblies are stacked in a longitudinally spaced relation within a carrier to form a payload concentrically mounted within the container. The payload package includes a spacer for each canister assembly, said spacer comprising a base member longitudinally spacing adjacent canister assemblies from each other and sleeve surrounding the associated canister assembly for centering the same and conducting heat from the radioactive material in a desired flow path. 7 figures.

Fields, S.R.

1984-05-30T23:59:59.000Z

26

Assessment of Quality Assurance Measures for Radioactive Material Transport Packages not Requiring Competent Authority Design Approval - 13282  

SciTech Connect (OSTI)

The majority of transports of radioactive materials are carried out in packages which don't need a package design approval by a competent authority. Low-active radioactive materials are transported in such packages e.g. in the medical and pharmaceutical industry and in the nuclear industry as well. Decommissioning of NPP's leads to a strong demand for packages to transport low and middle active radioactive waste. According to IAEA regulations the 'non-competent authority approved package types' are the Excepted Packages and the Industrial Packages of Type IP-1, IP-2 and IP-3 and packages of Type A. For these types of packages an assessment by the competent authority is required for the quality assurance measures for the design, manufacture, testing, documentation, use, maintenance and inspection (IAEA SSR 6, Chap. 306). In general a compliance audit of the manufacturer of the packaging is required during this assessment procedure. Their regulatory level in the IAEA regulations is not comparable with the 'regulatory density' for packages requiring competent authority package design approval. Practices in different countries lead to different approaches within the assessment of the quality assurance measures in the management system as well as in the quality assurance program of a special package design. To use the package or packaging in a safe manner and in compliance with the regulations a management system for each phase of the life of the package or packaging is necessary. The relevant IAEA-SSR6 chap. 801 requires documentary verification by the consignor concerning package compliance with the requirements. (authors)

Komann, Steffen; Groeke, Carsten; Droste, Bernhard [BAM Federal Institute for Materials Research and Testing, Unter den Eichen 44-46, 12203 Berlin (Germany)] [BAM Federal Institute for Materials Research and Testing, Unter den Eichen 44-46, 12203 Berlin (Germany)

2013-07-01T23:59:59.000Z

27

COGEMA operating experience in the transportation of spent fuel, nuclear materials and radioactive waste  

SciTech Connect (OSTI)

Were a spent fuel transportation accident to occur, no matter how insignificant, the public outcry could jeopardize both reprocessing operations and power plant operations for utilities that have elected to reprocess their spent fuel. Aware of this possibility, COGEMA has become deeply involved in spent fuel transportation to ensure that it is performed according to the highest standards of transportation safety. Spent fuel transportation is a vital link between the reactor site and the reprocessing plant. This paper gives an overview of COGEMA`s experience in the transportation of spent fuel.

Bernard, H. [COGEMA, Velizy-Villacoublay (France)

1993-12-31T23:59:59.000Z

28

INMM 55th Annual Meeting, July 2024, 2014, Atlanta Marriott Marquis, Atlanta, Georgia, USA Transport Security for Nuclear and Other Radioactive Materials --A DOE Training Course  

E-Print Network [OSTI]

Laboratory. The course was developed by Argonne for the U.S. Department of Energy Packaging Certification of Energy, Washington, D.C. 20585 ABSTRACT In early December of 2013, a weeklong training course on security Transport Security for Nuclear and Other Radioactive Materials -- A DOE Training Course Ronald B. Pope, Yung

Kemner, Ken

29

TRESS: A Transportable Radioactive Effluent Solidification System  

SciTech Connect (OSTI)

This paper describes an attempt to produce a totally new concept for a transportable plant capable of encapsulating radioactive sludges and ion exchange resins, employing recently developed dewatering and mixing techniques. One of the prime aims of the investigation was to produce a plant which could handle both beta/gamma and alpha-bearing materials.

Sims, J. [BBN Environmental Management Ltd., Bramhall (United Kingdom). WasteChem Div.; Schneider, K. [NUKEM GmbH, Alzenau (Germany)

1993-12-31T23:59:59.000Z

30

Storage depot for radioactive material  

DOE Patents [OSTI]

Vertical drilling of cylindrical holes in the soil, and the lining of such holes, provides storage vaults called caissons. A guarded depot is provided with a plurality of such caissons covered by shielded closures preventing radiation from penetrating through any linear gap to the atmosphere. The heat generated by the radioactive material is dissipated through the vertical liner of the well into the adjacent soil and thus to the ground surface so that most of the heat from the radioactive material is dissipated into the atmosphere in a manner involving no significant amount of biologically harmful radiation. The passive cooling of the radioactive material without reliance upon pumps, personnel, or other factor which might fail, constitutes one of the most advantageous features of this system. Moreover this system is resistant to damage from tornadoes or earthquakes. Hermetically sealed containers of radioactive material may be positioned in the caissons. Loading vehicles can travel throughout the depot to permit great flexibility of loading and unloading radioactive materials. Radioactive material can be shifted to a more closely spaced caisson after ageing sufficiently to generate much less heat. The quantity of material stored in a caisson is restricted by the average capacity for heat dissipation of the soil adjacent such caisson.

Szulinski, Milton J. (Richland, WA)

1983-01-01T23:59:59.000Z

31

Radiation Awareness TrainingRadiation Awareness Training Radioactive Material &Radioactive Material &  

E-Print Network [OSTI]

quarterly · Radioactive waste retrieval, storage, disposal · Dosimetry exchange · Leak tests of sealedRadiation Awareness TrainingRadiation Awareness Training Radioactive Material &Radioactive Material, Chemistry, Physics, Applied Physiology · Radioactive Material ­ Sealed Sources, Unsealed Sources (liquid

Sherrill, David

32

Completion of the Radioactive Materials Packaging Handbook  

SciTech Connect (OSTI)

The Radioactive Materials Packaging Handbook: Design, Operation and Maintenance, which will serve as a replacement for the Cask Designers Guide (Shappert, 1970), has now been completed and submitted to the Oak Ridge National Laboratory (ORNL) electronics publishing group for layout and printing; it is scheduled to be printed in late spring 1998. The Handbook, written by experts in their particular fields, is a compilation of technical chapters that address the design aspects of a package intended for transporting radioactive material in normal commerce; it was prepared under the direction of M. E. Wangler of the US Department of Energy (DOE) and is intended to provide a wealth of technical guidance that will give designers a better understanding of the regulatory approval process, preferences of regulators on specific aspects of package design, and the types of analyses that should be considered when designing a package to carry radioactive materials.

Shappert, L.B.

1998-02-01T23:59:59.000Z

33

Transporting particulate material  

DOE Patents [OSTI]

A material transporting system comprises a material transporting apparatus (100) including a material transporting apparatus hopper structure (200, 202), which comprises at least one rotary transporting apparatus; a stationary hub structure (900) constraining and assisting the at least one rotary transporting apparatus; an outlet duct configuration (700) configured to permit material to exit therefrom and comprising at least one diverging portion (702, 702'); an outlet abutment configuration (800) configured to direct material to the outlet duct configuration; an outlet valve assembly from the material transporting system venting the material transporting system; and a moving wall configuration in the material transporting apparatus capable of assisting the material transporting apparatus in transporting material in the material transporting system. Material can be moved from the material transporting apparatus hopper structure to the outlet duct configuration through the at least one rotary transporting apparatus, the outlet abutment configuration, and the outlet valve assembly.

Aldred, Derek Leslie (North Hollywood, CA); Rader, Jeffrey A. (North Hollywood, CA); Saunders, Timothy W. (North Hollywood, CA)

2011-08-30T23:59:59.000Z

34

Radioactive waste material disposal  

DOE Patents [OSTI]

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

1995-10-24T23:59:59.000Z

35

Radioactive waste material disposal  

DOE Patents [OSTI]

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.

Forsberg, Charles W. (155 Newport Dr., Oak Ridge, TN 37830); Beahm, Edward C. (106 Cooper Cir., Oak Ridge, TN 37830); Parker, George W. (321 Dominion Cir., Knoxville, TN 37922)

1995-01-01T23:59:59.000Z

36

Hazardous Materials Packaging and Transportation Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The Order establishes safety requirements for the proper packaging and transportation of Department of offsite shipments and onsite transfers of radioactive and other hazardous materials, and for modal transportation.

2015-04-20T23:59:59.000Z

37

Storage containers for radioactive material  

DOE Patents [OSTI]

A radioactive material storage system for use in the laboratory having a flat base plate with a groove in one surface thereof and a hollow pedestal extending perpendicularly away from the other surface thereof, a sealing gasket in the groove, a cover having a filter therein and an outwardly extending flange which fits over the plate, the groove and the gasket, and a clamp for maintaining the cover and the plate sealed together, whereby the plate and the cover and the clamp cooperate to provide a storage area for radioactive material readily accessible for use or

Groh, Edward F. (Naperville, IL); Cassidy, Dale A. (Valparaiso, IN); Dates, Leon R. (Elmwood Park, IL)

1981-01-01T23:59:59.000Z

38

Storage containers for radioactive material  

DOE Patents [OSTI]

A radioactive material storage system is claimed for use in the laboratory having a flat base plate with a groove in one surface thereof and a hollow pedestal extending perpendicularly away from the other surface thereof, a sealing gasket in the groove, a cover having a filter therein and an outwardly extending flange which fits over the plate, the groove and the gasket, and a clamp for maintaining the cover and the plate sealed together. The plate and the cover and the clamp cooperate to provide a storage area for radioactive material readily accessible for use or inventory. Wall mounts are provided to prevent accidental formation of critical masses during storage.

Groh, E.F.; Cassidy, D.A.; Dates, L.R.

1980-07-31T23:59:59.000Z

39

Annual Transportation Report for Radioactive Waste Shipments...  

National Nuclear Security Administration (NNSA)

ANNUAL TRANSPORTATION REPORT FY 2008 Radioactive Waste Shipments to and from the Nevada Test Site (NTS) February 2009 United States Department of Energy National Nuclear Security...

40

Radioactive material package seal tests  

SciTech Connect (OSTI)

General design or test performance requirements for radioactive materials (RAM) packages are specified in Title 10 of the US Code of Federal Regulations Part 71 (US Nuclear Regulatory Commission, 1983). The requirements for Type B packages provide a broad range of environments under which the system must contain the RAM without posing a threat to health or property. Seals that provide the containment system interface between the packaging body and the closure must function in both high- and low-temperature environments under dynamic and static conditions. A seal technology program, jointly funded by the US Department of Energy Office of Environmental Restoration and Waste Management (EM) and the Office of Civilian Radioactive Waste Management (OCRWM), was initiated at Sandia National Laboratories. Experiments were performed in this program to characterize the behavior of several static seal materials at low temperatures. Helium leak tests on face seals were used to compare the materials. Materials tested include butyl, neoprene, ethylene propylene, fluorosilicone, silicone, Eypel, Kalrez, Teflon, fluorocarbon, and Teflon/silicone composites. Because most elastomer O-ring applications are for hydraulic systems, manufacturer low-temperature ratings are based on methods that simulate this use. The seal materials tested in this program with a fixture similar to a RAM cask closure, with the exception of silicone S613-60, are not leak tight (1.0 {times} 10{sup {minus}7} std cm{sup 3}/s) at manufacturer low-temperature ratings. 8 refs., 3 figs., 1 tab.

Madsen, M.M.; Humphreys, D.L.; Edwards, K.R.

1990-01-01T23:59:59.000Z

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


41

Laboratory Surveys when Working with Radioactive Materials  

E-Print Network [OSTI]

radioactive materials (RAM) are used or stored, including waste areas. Negative results should be clearlyLaboratory Surveys when Working with Radioactive Materials Procedure: 7.546 Created: 9/25/14 Version: 1.0 Revised: Environmental Health & Safety Page 1 of 6 A. Purpose Radioactive contamination and

Jia, Songtao

42

Spills of Radioactive Materials -Emergency Procedures  

E-Print Network [OSTI]

to radioactive waste container. For surface decontamination, use soap and water and cleansers appropriateSpills of Radioactive Materials - Emergency Procedures Procedure: 7.53 Created: 1/16/2014 Version for injured personnel. B. Applicability/scope This policy applies to all facilities where radioactive

Jia, Songtao

43

August 1999 Radiation Safety Manual Section 12 Shipment of Radioactive Materials  

E-Print Network [OSTI]

August 1999 Radiation Safety Manual Section 12 ­ Shipment of Radioactive Materials UW Environmental Health and Safety Page 12-1 Section 12 Shipment of Radioactive Materials Contents A. Shipping Regulations regulations for the safe transportation of radioactive materials. These regulations are adopted from those

Wilcock, William

44

Radioactive Material Use at the EMSL Radiochemistry Annex The EMSL Radiochemistry Annex, located in the 3410 Material Science and  

E-Print Network [OSTI]

contamination during transportation. Dispersible radioactive material must be placed in rigid, leak- tight inner be sufficient such that EMSL staff will not encounter radioactive contamination when they open the shippingRadioactive Material Use at the EMSL Radiochemistry Annex The EMSL Radiochemistry Annex, located

45

RADIOACTIVE MATERIAL PACKAGING TORQUE REQUIREMENTS COMPLIANCE  

SciTech Connect (OSTI)

Shipping containers used to transport radioactive material (RAM) in commerce employ a variety of closure mechanisms. Often, these closure mechanisms require a specific amount of torque be applied to a bolt, nut or other threaded fastener. It is important that the required preload is achieved so that the package testing and analysis is not invalidated for the purpose of protecting the public. Torque compliance is a means of ensuring closure preload, is a major factor in accomplishing the package functions of confinement/containment, sub-criticality, and shielding. This paper will address the importance of applying proper torque to package closures, discuss torque value nomenclature, and present one methodology to ensure torque compliance is achieved.

Watkins, R.; Leduc, D.

2011-03-24T23:59:59.000Z

46

Radioactive materials shipping cask anticontamination enclosure  

DOE Patents [OSTI]

An anticontamination device for use in storing shipping casks for radioactive materials comprising (1) a seal plate assembly; (2) a double-layer plastic bag; and (3) a water management system or means for water management.

Belmonte, Mark S. (Irwin, PA); Davis, James H. (Pittsburgh, PA); Williams, David A. (Pittsburgh, PA)

1982-01-01T23:59:59.000Z

47

Radioactive Material Use at the EMSL Radiochemistry Annex  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Dispersible radioactive material must be placed in rigid, leak- tight inner containers (e.g., durable screw-top sample jars). Non-dispersible radioactive material may...

48

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both radioactive materials  

E-Print Network [OSTI]

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both as noted on the list, you do not have a mixed waste and it may be managed as a normal radioactive waste radioactive waste after initially dating the container, the hold for decay time is extended, but you cannot

Straight, Aaron

49

Priorities for technology development and policy to reduce the risk from radioactive materials.  

SciTech Connect (OSTI)

The Standing Committee on International Security of Radioactive and Nuclear Materials in the Nonproliferation and Arms Control Division conducted its fourth annual workshop in February 2010 on Reducing the Risk from Radioactive and Nuclear Materials. This workshop examined new technologies in real-time tracking of radioactive materials, new risks and policy issues in transportation security, the best practices and challenges found in addressing illicit radioactive materials trafficking, industry leadership in reducing proliferation risk, and verification of the Nuclear Nonproliferation Treaty, Article VI. Technology gaps, policy gaps, and prioritization for addressing the identified gaps were discussed. Participants included academia, policy makers, radioactive materials users, physical security and safeguards specialists, and vendors of radioactive sources and transportation services. This paper summarizes the results of this workshop with the recommendations and calls to action for the Institute of Nuclear Materials Management (INMM) membership community.

Duggan, Ruth Ann

2010-06-01T23:59:59.000Z

50

Radioactive Material or Multiple Hazardous Materials Decontamination |  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG |September 15,2015 | DepartmentLoansDepartment of Energy Radioactive

51

Handbook of high-level radioactive waste transportation  

SciTech Connect (OSTI)

The High-Level Radioactive Waste Transportation Handbook serves as a reference to which state officials and members of the general public may turn for information on radioactive waste transportation and on the federal government`s system for transporting this waste under the Civilian Radioactive Waste Management Program. The Handbook condenses and updates information contained in the Midwestern High-Level Radioactive Waste Transportation Primer. It is intended primarily to assist legislators who, in the future, may be called upon to enact legislation pertaining to the transportation of radioactive waste through their jurisdictions. The Handbook is divided into two sections. The first section places the federal government`s program for transporting radioactive waste in context. It provides background information on nuclear waste production in the United States and traces the emergence of federal policy for disposing of radioactive waste. The second section covers the history of radioactive waste transportation; summarizes major pieces of legislation pertaining to the transportation of radioactive waste; and provides an overview of the radioactive waste transportation program developed by the US Department of Energy (DOE). To supplement this information, a summary of pertinent federal and state legislation and a glossary of terms are included as appendices, as is a list of publications produced by the Midwestern Office of The Council of State Governments (CSG-MW) as part of the Midwestern High-Level Radioactive Waste Transportation Project.

Sattler, L.R.

1992-10-01T23:59:59.000Z

52

The radioactive materials packaging handbook: Design, operations, and maintenance  

SciTech Connect (OSTI)

As part of its required activities in 1994, the US Department of Energy (DOE) made over 500,000 shipments. Of these shipments, approximately 4% were hazardous, and of these, slightly over 1% (over 6,400 shipments) were radioactive. Because of DOE`s cleanup activities, the total quantities and percentages of radioactive material (RAM) that must be moved from one site to another is expected to increase in the coming years, and these materials are likely to be different than those shipped in the past. Irradiated fuel will certainly be part of the mix as will RAM samples and waste. However, in many cases these materials will be of different shape and size and require a transport packaging having different shielding, thermal, and criticality avoidance characteristics than are currently available. This Handbook provides guidance on the design, testing, certification, and operation of packages for these materials.

Shappert, L.B.; Bowman, S.M. [Oak Ridge National Lab., TN (United States); Arnold, E.D. [Lockheed Martin Energy Systems, Oak Ridge, TN (United States)] [and others

1998-08-01T23:59:59.000Z

53

South Carolina Radioactive Waste Transportation and Disposal Act (South Carolina)  

Broader source: Energy.gov [DOE]

The Department of Health and Environmental Control is responsible for regulating the transportation of radioactive waste, with some exceptions, into or within the state for storage, disposal, or...

54

RECERTIFICATION OF THE MODEL 9977 RADIOACTIVE MATERIAL PACKAGING  

SciTech Connect (OSTI)

The Model 9977 Packaging was initially issued a Certificate of Compliance (CoC) by the Department of Energys Office of Environmental Management (DOE-EM) for the transportation of radioactive material (RAM) in the Fall of 2007. This first CoC was for a single radioactive material and two packing configurations. In the five years since that time, seven Addendums have been written to the Safety Analysis Report for Packaging (SARP) and five Letter Amendments have been written that have authorized either new RAM contents or packing configurations, or both. This paper will discuss the process of updating the 9977 SARP to include all the contents and configurations, including the addition of a new content, and its submittal for recertification.

Abramczyk, G.; Bellamy, S.; Loftin, B.; Nathan, S.

2013-06-05T23:59:59.000Z

55

Film Badge Application Radioactive Material Package Receipt Log  

E-Print Network [OSTI]

;RADIOACTIVE MATERIAL PACKAGE RECEIPT LOG DATE: DELIVERED BY: AUTHORIZED BY: Contamination Check DPM/100 cm2APPENDIX A Film Badge Application Radioactive Material Package Receipt Log Radioactive Material Package Receipt Form (Off-Campus Locations) Radiation / Contamination Survey Form #12;PERSONNEL MONITORING

Slatton, Clint

56

Corrosion resistant storage container for radioactive material  

DOE Patents [OSTI]

A corrosion resistant long-term storage container for isolating radioactive waste material in a repository. The container is formed of a plurality of sealed corrosion resistant canisters of different relative sizes, with the smaller canisters housed within the larger canisters, and with spacer means disposed between judxtaposed pairs of canisters to maintain a predetermined spacing between each of the canisters. The combination of the plural surfaces of the canisters and the associated spacer means is effective to make the container capable of resisting corrosion, and thereby of preventing waste material from leaking from the innermost canister into the ambient atmosphere.

Schweitzer, Donald G. (Bayport, NY); Davis, Mary S. (Wading River, NY)

1990-01-01T23:59:59.000Z

57

Corrosion resistant storage container for radioactive material  

DOE Patents [OSTI]

A corrosion resistant long-term storage container for isolating high-level radioactive waste material in a repository is claimed. The container is formed of a plurality of sealed corrosion resistant canisters of different relative sizes, with the smaller canisters housed within the larger canisters, and with spacer means disposed between juxtaposed pairs of canisters to maintain a predetermined spacing between each of the canisters. The combination of the plural surfaces of the canisters and the associated spacer means is effective to make the container capable of resisting corrosion, and thereby of preventing waste material from leaking from the innermost canister into the ambient atmosphere.

Schweitzer, D.G.; Davis, M.S.

1984-08-30T23:59:59.000Z

58

Hanford Site radioactive hazardous materials packaging directory  

SciTech Connect (OSTI)

The Hanford Site Radioactive Hazardous Materials Packaging Directory (RHMPD) provides information concerning packagings owned or routinely leased by Westinghouse Hanford Company (WHC) for offsite shipments or onsite transfers of hazardous materials. Specific information is provided for selected packagings including the following: general description; approval documents/specifications (Certificates of Compliance and Safety Analysis Reports for Packaging); technical information (drawing numbers and dimensions); approved contents; areas of operation; and general information. Packaging Operations & Development (PO&D) maintains the RHMPD and may be contacted for additional information or assistance in obtaining referenced documentation or assistance concerning packaging selection, availability, and usage.

McCarthy, T.L.

1995-12-01T23:59:59.000Z

59

Cask for radioactive material and method for preventing release of neutrons from radioactive material  

SciTech Connect (OSTI)

A cask for radioactive material, such as nuclear reactor fuel or spent nuclear reactor fuel, includes a plurality of associated walled internal compartments for containing such radioactive material, with neutron absorbing material present to absorb neutrons emitted by the radioactive material, and a plurality of thermally conductive members, such as longitudinal copper or aluminum castings, about the compartment and in thermal contact with the compartment walls and with other such thermally conductive members and having thermal contact surfaces between such members extending, preferably radially, from the compartment walls to external surfaces of the thermally conductive members, which surfaces are preferably in the form of a cylinder. The ends of the shipping cask also preferably include a neutron absorber and a conductive metal covering to dissipate heat released by decay of the radioactive material. A preferred neutron absorber utilized is boron carbide, preferably as plasma sprayed with metal powder or as particles in a matrix of phenolic polymer, and the compartment walls are preferably of stainless steel, copper or other corrosion resistant and heat conductive metal or alloy. The invention also relates to shipping casks, storage casks and other containers for radioactive materials in which a plurality of internal compartments for such material, e.g., nuclear reactor fuel rods, are joined together, preferably in modular construction with surrounding heat conductive metal members, and the modules are joined together to form a major part of a finished shipping cask, which is preferably of cylindrical shape. Also within the invention are methods of safely storing radioactive materials which emit neutrons, while dissipating the heat thereof, and of manufacturing the present shipping casks.

Gaffney, M.F.; Shaffer, P.T.

1981-09-29T23:59:59.000Z

60

Enhancing Railroad Hazardous Materials Transportation Safety...  

Office of Environmental Management (EM)

Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing Presentation made by Kevin...

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


61

Radioactive Material Declaration Form Exhibit to the Radioactive Waste Manual (RWM)  

E-Print Network [OSTI]

Radioactive Material Declaration Form Exhibit to the Radioactive Waste Manual (RWM) 12/5/2013 (form Declaration Form Exhibit to the Radioactive Waste Manual (RWM) 12/5/2013 (form date) SLAC-I-760-2A08Z-001 (RWM date) SLAC-I-760-2A08Z-001 (RWM number) Page 1 of 2 RADIOACTIVE MATERIAL DECLARATION FORM For RP use

Wechsler, Risa H.

62

Office of Civilian Radioactive Waste Management Transportation...  

Broader source: Energy.gov (indexed) [DOE]

Jay Jones Office of Civilian Radioactive Waste Management April 22, 2004 Albuquerque, New Mexico 2 Session Overview * Meeting objectives and expectations * Topic Group...

63

Introduction to naturally occurring radioactive material  

SciTech Connect (OSTI)

Naturally occurring radioactive material (NORM) is everywhere; we are exposed to it every day. It is found in our bodies, the food we eat, the places where we live and work, and in products we use. We are also bathed in a sea of natural radiation coming from the sun and deep space. Living systems have adapted to these levels of radiation and radioactivity. But some industrial practices involving natural resources concentrate these radionuclides to a degree that they may pose risk to humans and the environment if they are not controlled. Other activities, such as flying at high altitudes, expose us to elevated levels of NORM. This session will concentrate on diffuse sources of technologically-enhanced (TE) NORM, which are generally large-volume, low-activity waste streams produced by industries such as mineral mining, ore benefication, production of phosphate Fertilizers, water treatment and purification, and oil and gas production. The majority of radionuclides in TENORM are found in the uranium and thorium decay chains. Radium and its subsequent decay products (radon) are the principal radionuclides used in characterizing the redistribution of TENORM in the environment by human activity. We will briefly review other radionuclides occurring in nature (potassium and rubidium) that contribute primarily to background doses. TENORM is found in many waste streams; for example, scrap metal, sludges, slags, fluids, and is being discovered in industries traditionally not thought of as affected by radionuclide contamination. Not only the forms and volumes, but the levels of radioactivity in TENORM vary. Current discussions about the validity of the linear no dose threshold theory are central to the TENORM issue. TENORM is not regulated by the Atomic Energy Act or other Federal regulations. Control and regulation of TENORM is not consistent from industry to industry nor from state to state. Proposed regulations are moving from concentration-based standards to dose-based standards. So when is TENORM a problem? Where is it a problem? That depends on when, where, and whom you talk to! We will start by reviewing background radioactivity, then we will proceed to the geology, mobility, and variability of these radionuclides. We will then review some of the industrial sectors affected by TENORM, followed by a brief discussion on regulatory aspects of the issue.

Egidi, P.

1997-08-01T23:59:59.000Z

64

NEW APPROACH TO ADDRESSING GAS GENERATION IN RADIOACTIVE MATERIAL PACKAGING  

SciTech Connect (OSTI)

Safety Analysis Reports for Packaging (SARP) document why the transportation of radioactive material is safe in Type A(F) and Type B shipping containers. The content evaluation of certain actinide materials require that the gas generation characteristics be addressed. Most packages used to transport actinides impose extremely restrictive limits on moisture content and oxide stabilization to control or prevent flammable gas generation. These requirements prevent some users from using a shipping container even though the material to be shipped is fully compliant with the remaining content envelope including isotopic distribution. To avoid these restrictions, gas generation issues have to be addressed on a case by case basis rather than a one size fits all approach. In addition, SARP applicants and review groups may not have the knowledge and experience with actinide chemistry and other factors affecting gas generation, which facility experts in actinide material processing have obtained in the last sixty years. This paper will address a proposal to create a Gas Generation Evaluation Committee to evaluate gas generation issues associated with Safety Analysis Reports for Packaging material contents. The committee charter could include reviews of both SARP approved contents and new contents not previously evaluated in a SARP.

Watkins, R; Leduc, D; Askew, N

2009-06-25T23:59:59.000Z

65

Transportation Security | ornl.gov  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Transportation Security SHARE Global Threat Reduction Initiative Transportation Security Cooperation Secure Transport Operations (STOP) Box Security of radioactive material while...

66

Transporting Hazardous Materials  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassiveSubmittedStatusButlerTransportation From modeling and simulationTransporting

67

Apparatus for transporting hazardous materials  

DOE Patents [OSTI]

An apparatus and method are provided for selectively receiving, transporting, and releasing one or more radioactive or other hazardous samples for analysis on a differential thermal analysis (DTA) apparatus. The apparatus includes a portable sample transporting apparatus for storing and transporting the samples and includes a support assembly for supporting the transporting apparatus when a sample is transferred to the DTA apparatus. The transporting apparatus includes a storage member which includes a plurality of storage chambers arrayed circumferentially with respect to a central axis. An adjustable top door is located on the top side of the storage member, and the top door includes a channel capable of being selectively placed in registration with the respective storage chambers thereby permitting the samples to selectively enter the respective storage chambers. The top door, when closed, isolates the respective samples within the storage chambers. A plurality of spring-biased bottom doors are located on the bottom sides of the respective storage chambers. The bottom doors isolate the samples in the respective storage chambers when the bottom doors are in the closed position. The bottom doors permit the samples to leave the respective storage chambers from the bottom side when the respective bottom doors are in respective open positions. The bottom doors permit the samples to be loaded into the respective storage chambers after the analysis for storage and transport to a permanent storage location.

Osterman, Robert A. (Canonsburg, PA); Cox, Robert (West Mifflin, PA)

1992-01-01T23:59:59.000Z

68

One million curies of radioactive material recovered  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Removal Program and OSRP mission includes removal and disposal of excess, unwanted, abandoned, or orphan radioactive sealed sources that pose a potential risk to national...

69

Experiences in the field of radioactive materials seizures in the Czech Republic  

SciTech Connect (OSTI)

In recent years, the amount of radioactive materials seizures (captured radioactive materials) has been rising. It was above all due to newly installed detection facilities that were able to check metallic scrap during its collection in scrap yards or on the entrance to iron-mills, checking municipal waste upon entrance to municipal disposal sites, even incineration plants, or through checking vehicles going through the borders of the Czech Republic. Most cases bore a relationship to secondary raw materials or they were connected to the application of machines and installations made from contaminated metallic materials. However, in accordance to our experience, the number of cases of seizures of materials and devices containing radioactive sources used in the public domain was lower, but not negligible, in the municipal storage yards or incineration plants. Atomic Act No. 18/1997 Coll. will apply to everybody who provides activities leading to exposure, mandatory assurance as high radiation safety as risk of the endangering of life, personal health and environment is as low as reasonably achievable in according to social and economic aspects. Hence, attention on the examination of all cases of the radioactive material seizure based on detection facilities alarm or reasonably grounds suspicion arising from the other information is important. Therefore, a service carried out by group of workers who ensure assessment of captured radioactive materials and eventual retrieval of radioactive sources from the municipal waste has come into existence in the Nuclear Research Institute Rez plc. This service has covered also transport, storage, processing and disposal of found radioactive sources. This service has arisen especially for municipal disposal sites, but later on even other companies took advantage of this service like incineration plants, the State Office for Nuclear Safety, etc. Our experience in the field of ensuring assessment of captured radioactive materials and eventual retrieval of radioactive sources will be presented in the paper. (authors)

Svoboda, Karel; Podlaha, Josef; Sir, David; Mudra, Josef [Nuclear Research Institute Rez plc (Czech Republic)

2007-07-01T23:59:59.000Z

70

Distribution of Radioactive Materials in the Absheron Peninsula, Azerbaijan - 13567  

SciTech Connect (OSTI)

The Absheron Peninsula forms the extreme Eastern part of Azerbaijan and juts into the Caspian Sea. The region has a long history of oil and gas exploration, transport, and processing and includes a number of abandoned chemical plants that were used in the separation of iodine from formation waters. As a result of lax environmental standards during the Soviet era, the industrial activity has led to serious contamination from oils residues, heavy metals and naturally occurring radioactive materials (NORM). Radiometric surveys performed over a wide range of the Absheron Peninsula showed generally low NORM concentrations. However, radiation levels two to three orders of magnitude above background levels were detected at two abandoned iodine separation plants near the capital city, Baku. These elevated radiation levels are mainly due to Ra-226 and U-238 with lower contributions from Ra-228 and U-235. (authors)

Vandergraaf, Tjalle T. [Consultant, Pinawa, MB, R0E 1L0 (Canada)] [Consultant, Pinawa, MB, R0E 1L0 (Canada); Mamedov, Gudrat G.; Ramazanov, Mahammadali A.; Badalov, Vatan H. [Baku State University, Baku (Azerbaijan)] [Baku State University, Baku (Azerbaijan); Naghiyev, Jalal A. [Institute of Radiation Problems of ANAS, Baku (Azerbaijan)] [Institute of Radiation Problems of ANAS, Baku (Azerbaijan); Mehdiyeva, Afat A. [National Aerospace Agency of Ministry of Defense Industry, Baku (Azerbaijan)] [National Aerospace Agency of Ministry of Defense Industry, Baku (Azerbaijan)

2013-07-01T23:59:59.000Z

71

Hazardous Material Packaging for Transport - Administrative Procedures  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establ1sh administrative procedures for the certification and use of radioactive and other hazardous materials packaging by the Department of Energy (DOE).

1986-09-30T23:59:59.000Z

72

Packaging and transportation of radioactive liquid at the U.S. Department of Energy Hanford Site  

SciTech Connect (OSTI)

Beginning in the 1940`s, radioactive liquid waste has been generated at the US Department of Energy (DOE) Hanford Site as a result of defense material production. The liquid waste is currently stored in 177 underground storage tanks. As part of the tank remediation efforts, Type B quantity packagings for the transport of large volumes of radioactive liquids are required. There are very few Type B liquid packagings in existence because of the rarity of large-volume radioactive liquid payloads in the commercial nuclear industry. Development of aboveground transport systems for large volumes of radioactive liquids involves institutional, economic, and technical issues. Although liquid shipments have taken place under DOE-approved controlled conditions within the boundaries of the Hanford Site for many years, offsite shipment requires compliance with DOE, US Nuclear Regulatory Commission (NRC), and US Department of Transportation (DOT) directives and regulations. At the present time, no domestic DOE nor NRC-certified Type B packagings with the appropriate level of shielding are available for DOT-compliant transport of radioactive liquids in bulk volumes. This paper will provide technical details regarding current methods used to transport such liquids on and off the Hanford Site, and will provide a status of packaging development programs for future liquid shipments.

Smith, R.J.

1995-02-01T23:59:59.000Z

73

Naturally Occurring Radioactive Materials in Cargo at US Borders  

SciTech Connect (OSTI)

In the U.S. and other countries, large numbers of vehicles pass through border crossings each day. The illicit movement of radioactive sources is a concern that has resulted in the installation of radiation detection and identification instruments at border crossing points. This activity is judged to be necessary because of the possibility of an act of terrorism involving a radioactive source that may include any number of dangerous radionuclides. The problem of detecting, identifying, and interdicting illicit radioactive sources is complicated by the fact that many materials present in cargo are somewhat radioactive. Some cargo contains naturally occurring radioactive material or technologically-enhanced naturally occurring radioactive material that may trigger radiation portal monitor alarms. Man-made radioactive sources, especially medical isotopes, are also frequently observed and produce alarms. Such nuisance alarms can be an operational limiting factor for screening of cargo at border crossings. Information about the nature of the radioactive materials in cargo that can interfere with the detection of radionuclides of concern is necessary. This paper provides such information for North American cargo, but the information may also be of use to border control officials in other countries. (PIET-43741-TM-361)

Kouzes, Richard T.; Ely, James H.; Evans, John C.; Hensley, Walter K.; Lepel, Elwood A.; McDonald, Joseph C.; Schweppe, John E.; Siciliano, Edward R.; Strom, Daniel J.; Woodring, Mitchell L.

2006-01-01T23:59:59.000Z

74

Regulatory and extra-regulatory testing to demonstrate radioactive material packaging safety  

SciTech Connect (OSTI)

Packages for the transportation of radioactive material must meet performance criteria to assure safety and environmental protection. The stringency of the performance criteria is based on the degree of hazard of the material being transported. Type B packages are used for transporting large quantities of radioisotopes (in terms of A{sub 2} quantities). These packages have the most stringent performance criteria. Material with less than an A{sub 2} quantity are transported in Type A packages. These packages have less stringent performance criteria. Transportation of LSA and SCO materials must be in {open_quotes}strong-tight{close_quotes} packages. The performance requirements for the latter packages are even less stringent. All of these package types provide a high level of safety for the material being transported. In this paper, regulatory tests that are used to demonstrate this safety will be described. The responses of various packages to these tests will be shown. In addition, the response of packages to extra-regulatory tests will be discussed. The results of these tests will be used to demonstrate the high level of safety provided to workers, the public, and the environment by packages used for the transportation of radioactive material.

Ammerman, D.J.

1997-06-01T23:59:59.000Z

75

Midwestern Radioactive Materials Transportation Committee Agenda |  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG | DepartmentEnergyMagna:MasterOffice0RecordsDomestic Natural Gas

76

Midwestern Radioactive Materials Transportation Committee Agenda  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalanced Scorecard Federal2 to: A DispersionMid-LevelProposed PenaltyDepartment

77

Departmental Materials Transportation and Packaging Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes requirements and responsibilities for management of Department of Energy (DOE), including National Nuclear Security Administration, materials transportation and packaging and ensures the safe, secure, efficient packaging and transportation of materials, both hazardous and non-hazardous.

2010-11-18T23:59:59.000Z

78

Radioactive Samples / Materials at the APS  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassive Solar HomePromising Science for1 20115,PerformanceUsing Radioactive Samples /

79

One million curies of radioactive material recovered  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratorySpeeding access1 TechnicalOil inventoriesquasicrystalsRadioactive

80

Waste minimization for commercial radioactive materials users generating low-level radioactive waste  

SciTech Connect (OSTI)

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature.

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L. (Science Applications International Corp., Idaho Falls, ID (United States))

1991-07-01T23:59:59.000Z

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


81

Waste minimization for commercial radioactive materials users generating low-level radioactive waste. Revision 1  

SciTech Connect (OSTI)

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature.

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L. [Science Applications International Corp., Idaho Falls, ID (United States)

1991-07-01T23:59:59.000Z

82

Commercial low-level radioactive waste transportation liability and radiological risk  

SciTech Connect (OSTI)

This report was prepared for States, compact regions, and other interested parties to address two subjects related to transporting low-level radioactive waste to disposal facilities. One is the potential liabilities associated with low-level radioactive waste transportation from the perspective of States as hosts to low-level radioactive waste disposal facilities. The other is the radiological risks of low-level radioactive waste transportation for drivers, the public, and disposal facility workers.

Quinn, G.J.; Brown, O.F. II; Garcia, R.S.

1992-08-01T23:59:59.000Z

83

Radioactivity measurements of ITER materials using TFTR D-T neutron field  

SciTech Connect (OSTI)

TFTR successfully initiated trace tritium plasma experiments in mid-November 1993. During the coming year, the TFTR plasma tritium fraction is scheduled to be increased to at least 50%. The availability of larger amounts of D-T fusion neutrons in the high power D-T plasma phase of TFTR provides an useful opportunity to directly measure D-T neutron induced radioactivity in a realistic tokamak-environment in materials of vital interest to ITER. These measurements are invaluable for characterizing short and long lived radioactivity in various ITER candidate materials, for validating complex neutron transport calculations, and for meeting fusion reactor licensing requirements. The radioactivity measurements at TFTR will involve potential ITER materials that include stainless steel 316, vanadium-alloy, copper, iron, nickel, chromium, vanadium, titanium, manganese, cobalt, molybdenum, zinc, niobium, zirconium, tungsten, lead, tin, silicon, etc. Small samples of these materials will be irradiated in varying neutron energy spectra at the vacuum vessel first wall. These irradiated samples will then be counted for {gamma}-radioactivity at different cooling times to get extensive information on as many {gamma}-emitting radioactive products as feasible.

Kumar, A.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Kugel, H.W. [Princeton Univ., NJ (United States)] [and others

1994-12-31T23:59:59.000Z

84

Transportation functions of the Civilian Radioactive Waste Management System  

SciTech Connect (OSTI)

Within the framework of Public Law 97.425 and provisions specified in the Code of Federal Regulations, Title 10 Part 961, the US Department of Energy has the responsibility to accept and transport spent fuel and high-level waste from various organizations which have entered into a contract with the federal government in a manner that protects the health and safety of the public and workers. In implementing these requirements, the Office of Civilian Radioactive Waste Management (OCRWM) has, among other things, supported the identification of functions that must be performed by a transportation system (TS) that will accept the waste for transport to a federal facility for storage and/or disposal. This document, through the application of system engineering principles, identifies the functions that must be performed to transport waste under this law.

Shappert, L.B. [ed.; Attaway, C.R.; Pope, R.B. [Oak Ridge National Lab., TN (United States); Best, R.E.; Danese, F.L. [Science Applications International Corp., Oak Ridge, TN (United States); Dixon, L.D. [Dixon (L.D.), Martinez, GA (United States); Jones, R.H. [Jones (R.H.), Los Gatos, CA (United States); Klimas, M.J. [USDOE Chicago Operations Office, Argonne, IL (United States); Peterson, R.W. [Bentz (E.J.) and Associates, Inc., Alexandria, VA (United States)

1992-03-01T23:59:59.000Z

85

Removal of radioactive and other hazardous material from fluid waste  

DOE Patents [OSTI]

Hollow glass microspheres obtained from fly ash (cenospheres) are impregnated with extractants/ion-exchangers and used to remove hazardous material from fluid waste. In a preferred embodiment the microsphere material is loaded with ammonium molybdophosphonate (AMP) and used to remove radioactive ions, such as cesium-137, from acidic liquid wastes. In another preferred embodiment, the microsphere material is loaded with octyl(phenyl)-N-N-diisobutyl-carbamoylmethylphosphine oxide (CMPO) and used to remove americium and plutonium from acidic liquid wastes.

Tranter, Troy J. (Idaho Falls, ID); Knecht, Dieter A. (Idaho Falls, ID); Todd, Terry A. (Aberdeen, ID); Burchfield, Larry A. (W. Richland, WA); Anshits, Alexander G. (Krasnoyarsk, RU); Vereshchagina, Tatiana (Krasnoyarsk, RU); Tretyakov, Alexander A. (Zheleznogorsk, RU); Aloy, Albert S. (St. Petersburg, RU); Sapozhnikova, Natalia V. (St. Petersburg, RU)

2006-10-03T23:59:59.000Z

86

Management of sewage sludge and ash containing radioactive materials.  

SciTech Connect (OSTI)

Approximately 50% of the seven to eight million metric tonnes of municipal sewage sludge produced annually in the US is reused. Beneficial uses of sewage sludge include agricultural land application, land reclamation, forestry, and various commercial applications. Excessive levels of contaminants, however, can limit the potential usefulness of land-applied sewage sludge. A recently completed study by a federal inter-agency committee has identified radioactive contaminants that could interfere with the safe reuse of sewage sludge. The study found that typical levels of radioactive materials in most municipal sewage sludge and incinerator ash do not present a health hazard to sewage treatment plant workers or to the general public. The inter-agency committee has developed recommendations for operators of sewage treatment plants for evaluating measured or estimated levels of radioactive material in sewage sludge and for determining whether actions to reduce potential exposures are appropriate.

Bachmaier, J. T.; Aiello, K.; Bastian, R. K.; Cheng, J.-J.; Chiu, W. A.; Goodman, J.; Hogan, R.; Jones, A. R.; Kamboj, S.; Lenhart, T.; Ott, W. R.; Rubin, A. B.; Salomon, S. N.; Schmidt, D. W.; Setlow, L. W.; Yu, C.; Wolbarst, A. B.; Environmental Science Division; Middlesex County Utilities Authority; U.S. EPA; N.J. Dept of Environmental Protection; NRC

2007-01-01T23:59:59.000Z

87

Packaging and transportation manual. Chapter on the packaging and transportation of hazardous and radioactive waste  

SciTech Connect (OSTI)

The purpose of this chapter is to outline the requirements that Los Alamos National Laboratory employees and contractors must follow when they package and ship hazardous and radioactive waste. This chapter is applied to on-site, intra-Laboratory, and off-site transportation of hazardous and radioactive waste. The chapter contains sections on definitions, responsibilities, written procedures, authorized packaging, quality assurance, documentation for waste shipments, loading and tiedown of waste shipments, on-site routing, packaging and transportation assessment and oversight program, nonconformance reporting, training of personnel, emergency response information, and incident and occurrence reporting. Appendices provide additional detail, references, and guidance on packaging for hazardous and radioactive waste, and guidance for the on-site transport of these wastes.

NONE

1998-03-01T23:59:59.000Z

88

Modeling of transport and reaction in an engineered barrier for radioactive waste confinement  

E-Print Network [OSTI]

Modeling of transport and reaction in an engineered barrier for radioactive waste confinement G bentonite; Radioactive waste; Modelling; KIRMAT code; Chemical transformations; Mass transport 0169;1. Introduction A particular radioactive waste disposal design proposes to store waste in deep geological layers

Montes-Hernandez, German

89

t -software package for numerical simulations of radioactive contaminant transport in groundwater  

E-Print Network [OSTI]

r3 t - software package for numerical simulations of radioactive contaminant transport equations that arise from the modelling of radioactive contaminant transport in porous media. It can solve, see [6]) can help to numerically simulate the spreading of radioactive contaminants in flowing ground

Frolkovic, Peter

90

A pill to treat people exposed to radioactive materials  

SciTech Connect (OSTI)

Berkeley Lab's Rebecca Abergel discusses "A pill to treat people exposed to radioactive materials" in this Oct. 28, 2013 talk, which is part of a Science at the Theater event entitled Eight Big Ideas. Go here to watch the entire event with all 8 speakers:

Abergel, Rebecca

2013-10-31T23:59:59.000Z

91

A pill to treat people exposed to radioactive materials  

ScienceCinema (OSTI)

Berkeley Lab's Rebecca Abergel discusses "A pill to treat people exposed to radioactive materials" in this Oct. 28, 2013 talk, which is part of a Science at the Theater event entitled Eight Big Ideas. Go here to watch the entire event with all 8 speakers:

Abergel, Rebecca

2014-06-24T23:59:59.000Z

92

Working with Radioactive Materials in Clinical Areas -Documentation  

E-Print Network [OSTI]

Working with Radioactive Materials in Clinical Areas - Documentation Procedure: 7.54 Created: 2008 Documentation A. Purpose This SOP summarizes records that must be maintained as required by the Rules. Responsibility Authorized User, approved technologist or lab manager maintain records of receipt, use, spill

Jia, Songtao

93

Radcalc: An Analytical Tool for Shippers of Radioactive Material and Waste  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) ships radioactive materials in support of its research and development, environmental restoration, and national defense activities. The Radcalc software program assists personnel working on behalf of DOE in packaging and transportation determinations (e.g., isotopic decay, decay heat, regulatory classification, and gas generation) for shipment of radioactive materials and waste. Radcalc performs: - The U.S. Department of Transportation determinations and classifications (i.e., activity concentration for exempt material Type A or B, effective A1/A2, limited quantity, low specific activity, highway route controlled quantity, fissile quantity, fissile excepted, reportable quantity, list of isotopes required on shipping papers) - DOE calculations (i.e., transuranic waste, Pu-239 equivalent curies, fissile-gram equivalents) - The U.S. Nuclear Regulatory Commission packaging category (i.e., Category I, II, or III) - Dose-equivalent curie calculations - Radioactive decay calculations using a novel decay methodology and a decay data library of 1,867 isotopes typical of the range of materials encountered in DOE laboratory environments - Hydrogen and helium gas calculations - Pressure calculations. Radcalc is a validated and cost-effective tool to provide consistency, accuracy, reproducibility, timeliness, quality, compliance, and appropriate documentation to shippers of radioactive materials and waste at DOE facilities nationwide. Hundreds of shippers and engineers throughout the DOE Complex routinely use this software to automate various determinations and to validate compliance with the regulations. The effective use of software by DOE sites contributes toward minimizing risk involved in radioactive waste shipments and assuring the safety of workers and the public. (authors)

Kapoor, A.K. [U.S. Department of Energy, Office of Transportation, Washington, DC (United States); Stuhl, L.A. [EnergySolutions Federal Services, Inc., Richland, WA (United States)

2008-07-01T23:59:59.000Z

94

A manual for implementing residual radioactive material guidelines  

SciTech Connect (OSTI)

This manual presents information for implementing US Department of Energy (DOE) guidelines for residual radioactive material at sites identified by the Formerly Utilized Sites Remedial Action Program (FUSRAP) and the Surplus Facilities Management Program (SFMP). It describes the analysis and models used to derive site-specific guidelines for allowable residual concentrations of radionuclides in soil and the design and use of the RESRAD computer code for calculating guideline values. It also describes procedures for implementing DOE policy for reducing residual radioactivity to levels that are as low as reasonably achievable. 36 refs., 16 figs, 22 tabs.

Gilbert, T.L.; Yu, C.; Yuan, Y.C.; Zielen, A.J.; Jusko, M.J.; Wallo, A. III

1989-06-01T23:59:59.000Z

95

Hazardous Material Transportation Safety (South Dakota)  

Broader source: Energy.gov [DOE]

This legislation authorizes the Division of Highway Safety, in the Department of Public Safety, to promulgate regulations pertaining to the safe transportation of hazardous materials by a motor...

96

Slovak Nuclear Regulatory Body Position in the Transport of Radioactive Waste  

SciTech Connect (OSTI)

This paper describes safety requirements for transport of radioactive waste in Slovakia and the role of regulatory body in the transport licensing and assessment processes. Importance of radioactive waste shipments have been increased since 1999 by starting of NPP A-1 decommissioning and operation of near surface disposal facility. Also some information from history of shipment as well as future activities are given. Legal basis for radioactive waste transport is resulting from IAEA recommendations in this area. Different types of transport equipment were approved by regulatory body for both liquid and solid waste and transportation permits were issued to their shipment. Regulatory body attention during evaluation of transport safety is focused mainly on ability of individual packages to withstand different transport conditions and on safety analyses performed for transport equipment for liquid waste with high frequency of shipments. During past three years no event was occurred in connection with radioactive waste transport in Slovakia.

Homola, J.

2003-02-27T23:59:59.000Z

97

Departmental Materials Transportation and Packaging Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The Order establishes requirements and responsibilities for management of Department of Energy (DOE), including National Nuclear Security Administration (NNSA), materials transportation and packaging to ensure the safe, secure, efficient packaging and transportation of materials, both hazardous and nonhazardous. Cancels DOE O 460.2 and DOE O 460.2 Chg 1

2004-12-22T23:59:59.000Z

98

Processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents [OSTI]

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter.

Gotovchikov, Vitaly T. (Moscow, RU); Ivanov, Alexander V. (Moscow, RU); Filippov, Eugene A. (Moscow, RU)

1998-05-12T23:59:59.000Z

99

Processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents [OSTI]

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter. 6 figs.

Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

1998-05-12T23:59:59.000Z

100

Safe Use of Radioactive Materials Procedure: 7.542 Created: 3/7/2014  

E-Print Network [OSTI]

-level radioactive waste and still provide for ease of decontamination. Trays made of impervious material (iSafe Use of Radioactive Materials Procedure: 7.542 Created: 3/7/2014 Version: 1.0 Revised of radioactive materials (RAM). They are designed to reduce the risk of a significant contamination event

Jia, Songtao

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


101

rev September 2003 Radiation Safety Manual Section 11 Procurement of Radioactive Material  

E-Print Network [OSTI]

rev September 2003 Radiation Safety Manual Section 11 ­ Procurement of Radioactive Material Page 11-1 Section 11 Procurement of Radioactive Materials Contents A. Authorization to Order Radioactive Materials. Authorized Investigator Package Monitoring.................................11-3 3. No Contamination Detected

Wilcock, William

102

System for chemically digesting low level radioactive, solid waste material  

DOE Patents [OSTI]

An improved method and system for chemically digesting low level radioactive, solid waste material having a high through-put. The solid waste material is added to an annular vessel (10) substantially filled with concentrated sulfuric acid. Concentrated nitric acid or nitrogen dioxide is added to the sulfuric acid within the annular vessel while the sulfuric acid is reacting with the solid waste. The solid waste is mixed within the sulfuric acid so that the solid waste is substantilly fully immersed during the reaction. The off gas from the reaction and the products slurry residue is removed from the vessel during the reaction.

Cowan, Richard G. (Kennewick, WA); Blasewitz, Albert G. (Richland, WA)

1982-01-01T23:59:59.000Z

103

Management of Naturally Occurring Radioactive Materials (NORM) in Canada  

SciTech Connect (OSTI)

In Canada, nuclear and radiological regulatory responsibilities are shared between the provinces/territories and the federal government. The Canadian Nuclear Safety Commission (CNSC) regulates nuclear fuel cycle materials and man-made radionuclides under the Nuclear Safety and Control Act (2000). The provinces and territories regulate NORM arising from industrial activities, not involving the nuclear fuel cycle materials. Present guideline--Canadian Guidelines for the Management of Naturally Occurring Radioactive Materials (NORM)--was published in 2000 in order to bring uniformity to the management of NORM-related procedures to provide adequate radiation protection for workers and the general public. The basic premise of these guidelines is that the NORM-related activities should not be posing any greater hazard than those activities regulated under the Nuclear Safety and Control Act; these concepts are described in this paper.

Baweja, Anar S.; Tracy, Bliss L. [Radiation Protection Bureau, Health Canada, Ottawa, Ontario (Canada)

2008-08-07T23:59:59.000Z

104

INTRODUCTION In every laboratory where radioactive materials are utilized, it is necessary to maintain a  

E-Print Network [OSTI]

) in their work habits and to minimize the potential for exposures, contamination or release of radioactiveINTRODUCTION In every laboratory where radioactive materials are utilized, it is necessary of Texas the privilege of using large varieties of radioactive materials. Large amounts of activity

105

THERMAL EVALUATION OF DRUM TYPE RADIOACTIVE MATERIAL PACKAGING ARRAYS IN STORAGE  

SciTech Connect (OSTI)

Drum type packages are routinely used to transport radioactive material (RAM) in the U.S. Department of Energy (DOE) complex. These packages are designed to meet the federal regulations described in 10 CFR 71.[1] In recent years, there has been a greater need to use these packagings to store the excess fissile material, especially plutonium for long term storage. While the design requirements for safe transportation of these packagings are well defined, the requirements for safe long term storage are not well established. Since the RAM contents in the packagings produce decay heat, it is important that they are stored carefully to prevent overheating of the containment vessel (CV) seals to prevent any leakage and the impact limiter to maintain the package structural integrity. This paper analyzes different storage arrays for a typical 9977 packaging for thermal considerations and makes recommendations for their safe storage under normal operating conditions.

Gupta, N

2009-04-27T23:59:59.000Z

106

Electronic transport in atomically thin layered materials  

E-Print Network [OSTI]

Electronic transport in atomically thin layered materials has been a burgeoning field of study since the discovery of isolated single layer graphene in 2004. Graphene, a semi-metal, has a unique gapless Dirac-like band ...

Baugher, Britton William Herbert

2014-01-01T23:59:59.000Z

107

Departmental Materials Transportation and Packaging Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes Department of Energy (DOE) policies and requirements to supplement applicable laws, rules, regulations, and other DOE Orders for materials transportation and packaging operations. Cancels: DOE 1540.1A, DOE 1540.2, and DOE 1540.3A.

1995-10-26T23:59:59.000Z

108

Departmental Materials Transportation and Packaging Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes Department of Energy (DOE) policies and requirements to supplement applicable laws, rules, regulations, and other DOE Orders for materials transportation and packaging operations. Cancels DOE 1540.1A, DOE 1540.2, DOE 1540.3A.

1995-09-27T23:59:59.000Z

109

Best Practices for the Security of Radioactive Materials  

SciTech Connect (OSTI)

This work is funded under a grant provided by the US Department of Health and Human Services, Centers for Disease Control. The Department of Health and Mental Hygiene (DOHMH) awarded a contract to Brookhaven National Laboratory (BNL) to develop best practices guidance for Office of Radiological Health (ORH) licensees to increase on-site security to deter and prevent theft of radioactive materials (RAM). The purpose of this document is to describe best practices available to manage the security of radioactive materials in medical centers, hospitals, and research facilities. There are thousands of such facilities in the United States, and recent studies suggest that these materials may be vulnerable to theft or sabotage. Their malevolent use in a radiological-dispersion device (RDD), viz., a dirty bomb, can have severe environmental- and economic- impacts, the associated area denial, and potentially large cleanup costs, as well as other effects on the licensees and the public. These issues are important to all Nuclear Regulatory Commission and Agreement State licensees, and to the general public. This document outlines approaches for the licensees possessing these materials to undertake security audits to identify vulnerabilities in how these materials are stored or used, and to describe best practices to upgrade or enhance their security. Best practices can be described as the most efficient (least amount of effort/cost) and effective (best results) way of accomplishing a task and meeting an objective, based on repeatable procedures that have proven themselves over time for many people and circumstances. Best practices within the security industry include information security, personnel security, administrative security, and physical security. Each discipline within the security industry has its own 'best practices' that have evolved over time into common ones. With respect to radiological devices and radioactive-materials security, industry best practices encompass both physical security (hardware and engineering) and administrative procedures. Security regimes for these devices and materials typically use a defense-in-depth- or layered-security approach to eliminate single points of failure. The Department of Energy, the Department of Homeland Security, the Department of Defense, the American Society of Industrial Security (ASIS), the Security Industry Association (SIA) and Underwriters Laboratory (UL) all rovide design guidance and hardware specifications. With a graded approach, a physical-security specialist can tailor an integrated security-management system in the most appropriate cost-effective manner to meet the regulatory and non-regulatory requirements of the licensee or client.

Coulter, D.T.; Musolino, S.

2009-05-01T23:59:59.000Z

110

Experimental determination of the shipboard fire environment for simulated radioactive material packages  

SciTech Connect (OSTI)

A series of eight fire tests with simulated radioactive material shipping containers aboard the test ship Mayo Lykes, a break-bulk freighter, is described. The tests simulate three basic types of fires: engine room fires, cargo fires and open pool fires. Detailed results from the tests include temperatures, heat fluxes and air flows measured during the fires. The first examination of the results indicates that shipboard fires are not significantly different from fires encountered in land transport. 13 refs., 15 figs., 11 tabs.

Koski, J.A.; Bobbe, J.G.; Arviso, M. [and others

1997-03-01T23:59:59.000Z

111

ELUCIDATING THE DIFFERENCES BETWEEN ONSITE AND OFFSITE SHIPMENT OF RADIOACTIVE MATERIALS  

SciTech Connect (OSTI)

Federal regulations stipulate how radioactive materials are transported within the United States. However, the Department of Energy, under Department of Energy Order, has the authority to operate, within the boundaries of their physical site, to other stipulations. In many cases the DOE sites have internal reviews for onsite transfers that rival reviews performed by the regulatory authorities for offsite shipments. Most of the differences are in the level or type of packaging that is required, but in some cases it may be in the amount and type of material that is allowed to be transferred. This paper will describe and discuss those differences and it will discuss ways to effectively align the onsite rules for transferring materials with those for offsite shipment.

Loftin, B.; Watkins, R.

2013-06-19T23:59:59.000Z

112

2011 Radioactive Materials Usage Survey for Unmonitored Point Sources  

SciTech Connect (OSTI)

This report provides the results of the 2011 Radioactive Materials Usage Survey for Unmonitored Point Sources (RMUS), which was updated by the Environmental Protection (ENV) Division's Environmental Stewardship (ES) at Los Alamos National Laboratory (LANL). ES classifies LANL emission sources into one of four Tiers, based on the potential effective dose equivalent (PEDE) calculated for each point source. Detailed descriptions of these tiers are provided in Section 3. The usage survey is conducted annually; in odd-numbered years the survey addresses all monitored and unmonitored point sources and in even-numbered years it addresses all Tier III and various selected other sources. This graded approach was designed to ensure that the appropriate emphasis is placed on point sources that have higher potential emissions to the environment. For calendar year (CY) 2011, ES has divided the usage survey into two distinct reports, one covering the monitored point sources (to be completed later this year) and this report covering all unmonitored point sources. This usage survey includes the following release points: (1) all unmonitored sources identified in the 2010 usage survey, (2) any new release points identified through the new project review (NPR) process, and (3) other release points as designated by the Rad-NESHAP Team Leader. Data for all unmonitored point sources at LANL is stored in the survey files at ES. LANL uses this survey data to help demonstrate compliance with Clean Air Act radioactive air emissions regulations (40 CFR 61, Subpart H). The remainder of this introduction provides a brief description of the information contained in each section. Section 2 of this report describes the methods that were employed for gathering usage survey data and for calculating usage, emissions, and dose for these point sources. It also references the appropriate ES procedures for further information. Section 3 describes the RMUS and explains how the survey results are organized. The RMUS Interview Form with the attached RMUS Process Form(s) provides the radioactive materials survey data by technical area (TA) and building number. The survey data for each release point includes information such as: exhaust stack identification number, room number, radioactive material source type (i.e., potential source or future potential source of air emissions), radionuclide, usage (in curies) and usage basis, physical state (gas, liquid, particulate, solid, or custom), release fraction (from Appendix D to 40 CFR 61, Subpart H), and process descriptions. In addition, the interview form also calculates emissions (in curies), lists mrem/Ci factors, calculates PEDEs, and states the location of the critical receptor for that release point. [The critical receptor is the maximum exposed off-site member of the public, specific to each individual facility.] Each of these data fields is described in this section. The Tier classification of release points, which was first introduced with the 1999 usage survey, is also described in detail in this section. Section 4 includes a brief discussion of the dose estimate methodology, and includes a discussion of several release points of particular interest in the CY 2011 usage survey report. It also includes a table of the calculated PEDEs for each release point at its critical receptor. Section 5 describes ES's approach to Quality Assurance (QA) for the usage survey. Satisfactory completion of the survey requires that team members responsible for Rad-NESHAP (National Emissions Standard for Hazardous Air Pollutants) compliance accurately collect and process several types of information, including radioactive materials usage data, process information, and supporting information. They must also perform and document the QA reviews outlined in Section 5.2.6 (Process Verification and Peer Review) of ES-RN, 'Quality Assurance Project Plan for the Rad-NESHAP Compliance Project' to verify that all information is complete and correct.

Sturgeon, Richard W. [Los Alamos National Laboratory

2012-06-27T23:59:59.000Z

113

Colloid Facilitated Transport of Radioactive Cations in the Vadose Zone: Field Experiments Oak Ridge  

SciTech Connect (OSTI)

The overarching goal of this study was to improve understanding of colloid-facilitated transport of radioactive cations through unsaturated soils and sediments. We conducted a suite of laboratory experiments and field experiments on the vadose-zone transport of colloids, organic matter, and associated contaminants of interest to the U.S. Department of Energy (DOE). The laboratory and field experiments, together with transport modeling, were designed to accomplish the following detailed objectives: 1. Evaluation of the relative importance of inorganic colloids and organic matter to the facilitation of radioactive cation transport in the vadose zone; 2. Assessment of the role of adsorption and desorption kinetics in the facilitated transport of radioactive cations in the vadose zone; 3. Examination of the effects of rainfall and infiltration dynamics and in the facilitated transport of radioactive cations through the vadose zone; 4. Exploration of the role of soil heterogeneity and preferential flow paths (e.g., macropores) on the facilitated transport of radioactive cations in the vadose zone; 5. Development of a mathematical model of facilitated transport of contaminants in the vadose zone that accurately incorporates pore-scale and column-scale processes with the practicality of predicting transport with readily available parameters.

James E. Saiers

2012-09-20T23:59:59.000Z

114

Information-Sharing Protocol for the Transportation of Radioactive...  

Broader source: Energy.gov (indexed) [DOE]

Logistics Management Office of Civilian Radioactive Waste Management U. S. Department of Energy Preliminary Draft July 2007 1 Preliminary Draft for Review Only TABLE OF CONTENTS...

115

Heat transport system, method and material  

DOE Patents [OSTI]

A heat transport system, method and composite material are disclosed in which a plurality of hollow spherical shells or microspheres having an outside diameter of less than or equal to 500 microns are encapsulated or embedded within a bulk material. Each shell has captured therein a volatile working fluid, such that each shell operates as a microsized heat pipe for conducting heat through the composite structure. 1 fig.

Musinski, D.L.

1987-04-28T23:59:59.000Z

116

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

E-Print Network [OSTI]

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

Firestone, Jeremy

117

Albert Einstein College of Medicine Amendment to Non-human Use of Radioactive Material License  

E-Print Network [OSTI]

RSO-2 Rev.0 Albert Einstein College of Medicine Amendment to Non-human Use of Radioactive Material License INSTRUCTIONS: If you wish to make changes to your license to use radioactive material please exposure; Glove box: Mechanical pipettes: Fume hood: Absorbent liner & Tray Shielding: Lead: Lucite: GM

Emmons, Scott

118

SSRL Radioactive Material Sample Holder Catalog 5/30/14 Page 1 of 17  

E-Print Network [OSTI]

SSRL Radioactive Material Sample Holder Catalog 5/30/14 Page 1 of 17 Hazard Class Category finger under vacuum #12;SSRL Radioactive Material Sample Holder Catalog 5/30/14 Page 2 of 17 1.d USGS polyethylene envelopes. Check for no contamination of each envelope. - External envelope glued onto the cell

Wechsler, Risa H.

119

RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT  

SciTech Connect (OSTI)

This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below.

KOZLOWSKI, S.D.

2007-05-30T23:59:59.000Z

120

MATERIALS HANDLING AND TRANSPORTATION PLAN CSMRI SITE REMEDIATION  

E-Print Network [OSTI]

MATERIALS HANDLING AND TRANSPORTATION PLAN CSMRI SITE REMEDIATION April 13, 2004 Prepared for. Wright Street Littleton, CO 80127 #12;MATERIALS HANDLING AND TRANSPORTATION PLAN CSMRI Site Remediation By: Date: Robert Krumberger Project Manager New Horizons Environmental Consultants, Inc. Approved By

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


121

Semianalytical Solutions of Radioactive or Reactive Tracer Transport in Layered Fractured Media  

SciTech Connect (OSTI)

In this paper, semianalytical solutions are developed for the problem of transport of radioactive or reactive tracers (solutes or colloids) through a layered system of heterogeneous fractured media with misaligned fractures. The tracer transport equations in the matrix account for (a) diffusion, (b) surface diffusion (for solutes only), (c) mass transfer between the mobile and immobile water fractions, (d) linear kinetic or equilibrium physical, chemical, or combined solute sorption or colloid filtration, and (e) radioactive decay or first order chemical reactions. Any number of radioactive decay daughter products (or products of a linear, first-order reaction chain) can be tracked. The tracer-transport equations in the fractures account for the same processes, in addition to advection and hydrodynamic dispersion. Additionally, the colloid transport equations account for straining and velocity adjustments related to the colloidal size. The solutions, which are analytical in the Laplace space, are numerically inverted to provide the solution in time and can accommodate any number of fractured and/or porous layers. The solutions are verified using analytical solutions for limiting cases of solute and colloid transport through fractured and porous media. The effect of important parameters on the transport of {sup 3}H, {sup 237}Np and {sup 239}Pu (and its daughters) is investigated in several test problems involving layered geological systems of varying complexity. {sup 239}Pu colloid transport problems in multilayered systems indicate significant colloid accumulations at straining interfaces but much faster transport of the colloid than the corresponding strongly sorbing solute species.

G.J. Moridis; G. S. Bodvarsson

2001-10-01T23:59:59.000Z

122

Manual for implementing residual radioactive material guidelines using RESRAD, Version 5.0  

SciTech Connect (OSTI)

This manual presents information for implementing US Department of Energy (DOE) guidelines for residual radioactive material. It describes the analysis and models used to derive site-specific guidelines for allowable residual concentrations of radionuclides in soil and the design and use of the RESRAD computer code for calculating doses, risks, and guideline values. It also describes procedures for implementing DOE policy for reducing residual radioactivity to levels that are as low as reasonably achievable. Two new pathways, radon inhalation and soil ingestion, have been added to RESRAD. Twenty-seven new radionuclides have also been added, and the cutoff half-life for associated radionuclides has been reduced to six months. Other major improvements to the RESRAD code include the ability to run sensitivity analyses, the addition of graphical output, user-specified dose factors, updated databases, an improved groundwater transport model, optional input of a groundwater concentration and a solubility constant, special models for tritium and carbon-14, calculation of cancer incidence risk, and the use of a mouse with menus.

Yu, C.; Zielen, A.J.; Cheng, J.J. [and others

1993-09-01T23:59:59.000Z

123

DEVELOPMENT OF A NEW TYPE A(F)RADIOACTIVE MATERIAL PACKAGING FOR THE DEPARTMENT OF ENERGY  

SciTech Connect (OSTI)

In a coordinated effort, the Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) proposed the elimination of the Specification Packaging from 49 CFR 173.[1] In accordance with the Federal Register, issued on October 1, 2004, new fabrication of Specification Packages would no longer be authorized. In accordance with the NRC final rulemaking published January 26, 2004, Specification Packagings are mandated by law to be removed from service no later than October 1, 2008. This coordinated effort and resulting rulemaking initiated a planned phase out of Specification Type B and Type A fissile (F) material transportation packages within the Department of Energy (DOE) and its subcontractors. One of the Specification Packages affected by this regulatory change is the UN1A2 Specification Package, per DOT 49 CFR 173.417(a)(6). To maintain continuing shipments of DOE materials currently transported in UN1A2 Specification Package after the existing authorization expires, a replacement Type A(F) material packaging design is under development by the Savannah River National Laboratory. This paper presents a summary of the prototype design effort and testing of the new Type A(F) Package development for the DOE. This paper discusses the progress made in the development of a Type A Fissile Packaging to replace the expiring 49 CFR UN1A2 Specification Fissile Package. The Specification Package was mostly a single-use waste disposal container. The design requirements and authorized radioactive material contents of the UN1A2 Specification Package were defined in 49 CFR. A UN1A2 Specification Package was authorized to ship up to 350 grams of U-235 in any enrichment and in any non-pyrophoric form. The design was specified as a 55-gallon 1A2 drum overpack with a body constructed from 18 gauge steel with a 16 gauge drum lid. Drum closure was specified as a standard 12-gauge ring closure. The inner product container size was not specified but was listed as any container that met Specification 7A requirements per 49 CFR 178.350. Specification 7A containers were required to withstand Type A packaging tests required by 49CFR173.465 with compliance demonstrated through testing, analysis or similarity to other containers. The maximum weight of the 7A product container, the radioactive content, and any internal packaging was limited to 200 lbs. The total gross weight for the UN1A2 Specification Package was limited to 350 lbs. No additional restrictions were applied. Authorization for use did not require the UN1A2 Specification Package to be tested to the Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC) required for performance based, Type A(F) packages certified by the NRC or DOE. The Type A(F) Packaging design discussed in this paper is required to be in compliance with the regulatory safety requirements defined in Code of Federal Regulations (CFR) 10 CFR 71.41 through 71.47 and 10 CFR71.71. Sub-criticality of content must be maintained under the Hypothetical Accident Conditions specified under 10 CFR71.73. These federal regulations, and other applicable DOE Orders and Guides, govern design requirements for a Type A(F) package. Type A(F) packages with less than an A2 quantity of radioactive material are not required to have a leak testable boundary. With this exception a Type A(F) package design is subject to the same test requirements set forth for the design of a performance based Type B packaging.

Blanton, P.; Eberl, K.

2008-09-14T23:59:59.000Z

124

Albert Einstein College of Medicine Application for Non-human Use of Radioactive Material  

E-Print Network [OSTI]

RSO-1 Rev.0 Albert Einstein College of Medicine Application for Non-human Use of Radioactive pipettes: Fume hood: Absorbent liner & Tray Shielding: Lead: Lucite: GM survey meter: Handling tongs radioactive material is secure against unauthorized access: 9. Please check the type of application below

Emmons, Scott

125

Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect (OSTI)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Not Listed

2011-09-01T23:59:59.000Z

126

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect (OSTI)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-09-01T23:59:59.000Z

127

ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY  

SciTech Connect (OSTI)

The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information.

Romano, Stephen; Welling, Steven; Bell, Simon

2003-02-27T23:59:59.000Z

128

Lightweight materials for transportation: Program plan  

SciTech Connect (OSTI)

This Program Plan has been prepared by the Office of Transportation Materials in response to a request by the House Committee on Appropriations. It recognizes that a significant commitment to long-term, stable materials research and development (R&D) is required to realize the benefits of lighter weight vehicles, including economic, environmental and energy related benefits. Extensive input was obtained from the major US automakers and from representative materials and component suppliers. Considerable interaction with the key members of the US Automotive Materials Partnership (USAMP) has ensured consistency of technical direction. The program will support R&D activity at industrial sites through competitively bid subcontracts with cost sharing anticipated at 30--50%, with the higher amounts in process scale-up and manufacturing technology development. The recommended LWM Program will enable industry to develop pecessary technology by utilizing their capabilities as well as accessing supporting technology at national laboratories, universities, ongoing program activity at NASA, DoD, DOT, NIST, etc., and thereby leverage industry resources through integrated team approaches. Many individual program efforts are currently in place that address small portions of the overall needs of the LWM Program, both within DOE and in other agencies. Cognizance of these and overall integration of research activities are planned as significant program management tasks. Because of the international nature of the automobile business, benchmarking of foreign technology and tracking of worldwide developments are also key program elements.

Not Available

1993-07-01T23:59:59.000Z

129

Ion-exchange material and method of storing radioactive wastes  

DOE Patents [OSTI]

A new cation exchanger is a modified tobermorite containing aluminum isomorphously substituted for silicon and containing sodium or potassium. The exchanger is selective for lead, rubidium, cobalt, and cadmium and is selective for cesium over calcium or sodium. The tobermorites are compatible with cement and are useful for the long-term fixation and storage of radioactive nuclear wastes.

Komarneni, S.; Roy, D.M.

1983-10-31T23:59:59.000Z

130

Compilation of current literature on seals, closures, and leakage for radioactive material packagings  

SciTech Connect (OSTI)

This report presents an overview of the features that affect the sealing capability of radioactive material packagings currently certified by the US Nuclear Regulatory Commission. The report is based on a review of current literature on seals, closures, and leakage for radioactive material packagings. Federal regulations that relate to the sealing capability of radioactive material packagings, as well as basic equations for leakage calculations and some of the available leakage test procedures are presented. The factors which affect the sealing capability of a closure, including the properties of the sealing surfaces, the gasket material, the closure method and the contents are discussed in qualitative terms. Information on the general properties of both elastomer and metal gasket materials and some specific designs are presented. A summary of the seal material, closure method, and leakage tests for currently certified packagings with large diameter seals is provided. 18 figs., 9 tabs.

Warrant, M.M.; Ottinger, C.A.

1989-01-01T23:59:59.000Z

131

Roadmapping the Resolution of Gas Generation Issues in Packages Containing Radioactive Waste/Materials - A Status Report  

SciTech Connect (OSTI)

Gas generation issues, particularly hydrogen, have been an area of concern for the transport and storage of radioactive materials and waste in the Department of Energy (DOE) Complex. Potentially combustible gases can be generated through a variety of reactions, including chemical reactions and radiolytic decomposition of hydrogen- containing material. Since transportation regulations prohibit shipment of explosives and radioactive materials together, it was decided that hydrogen generation was a problem that warranted the execution of a high-level roadmapping effort. This paper discusses the major gas generation issues within the DOE Complex and the research that has been and is being conducted by the transuranic (TRU) waste, nuclear materials, and spent nuclear fuels (SNF) programs within DOEs Environmental Management (EM) organizations to address gas generation concerns. This paper presents a "program level" roadmap that links technology development to program needs and identifies the probability of success in an effort to understand the programmatic risk associated with the issue of gas generation. This paper also presents the status of the roadmap and follow-up activities.

Luke, Dale Elden; Hamp, S.

2002-02-01T23:59:59.000Z

132

Roadmapping the Resolution of Gas Generation Issues in Packages Containing Radioactive Waste/Materials - A Status Report  

SciTech Connect (OSTI)

Gas generation issues, particularly hydrogen, have been an area of concern for the transport and storage of radioactive materials and waste in the Department of Energy (DOE) Complex. Potentially combustible gases can be generated through a variety of reactions, including chemical reactions and radiolytic decomposition of hydrogen-containing material. Since transportation regulations prohibit shipment of explosives and radioactive materials together, it was decided that hydrogen generation was a problem that warranted the execution of a high-level roadmapping effort. This paper discusses the major gas generation issues within the DOE Complex and the research that has been and is being conducted by the transuranic (TRU) waste, nuclear materials, and spent nuclear fuels (SNF) programs within DOE's Environmental Management (EM) organizations to address gas generation concerns. This paper presents a ''program level'' roadmap that links technology development to program needs and identifies the probability of success in an effort to understand the programmatic risk associated with the issue of gas generation. This paper also presents the status of the roadmap and follow-up activities.

Luke, D.E. (INEEL); Hamp, S. (DOE-Albuquerque Operations Office)

2002-01-04T23:59:59.000Z

133

RADIATION HEAT TRANSFER ENVIRONMENT IN FIRE AND FURNACE TESTS OF RADIOACTIVE MATERIALS PAKCAGES  

SciTech Connect (OSTI)

The Hypothetical Accident Conditions (HAC) sequential test of radioactive materials packages includes a thermal test to confirm the ability of the package to withstand a transportation fire event. The test specified by the regulations (10 CFR 71) consists of a 30 minute, all engulfing, hydrocarbon fuel fire, with an average flame temperature of at least 800 C. The requirements specify an average emissivity for the fire of at least 0.9, which implies an essentially black radiation environment. Alternate test which provide equivalent total heat input at the 800 C time averaged environmental temperature may also be employed. When alternate tests methods are employed, such as furnace or gaseous fuel fires, the equivalence of the radiation environment may require justification. The effects of furnace and open confinement fire environments are compared with the regulatory fire environment, including the effects of gases resulting from decomposition of package overpack materials. The results indicate that furnace tests can produce the required radiation heat transfer environment, i.e., equivalent to the postulated pool fire. An open enclosure, with transparent (low emissivity) fire does not produce an equivalent radiation environment.

Smith, A

2008-12-31T23:59:59.000Z

134

Fast Neutron Radioactivity and Damage Studies on Materials  

E-Print Network [OSTI]

Materials We know that binary Sm x Co y compounds are more radi- ation resistant and have better thermal

Spencer, J.; Anderson, S. D.; Wolf, Z.; Volk, J. T.; Pellett, D.; Boussoufi, M.

2007-01-01T23:59:59.000Z

135

Monitoring Potential Transport of Radioactive Contaminants in Shallow Ephemeral Channels  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Nevada Site Office (NSO), Environmental Restoration Soils Activity has authorized the Desert Research Institute (DRI) to conduct field assessments of potential sediment transport of contaminated soil from Corrective Action Unit (CAU) 550, Area 8 Smoky Contamination Area (CA), during precipitation runoff events. CAU 550 includes Corrective Action Sites (CASs) 08-23-03, 08-23-04, 08-23-06, and 08-23-07; these CASs are associated with tests designated Ceres, Smoky, Oberon, and Titania, respectively.

Miller Julianne J.,Mizell Steve A.,Nikolich George,Campbell Scott A.

2012-02-01T23:59:59.000Z

136

Applying Risk Communication to the Transportation of Radioactive Materials  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergy Cooperation |South42.2 (April 2012)Tie Ltd |Line, LLC:LLC |Department ofOpportunity

137

Applying Risk Communication to the Transportation of Radioactive Materials  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power Systems EngineeringDepartment of4 Federal RegisterPowerPA00133 - March 2011 AppliedStudents|

138

Q A RADIOACTIVE MATERIALS Transportation Emergency Preparedness Program  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalancedDepartment ofColumbus HTS1, 2008 Company Affilation|Pumpkin| Department2 Q

139

Radioactive Materials Transportation and Incident Response | Department of  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalancedDepartment ofColumbus HTS1,Geologic Disposal= J .MEASUREMENTEnergy

140

Water Transport in PEM Fuel Cells: Advanced Modeling, Material...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Testing, and Design Optimization Water Transport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing, and Design Optimization This presentation, which focuses on...

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


141

Water Transport in PEM Fuel Cells: Advanced Modeling, Material...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Testing and Design Optimization Water Transport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing and Design Optimization Part of a 100 million fuel cell award...

142

Determination of Fire Enviroment in Stacked Cargo Containers with Radioactive Materials Packages  

SciTech Connect (OSTI)

Results from a Fire Test with a three-by-three stack of standard 6 m long International Standards Organization shipping containers containing combustible fuels and empty radioactive materials packages are reported and discussed. The stack is intended to simulate fire conditions that could occur during on-deck stowage on container cargo ships. The fire is initated by locating the container stack adjacent to a 9.8 x 6 m pool fire. Temperatures of both cargoes (empty and simulated radioactive materials packages) and containers are recorded and reported. Observations on the duration, intensity and spread of the fire are discussed. Based on the results, models for simulation of fire exposure of radioactive materials packages in such fires are suggested.

Arviso, M.; Bobbe, J.G.; Dukart, R.D.; Koski, J.A.

1999-05-01T23:59:59.000Z

143

Monitoring Potential Transport of Radioactive Contaminants in Shallow Ephemeral Channels: FY 2012  

SciTech Connect (OSTI)

The US Department of Energy (DOE) National Nuclear Security Administration (NNSA), Nevada Site Office (NSO), Environmental Managements Soils Activity has authorized the Desert Research Institute (DRI) to conduct field assessments of potential sediment transport of contaminated soil from Corrective Action Unit (CAU) 550, Smoky Contamination Area (CA), during precipitation runoff events. CAU 550 includes Corrective Action Sites (CASs) 08-23-03, 08-23-04, 08-23-06, and 08-23-07; these CASs are associated with tests designated Ceres, Smoky, Oberon, and Titania, respectively. Field measurements at the T-4 Atmospheric Test Site, CAU 370, suggest that radioactive material may have migrated along a shallow ephemeral drainage that traverses the site (NNSA/NSO, 2009). (It is not entirely clear how contaminated soils got into their present location at the T-4 Site, but flow to the channel has been redirected and the contamination does not appear to be migrating at present.) Although DRI initially looked at the CAU 370 site, given that it could not be confirmed that migration of contamination into the channel was natural, an alternate study site was selected at CAU 550. Aerial surveys in selected portions of the Nevada National Security Site (NNSS) also suggest that radioactivity may be migrating along ephemeral channels in Areas 3, 8, 11, 18, and 25 (Colton, 1999). Figure 1 shows the results of a low-elevation aerial survey (Colton, 1999) in Area 8. The numbered markers in Figure 1 identify ground zero for three safety experiments conducted in 1958 [Oberon (number 1), Ceres (number 2), and Titania (number 4)] and a weapons effects test conducted in 1964, Mudpack (number 3). This survey suggests contaminants may be migrating down the ephemeral channels that traverse CAU 550. Note particularly the lobe of higher concentration extending southeastward at the south end of the high concentration area marked as number 3 in Figure 1. CAU 550 in Area 8 of the NNSS was selected for the study because the aerial survey indicates that a channel mapped on the United States Geological Survey topographic map of the area traverses the south end of the area of surface contamination; this channel lies south of the point marked number 3 in Figure 1, and anecdotal information indicates that sediment has been deposited on the road bordering the southeast boundary of the CAU from an adjacent channel (Traynor, J, personal communication, 2011). Because contamination is particularly close to the boundary of CAU 550, Smoky CA, it is important to know if contaminants are moving, what meteorological conditions result in movement of contaminated soils, and what particle size fractions associated with contamination are involved. Closure plans are being developed for the CAUs on the NNSS. The closure plans may include post-closure monitoring for possible release of radioactive contaminants. Determining the potential for transport of contaminated soils under ambient climatic conditions will facilitate an appropriate closure design and post-closure monitoring program.

Julianne J. Miller, Steve A. Mizell, Greg McCurdy, and Scott A. Campbell

2012-09-01T23:59:59.000Z

144

Enhancements to System for Tracking Radioactive Waste Shipments...  

Energy Savers [EERE]

Multiple Users January 30, 2013 - 12:00pm Addthis Transportation Tracking and Communication System users can now track shipments of radioactive materials and access...

145

Method for acid oxidation of radioactive, hazardous, and mixed organic waste materials  

DOE Patents [OSTI]

The present invention is directed to a process for reducing the volume of low level radioactive and mixed waste to enable the waste to be more economically stored in a suitable repository, and for placing the waste into a form suitable for permanent disposal. The invention involves a process for preparing radioactive, hazardous, or mixed waste for storage by contacting the waste starting material containing at least one organic carbon-containing compound and at least one radioactive or hazardous waste component with nitric acid and phosphoric acid simultaneously at a contacting temperature in the range of about 140.degree. C. to about 210 .degree. C. for a period of time sufficient to oxidize at least a portion of the organic carbon-containing compound to gaseous products, thereby producing a residual concentrated waste product containing substantially all of said radioactive or inorganic hazardous waste component; and immobilizing the residual concentrated waste product in a solid phosphate-based ceramic or glass form.

Pierce, Robert A. (Aiken, SC); Smith, James R. (Corrales, NM); Ramsey, William G. (Aiken, SC); Cicero-Herman, Connie A. (Aiken, SC); Bickford, Dennis F. (Folly Beach, SC)

1999-01-01T23:59:59.000Z

146

Development of the Office of Civilian Radioactive Waste Management National Transportation Plan  

SciTech Connect (OSTI)

The Director of the Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) designated development of the National Transportation Plan (NTP) as one of his four strategic objectives for the program. The Office of Logistics Management (OLM) within OCRWM was tasked to develop the plan, which will accommodate state, local, and tribal concerns and input to the greatest extent practicable. The plan will describe each element of the national transportation system that OCRWM is developing for shipping spent nuclear fuel and high-level radioactive waste to the proposed geologic repository at Yucca Mountain, Nevada. The plan will bring together OCRWM's approach for acquiring capital assets (casks, rail cars, and a rail line in Nevada) and its operational planning efforts in a single, comprehensive document. It will also provide a timetable for major transportation decisions and milestones needed to support a 2017 start date for shipments to the Yucca Mountain repository. The NTP will be revised to incorporate new developments and decisions as they are finalized. This paper will describe the elements of the NTP, its importance in providing a comprehensive overview of the national transportation system, and the role of stakeholders in providing input on the NTP and the national transportation system. (authors)

Macaluso, C. [U.S. Department of Energy, Office of Civilian Radioactive Waste Management, Washington, DC (United States); Offner, J.; Patric, J. [Booz Allen Hamilton, Washington, DC (United States)

2008-07-01T23:59:59.000Z

147

Water Management in A PEMFC: Water Transport Mechanism and Material  

E-Print Network [OSTI]

Water Management in A PEMFC: Water Transport Mechanism and Material Degradation in Gas Diffusion on the water management of the PEMFC, namely the transport of product water (both liquid and vapor its water management performance and func- tion as indicators of the degradation of GDL material

Kandlikar, Satish

148

REAL-TIME IDENTIFICATION AND CHARACTERIZATION OF ASBESTOS AND CONCRETE MATERIALS WITH RADIOACTIVE CONTAMINATION  

SciTech Connect (OSTI)

Concrete and asbestos-containing materials were widely used in DOE building construction in the 1940s and 1950s. Over the years, many of these porous materials have been contaminated with radioactive sources, on and below the surface. To improve current practice in identifying hazardous materials and in characterizing radioactive contamination, an interdisciplinary team from Rensselaer has conducted research in two aspects: (1) to develop terahertz time-domain spectroscopy and imaging system that can be used to analyze environmental samples such as asbestos in the field, and (2) to develop algorithms for characterizing the radioactive contamination depth profiles in real-time in the field using gamma spectroscopy. The basic research focused on the following: (1) mechanism of generating of broadband pulsed radiation in terahertz region, (2) optimal free-space electro-optic sampling for asbestos, (3) absorption and transmission mechanisms of asbestos in THz region, (4) the role of asbestos sample conditions on the temporal and spectral distributions, (5) real-time identification and mapping of asbestos using THz imaging, (7) Monte Carlo modeling of distributed contamination from diffusion of radioactive materials into porous concrete and asbestos materials, (8) development of unfolding algorithms for gamma spectroscopy, and (9) portable and integrated spectroscopy systems for field testing in DOE. Final results of the project show that the combination of these innovative approaches has the potential to bring significant improvement in future risk reduction and cost/time saving in DOE's D and D activities.

XU, X. George; Zhang, X.C.

2002-05-10T23:59:59.000Z

149

The Regional Role in Addressing DOE Transportation Concerns  

Broader source: Energy.gov (indexed) [DOE]

CSG's Midwestern Radioactive Materials Transportation Project Presented to the U.S. Department of Energy's Transportation External Coordination Working Group April 21, 2004 Lisa R....

150

Fluorescent Functionalized Mesoporous Silica for Radioactive Material Extraction  

SciTech Connect (OSTI)

Mesoporous silica with covalently bound salicylic acid molecules incorporated in the structure was synthesized with a one-pot, co-condensation reaction at room temperature. The as-synthesized material has a large surface area, uniform particle size, and an ordered pore structure as determined by characterization with transmission electron microscopy, thermal gravimetric analysis, and infrared spectra, etc. Using the strong fluorescence and metal coordination capability of salicylic acid, functionalized mesoporous silica (FMS) was developed to track and extract radionuclide contaminants, such as uranyl [U(VI)] ions encountered in subsurface environments. Adsorption measurements showed a strong affinity of the FMS toward U(VI) with a Kd value of 105 mL/g, which is four orders of magnitude higher than the adsorption of U(VI) onto most of the sediments in natural environments. The new materials have a potential for synergistic environmental monitoring and remediation of the radionuclide U(VI) from contaminated subsurface environments.

Li, Juan; Zhu, Kake; Shang, Jianying; Wang, Donghai; Nie, Zimin; Guo, Ruisong; Liu, Chongxuan; Wang, Zheming; Li, Xiaolin; Liu, Jun

2012-08-01T23:59:59.000Z

151

Guidance for use of Radiology Devices and Radioactive Materials in Research Protocols  

E-Print Network [OSTI]

Guidance for use of Radiology Devices and Radioactive Materials in Research Protocols Definition preparation, handling, storage, administration, and waste disposal in sufficient detail to permit a radiological hazards evaluation of the proposal, including potential for radiation dose to other health care

Puglisi, Joseph

152

Physical test report for drop test of a 9974 radioactive material shipping packaging  

SciTech Connect (OSTI)

This report presents the drop test results for the 9974 radioactive material shipping package being dropped onto 6-inch diameter, 40-inch long puncture pin. Also reported are the drop test resuls for a 30-foot impact that failed the drum confinement boundary. The purpose of these drops was to show that the package lid would remain attached to the drum.

Blanton, P.S. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1997-10-01T23:59:59.000Z

153

Data collection handbook to support modeling the impacts of radioactive material in soil  

SciTech Connect (OSTI)

A pathway analysis computer code called RESRAD has been developed for implementing US Department of Energy Residual Radioactive Material Guidelines. Hydrogeological, meteorological, geochemical, geometrical (size, area, depth), and material-related (soil, concrete) parameters are used in the RESRAD code. This handbook discusses parameter definitions, typical ranges, variations, measurement methodologies, and input screen locations. Although this handbook was developed primarily to support the application of RESRAD, the discussions and values are valid for other model applications.

Yu, C.; Cheng, J.J.; Jones, L.G.; Wang, Y.Y.; Faillace, E. [Argonne National Lab., IL (United States). Environmental Assessment and Information Sciences Div.; Loureiro, C. [Minas Gerais Univ., Belo Horizonte, MG (Brazil). Escola de Engenharia; Chia, Y.P. [National Taiwan Univ., Taipei (Taiwan, Province of China). Dept. of Geology

1993-04-01T23:59:59.000Z

154

Nondestructive NMR technique for moisture determination in radioactive materials.  

SciTech Connect (OSTI)

This progress report focuses on experimental and computational studies used to evaluate nuclear magnetic resonance (NMR) spectroscopy and magnetic resonance imaging (MRI) for detecting, quantifying, and monitoring hydrogen and other magnetically active nuclei ({sup 3}H, {sup 3}He, {sup 239}Pu, {sup 241}Pu) in Spent nuclear fuels and packaging materials. The detection of moisture by using a toroid cavity NMR imager has been demonstrated in SiO{sub 2} and UO{sub 2} systems. The total moisture was quantified by means of {sup 1}H NMR detection of H{sub 2}O with a sensitivity of 100 ppm. In addition, an MRI technique that was used to determine the moisture distribution also enabled investigators to discriminate between bulk and stationary water sorbed on the particles. This imaging feature is unavailable in any other nondestructive assay (NDA) technique. Following the initial success of this program, the NMR detector volume was scaled up from the original design by a factor of 2000. The capacity of this detector exceeds the size specified by DOE-STD-3013-96.

Aumeier, S.; Gerald, R.E. II; Growney, E.; Nunez, L.; Kaminski, M.

1998-12-04T23:59:59.000Z

155

Measurements and analyses of decay radioactivity induced in simulated deuterium-tritium neutron environments for fusion reactor structural materials  

SciTech Connect (OSTI)

To meet urgent requirements for data validation, an experimental analysis has been carried out for isotopic radioactivity induced by deuterium-tritium neutron irradiation in structural materials. The primary objective is to examine the adequacy of the activation cross sections implemented in the current activation calculation codes considered for use in fusion reactor nuclear design. Four activation cross-section libraries, namely, JENDL, LIB90, REAC{sup *}63, and REAC{sup *}175 were investigated in this current analysis. The isotopic induced radioactivity calculations using these four libraries are compared with experimental values obtained in the Japan Atomic Energy Research Institute/U.S. Department of Energy collaborative program on fusion blanket neutronics. The nine materials studied are aluminum, silicon, titanium, vanadium, chromium, MnCu alloy, iron, nickel, niobium, and Type 316 stainless steel. The adequacy of the cross sections is investigated through the calculation to experiment analysis. As a result, most of the discrepancies in the calculations from experiments can be explained by inadequate activation cross sections. In addition, uncertainties due to neutron energy groups and neutron transport calculation are considered. The JENDL library gives the best agreement with experiments, followed by REAC{sup *}175, LIB90, and REAC{sup *}63, in this order. 45 refs., 32 figs., 5 tabs.

Ikeda, Y.; Konno, C.; Kosako, K.; Oyama, Y.; Maekawa, F.; Maekawa, H. [Japan Atomic Energy Research Inst., Ibaraki (Japan); Kumar, A.; Youssef, M.Z.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States)

1995-08-01T23:59:59.000Z

156

APPLICATION FO FLOW FORMING FOR USE IN RADIOACTIVE MATERIAL PACKAGING DESIGNS  

SciTech Connect (OSTI)

This paper reports on the development and testing performed to demonstrate the use of flow forming as an alternate method of manufacturing containment vessels for use in radioactive material shipping packaging designs. Additionally, ASME Boiler and Pressure Vessel Code, Section III, Subsection NB compliance along with the benefits compared to typical welding of containment vessels will be discussed. SRNL has completed fabrication development and the testing on flow formed containment vessels to demonstrate the use of flow forming as an alternate method of manufacturing a welded 6-inch diameter containment vessel currently used in the 9975 and 9977 radioactive material shipping packaging. Material testing and nondestructive evaluation of the flow formed parts demonstrate compliance to the minimum material requirements specified in applicable parts of ASME Boiler and Pressure Vessel Code, Section II. Destructive burst testing shows comparable results to that of a welded design. The benefits of flow forming as compared to typical welding of containment vessels are significant: dimensional control is improved due to no weld distortion; less final machining; weld fit-up issues associated with pipes and pipe caps are eliminated; post-weld non-destructive testing (i.e., radiography and die penetrant tests) is not necessary; and less fabrication steps are required. Results presented in this paper indicate some of the benefits in adapting flow forming to design of future radioactive material shipping packages containment vessels.

Blanton, P.; Eberl, K.; Abramczyk, G.

2012-07-11T23:59:59.000Z

157

Decay radioactivity induced in plasma-facing materials by deutrium-tritium neutrons  

SciTech Connect (OSTI)

Deuterium-tritium (D-T) neutron-induced radioactivity constitutes one of the foremost issues in fusion reactor design. Designers have been using radioactivity codes and associated nuclear data libraries for nucleonic designs of fusion reactors. However, in the past, there was hardly any experimental validation of these codes/libraries. An elaborate, experimental program was initiated in 1988 under a U.S. Department of Energy/Japan Atomic Energy Research Institute collaborative program to validate the radioactivity codes/libraries. As many as 14 neutron energy spectra were covered for a number of materials. The analyses of the isotopic activities of the irradiated materials using the activation cross-section libraries of four leading radioactivity codes, i.e., ACT4/THIDA-1, REAC-3. DKR-ICF; and RACC, have shown large discrepancies among the calculations on one hand and between the calculations and the measurements, on the other. Vanadium, Co, Ni, Zn, Zr, Mo, In, Sn, and W each count the largest number of discrepant isotopic activities. In addition to providing detailed results of the status of predictability of individual isotopic activities using the ACT4, REAC-3, DKR-ICF, and RACC activation cross-section libraries, safety factors cum quality factors characterizing each library are presented and discussed. The related issues of confidence level and associated uncertainty are also highlighted. 37 refs., 112 figs., 24 tabs.

Kumar, A.; Abdou, M.A.; Youssef, M.Z. [Univ. of California, Los Angeles, CA (United States); Ikeda, Y.; Konno, C.; Kosako, K.; Oyama, Y.; Nakamura, T.; Maekawa, H. [Japan Atomic Energy Research Inst., Ibaraki (Japan)

1995-08-01T23:59:59.000Z

158

Hazardous materials transportation and emergency response programs  

SciTech Connect (OSTI)

This presentation consists of the following visual aids; (1) detailed routing capabilities of truck, rail, barge; (2) legislative data base for hazardous materials; and (3) emergency response of accident site Eddyville, Kentucky (airports in vicinity of Eddyville, KY).

Joy, D.S.; Fore, C.S.

1983-01-01T23:59:59.000Z

159

Vulnerability Analysis Considerations for the Transportation of Special Nuclear Material  

SciTech Connect (OSTI)

The vulnerability analysis methodology developed for fixed nuclear material sites has proven to be extremely effective in assessing associated transportation issues. The basic methods and techniques used are directly applicable to conducting a transportation vulnerability analysis. The purpose of this paper is to illustrate that the same physical protection elements (detection, delay, and response) are present, although the response force plays a dominant role in preventing the theft or sabotage of material. Transportation systems are continuously exposed to the general public whereas the fixed site location by its very nature restricts general public access.

Nicholson, Lary G.; Purvis, James W.

1999-07-21T23:59:59.000Z

160

In-situ remediation of naturally occurring radioactive materials with high-permeability hydraulic fracturing  

E-Print Network [OSTI]

IN-SITU REMEDIATION OF NATURALLY OCCURRING RADIOACTIVE MATERIALS WITH HIGH-PERMEABILITY HYDRAULIC FRACTURING A Thesis by ANDRONIKOS STAVROS DEMARCHOS Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment... Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE Approved as to style and content by: Michael J. Economides (Chair of Committee) ulat D. Mamora (Member...

Demarchos, Andronikos Stavros

1998-01-01T23:59:59.000Z

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


161

Radioactive materials released from nuclear power plants: Annual report, 1993. Volume 14  

SciTech Connect (OSTI)

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1993 have been compiled and reported. The summary data for the years 1974 through 1992 are included for comparison. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1993 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Tichler, J.; Doty, K.; Lucadamo, K. [Brookhaven National Lab., Upton, NY (United States)

1995-12-01T23:59:59.000Z

162

Transportation of Nuclear Materials | Department of Energy  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up from theDepartment of EnergyThe SunMelissa HowellTechnologies »Transportation of

163

A regulatory analysis on emergency preparedness for fuel cycle and other radioactive material licensees: Final report  

SciTech Connect (OSTI)

The question this Regulatory Analysis sought to answer is: should the NRC impose additional emergency preparedness requirements on certain fuel cycle and other radioactive material licensees for dealing with accidents that might have offsite releases of radioactive material. To answer the question, we analyzed potential accidents for 15 types of fuel cycle and other radioactive material licensees. An appropriate plan would: (1) identify accidents for which protective actions should be taken by people offsite; (2) list the licensee's responsibilities for each type of accident, including notification of local authorities (fire and police generally); and (3) give sample messages for local authorities including protective action recommendations. This approach more closely follows the approach used for research reactors than for power reactors. The low potential offsite doses (acute fatalities and injuries not possible except possibly for UF/sub 6/ releases), the small areas where actions would be warranted, the small number of people involved, and the fact that the local police and fire departments would be doing essentially the same things they normally do, are all factors that tend to make a simple plan adequate. This report discusses the potentially hazardous accidents, and the likely effects of these accidents in terms of personnel danger.

McGuire, S.A.

1988-01-01T23:59:59.000Z

164

Apparatus for the processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents [OSTI]

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination oaf plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter.

Gotovchikov, Vitaly T. (Moscow, RU); Ivanov, Alexander V. (Moscow, RU); Filippov, Eugene A. (Moscow, RU)

1999-03-16T23:59:59.000Z

165

Apparatus for the processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents [OSTI]

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter. 6 figs.

Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

1999-03-16T23:59:59.000Z

166

Real time method and computer system for identifying radioactive materials from HPGe gamma-ray spectroscopy  

DOE Patents [OSTI]

A real-time method and computer system for identifying radioactive materials which collects gamma count rates from a HPGe gamma-radiation detector to produce a high-resolution gamma-ray energy spectrum. A library of nuclear material definitions ("library definitions") is provided, with each uniquely associated with a nuclide or isotope material and each comprising at least one logic condition associated with a spectral parameter of a gamma-ray energy spectrum. The method determines whether the spectral parameters of said high-resolution gamma-ray energy spectrum satisfy all the logic conditions of any one of the library definitions, and subsequently uniquely identifies the material type as that nuclide or isotope material associated with the satisfied library definition. The method is iteratively repeated to update the spectrum and identification in real time.

Rowland, Mark S. (Alamo, CA); Howard, Douglas E. (Livermore, CA); Wong, James L. (Dublin, CA); Jessup, James L. (Tracy, CA); Bianchini, Greg M. (Livermore, CA); Miller, Wayne O. (Livermore, CA)

2007-10-23T23:59:59.000Z

167

Greater-than-Class C low-level radioactive waste transportation regulations and requirements study. National Low-Level Waste Management Program  

SciTech Connect (OSTI)

The purpose of this report is to identify the regulations and requirements for transporting greater-than-Class C (GTCC) low-level radioactive waste (LLW) and to identify planning activities that need to be accomplished in preparation for transporting GTCC LLW. The regulations and requirements for transporting hazardous materials, of which GTCC LLW is included, are complex and include several Federal agencies, state and local governments, and Indian tribes. This report is divided into five sections and three appendices. Section 1 introduces the report. Section 2 identifies and discusses the transportation regulations and requirements. The regulations and requirements are divided into Federal, state, local government, and Indian tribes subsections. This report does not identify the regulations or requirements of specific state, local government, and Indian tribes, since the storage, treatment, and disposal facility locations and transportation routes have not been specifically identified. Section 3 identifies the planning needed to ensure that all transportation activities are in compliance with the regulations and requirements. It is divided into (a) transportation packaging; (b) transportation operations; (c) system safety and risk analysis, (d) route selection; (e) emergency preparedness and response; and (f) safeguards and security. This section does not provide actual planning since the details of the Department of Energy (DOE) GTCC LLW Program have not been finalized, e.g., waste characterization and quantity, storage, treatment and disposal facility locations, and acceptance criteria. Sections 4 and 5 provide conclusions and referenced documents, respectively.

Tyacke, M.; Schmitt, R.

1993-07-01T23:59:59.000Z

168

CLOSURE WELDING RADIOACTIVE MATERIALS CONTAINERS AT THE DEPARTMENT OF ENERGY (DOE) HANFORD SITE  

SciTech Connect (OSTI)

The Department of Energy's (DOE) responsibility for the disposition of radioactive materials has given rise to several unique welding applications. Many of these materials require packaging into containers for either Interim or long-term storage. It is not uncommon that final container fabrication, i.e., closure welding, is performed with these materials already placed into the container. Closure welding is typically performed remote to the container, and routine post-weld testing and nondestructive examination (NDE) are often times not feasible. Fluor Hanford has packaged many such materials in recent years as park of the Site's cleanup mission. In lieu of post-weld testing and NDE, the Fluor-Hanford approach has been to establish weld quality through ''upfront'' development and qualification of welding parameters, and then ensure parameter compliance during welding. This approach requires a rigor not usually afforded to typical welding development activities, and may involve statistical analysis and extensive testing, including burst, drop, sensitive leak testing, etc. This paper provides an instructive review of the development and qualification activities associated with the closure of radioactive materials containers, including a brief report on activities for closure welding research reactor, spent nuclear fuel (SNF) overpacks at the Hanford Site.

CANNELL, G.R.

2006-09-01T23:59:59.000Z

169

Enhancing Railroad Hazardous Materials Transportation Safety  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES AND INTER-JURISDICTIONAL CHALLENGESRailroad Hazardous g Materials

170

Materials and Transportation Services | The Ames Laboratory  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recovery challenge fund LasDubey selectedContract ResearchMaterials and

171

Mixed-layered bismuth-oxygen-iodine materials for capture and waste disposal of radioactive iodine  

DOE Patents [OSTI]

Materials and methods of synthesizing mixed-layered bismuth oxy-iodine materials, which can be synthesized in the presence of aqueous radioactive iodine species found in caustic solutions (e.g. NaOH or KOH). This technology provides a one-step process for both iodine sequestration and storage from nuclear fuel cycles. It results in materials that will be durable for repository conditions much like those found in Waste Isolation Pilot Plant (WIPP) and estimated for Yucca Mountain (YMP). By controlled reactant concentrations, optimized compositions of these mixed-layered bismuth oxy-iodine inorganic materials are produced that have both a high iodine weight percentage and a low solubility in groundwater environments.

Krumhansl, James L; Nenoff, Tina M

2013-02-26T23:59:59.000Z

172

Criteria for cesium capsules to be shipped as special form radioactive material  

SciTech Connect (OSTI)

The purpose of this report is to compile all the documentation which defines the criteria for Waste Encapsulation and Storage Facility (WESF) cesium capsules at the IOTECH facility and Applied Radiant Energy Corporation (ARECO) to be shipped as special form radioactive material in the Beneficial Uses Shipping System (BUSS) Cask. The capsules were originally approved as special form in 1975, but in 1988 the integrity of the capsules came into question. WHC developed the Pre-shipment Acceptance Test Criteria for capsules to meet in order to be shipped as special form material. The Department of Energy approved the criteria and directed WHC to ship the capsules at IOTECH and ARECO meeting this criteria to WHC as special form material.

Lundeen, J.E.

1994-10-01T23:59:59.000Z

173

Derivation of uranium residual radioactive material guidelines for the Shpack site  

SciTech Connect (OSTI)

Residual radioactive material guidelines for uranium were derived for the Shpack site in Norton, Massachusetts. This site has been identified for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy (DOE). The uranium guidelines were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the Shpack site should not exceed a dose of 100 mrem/yr following decontamination. The DOE residual radioactive material guideline computer code, RESRAD, which implements the methodology described in the DOE manual for implementing residual radioactive material guidelines, was used in this evaluation. Three potential scenarios were considered for the site; the scenarios vary with regard to time spent at the site, sources of water used, and sources of food consumed. The results of the evaluation indicate that the basic dose limit of 100 mrem/yr will not be exceeded for uranium (including uranium-234, uranium-235, and uranium-238) within 1000 years, provided that the soil concentration of combined uranium (uranium-234 and uranium-238) at the Shpack site does not exceed the following levels: 2500 pCi/g for Scenario A (recreationist: the expected scenario); 1100 pCi/g for Scenario B (industrial worker: a plausible scenario); and 53 pCi/g for Scenario C (resident farmer using a well water as the only water source: a possible but unlikely scenario). The uranium guidelines derived in this report apply to the combined activity concentration of uranium-234 and uranium-238 and were calculated on the basis of a dose of 100 mrem/yr. In setting the actual uranium guidelines for the Shpack site, DOE will apply the as low as reasonably achievable (ALARA) policy to the decision-making process, along with other factors, such as whether a particular scenario is reasonable and appropriate. 8 refs., 2 figs., 8 tabs.

Cheng, J.J.; Yu, C.; Monette, F.; Jones, L.

1991-08-01T23:59:59.000Z

174

Analysis of emitter material transport in thermionic converter  

SciTech Connect (OSTI)

Output power and efficiency of a thermionic converter depend on temperatures, cesiated work functions, and emissivities of electrodes as well as the interelectrode gap size. Operation lifetime of a thermionic converter is directly related to the values as well as the stability of these parameters, which can be seriously altered by the transport of emitter material to the collector during operation. Loss rate of tungsten, a preferred emitter material, by sublimation at typical operating temperatures is small (about 3{times}10{sup 7} atom/cm{sup 2}sec at 2000 K). The loss rate, however, can be several orders of magnitude higher in the presence of gaseous contaminants. Accelerated transport of emitter material to collector surface changes the effective emissivity and work functions of the electrodes, resulting in performance degradation. A phenomenological model was developed to simulate emitter material transport to the collector in the presence of oxygen, water vapor, and carbon oxide contaminants. The model accounts for interaction of these contaminants with both emitter and collector. Model results were in agreement with experimental data and theoretical results of other investigators. An analysis was performed to determine steady-state chemical composition of deposited material onto the collector surface in the presence of H{sub 2}O, O{sub 2}, and H{sub 2} gaseous contaminants. {copyright} {ital 1996 American Institute of Physics.}

Paramonov, D.V.; El-Genk, M.S. [Institute for Space and Nuclear Power Studies, Chemical and Nuclear Engineering Department, University of New Mexico, Albuquerque, New Mexico 87131 (United States)

1996-03-01T23:59:59.000Z

175

Development of a computer model for calculation of radioactive materials into the atmosphere after an accident  

SciTech Connect (OSTI)

Secondary atmospheric contamination with radioactive dust and chemical species deposited on the ground and resuspended by wind occur very widely. This process is particularly pronounced in case of extensive contamination of soil and under extreme weather conditions, for example, during dust storms. The mechanism of wind dust generation consists in the following. At low wind speed U=2-3 m/s, which is most common in midlatitude, small radioactive dust particles (diameter of hundredth of a micron to 10-20 microns) are lifted from soil surface due to turbulent vortexes. Under the gravitational force the particles of 1-2 micron diameter practically do not settle. Larger dust particles cannot remain in the air for a long time: they are lifted by turbulent vortexes and settle, their motion in the wind flow is jump-wise and the interaction of particles with the flow is called saltation /I/. Saltation is the main mechanism of dust generation up to the wind velocity at which wind erosion starts. The size of dust particles can be as large as 100 pm. When dropping they can be ricocheting from ground or pass the impulse to other particles which begin rolling over and jumping up. The process of dust transport by wind can be compared to a chain reaction. At the velocity of 10 m/s large particles of about 500 pm stop skipping and roll over only, while particles of more than 1 mm remain stationary. Thus, the fine fraction is blown out from the polydispersed soil particles. The intensity of wind resuspension of radioactive dust from the ground is characterized either by a resuspension factor or a resuspension rate.

Schershakov, V. [Federal Information Analytical Centre, Obinski (Russia)

1997-11-01T23:59:59.000Z

176

A workshop on developing risk assessment methods for medical use of radioactive material. Volume 1: Summary  

SciTech Connect (OSTI)

A workshop was held at the Idaho National Engineering Laboratory, August 16--18, 1994 on the topic of risk assessment on medical devices that use radioactive isotopes. Its purpose was to review past efforts to develop a risk assessment methodology to evaluate these devices, and to develop a program plan and a scoping document for future methodology development. This report contains a summary of that workshop. Participants included experts in the fields of radiation oncology, medical physics, risk assessment, human-error analysis, and human factors. Staff from the US Nuclear Regulatory Commission (NRC) associated with the regulation of medical uses of radioactive materials and with research into risk-assessment methods participated in the workshop. The workshop participants concurred in NRC`s intended use of risk assessment as an important technology in the development of regulations for the medical use of radioactive material and encouraged the NRC to proceed rapidly with a pilot study. Specific recommendations are included in the executive summary and the body of this report. An appendix contains the 8 papers presented at the conference: NRC proposed policy statement on the use of probabilistic risk assessment methods in nuclear regulatory activities; NRC proposed agency-wide implementation plan for probabilistic risk assessment; Risk evaluation of high dose rate remote afterloading brachytherapy at a large research/teaching institution; The pros and cons of using human reliability analysis techniques to analyze misadministration events; Review of medical misadministration event summaries and comparison of human error modeling; Preliminary examples of the development of error influences and effects diagrams to analyze medical misadministration events; Brachytherapy risk assessment program plan; and Principles of brachytherapy quality assurance.

Tortorelli, J.P. [ed.] [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1995-08-01T23:59:59.000Z

177

Evaluation of exposure pathways to man from disposal of radioactive materials into sanitary sewer systems  

SciTech Connect (OSTI)

In accordance with 10 CFR 20, the US Nuclear Regulatory Commission (NRC) regulates licensees` discharges of small quantities of radioactive materials into sanitary sewer systems. This generic study was initiated to examine the potential radiological hazard to the public resulting from exposure to radionuclides in sewage sludge during its treatment and disposal. Eleven scenarios were developed to characterize potential exposures to radioactive materials during sewer system operations and sewage sludge treatment and disposal activities and during the extended time frame following sewage sludge disposal. Two sets of deterministic dose calculations were performed; one to evaluate potential doses based on the radionuclides and quantities associated with documented case histories of sewer system contamination and a second, somewhat more conservative set, based on theoretical discharges at the maximum allowable levels for a more comprehensive list of 63 radionuclides. The results of the stochastic uncertainty and sensitivity analysis were also used to develop a collective dose estimate. The collective doses for the various radionuclides and scenarios range from 0.4 person-rem for {sup 137}Cs in Scenario No. 5 (sludge incinerator effluent) to 420 person-rem for {sup 137}Cs in Scenario No. 3 (sewage treatment plant liquid effluent). None of the 22 scenario/radionuclide combinations considered have collective doses greater than 1000 person-rem/yr. However, the total collective dose from these 22 combinations was found to be about 2100 person-rem.

Kennedy, W.E. Jr.; Parkhurst, M.A.; Aaberg, R.L.; Rhoads, K.C.; Hill, R.L.; Martin, J.B. [Pacific Northwest Lab., Richland, WA (United States)

1992-05-01T23:59:59.000Z

178

USING A RISK-BASED METHODOLOGY FOR THE TRANSFER OF RADIOACTIVE MATERIAL WITHIN THE SAVANNAH RIVER SITE BOUNDARY  

SciTech Connect (OSTI)

Shipment of radioactive materials (RAM) is discussed in the Code of Federal Regulations in parts of both 49 CFR and 10 CFR. The regulations provide the requirements and rules necessary for the safe shipment of RAM across public highways, railways, waterways, and through the air. These shipments are sometimes referred to as in-commerce shipments. Shipments of RAM entirely within the boundaries of Department of Energy sites, such as the Savannah River Site (SRS), can be made using methodology allowing provisions to maintain equivalent safety while deviating from the regulations for in-commerce shipments. These onsite shipments are known as transfers at the SRS. These transfers must follow the requirements approved in a site-specific Transportation Safety Document (TSD). The TSD defines how the site will transfer materials so that they have equivalence to the regulations. These equivalences are documented in an Onsite Safety Assessment (OSA). The OSA can show how a particular packaging used onsite is equivalent to that which would be used for an in-commerce shipment. This is known as a deterministic approach. However, when a deterministic approach is not viable, the TSD allows for a risk-based OSA to be written. These risk-based assessments show that if a packaging does not provide the necessary safety to ensure that materials are not released (during normal or accident conditions) then the worst-case release of materials does not result in a dose consequence worse than that defined for the SRS. This paper will discuss recent challenges and successes using this methodology at the SRS.

Loftin, B.; Watkins, R.; Loibl, M.

2010-06-03T23:59:59.000Z

179

Compendium of Material Composition Data for Radiation Transport Modeling  

SciTech Connect (OSTI)

Introduction Meaningful simulations of radiation transport applications require realistic definitions of material composition and densities. When seeking that information for applications in fields such as homeland security, radiation shielding and protection, and criticality safety, researchers usually encounter a variety of materials for which elemental compositions are not readily available or densities are not defined. Publication of the Compendium of Material Composition Data for Radiation Transport Modeling, Revision 0, in 2006 was the first step toward mitigating this problem. Revision 0 of this document listed 121 materials, selected mostly from the combined personal libraries of staff at the Pacific Northwest National Laboratory (PNNL), and thus had a scope that was recognized at the time to be limited. Nevertheless, its creation did provide a well-referenced source of some unique or hard-to-define material data in a format that could be used directly in radiation transport calculations being performed at PNNL. Moreover, having a single common set of material definitions also helped to standardize at least one aspect of the various modeling efforts across the laboratory by providing separate researchers the ability to compare different model results using a common basis of materials. The authors of the 2006 compendium understood that, depending on its use and feedback, the compendium would need to be revised to correct errors or inconsistencies in the data for the original 121 materials, as well as to increase (per users suggestions) the number of materials listed. This 2010 revision of the compendium has accomplished both of those objectives. The most obvious change is the increased number of materials from 121 to 372. The not-so-obvious change is the mechanism used to produce the data listed here. The data listed in the 2006 document were compiled, evaluated, entered, and error-checked by a group of individuals essentially by hand, providing no library file or mechanism for revising the data in a consistent and traceable manner. The authors of this revision have addressed that problem by first compiling all of the information (i.e., numbers and references) for all the materials into a single database, maintained at PNNL, that was then used as the basis for this document.

McConn, Ronald J.; Gesh, Christopher J.; Pagh, Richard T.; Rucker, Robert A.; Williams III, Robert

2011-03-04T23:59:59.000Z

180

Operations of the LR56 radioactive liquid cask transport system at U.S. Department of Energy sites  

SciTech Connect (OSTI)

The LR56 cask system is licensed for use in France under Certificate of Compliance F/309/B(U)F for transport of 4,000-liter volumes of radioactive liquids. Three LR56 cask systems (with modifications for use at Department of Energy (DOE) sites) have been purchased for delivery at the Hanford Site, Oak Ridge National Laboratory (ORNL), and Savannah River Site (SRS). The LR56 cask systems will be used for on-site transfers of Type B quantities of radioactive liquid waste. The ORNL unit will also be used as a Type A packaging for transfers of radioactive liquids between DOE sites. This paper discusses LR56 operating features and the use of the cask system at the three DOE sites.

Davidson, J.S. [Lockheed Martin Energy Systems, Oak Ridge, TN (United States); Hornstra, D.J. [Performance Development Corp., Oak Ridge, TN (United States); Sazawal, V.K. [NUMATEC, Inc., Bethesda, MD (United States); Clement, G. [SGN, St. Quentin en Yvelines (France)

1996-06-01T23:59:59.000Z

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


181

Annual Transportation Report for Radioactive Waste Shipments to and from the Nevada Test Site, Fiscal Year 2009  

SciTech Connect (OSTI)

In February 1997, the U.S. Department of Energy (DOE), Nevada Operations Office (now known as the Nevada Site Office) issued the Mitigation Action Plan which addressed potential impacts described in the Final Environmental Impact Statement for the Nevada Test Site and Off-Site Locations in the State of Nevada (DOE/EIS 0243). The DOE, Nevada Operations Office committed to several actions, including the preparation of an annual report, which summarizes waste shipments to and from the Nevada Test Site (NTS) Radioactive Waste Management Site (RWMS) at Area 5 and Area 3. Since 2006, the Area 3 RWMS has been in cold stand-by. This document satisfies requirements regarding low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) transported to and from the NTS during FY 2009. In addition, this document provides shipment, volume, and route information on transuranic (TRU) waste shipped from the NTS to the Idaho National Laboratory, near Idaho Falls, Idaho.

U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2010-02-01T23:59:59.000Z

182

A Transportation Risk Assessment Tool for Analyzing the Transport of Spent Nuclear Fuel and High-Level Radioactive Waste to the Proposed Yucca Mountain Repository  

SciTech Connect (OSTI)

The Yucca Mountain Transportation Database was developed as a data management tool for assembling and integrating data from multiple sources to compile the potential transportation impacts presented in the Draft Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada (DEIS). The database uses the results from existing models and codes such as RADTRAN, RISKIND, INTERLINE, and HIGHWAY to estimate transportation-related impacts of transporting spent nuclear fuel and high-level radioactive waste from commercial reactors and U. S. Department of Energy (DOE) facilities to Yucca Mountain. The source tables in the database are compendiums of information from many diverse sources including: radionuclide quantities for each waste type; route and route characteristics for rail, legal-weight truck, heavy haul. truck, and barge transport options; state-specific accident and fatality rates for routes selected for analysis; packaging and shipment data by waste type; unit risk factors; the complex behavior of the packaged waste forms in severe transport accidents; and the effects of exposure to radiation or the isotopic specific effects of radionclides should they be released in severe transportation accidents. The database works together with the codes RADTRAN (Neuhauser, et al, 1994) and RISKlND (Yuan, et al, 1995) to calculate incident-free dose and accident risk. For the incident-free transportation scenario, the database uses RADTRAN and RISKIND-generated data to calculate doses to offlink populations, onlink populations, people at stops, crews, inspectors, workers at intermodal transfer stations, guards at overnight stops, and escorts, as well as non-radioactive pollution health effects. For accident scenarios, the database uses RADTRAN-generated data to calculate dose risks based on ingestion, inhalation, resuspension, immersion (cloudshine), and groundshine as well as non-radioactive traffic fatalities. The Yucca Mountain EIS Transportation Database was developed using Microsoft Access 97{trademark} software and the Microsoft Windows NT{trademark} operating system. The database consists of tables for storing data, forms for selecting data for querying, and queries for retrieving the data in a predefined format. Database queries retrieve records based on input parameters and are used to calculate incident-free and accident doses using unit risk factors obtained from RADTRAN results. The next section briefly provides some background that led to the development of the database approach used in preparing the Yucca Mountain DEIS. Subsequent sections provide additional details on the database structure and types of impacts calculated using the database.

Ralph Best; T. Winnard; S. Ross; R. Best

2001-08-17T23:59:59.000Z

183

Understanding radioactive waste  

SciTech Connect (OSTI)

This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)

Murray, R.L.

1981-12-01T23:59:59.000Z

184

Demonstration of a computer model for residual radioactive material guidelines, RESRAD  

SciTech Connect (OSTI)

A computer model was developed to calculate residual radioactive material guidelines for the US Department of Energy (DOE). This model, called RESRAD, can be run on IBM or IBM-compatible microcomputer. Seven potential exposure pathways from contaminated soil are analyzed, including external radiation exposure and internal radiation exposure from inhalation and food digestion. The RESRAD code has been applied to several DOE sites to derive soil cleanup guidelines. The experience gained indicates that a comprehensive set of site-specific hydrogeologic and geochemical input parameters must be used for a realistic pathway analysis. The RESRAD code is a useful tool; it is easy to run and very user-friendly. 6 refs., 12 figs.

Yu, C.; Yuan, Y.C.; Zielen, A.J.; Wallo, A. III (Argonne National Lab., IL (USA); USDOE, Washington, DC (USA))

1989-01-01T23:59:59.000Z

185

High temperature materials for radioactive waste incineration and vitrification. Revision 1  

SciTech Connect (OSTI)

Incineration or vitrification of radioactive waste subjects equipment to alkaline or acidic fluxing, oxidation, sulfidation, carburization, and thermal shock. It is necessary to select appropriate materials of construction and control operating conditions to avoid rapid equipment failure. Nickel- and cobalt-based alloys with high chromium or aluminum content and aluminum oxide/chromium oxide refractories with high chromium oxide content have provided the best service in pilot-scale melter tests. Inconel 690 and Monofrax K-3 are being used for waste vitrification. Haynes 188 and high alumina refractory are undergoing pilot scale tests for incineration equipment. Laboratory tests indicate that alloys and refractories containing still higher concentrations of chromium or chromium oxide, such as Inconel 671 and Monofrax E, may provide superior resistance to attack in glass melter environments.

Bickford, D F; Ondrejcin, R S; Salley, L

1986-01-01T23:59:59.000Z

186

Modular glovebox connector and associated good practices for control of radioactive and chemically toxic materials  

SciTech Connect (OSTI)

Design and associated good practices are described for a modular glovebox connector to improve control of radioactive and chemically toxic materials. The connector consists of an anodized aluminum circular port with a mating spacer, gaskets, and retaining rings for joining two parallel ends of commercially available or custom-manufactured glovebox enclosures. Use of the connector allows multiple gloveboxes to be quickly assembled or reconfigured in functional units. Connector dimensions can be scaled to meet operational requirements for access between gloveboxes. Options for construction materials are discussed, along with recommendations for installation of the connector in new or retrofitted systems. Associated good practices include application of surface coatings and caulking, use of disposable glovebags, and proper selection and protection of gasket and glove materials. Use of the connector at an inhalation toxicology research facility has reduced the time and expense required to reconfigure equipment for changing operational requirements, the dispersion of contamination during reconfigurations, and the need for decommissioning and disposal of contaminated enclosures.

Hoover, M.D.; Mewhinney, C.J.; Newton, G.J. [Lovelace Respiratory Research Inst., Albuquerque, NM (United States)

1999-01-01T23:59:59.000Z

187

The design, fabrication and maintenance of semi-trailers employed in the highway transport of weight-concentrated radioactive loads  

SciTech Connect (OSTI)

Transportation of weight-concentrated radioactive loads by truck is an essential part of a safe and economical nuclear industry. This proposed standard presents guidance and performance criteria for the safe transport of these weight-concentrated radioactive loads. ANSI N14.30 will detail specific requirements for the design, fabrication, testing, in-service inspections, maintenance and certification of the semi-trailers to be employed in said service. Furthermore, guidelines for a quality assurance program are also enumerated. This standard would apply to any semi-trailer that may or may not be specifically designed to carry weight-concentrated loads. Equipment not suitable per the criteria established in the standard would be removed from service. The nature of the nuclear industry and the need for a positive public perception of the various processes and players, mandates that the highway transportation of weight-concentrated radioactive loads be standardized and made inherently safe. This proposed standard takes a giant step in that direction.

Huffman, D.S. [Allied-Signal Inc., Metropolis, IL (United States)

1991-12-31T23:59:59.000Z

188

Electron Transport Materials: Synthesis, Properties and Device Performance  

SciTech Connect (OSTI)

We report the design, synthesis and characterization, thermal and photophysical properties of two silane based electron transport materials, dibenzo[b,d]thiophen-2-yltriphenylsilane (Si{phi}87) and (dibenzo[b,d]thiophen-2-yl)diphenylsilane (Si{phi}88) and their performance in blue organic light emitting devices (OLEDs). The utility of these materials in blue OLEDs with iridium (III) bis[(4,6-difluorophenyl)-pyridinato-N,C']picolinate (Firpic) as the phosphorescent emitter was demonstrated. Using the silane Si{phi}87 as the electron transport material (ETm) an EQE of 18.2% was obtained, with a power efficiency of 24.3 lm/W (5.8V at 1mA/cm{sup 2}), in a heterostructure. When Si{phi}88 is used, the EQE is 18.5% with a power efficiency of 26.0 lm/W (5.5V at 1mA/cm{sup 2}).

Cosimbescu, Lelia; Wang, Liang; Helm, Monte L.; Polikarpov, Evgueni; Swensen, James S.; Padmaperuma, Asanga B.

2012-06-01T23:59:59.000Z

189

A HOLISTIC APPROACH FOR DISPOSITION OF LONG-LIVED RADIOACTIVE MATERIALS  

SciTech Connect (OSTI)

During the past 45 years, one of the most challenging scientific, engineering, socio-economic, and political tasks and obligations of our time has been to site and develop technical, politically acceptable, solutions to the safe disposition of long-lived radioactive materials (LLRMs). However, at the end of the year 2002, the Waste Isolation Pilot Plant (WIPP) site in the United States of America (USA) hosts the world's only operating LLRM-disposal system, which (1) is based on the LLRM-disposal principles recommended by the National Academy of Sciences (NAS) in 1957, i.e., deep geological disposal in a ''stable'' salt vault/repository, (2) complies with the nation's ''Environmental Radiation Protection Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes'', and (3) may receive 175,584 cubic meters (m3) of transuranic radioactive waste (TRUW)a. Pending the scheduled opening of repositories for once-used nuclear fuel (OUNF) in the USA, Sweden, and Finland in the years 2010, 2015, and 2017, respectively, LLRM-disposal solutions remain the missing link in all national LLRM-disposition programs. Furthermore, for a variety of reasons, many nations with nuclear programs have chosen a ''spectator'' stance in terms of enhancing the global nuclear safety culture and the nuclear renaissance, and have either ''slow-tracked'' or deferred their LLRM-disposal programs to allow time for an informed national consensus to evolve based on LLRM-disposition experiences and solutions gained elsewhere. In the meantime, LLRMs will continue to amass in different types and levels of safeguarded storage facilities around the world. In an attempt to contribute to the enhancement of the global nuclear safety culture and the nuclear renaissance, the authors developed the sample holistic approach for synergistic disposition of LLRMs comprising LLRM-disposition components considered either ''proven'' or ''promising'' by the authors. The fundamental principles of the holistic approach are: (1) Risk minimization; (2) Minimization of the LLRM volume requiring deep geological disposal; and (3) LLRM-disposition flexibility. An integral element of these principles is to allow time for LLRM-disposition solutions to evolve/mature technically, financially, and politically. Furthermore, contingent upon the desired outcome(s), available financial, scientific, and technical resources, and political will, these components may be implemented separately or in combinations by one or a group of nations.

Eriksson, Leif G.; Dials, George E.; Parker, Frank L.

2003-02-27T23:59:59.000Z

190

Materials performance in a high-level radioactive waste vitrification system  

SciTech Connect (OSTI)

The Defense Waste Processing Facility (DWPF) is a Department of Energy Facility designed to vitrify highly radioactive waste. An extensive materials evaluation program has been completed on key components in the DWPF after twelve months of operation using nonradioactive simulated wastes. Results of the visual inspections of the feed preparation system indicate that the system components, which were fabricated from Hastelloy C-276, should achieve their design lives. Significant erosion was observed on agitator blades that process glass frit slurries; however, design modifications should mitigate the erosion. Visual inspections of the DWPF melter top head and off gas components, which were fabricated from Inconel 690, indicated that varying degrees of degradation occurred. Most of the components will perform satisfactorily for their two year design life. The components that suffered significant attack were the borescopes, primary film cooler brush, and feed tubes. Changes in the operation of the film cooler brush and design modifications to the feed tubes and borescopes is expected to extend their service lives to two years. A program to investigate new high temperature engineered materials and alloys with improved oxidation and high temperature corrosion resistance will be initiated.

Imrich, K.J.; Chandler, G.T.

1996-06-17T23:59:59.000Z

191

Regulatory Initiatives for Control and Release of Technologically Enhanced Naturally-Occurring Radioactive Materials  

SciTech Connect (OSTI)

Current drafts of proposed standards and suggested State regulations for control and release of technologically-enhanced naturally-occurring radioactive material (TENORM), and standards for release of volumetrically-contaminated material in the US are reviewed. These are compared to the recommendations of the International Atomic Energy Association (IAEA) Safety Series and the European Commission (EC) proposals. Past regulatory efforts with respect to TENORM in the US dealt primarily with oil-field related wastes. Currently, nine states (AK, GA, LA, MS, NM, OH, OR SC, TX) have specific regulations pertaining to TENORM, mostly based on uranium mill tailings cleanup criteria. The new US proposals are dose- or risk-based, as are the IAEA and EC recommendations, and are grounded in the linear no threshold hypothesis (LNT). TENORM wastes involve extremely large volumes, particularly scrap metal and mine wastes. Costs to control and dispose of these wastes can be considerable. The current debate over the validity of LNT at low doses and low dose rates is particularly germane to this discussion. Most standards setting organizations and regulatory agencies base their recommendations on the LNT. The US Environmental Protection Agency has released a draft Federal Guidance Report that recommends calculating health risks from low-level exposure to radionuclides based on the LNT. However, some scientific and professional organizations are openly questioning the validity of LNT and its basis for regulations, practices, and costs to society in general. It is not clear at this time how a non-linear regulatory scheme would be implemented.

Egidi, P.V.

1999-03-02T23:59:59.000Z

192

Materials Science and Materials Chemistry for Large Scale Electrochemical Energy Storage: From Transportation to Electrical Grid  

SciTech Connect (OSTI)

Large-scale electrical energy storage has become more important than ever for reducing fossil energy consumption in transportation and for the widespread deployment of intermittent renewable energy in electric grid. However, significant challenges exist for its applications. Here, the status and challenges are reviewed from the perspective of materials science and materials chemistry in electrochemical energy storage technologies, such as Li-ion batteries, sodium (sulfur and metal halide) batteries, Pb-acid battery, redox flow batteries, and supercapacitors. Perspectives and approaches are introduced for emerging battery designs and new chemistry combinations to reduce the cost of energy storage devices.

Liu, Jun; Zhang, Jiguang; Yang, Zhenguo; Lemmon, John P.; Imhoff, Carl H.; Graff, Gordon L.; Li, Liyu; Hu, Jian Z.; Wang, Chong M.; Xiao, Jie; Xia, Guanguang; Viswanathan, Vilayanur V.; Baskaran, Suresh; Sprenkle, Vincent L.; Li, Xiaolin; Shao, Yuyan; Schwenzer, Birgit

2013-02-15T23:59:59.000Z

193

An overview of naturally occurring radioactive materials (NORM) in the petroleum industry  

SciTech Connect (OSTI)

Oil and gas extraction and processing operations sometimes accumulate naturally occurring radioactive materials (NORM) at concentrations above normal in by-product waste streams. Results from NORM surveys indicate that radionuclide concentrations can be quite variable, ranging from undetectable to extremely high levels. To date, efforts to characterize the geographic distribution of NORM have been limited by poor statistical representation. In addition, the fate of NORM in the environment has not been fully defined, and few human health risk assessment have been conducted. Both the petroleum industry and regulators are becoming increasingly concerned about the presence of NORM. At present, most existing federal environmental regulations do not address oil and gas NORM, and only a few states have developed regulatory programs. Available data suggest that the occurrence of NORM (and associated health risks) is significant enough to warrant increased regulatory control. However, before these regulations can be developed, additional research is needed to (1) better characterize the occurrence and distribution of NORM throughout the industry, (2) quantify hazards posed by NORM to industry workers and the general public, and (3) develop effective waste treatment and minimization technologies that will lower the risk associated with NORM and reduce disposal costs.

Smith, K.P.

1992-12-01T23:59:59.000Z

194

Methods of chemical analysis for organic waste constituents in radioactive materials: A literature review  

SciTech Connect (OSTI)

Most of the waste generated during the production of defense materials at Hanford is presently stored in 177 underground tanks. Because of the many waste treatment processes used at Hanford, the operations conducted to move and consolidate the waste, and the long-term storage conditions at elevated temperatures and radiolytic conditions, little is known about most of the organic constituents in the tanks. Organics are a factor in the production of hydrogen from storage tank 101-SY and represent an unresolved safety question in the case of tanks containing high organic carbon content. In preparation for activities that will lead to the characterization of organic components in Hanford waste storage tanks, a thorough search of the literature has been conducted to identify those procedures that have been found useful for identifying and quantifying organic components in radioactive matrices. The information is to be used in the planning of method development activities needed to characterize the organics in tank wastes and will prevent duplication of effort in the development of needed methods.

Clauss, S.A.; Bean, R.M.

1993-02-01T23:59:59.000Z

195

Comments on a paper tilted `The sea transport of vitrified high-level radioactive wastes: Unresolved safety issues`  

SciTech Connect (OSTI)

The cited paper estimates the consequences that might occur should a purpose-built ship transporting Vitrified High Level Waste (VHLW) be involved in a severe collision that causes the VHLW canisters in one Type-B package to spill onto the floor of a major ocean fishing region. Release of radioactivity from VHLW glass logs, failure of elastomer cask seals, failure of VHLW canisters due to stress corrosion cracking (SCC), and the probabilities of the hypothesized accident scenario, of catastrophic cask failure, and of cask recovery from the sea are all discussed.

Sprung, J.L.; McConnell, P.E.; Nigrey, P.J.; Ammerman, D.J. [and others

1997-05-01T23:59:59.000Z

196

Method for making a low density polyethylene waste form for safe disposal of low level radioactive material  

DOE Patents [OSTI]

In the method of the invention low density polyethylene pellets are mixed in a predetermined ratio with radioactive particulate material, then the mixture is fed through a screw-type extruder that melts the low density polyethylene under a predetermined pressure and temperature to form a homogeneous matrix that is extruded and separated into solid monolithic waste forms. The solid waste forms are adapted to be safely handled, stored for a short time, and safely disposed of in approved depositories.

Colombo, P.; Kalb, P.D.

1984-06-05T23:59:59.000Z

197

Physical test report to drop test of a 9975 radioactive material shipping packaging  

SciTech Connect (OSTI)

This report presents the drop test results for the 9975 radioactive material shipping package being dropped 30 feet onto a unyielding surface followed by a 40-inch puncture pin drop. The purpose of these drops was to show that the package lid would remain attached to the drum. The 30-foot drop was designed to weaken the lid closure lug while still maintaining maximum extension of the lugs from the drum surface. This was accomplished by angling the drum approximately 30 degrees from horizontal in an inverted position. In this position, the drum was rotated slightly so as not to embed the closure lugs into the drum as a result of the 30-foot drop. It was determined that this orientation would maximize deformation to the closure ring around the closure lug while still maintaining the extension of the lugs from the package surface. The second drop was from 40 inches above a 40-inch tall 6-inch diameter puncture pin. The package was angled 10 degrees from vertical and aligned over the puncture pin to solidly hit the drum lug(s) in an attempt to disengage the lid when dropped.Tests were performed in response to DOE EM-76 review Q5 inquires that questioned the capability of the 9975 drum lid to remain in place under this test sequence. Two packages were dropped utilizing this sequence, a 9974 and 9975. Test results for the 9974 package are reported in WSRC-RP-97-00945. A series of 40-inch puncture pin tests were also performed on undamaged 9975 and 9974 packages.

Blanton, P.S.

1997-11-11T23:59:59.000Z

198

A workshop on developing risk assessment methods for medical use of radioactive material. Volume 2: Supporting documents  

SciTech Connect (OSTI)

A workshop was held at the Idaho National Engineering Laboratory, August 16--18, 1994 on the topic of risk assessment on medical devices that use radioactive isotopes. Its purpose was to review past efforts to develop a risk assessment methodology to evaluate these devices, and to develop a program plan and a scoping document for future methodology development. This report contains presentation material and a transcript of the workshop. Participants included experts in the fields of radiation oncology, medical physics, risk assessment, human-error analysis, and human factors. Staff from the US Nuclear Regulatory Commission (NRC) associated with the regulation of medical uses of radioactive materials and with research into risk-assessment methods participated in the workshop. The workshop participants concurred in NRC`s intended use of risk assessment as an important technology in the development of regulations for the medical use of radioactive material and encouraged the NRC to proceed rapidly with a pilot study. Specific recommendations are included in the executive summary and the body of this report.

Tortorelli, J.P. [ed.] [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1995-08-01T23:59:59.000Z

199

Upgrading the Radioactive Waste Management Infrastructure in Azerbaijan  

SciTech Connect (OSTI)

Radionuclide uses in Azerbaijan are limited to peaceful applications in the industry, medicine, agriculture and research. The Baku Radioactive Waste Site (BRWS) 'IZOTOP' is the State agency for radioactive waste management and radioactive materials transport. The radioactive waste processing, storage and disposal facility is operated by IZOTOP since 1963 being significantly upgraded from 1998 to be brought into line with international requirements. The BRWS 'IZOTOP' is currently equipped with state-of-art devices and equipment contributing to the upgrade the radioactive waste management infrastructure in Azerbaijan in line with current internationally accepted practices. The IAEA supports Azerbaijan specialists in preparing syllabus and methodological materials for the Training Centre that is currently being organized on the base of the Azerbaijan BRWS 'IZOTOPE' for education of specialists in the area of safety management of radioactive waste: collection, sorting, processing, conditioning, storage and transportation. (authors)

Huseynov, A. [Baku Radioactive Waste Site IZOTOP, Baku (Azerbaijan); Batyukhnova, O. [State Unitary Enterprise Scientific and Industrial Association Radon, Moscow (Russian Federation); Ojovan, M. [Sheffield Univ., Immobilisation Science Lab. (United Kingdom); Rowat, J. [International Atomic Energy Agency, Dept. of Nuclear Safety and Security, Vienna (Austria)

2007-07-01T23:59:59.000Z

200

Radioactive Waste Management (Minnesota)  

Broader source: Energy.gov [DOE]

This section regulates the transportation and disposal of high-level radioactive waste in Minnesota, and establishes a Nuclear Waste Council to monitor the federal high-level radioactive waste...

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


201

A TRANSPORTATION RISK ASSESSMENT TOOL FOR ANALYZING THE TRANSPORT OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE TO THE PROPOSED YUCCA MOUNTAIN REPOSITORY  

SciTech Connect (OSTI)

The Yucca Mountain Draft Environmental Impact Statement (DEIS) analysis addressed the potential for transporting spent nuclear fuel and high-level radioactive waste from 77 origins for 34 types of spent fuel and high-level radioactive waste, 49,914 legal weight truck shipments, and 10,911 rail shipments. The analysis evaluated transportation over 59,250 unique shipment links for travel outside Nevada (shipment segments in urban, suburban or rural zones by state), and 22,611 links in Nevada. In addition, the analysis modeled the behavior of 41 isotopes, 1091 source terms, and used 8850 food transfer factors (distinct factors by isotope for each state). The analysis also used mode-specific accident rates for legal weight truck, rail, and heavy haul truck by state, and barge by waterway. This complex mix of data and information required an innovative approach to assess the transportation impacts. The approach employed a Microsoft{reg_sign} Access database tool that incorporated data from many sources, including unit risk factors calculated using the RADTRAN IV transportation risk assessment computer program. Using Microsoft{reg_sign} Access, the analysts organized data (such as state-specific accident and fatality rates) into tables and developed queries to obtain the overall transportation impacts. Queries are instructions to the database describing how to use data contained in the database tables. While a query might be applied to thousands of table entries, there is only one sequence of queries that is used to calculate a particular transportation impact. For example, the incident-free dose to off-link populations in a state is calculated by a query that uses route segment lengths for each route in a state that could be used by shipments, populations for each segment, number of shipments on each segment, and an incident-free unit risk factor calculated using RADTRAN IV. In addition to providing a method for using large volumes of data in the calculations, the queries provide a straight-forward means used to verify results. Another advantage of using the MS Access database was the ability to develop query hierarchies using nested queries. Calculations were broken into a series of steps, each step represented by a query. For example, the first query might calculate the number of shipment kilometers traveled through urban, rural and suburban zones for all states. Subsequent queries could join the shipment kilometers query results with another table containing unit risk factors calculated using RADTRAN IV to produce radiological impacts. Through the use of queries, impacts by origin, mode, fuel type or many other parameters can be obtained. The paper will show both the flexibility of the assessment tool and the ease it provides for verifying results.

NA

2001-02-15T23:59:59.000Z

202

Packaging and Transportation Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The order establishes safety requirements for the proper packaging and transportation of DOE, including NNSA, offsite shipments and onsite transfers of radioactive and other hazardous materials and for modal transportation. Cancels DOE O 460.1B, 5-14-10

2010-05-14T23:59:59.000Z

203

Packaging and Transfer or Transportation of Materials of National Security Interest  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish requirements and responsibilities for the Transportation Safeguards System (TSS) packaging and transportation and onsite transfer of nuclear explosives, nuclear components, Naval nuclear fuel elements, Category I and Category II special nuclear materials, special assemblies, and other materials of national security interest. Cancels: DOE 5610.12 and DOE 5610.14.

2000-09-29T23:59:59.000Z

204

Optimizing Tank Car Safety Design to Reduce Hazardous Materials Transportation Risk  

E-Print Network [OSTI]

1 Optimizing Tank Car Safety Design to Reduce Hazardous Materials Transportation Risk M. Rapik Saat hazardous materials transport risk by rail · Tank Car Design Optimization Model Tank car weight and capacity model Metrics to assess tank car performance Illustration of the optimization model

Barkan, Christopher P.L.

205

Radioactive Waste Radioactive Waste  

E-Print Network [OSTI]

#12;Radioactive Waste at UF Bldg 831 392-8400 #12;Radioactive Waste · Program is designed to;Radioactive Waste · Program requires · Generator support · Proper segregation · Packaging · labeling #12;Radioactive Waste · What is radioactive waste? · Anything that · Contains · or is contaminated

Slatton, Clint

206

Preliminary 3-D site-scale studies of radioactive colloid transport in the unsaturated zone at  

E-Print Network [OSTI]

at Yucca Mountain, Nevada G.J. Moridis *, Q. Hu, Y.-S. Wu, G.S. Bodvarsson Earth Sciences Division in a repository to be situated in the unsaturated zone (UZ) at Yucca Mountain (YM), Nevada. In this study we of the spatial distribution of hydraulic and transport properties in the Yucca Mountain subsurface are considered

Hu, Qinhong "Max"

207

Summary report on transportation of nuclear fuel materials in Japan : transportation infrastructure, threats identified in open literature, and physical protection regulations.  

SciTech Connect (OSTI)

This report summarizes the results of three detailed studies of the physical protection systems for the protection of nuclear materials transport in Japan, with an emphasis on the transportation of mixed oxide fuel materials1. The Japanese infrastructure for transporting nuclear fuel materials is addressed in the first section. The second section of this report presents a summary of baseline data from the open literature on the threats of sabotage and theft during the transport of nuclear fuel materials in Japan. The third section summarizes a review of current International Atomic Energy Agency, Japanese and United States guidelines and regulations concerning the physical protection for the transportation of nuclear fuel materials.

Cochran, John Russell; Ouchi, Yuichiro (Japan Atomic Energy Agency, Japan); Furaus, James Phillip; Marincel, Michelle K.

2008-03-01T23:59:59.000Z

208

Exciton transport and coherence in molecular and nanostructured materials  

E-Print Network [OSTI]

Over the past 20 years a new classes of optically active materials have been developed that are composites of nano-engineered constituents such as molecules, polymers, and nanocrystals. These disordered materials have ...

Akselrod, Gleb M. (Gleb Markovitch)

2013-01-01T23:59:59.000Z

209

Thermal Transport in Nanoporous Materials for Energy Applications  

E-Print Network [OSTI]

based materials as supercapacitor electrodes, Chemicalas electrochemical supercapacitor electrodes, Chemicaland heat management of supercapacitor modules for vehicle

Fang, Jin

2012-01-01T23:59:59.000Z

210

Derivation of residual radioactive material guidelines for uranium in soil at the Middlesex Sampling Plant Site, Middlesex, New Jersey  

SciTech Connect (OSTI)

Residual radioactive material guidelines for uranium in soil were derived for the Middlesex Sampling Plant (MSP) site in Middlesex, New Jersey. This site has been designated for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy. The site became contaminated from operations conducted in support of the Manhattan Engineer District (MED) and the Atomic Energy Commission (AEC) between 1943 and 1967. Activities conducted at the site included sampling, storage, and shipment of uranium, thorium, and beryllium ores and residues. Uranium guidelines for single radioisotopes and total uranium were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual living or working in the immediate vicinity of the MSP site should not exceed a dose of 30 mrem/yr following remedial action for the current-use and likely future-use scenarios or a dose of 100 mrem/yr for less likely future-use scenarios. The RESRAD computer code, which implements the methodology described in the DOE manual for establishing residual radioactive material guidelines, was used in this evaluation. Four scenarios were considered for the site. These scenarios vary regarding future land use at the site, sources of water used, and sources of food consumed.

Dunning, D.E. [Argonne National Lab., IL (United States). Environmental Assessment Div.

1995-02-01T23:59:59.000Z

211

A guide for the ASME code for austenitic stainless steel containment vessels for high-level radioactive materials  

SciTech Connect (OSTI)

The design and fabrication criteria recommended by the US Department of Energy (DOE) for high-level radioactive materials containment vessels used in packaging is found in Section III, Division 1, Subsection NB of the ASME Boiler and Pressure Vessel Code. This Code provides material, design, fabrication, examination, and testing specifications for nuclear power plant components. However, many of the requirements listed in the Code are not applicable to containment vessels made from austenitic stainless steel with austenitic or ferritic steel bolting. Most packaging designers, engineers, and fabricators are intimidated by the sheer volume of requirements contained in the Code; consequently, the Code is not always followed and many requirements that do apply are often overlooked during preparation of the Safety Analysis Report for Packaging (SARP) that constitutes the basis to evaluate the packaging for certification.

Raske, D.T.

1995-06-01T23:59:59.000Z

212

NGATS ATM-Airportal Project Reference Material (External Release) Next Generation Air Transportation System  

E-Print Network [OSTI]

NGATS ATM-Airportal Project Reference Material (External Release) Next Generation Air Transportation System (NGATS) Air Traffic Management (ATM) - Airportal Project Reference Material May 23, 2007 Manager NASA Mike Madson Project Scientist NASA #12;NGATS ATM-Airportal Project Reference Material

213

ASSESSING EXPOSURE TO THE PUBLIC FROM LOW LEVEL RADIOACTIVE WASTE (LLW) TRANSPORTATION TO THE NEVADA TEST SITE.  

SciTech Connect (OSTI)

The United States (U.S.) Department of Energy (DOE) Nevada Test Site (NTS) is one of two regional sites where low-level radioactive waste (LLW) from approved DOE and U.S. DOD generators across the United States is disposed. In federal fiscal year (FY) 2002, over 57,000 cubic meters of waste was transported to and disposed at the NTS. DOE and U.S. Department of Transportation (DOT) regulations ensure that radiation exposure from truck shipments to members of the public is negligible. Nevertheless, particularly in rural communities along transportation routes in Utah and Nevada, there is perceived risk from members of the public about incremental exposure from LLW trucks, especially when ''Main Street'' and the LLW transportation route are the same. To better quantify the exposure to gamma radiation, a stationary monitoring array of four pressurized ion chambers (PICs) have been set up in a pullout just before LLW trucks reach the entrance to the NTS. The PICs are positioned at a distance of one meter from the sides of the truck trailer and at a height appropriate for the design of the trucks that will be used in FY2003 to haul LLW to the NTS. The use of four PICs (two on each side of the truck) is to minimize and to correct for non-uniformity where radiation levels from waste packages vary from side to side, and from front to back in the truck trailer. The PIC array is being calibrated by collecting readings from each PIC exposed to a known 137Cs source that was positioned at different locations on a flatbed stationed in the PIC array, along with taking secondary readings from other known sources. Continuous data collection using the PICs, with and without a truck in the array, is being used to develop background readings. In addition, acoustic sensors are positioned on each side of the PIC array to record when a large object (presumably a truck) enters the array. In FY2003, PIC surveys from as many incoming LLW trucks as possible will be made and survey data recorded automatically by dataloggers that will be periodically downloaded. Solar panels provide power for the batteries to run both the dataloggers and PICs. Truck drivers have been asked to park their truck within the PIC array for only the time it takes to complete an information log before moving on to one of two Radioactive Waste Management Sites (RWMS) on the NTS. On the log, the truck drivers record their shipment identification number, the time of day, where the waste originated, and information on the route they used to reach the NTS. This data will facilitate comparison of PIC readings with waste manifests and other waste disposal operations data collected at the RWMSs. Gamma radiation measurements collected from the PICs will be analyzed using standard health physics and statistical methods for comparison to DOT standards, but with the added benefit of obtaining an improved understanding of the variability of readings that can occur in the near vicinity of a LLW truck. The data collected will be combined with measurements of street width and other information about transportation routes through towns to develop realistic dose scenarios for citizens in Nevada and Utah towns.

Miller, J.J.; Campbell, S.; Church, B.W.; Shafer, D. S.; Gillespie, D.; Sedano, S.; Cebe, J.J.

2003-02-27T23:59:59.000Z

214

Radiation sensitive devices and systems for detection of radioactive materials and related methods  

DOE Patents [OSTI]

Radiation sensitive devices include a substrate comprising a radiation sensitive material and a plurality of resonance elements coupled to the substrate. Each resonance element is configured to resonate responsive to non-ionizing incident radiation. Systems for detecting radiation from a special nuclear material include a radiation sensitive device and a sensor located remotely from the radiation sensitive device and configured to measure an output signal from the radiation sensitive device. In such systems, the radiation sensitive device includes a radiation sensitive material and a plurality of resonance elements positioned on the radiation sensitive material. Methods for detecting a presence of a special nuclear material include positioning a radiation sensitive device in a location where special nuclear materials are to be detected and remotely interrogating the radiation sensitive device with a sensor.

Kotter, Dale K

2014-12-02T23:59:59.000Z

215

GNEP Material Transportation, Storage and Disposal Analysis FY-08 Summary Report  

SciTech Connect (OSTI)

This report provides a summary for FY-2008 of activities, analyses and products from the Material Transportation, Storage and Disposal (M-TSD) sub-task of Systems Analysis within the Advanced Fuel Cycle Research & Development area of the Global Nuclear Energy Partnership. The objective of this work is to evaluate near-term material management requirements for initial GNEP facilities and activities, long-term requirements for large-scale GNEP technology deployment, and alternatives and paths forward to meet these needs. For FY-08, the work expanded to include the Integrated Waste Management Strategy as well as integration with the newly formed Waste Forms Campaign. The M-TSD team was expanded with the addition of support from Savannah River National Lab (SRNL) to the existing team of Lawrence Livermore National Lab (LLNL), Argonne National Lab (ANL), Idaho National Lab (INL), Sandia National Lab (SNL) and University of Nevada - Reno (UN-R). During the first half of the year, analysis was focused on providing supporting technical analysis and documentation to support anticipated high-level decisions on program direction. A number of analyses were conducted and reports prepared as program deliverables. This work is briefly summarized in this report. Analyses provided informally to other program efforts are included in this report to provide documentation. This year-end summary was planned primarily as a compilation of activities following the anticipated programmatic decisions. These decisions were deferred beyond the end of the year, and funds were reallocated in a number of areas, thus reducing the M-TSD activities. This report summarizes the miscellaneous 'ad-hoc' work conducted during the later part of the year, such as support to the draft Programmatic Environmental Impact Statement (PEIS), and support to other program studies. Major programmatic contributions from the M-TSD team during the year included: (1) Completion of the IWMS in March 2008 as the baseline for waste management calculations for the GNEP Programmatic Environmental Impact Statement (PEIS). The IWMS represents a collaborative effort between the Systems Analysis, Waste Forms, and Separations Campaigns with contributing authors from multiple laboratories. The IWMS reference is: 'Global Nuclear Energy Partnership Integrated Waste Management Strategy, D. Gombert, INL, et al, GNEP-WAST-WAST-AI-RT-2008-000214, March 2008'. (2) As input to the IWMS and support for program decisions, an evaluation of the current regulatory framework in the U.S. pertaining to the disposal of radioactive wastes under an advanced nuclear fuel cycle was completed by ANL. This evaluation also investigated potential disposal pathways for these wastes. The entire evaluation is provided in Appendix A of this report. (3) Support was provided to the development of the GNEP Programmatic Environmental Impact Statement from INL, SNL and ANL M-TSD staff. (4) M-TSD staff prepared input for DSARR (Dynamic Systems Analysis Report for Nuclear Fuel Recycle) report. The DSARR is an INL led report to examine the time-dependent dynamics for a transition from the current open fuel cycle to either a 1-tier or 2-tier closed fuel cycle. Section 5.3 Waste Management Impacts was provided to INL for incorporation into the DSARR. (5) SNL M-TSD staff prepared a M2 milestone report 'Material Transportation, Storage and Disposal Contribution for Secretarial Decision Package'. The report purpose was to comprehensively evaluate and discuss packaging, storage, and transportation for all potential nuclear and radioactive materials in the process and waste streams being considered by the GNEP program. In particular, a systems view was used to capture all packaging, storage, and transport operations needed to link the various functional aspects of the fuel cycle. (6) SRNL M-TSD staff developed a deliverable report 'Management of Decay Heat from Spent Nuclear Fuel'. This report evaluated a range of options for managing the near-term decay heat associated with Cs and Sr in spent nuclear fuel (SNF) reprocessing waste

Halsey, W

2009-01-15T23:59:59.000Z

216

Implementation Guide for Use with DOE O 460.2 Departmental Materials Transportation and Packaging Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The purpose of this guide is to assist those responsible for transporting and packaging Department materials, and to provide an understanding of Department policies on activities which supplement regulatory requirements.

1996-11-15T23:59:59.000Z

217

Computational study of the transport mechanisms of molecules and ions in solid materials  

E-Print Network [OSTI]

electrolytes is a key element in the development of the solid lithium ion batteries. One promising material is dilithium phthalocyanine (Li2Pc), which upon self-assembly may form conducting channels for fast ion transport. Computational chemistry is employed...

Zhang, Yingchun

2009-06-02T23:59:59.000Z

218

Regulations Establishing Restricted Zones for the Transportation of Hazardous Materials (Connecticut)  

Broader source: Energy.gov [DOE]

These regulations establish a Shore Clearance Line which cannot be crossed except in an emergency by any vessel transporting oil or hazardous materials in bulk in Long Island Sound. For the purpose...

219

PERFORMANCE TESTING OF SPRING ENERGIZED C-RINGS FOR USE IN RADIOACTIVE MATERIAL PACKAGINGS CONTAINING TRITIUM  

SciTech Connect (OSTI)

This paper describes the sealing performance testing and results of silver-plated inconel Spring Energized C-Rings used for tritium containment in radioactive shipping packagings. The test methodology used follows requirements of the American Society of Mechanical Engineers (ASME) summarized in ASME Pressure Vessel Code (B&PVC), Section V, Article 10, Appendix IX (Helium Mass Spectrometer Test - Hood Technique) and recommendations by the American National Standards Institute (ANSI) described in ANSI N14.5-1997. The tests parameters bound the predicted structural and thermal responses from conditions defined in the Code of Federal Regulations 10 CFR 71. The testing includes an evaluation of the effects of pressure, temperature, flange deflection, surface roughness, permeation, closure torque, torque sequencing and re-use on performance of metal C-Ring seals.

Blanton, P; Kurt Eberl, K

2007-10-23T23:59:59.000Z

220

Disposition and transportation of surplus radioactive low specific activity nitric acid. Volume 1, Environmental Assessment  

SciTech Connect (OSTI)

DOE is deactivating the PUREX plant at Hanford; this will involve the disposition of about 692,000 liters (183,000 gallons) of surplus nitric acid contaminated with low levels of U and other radionuclides. The nitric acid, designated as low specific activity, is stored in 4 storage tanks at PUREX. Five principal alternatives were evaluated: transfer for reuse (sale to BNF plc), no action, continued storage in Hanford upgraded or new facility, consolidation of DOE surplus acid, and processing the LSA nitric acid as waste. The transfer to BNF plc is the preferred alternative. From the analysis, it is concluded that the proposed disposition and transportation of the acid does not constitute a major federal action significantly affecting the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required.

NONE

1995-05-01T23:59:59.000Z

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


221

PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 |  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) " ,"ClickPipelinesProvedDecemberInitiativesNationalNuclearRocky Mountain OTC

222

Calculation of releases of radioactive materials in gaseous and liquid effluents from pressurized water reactors (PWR-GALE Code). Revision 1  

SciTech Connect (OSTI)

This report revises the original issuance of NUREG-0017, ''Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE-Code)'' (April 1976), to incorporate more recent operating data now available as well as the results of a number of in-plant measurement programs at operating pressurized water reactors. The PWR-GALE Code is a computerized mathematical model for calculating the releases of radioactive material in gaseous and liquid effluents (i.e., the gaseous and liquid source terms). The US Nuclear Regulatory Commission uses the PWR-GALE Code to determine conformance with the requirements of Appendix I to 10 CFR Part 50.

Chandrasekaran, T.; Lee, J.Y.; Willis, C.A.

1985-04-01T23:59:59.000Z

223

Cathode and electrolyte materials for solid oxide fuel cells and ion transport membranes  

DOE Patents [OSTI]

Novel cathode, electrolyte and oxygen separation materials are disclosed that operate at intermediate temperatures for use in solid oxide fuel cells and ion transport membranes based on oxides with perovskite related structures and an ordered arrangement of A site cations. The materials have significantly faster oxygen kinetics than in corresponding disordered perovskites.

Jacobson, Allan J; Wang, Shuangyan; Kim, Gun Tae

2014-01-28T23:59:59.000Z

224

Multiscale modeling of fluid transport in heterogeneous materials using discrete Boltzmann methods  

E-Print Network [OSTI]

transport in porous materials like ceramics, concrete, soils, and rocks plays an impor- tant role in many geometries like porous materials. Here, we review some of our previous work and discuss some recent environmental and technological processes [11.For example, the service life and durability of concrete can

Bentz, Dale P.

225

Fundamental properties of monolithic bentonite buffer material formed by cold isostatic pressing for high-level radioactive waste repository  

SciTech Connect (OSTI)

The methods of fabrication, handling, and emplacement of engineered barriers used in a deep geological repository for high level radioactive waste should be planned as simply as possible from the engineering and economic viewpoints. Therefore, a new concept of a monolithic buffer material around a waste package have been proposed instead of the conventional concept with the use of small blocks, which would decrease the cost for buffer material. The monolithic buffer material is composed of two parts of highly compacted bentonite, a cup type body and a cover. As the forming method of the monolithic buffer material, compaction by the cold isostatic pressing process (CIP) has been employed. In this study, monolithic bentonite bodies with the diameter of about 333 mm and the height of about 455 mm (corresponding to the approx. 1/5 scale for the Japanese reference concept) were made by the CIP of bentonite powder. The dry densities: {rho}d of the bodies as a whole were measured and the small samples were cut from several locations to investigate the density distribution. The swelling pressure and hydraulic conductivity as function of the monolithic body density for CIP-formed specimens were also measured. High density ({rho}d: 1.4--2.0 Mg/m{sup 3}) and homogeneous monolithic bodies were formed by the CIP. The measured results of the swelling pressure (3--15 MPa) and hydraulic conductivity (0.5--1.4 x 10{sup {minus}13} m/s) of the specimens were almost the same as those for the uniaxial compacted bentonite in the literature. It is shown that the vacuum hoist system is an applicable handling method for emplacement of the monolithic bentonite.

Kawakami, S.; Yamanaka, Y.; Kato, K.; Asano, H.; Ueda, H.

1999-07-01T23:59:59.000Z

226

Survey of the degradation modes of candidate materials for high-level radioactive waste disposal containers  

SciTech Connect (OSTI)

Oxidation and atmospheric corrosion data suggest that addition of Cr provides the greatest improvement in oxidation resistance. Cr-bearing cast irons are resistant to chloride environments and solutions containing strongly oxidizing constituents. Weathering steels, including high content and at least 0.04% Cu, appear to provide adequate resistance to oxidation under temperate conditions. However, data from long-term, high-temperature oxidation studies on weathering steels were not available. From the literature, it appears that the low alloy steels, plain carbon steels, cast steels, and cast irons con-ode at similar rates in an aqueous environment. Alloys containing more than 12% Cr or 36% Ni corrode at a lower rate than plain carbon steels, but pitting may be worse. Short term tests indicate that an alloy of 9Cr-1Mo may result in increased corrosion resistance, however long term data are not available. Austenitic cast irons show the best corrosion resistance. A ranking of total corrosion performance of the materials from most corrosion resistant to least corrosion resistant is: Austenitic Cast Iron; 12% Cr = 36% Ni = 9Cr-1Mo; Carbon Steel = Low Alloy Steels; and Cast Iron. Since the materials to be employed in the Advanced Conceptual Design (ACD) waste package are considered to be corrosion allowance materials, the austenitic cast irons, high Cr steels, high Ni steels and the high Cr-Mo steels should not be considered as candidates for the outer containment barrier. Based upon the oxidation and corrosion data available for carbon steels, low alloy steels, and cast irons, a suitable list of candidate materials for a corrosion allowance outer barrier for an ACD waste package could include, A516, 2.25%Cr -- 1%Mo Steel, and A27.

Vinson, D.W.; Nutt, W.M.; Bullen, D.B. [Iowa State Univ. of Science and Technology, Ames, IA (United States)

1995-06-01T23:59:59.000Z

227

Evaluation of geologic materials to limit biological intrusion into low-level radioactive waste disposal sites  

SciTech Connect (OSTI)

This report describes the results of a three-year research program to evaluate the performance of selected soil and rock trench cap designs in limiting biological intrusion into simulated waste. The report is divided into three sections including a discussion of background material on biological interactions with waste site trench caps, a presentation of experimental data from field studies conducted at several scales, and a final section on the interpretation and limitations of the data including implications for the user.

Hakonson, T.E.

1986-02-01T23:59:59.000Z

228

Burnup estimation of fuel sourcing radioactive material based on monitored Cs and Pu isotopic activity ratios in Fukushima N. P. S. accident  

SciTech Connect (OSTI)

After the severe core damage of Fukushima Dai-Ichi Nuclear Power Station, radioactive material leaked from the reactor buildings. As part of monitoring of radioactivity in the site, measurements of radioactivity in soils at three fixed points have been performed for {sup 134}Cs and {sup 137}Cs with gamma-ray spectrometry and for Pu, Pu, and {sup 240}Pu with {alpha}-ray spectrometry. Correlations of radioactivity ratios of {sup 134}Cs to {sup 137}Cs, and {sup 238}Pu to the sum of {sup 239}Pu and {sup 240}Pu with fuel burnup were studied by using theoretical burnup calculations and measurements on isotopic inventories, and compared with the Cs and Pu radioactivity rations in the soils. The comparison indicated that the burnup of the fuel sourcing the radioactivity was from 18 to 38 GWd/t, which corresponded to that of the fuel in the highest power and, therefore, the highest decay heat in operating high-burnup fueled BWR cores. (authors)

Yamamoto, T.; Suzuki, M.; Ando, Y. [Japan Nuclear Energy Safety Organization, Toranomon Towers Office, 14F, 4-1-28, Toranomon, Minato-ku, Tokyo 105-0001 (Japan)

2012-07-01T23:59:59.000Z

229

Survey of the degradation modes of candidate materials for high-level radioactive waste disposal containers. Final report  

SciTech Connect (OSTI)

One of the most significant factors impacting the performance of waste package container materials under repository relevant conditions is the thermal environment. This environment will be affected by the areal power density of the repository, which is dictated by facility design, and the dominant heat transfer mechanism at the site. The near-field environment will evolve as radioactive decay decreases the thermal output of each waste package. Recent calculations (Buscheck and Nitao, 1994) have addressed the importance of thermal loading conditions on waste package performance at the Yucca Mountain site. If a relatively low repository thermal loading design is employed, the temperature and relative humidity near the waste package may significantly affect the degradation of corrosion allowance barriers due to moist air oxidation and radiolytically enhanced corrosion. The purpose this report is to present a literature review of the potential degradation modes for moderately corrosion resistant nickel copper and nickel based candidate materials that may be applicable as alternate barriers for the ACD systems in the Yucca Mountain environment. This report presents a review of the corrosion of nickel-copper alloys, summaries of experimental evaluations of oxidation and atmospheric corrosion in nickel-copper alloys, views of experimental studies of aqueous corrosion in nickel copper alloys, a brief review of galvanic corrosion effects and a summary of stress corrosion cracking in these alloys.

Vinson, D.W.; Bullen, D.B. [Iowa State Univ. of Science and Technology, Ames, IA (United States)

1995-09-22T23:59:59.000Z

230

The Development of an Effective Transportation Risk Assessment Model for Analyzing the Transport of Spent Fuel and High-Level Radioactive Waste to the Proposed Yucca Mountain Repository  

SciTech Connect (OSTI)

Past approaches for assessing the impacts of transporting spent fuel and high-level radioactive waste have not been effectively implemented or have used relatively simple approaches. The Yucca Mountain Draft Environmental Impact Statement (DEIS) analysis considers 83 origins, 34 fuel types, 49,914 legal weight truck shipments, 10,911 rail shipments, consisting of 59,250 shipment links outside Nevada (shipment kilometers and population density pairs through urban, suburban or rural zones by state), and 22,611 shipment links in Nevada. There was additional complexity within the analysis. The analysis modeled the behavior of 41 isotopes, 1091 source terms, and used 8850 food transfer factors (distinct factors by isotope for each state). The model also considered different accident rates for legal weight truck, rail, and heavy haul truck by state, and barge by waterway. To capture the all of the complexities of the transportation analysis, a Microsoft{reg_sign} Access database was created. In the Microsoft{reg_sign} Access approach the data is placed in individual tables and equations are developed in queries to obtain the overall impacts. While the query might be applied to thousands of table entries, there is only one equation for a particular impact. This greatly simplifies the validation effort. Furthermore, in Access, data in tables can be linked automatically using query joins. Another advantage built into MS Access is nested queries, or the ability to develop query hierarchies. It is possible to separate the calculation into a series of steps, each step represented by a query. For example, the first query might calculate the number of shipment kilometers traveled through urban, rural and suburban zones for all states. Subsequent queries could join the shipment kilometers query results with another table containing the state and mode specific accident rate to produce accidents by state. One of the biggest advantages of the nested queries is in validation. Temporarily restricting the query to one origin, one shipment, or one state and validating that the query calculation is returning the expected result allows simple validation. The paper will show the flexibility of the assessment tool to consider a wide variety of impacts. Through the use of pre-designed queries, impacts by origin, mode, fuel type or many other parameters can be obtained.

McSweeney; Thomas; Winnard; Ross; Steven B.; Best; Ralph E.

2001-02-06T23:59:59.000Z

231

FUNCTIONALIZED SILICA AEROGELS: ADVANCED MATERIALS TO CAPTURE AND IMMOBILIZE RADIOACTIVE IODINE  

SciTech Connect (OSTI)

To support the future expansion of nuclear energy, an effective method is needed to capture and safely store radiological iodine-129 released during reprocessing of spent nuclear fuel. Various materials have been investigated to capture and immobilize iodine. In most cases, however, the materials that are effective for capturing iodine cannot subsequently be sintered/densified to create a stable composite that could be a viable waste form. We have developed chemically modified, highly porous, silica aerogels that show sorption capacities higher than 440 mg of I2 per gram at 150 C. An iodine uptake test in dry air containing 4.2 ppm of iodine demonstrated no breakthrough after 3.5 h and indicated a decontamination factor in excess of 310. Preliminary densification tests showed that the I2-loaded aerogels retained more than 92 wt% of I2 after thermal sintering with pressure assistance at 1200 C for 30 min. These high capture and retention efficiencies for I2 can be further improved by optimizing the functionalization process and the chemistry as well as the sintering conditions.

Matyas, Josef; Fryxell, Glen E.; Busche, Brad J.; Wallace, Krys; Fifield, Leonard S.

2011-11-16T23:59:59.000Z

232

Sustainable Food Sustainable Water Land Use & Wildlife Culture & Commun ble Transport Sustainable Materials Local & Sustainable Food Sustainable Wat  

E-Print Network [OSTI]

Sustainable Food Sustainable Water Land Use & Wildlife Culture & Commun ble Transport Sustainable Materials Local & Sustainable Food Sustainable Wat appiness Zero Carbon Zero Waste Sustainable Transport Sustainable Materia munity Equity & Local Economy Health & Happiness Zero Carbon Zero Was Water Land Use

Netoff, Theoden

233

Risk assessment for the on-site transportation of radioactive wastes for the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement  

SciTech Connect (OSTI)

This report documents the risk assessment performed for the on-site transportation of radioactive wastes in the US Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). Risks for the routine shipment of wastes and the impacts from potential accidental releases are analyzed for operations at the Hanford Site (Hanford) near Richland, Washington. Like other large DOE sites, hanford conducts waste management operations for all wastes types; consequently, the impacts calculated for Hanford are expected to be greater than those for smaller sites. The risk assessment conducted for on-site transportation is intended to provide an estimate of the magnitude of the potential risk for comparison with off-site transportation risks assessed for the WM PEIS.

Biwer, B.M.; Monette, F.A.; Chen, S.Y. [Argonne National Lab., IL (United States). Environmental Assessment Div.

1996-12-01T23:59:59.000Z

234

Determination of the radioactive material and plutonium holdup in ducts and piping in the 324 Building  

SciTech Connect (OSTI)

This report describes the measurements Performed to determine the radionuclide content and mass of plutonium in exposed ducts, filters, and piping in the 324 Building at the US Department of Energy Hanford Site in Washington State. This information is needed to characterize facility radiation levels, to verify compliance with criticality safety specifications, and to allow more accurate nuclear material control using nondestructive assay (NDA) methods. Gamma assay techniques typically employed for NDA analysis were used to determine the gamma-emitting isotopes in the ducts, filters, and piping. Passive neutron counting was selected to estimate -the plutonium content because high gamma levels from fission and activation products effectively mask any gamma emissions from plutonium. A high-purity gamma-ray detector Was used to measure the mixed fission and activation radionuclides. A neutron slab detector containing five {sup 3}He proportional counters was used to determine the neutron emission rates and estimate the mass of plutonium present. Both measurement systems followed the methods and procedures routinely used for nuclear waste assay and safeguards measurements.

Haggard, D.L.; Brackenbush, L.W.; Tanner, J.E.

1996-01-01T23:59:59.000Z

235

Radiological Impact Associated to Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM) from Coal-Fired Power Plants Emissions - 13436  

SciTech Connect (OSTI)

Certain materials used and produced in a wide range of non-nuclear industries contain enhanced activity concentrations of natural radionuclides. In particular, electricity production from coal is one of the major sources of increased human exposure to naturally occurring radioactive materials. A methodology was developed to assess the radiological impact due to natural radiation background. The developed research was applied to a specific case study, the Sines coal-fired power plant, located in the southwest coastline of Portugal. Gamma radiation measurements were carried out with two different instruments: a sodium iodide scintillation detector counter (SPP2 NF, Saphymo) and a gamma ray spectrometer with energy discrimination (Falcon 5000, Canberra). Two circular survey areas were defined within 20 km of the power plant. Forty relevant measurements points were established within the sampling area: 15 urban and 25 suburban locations. Additionally, ten more measurements points were defined, mostly at the 20-km area. The registered gamma radiation varies from 20 to 98.33 counts per seconds (c.p.s.) corresponding to an external gamma exposure rate variable between 87.70 and 431.19 nGy/h. The highest values were measured at locations near the power plant and those located in an area within the 6 and 20 km from the stacks. In situ gamma radiation measurements with energy discrimination identified natural emitting nuclides as well as their decay products (Pb-212, Pb-2142, Ra-226, Th-232, Ac-228, Th-234, Pa-234, U- 235, etc.). According to the results, an influence from the stacks emissions has been identified both qualitatively and quantitatively. The developed methodology accomplished the lack of data in what concerns to radiation rate in the vicinity of Sines coal-fired power plant and consequently the resulting exposure to the nearby population. (authors)

Dinis, Maria de Lurdes; Fiuza, Antonio; Soeiro de Carvalho, Jose; Gois, Joaquim [Geo-Environment and Resources Research Centre (CIGAR), Porto University, Faculty of Engineering - FEUP, Rua Dr. Roberto Frias, 4200-465 Porto (Portugal)] [Geo-Environment and Resources Research Centre (CIGAR), Porto University, Faculty of Engineering - FEUP, Rua Dr. Roberto Frias, 4200-465 Porto (Portugal); Meira Castro, Ana Cristina [School of Engineering Polytechnic of Porto - ISEP, Rua Dr. Antonio Bernardino de Almeida, 431, 4200-072, Porto (Portugal)] [School of Engineering Polytechnic of Porto - ISEP, Rua Dr. Antonio Bernardino de Almeida, 431, 4200-072, Porto (Portugal)

2013-07-01T23:59:59.000Z

236

Regulatory analysis on emergency preparedness for fuel cycle and other radioactive material licensees. Draft report for comment  

SciTech Connect (OSTI)

Potential accidents for 15 types of fuel cycle and other radioactive material licensees were analyzed. The most potentially hazardous accident, by a large margin, was determined to be the sudden rupture of a heated multi-ton cylinder of UF/sub 6/. Acute fatalities offsite are probably not credible. Acute permanent injuries may be possible for many hundreds of meters, and clinically observable transient effects of unknown long term consequences may be possible for distances up to a few miles. These effects would be caused by the chemical toxicity of the UF/sub 6/. Radiation doses would not be significant. The most potentially hazardous accident due to radiation exposure was determined to be a large fire at certain facilities handling large quantities of alpha-emitting radionuclides (i.e., Po-210, Pu-238, Pu-239, Am-241, Cm-242, Cm-244) or radioiodines (I-125 and I-131). However, acute fatalities or injuries to people offsite due to accidental releases of these materials do not seem plausible. The only other significant accident was identified as a long-term pulsating criticality at fuel cycle facilities handling high-enriched uranium or plutonium. An important feature of the most serious accidents is that releases are likely to start without prior warning. The releases would usually end within about half an hour. Thus protective actions would have to be taken quickly to be effective. There is not likely to be enough time for dose projections, complicated decisionmaking during the accident, or the participation of personnel not in the immediate vicinity of the site. The appropriate response by the facility is to immediately notify local fire, police, and other emergency personnel and give them a brief predetermined message recommending protective actions. Emergency personnel are generally well qualified to respond effectively to small accidents of these types.

McGuire, S.A.

1985-06-01T23:59:59.000Z

237

Radioactive waste disposal package  

DOE Patents [OSTI]

A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

238

E-Print Network 3.0 - agent-based national radioactive Sample...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

The United Nations Scientific... 's Guidelines for Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM). d National... Radioactive Materials Board on...

239

Model simulation and experiments of flow and mass transport through a nano-material gas filter  

SciTech Connect (OSTI)

A computational model for evaluating the performance of nano-material packed-bed filters was developed. The porous effects of the momentum and mass transport within the filter bed were simulated. For the momentum transport, an extended Ergun-type model was employed and the energy loss (pressure drop) along the packed-bed was simulated and compared with measurement. For the mass transport, a bulk dsorption model was developed to study the adsorption process (breakthrough behavior). Various types of porous materials and gas flows were tested in the filter system where the mathematical models used in the porous substrate were implemented and validated by comparing with experimental data and analytical solutions under similar conditions. Good agreements were obtained between experiments and model predictions.

Yang, Xiaofan; Zheng, Zhongquan C.; Winecki, Slawomir; Eckels, Steve

2013-11-01T23:59:59.000Z

240

Water Transport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing,  

E-Print Network [OSTI]

Optimization J. Vernon Cole and Ashok Gidwani CFDRC Prepared for: DOE Hydrogen Fuel Cell Kickoff MeetingWater Transport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing, and Design fuel cell design and operation; Demonstrate improvements in water management resulting in improved

Note: This page contains sample records for the topic "radioactive materials transportation" from the National Library of EnergyBeta (NLEBeta).
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241

LEVERAGING AGING MATERIALS DATA TO SUPPORT EXTENSION OF TRANSPORTATION SHIPPING PACKAGES SERVICE LIFE  

SciTech Connect (OSTI)

Nuclear material inventories are increasingly being transferred to interim storage locations where they may reside for extended periods of time. Use of a shipping package to store nuclear materials after the transfer has become more common for a variety of reasons. Shipping packages are robust and have a qualified pedigree for performance in normal operation and accident conditions but are only certified over an approved transportation window. The continued use of shipping packages to contain nuclear material during interim storage will result in reduced overall costs and reduced exposure to workers. However, the shipping package materials of construction must maintain integrity as specified by the safety basis of the storage facility throughout the storage period, which is typically well beyond the certified transportation window. In many ways, the certification processes required for interim storage of nuclear materials in shipping packages is similar to life extension programs required for dry cask storage systems for commercial nuclear fuels. The storage of spent nuclear fuel in dry cask storage systems is federally-regulated, and over 1500 individual dry casks have been in successful service up to 20 years in the US. The uncertainty in final disposition will likely require extended storage of this fuel well beyond initial license periods and perhaps multiple re-licenses may be needed. Thus, both the shipping packages and the dry cask storage systems require materials integrity assessments and assurance of continued satisfactory materials performance over times not considered in the original evaluation processes. Test programs for the shipping packages have been established to obtain aging data on materials of construction to demonstrate continued system integrity. The collective data may be coupled with similar data for the dry cask storage systems and used to support extending the service life of shipping packages in both transportation and storage.

Dunn, K. [Savannah River National Laboratory; Bellamy, S. [Savannah River National Laboratory; Daugherty, W. [Savannah River National Laboratory; Sindelar, R. [Savannah River National Laboratory; Skidmore, E. [Savannah River National Laboratory

2013-08-18T23:59:59.000Z

242

Public involvement in radioactive waste management decisions  

SciTech Connect (OSTI)

Current repository siting efforts focus on Yucca Mountain, Nevada, where DOE`s Office of Civilian Radioactive Waste Management (OCRWM) is conducting exploratory studies to determine if the site is suitable. The state of Nevada has resisted these efforts: it has denied permits, brought suit against DOE, and publicly denounced the federal government`s decision to study Yucca Mountain. The state`s opposition reflects public opinion in Nevada, and has considerably slowed DOE`s progress in studying the site. The Yucca Mountain controversy demonstrates the importance of understanding public attitudes and their potential influence as DOE develops a program to manage radioactive waste. The strength and nature of Nevada`s opposition -- its ability to thwart if not outright derail DOE`s activities -- indicate a need to develop alternative methods for making decisions that affect the public. This report analyzes public participation as a key component of this openness, one that provides a means of garnering acceptance of, or reducing public opposition to, DOE`s radioactive waste management activities, including facility siting and transportation. The first section, Public Perceptions: Attitudes, Trust, and Theory, reviews the risk-perception literature to identify how the public perceives the risks associated with radioactivity. DOE and the Public discusses DOE`s low level of credibility among the general public as the product, in part, of the department`s past actions. This section looks at the three components of the radioactive waste management program -- disposal, storage, and transportation -- and the different ways DOE has approached the problem of public confidence in each case. Midwestern Radioactive Waste Management Histories focuses on selected Midwestern facility-siting and transportation activities involving radioactive materials.

NONE

1994-04-01T23:59:59.000Z

243

PAVAN: an atmospheric-dispersion program for evaluating design-basis accidental releases of radioactive materials from nuclear power stations  

SciTech Connect (OSTI)

This report provides a user's guide for the NRC computer program, PAVAN, which is a program used by the US Nuclear Regulatory Commission to estimate downwind ground-level air concentrations for potential accidental releases of radioactive material from nuclear facilities. Such an assessment is required by 10 CFR Part 100 and 10 CFR Part 50. The program implements the guidance provided in Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants. Using joint frequency distributions of wind direction and wind speed by atmospheric stability, the program provides relative air concentration (X/Q) values as functions of direction for various time periods at the exclusion area boundary (EAB) and the outer boundary of the low population zone (LPZ). Calculations of X/Q values can be made for assumed ground-level releases (e.g., through building penetrations and vents) or elevated releases from free-standing stacks. Various options may be selected by the user. They can account for variation in the location of release points, additional plume dispersion due to building wakes, plume meander under low wind speed conditions, and adjustments to consider non-straight trajectories. It computes an effective plume height using the physical release height which can be reduced by inputted terrain features. It cannot handle multiple emission sources. A description of the main program and all subroutines is provided. Also included as appendices are a complete listing of the program and two test cases with the required data inputs and the resulting program outputs.

Bander, T.J.

1982-11-01T23:59:59.000Z

244

Radioactive Material License.  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545*.MSE Cores"December 2010r* R

245

Radioactive Materials Product Stewardship  

E-Print Network [OSTI]

...................................................................................................26 Low Level Waste (LLW) Disposal Regulations...............................................................................13 4.1 RADIONUCLIDES AND NUCLEAR FIXED GAUGES

246

A Preliminary Evaluation of Using Fill Materials to Stabilize Used Nuclear Fuel During Storage and Transportation  

SciTech Connect (OSTI)

This report contains a preliminary evaluation of potential fill materials that could be used to fill void spaces in and around used nuclear fuel contained in dry storage canisters in order to stabilize the geometry and mechanical structure of the used nuclear fuel during extended storage and transportation after extended storage. Previous work is summarized, conceptual descriptions of how canisters might be filled were developed, and requirements for potential fill materials were developed. Elements of the requirements included criticality avoidance, heat transfer or thermodynamic properties, homogeneity and rheological properties, retrievability, material availability and cost, weight and radiation shielding, and operational considerations. Potential fill materials were grouped into 5 categories and their properties, advantages, disadvantages, and requirements for future testing were discussed. The categories were molten materials, which included molten metals and paraffin; particulates and beads; resins; foams; and grout. Based on this analysis, further development of fill materials to stabilize used nuclear fuel during storage and transportation is not recommended unless options such as showing that the fuel remains intact or canning of used nuclear fuel do not prove to be feasible.

Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Lahti, Erik A.; Richmond, David J.

2012-08-01T23:59:59.000Z

247

UW EH&S Radiation Safety Office Box 354400 201 Hall Health Seattle WA 98195-4400 206-543-0463 FORM 160 RADIOACTIVE MATERIAL DELIVERY AND USAGE RECORD (5/00)  

E-Print Network [OSTI]

160 RADIOACTIVE MATERIAL DELIVERY AND USAGE RECORD (5/00) AUI Name PO # AUI # Item # Order Date Order be surveyed if they are labeled with a Radioactive White I, Yellow II or Yellow III label. Swipes CONTAMINATION (WAC 246-221-160(4)): contamination

Wilcock, William

248

Novel Energy Sources -Material Architecture and Charge Transport in Solid State Ionic Materials for Rechargeable Li ion Batteries  

SciTech Connect (OSTI)

Since its introduction in the consumer market at the beginning of 1990s by Sony Corporation Li-ion rechargeable battery and LiCoO2 cathode is an inseparable couple for highly reliable practical applications. However, a separation is inevitable as Li-ion rechargeable battery industry demand more and more from this well serving cathode. Spinel-type lithium manganate (e.g., LiMn2O4), lithium-based layered oxide materials (e.g., LiNiO2) and lithium-based olivine-type compounds (e.g., LiFePO4) are nowadays being extensively studied for application as alternate cathode materials in Li-ion rechargeable batteries. Primary goal of this project was the advancement of Li-ion rechargeable battery to meet the future demands of the energy sector. Major part of the research emphasized on the investigation of electrodes and solid electrolyte materials for improving the charge transport properties in Li-ion rechargeable batteries. Theoretical computational methods were used to select electrodes and electrolyte material with enhanced structural and physical properties. The effect of nano-particles on enhancing the battery performance was also examined. Satisfactory progress has been made in the bulk form and our efforts on realizing micro-battery based on thin films is close to give dividend and work is progressing well in this direction.

Katiyar, Ram S; Gmez, M; Majumder, S B; Morell, G; Tomar, M S; Smotkin, E; Bhattacharya, P; Ishikawa, Y

2009-01-19T23:59:59.000Z

249

Operating Experience and Lessons Learned in the Use of Soft-Sided Packaging for Transportation and Disposal of Low Activity Radioactive Waste  

SciTech Connect (OSTI)

This paper describes the operating experience and lessons learned at U.S. Department of Energy (DOE) sites as a result of an evaluation of potential trailer contamination and soft-sided packaging integrity issues related to the disposal of low-level and mixed low-level (LLW/MLLW) radioactive waste shipments. Nearly 4.3 million cubic meters of LLW/MLLW will have been generated and disposed of during fiscal year (FY) 2010 to FY 2015either at commercial disposal sites or disposal sites owned by DOE. The LLW/MLLW is packaged in several different types of regulatory compliant packaging and transported via highway or rail to disposal sites safely and efficiently in accordance with federal, state, and local regulations and DOE orders. In 1999, DOE supported the development of LLW containers that are more volumetrically efficient, more cost effective, and easier to use as compared to metal or wooden containers that existed at that time. The DOE Idaho National Engineering and Environmental Laboratory (INEEL), working in conjunction with the plastic industry, tested several types of soft-sided waste packaging systems that meet U.S. Department of Transportation requirements for transport of low specific activity and surface contaminated objects. Since then, soft-sided packaging of various capacities have been used successfully by the decontamination and decommissioning (D&D) projects to package, transport, and dispose D&D wastes throughout the DOE complex. The joint team of experts assembled by the Energy Facility Contractors Group from DOE waste generating sites, DOE and commercial waste disposal facilities, and soft-sided packaging suppliers conducted the review of soft-sided packaging operations and transportation of these packages to the disposal sites. As a result of this evaluation, the team developed several recommendations and best practices to prevent or minimize the recurrences of equipment contamination issues and proper use of soft-sided packaging for transport and disposal of waste.

Kapoor, A. [DOE; Gordon, S. [NSTec; Goldston, W. [Energy Solutions

2013-07-08T23:59:59.000Z

250

Packaging and Transportation for Offsite Shipment of Materials of National Security Interest  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The purpose of this Order is to make clear that the packaging and transportation of all offsite shipments of materials of national security interest for DOE must be conducted in accordance with DOT and Nuclear Regulatory Commission (NRC) regulations that would be applicable to comparable commercial shipments, except where an alternative course of action is identified in this Order. Cancels DOE O 461.1A.

2010-12-20T23:59:59.000Z

251

Hole-transport material variation in fully vacuum deposited perovskite solar cells  

SciTech Connect (OSTI)

This work addresses the effect of energy level alignment between the hole-transporting material and the active layer in vacuum deposited, planar-heterojunction CH{sub 3}NH{sub 3}PbI{sub x?3}Cl{sub x} perovskite solar cells. Through a series of hole-transport materials, with conductivity values set using controlled p-doping of the layer, we correlate their ionization potentials with the open-circuit voltage of the device. With ionization potentials beyond 5.3 eV, a substantial decrease in both current density and voltage is observed, which highlights the delicate energetic balance between driving force for hole-extraction and maximizing the photovoltage. In contrast, when an optimal ionization potential match is found, the open-circuit voltage can be maximized, leading to power conversion efficiencies of up to 10.9%. These values are obtained with hole-transport materials that differ from the commonly used Spiro-MeO-TAD and correspond to a 40% performance increase versus this reference.

Polander, Lauren E.; Pahner, Paul; Schwarze, Martin; Saalfrank, Matthias; Koerner, Christian; Leo, Karl, E-mail: karl.leo@iapp.de [Institut fr Angewandte Photophysik, Technische Universitt Dresden, 01069 Dresden (Germany)

2014-08-01T23:59:59.000Z

252

Characterization of the National Petroleum Reserve No. 3 (NPR-3) Site for Naturally Occurring Radioactive Material(NORM)  

SciTech Connect (OSTI)

The National Petroleum Reserve No. 3 site (NPR-3) near Casper, Wyoming is being prepared for transfer to private industry. Remediation of the NPR-3 site has already begun in anticipation of this transfer. This document describes the characterization of the NPR-3 site for Naturally Occurring Radioactive Materials (NORM). Data generated on radionuclide concentrations and radon emanation may be used to determine disposal options and the need for remediation at this site. A preliminary gamma survey of the NPR-3 site was conducted to identify areas of potential NORM contamination. Based on these gamma surveys, two general areas of NORM contamination were found: the North Water Flood area and the BTP-10 produced water discharge steam. A maximum surface exposure rate of 120 {micro}R h{sup -1} was observed in the North Water Flood area, with the highest readings found along the drainage channel from the area. Exposure rates dropped to background quickly with increasing distance from the center of the drainage. The maximum observed exposure rate in the BTP-10 produced water drainage was 40 {micro}R h{sup -1}. Soil and sediment sampling were concentrated in these two areas. All samples were analyzed for concentration of {sup 226}Ra, {sup 228}Ra, and {sup 40}K. Maximum {sup 226}Ra concentrations observed in the samples collected were 46 pCi g{sup -1} for soil and 78 pCi g{sup -1} for sediment. Concentrations in most samples were considerably lower than these values. Radon emanation fraction was also measured for a randomly selected fraction of the samples. The mean Rn emanation fraction measured was 0.10, indicating that on average only 10 percent of the Rn produced is released from the medium. Based on the results of these analyses, NORM contamination at the NPR-3 site is minimal, and appears to be restricted to the two general areas sampled. Concentrations of NORM radionuclides found soils and sediments in these two locations do not justify remedial actions at present. However, continued discharge of NORM-contaminated produced waters from the BTP-10 area will likely result in the continued accumulation of NORM in sediment. It is therefore recommended that the sediments in the BTP-10 discharge stream be monitored periodically for NORM.

White, G.J; Rood, A.S.

1999-01-21T23:59:59.000Z

253

Automating Risk Assessments of Hazardous Material Shipments for Transportation Routes and Mode Selection  

SciTech Connect (OSTI)

The METEOR project at Idaho National Laboratory (INL) successfully addresses the difficult problem in risk assessment analyses of combining the results from bounding deterministic simulation results with probabilistic (Monte Carlo) risk assessment techniques. This paper describes a software suite designed to perform sensitivity and cost/benefit analyses on selected transportation routes and vehicles to minimize risk associated with the shipment of hazardous materials. METEOR uses Monte Carlo techniques to estimate the probability of an accidental release of a hazardous substance along a proposed transportation route. A METEOR user selects the mode of transportation, origin and destination points, and charts the route using interactive graphics. Inputs to METEOR (many selections built in) include crash rates for the specific aircraft, soil/rock type and population densities over the proposed route, and bounding limits for potential accident types (velocity, temperature, etc.). New vehicle, materials, and location data are added when available. If the risk estimates are unacceptable, the risks associated with alternate transportation modes or routes can be quickly evaluated and compared. Systematic optimizing methods will provide the user with the route and vehicle selection identified with the lowest risk of hazardous material release. The effects of a selected range of potential accidents such as vehicle impact, fire, fuel explosions, excessive containment pressure, flooding, etc. are evaluated primarily using hydrocodes capable of accurately simulating the material response of critical containment components. Bounding conditions that represent credible accidents (i.e; for an impact event, velocity, orientations, and soil conditions) are used as input parameters to the hydrocode models yielding correlation functions relating accident parameters to component damage. The Monte Carlo algorithms use random number generators to make selections at the various decision points such as; crash, location, etc. For each pass through the routines, when a crash is randomly selected, crash parameters are then used to determine if failure has occurred using either external look up tables, correlations functions from deterministic calculations, or built in data libraries. The effectiveness of the software was recently demonstrated in safety analyses of the transportation of radioisotope systems for the US Dept. of Energy. These methods are readily adaptable to estimating risks associated with a variety of hazardous shipments such as spent nuclear fuel, explosives, and chemicals.

Barbara H. Dolphin; William D. RIchins; Stephen R. Novascone

2010-10-01T23:59:59.000Z

254

The role of radiation transport in the thermal response of semitransparent materials to localized laser heating  

SciTech Connect (OSTI)

Lasers are widely used to modify the internal structure of semitransparent materials for a wide variety of applications, including waveguide fabrication and laser glass damage healing. The gray diffusion approximation used in past models to describe radiation cooling is not adequate for these materials, particularly near the heated surface layer. In this paper we describe a computational model based upon solving the radiation transport equation in 1D by the P{sub n} method with {approx}500 photon energy bands, and by multi-group radiation diffusion in 2D with fourteen photon energy bands. The model accounts for the temperature-dependent absorption of infrared laser light and subsequent redistribution of the deposited heat by both radiation and conductive transport. We present representative results for fused silica irradiated with 2-12 W of 4.6 or 10.6 {mu}m laser light for 5-10 s pulse durations in a 1 mm spot, which is small compared to the diameter and thickness of the silica slab. We show that, unlike the case for bulk heating, in localized infrared laser heating radiation transport plays only a very small role in the thermal response of silica.

Colvin, Jeffrey; Shestakov, Aleksei; Stoelken, James; Vignes, Ryan [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94551 (United States)

2011-03-01T23:59:59.000Z

255

Multi-Scale Studies of Transport and Adsorption Phenomena of Cement-based Materials in Aqueous and Saline Environment  

E-Print Network [OSTI]

saturated concrete during drying, Transport in Porous Media,Concrete is a composite material consisting of a porousand Concrete Research, 34 (2004) 1579- [25] L.A. Richards, Capillary conduction of liquids through porous

Yoon, Se Yoon

2012-01-01T23:59:59.000Z

256

Radiation shielding materials and containers incorporating same  

DOE Patents [OSTI]

An improved radiation shielding material and storage systems for radioactive materials incorporating the same. The PYRolytic Uranium Compound ("PYRUC") shielding material is preferably formed by heat and/or pressure treatment of a precursor material comprising microspheres of a uranium compound, such as uranium dioxide or uranium carbide, and a suitable binder. The PYRUC shielding material provides improved radiation shielding, thermal characteristic, cost and ease of use in comparison with other shielding materials. The shielding material can be used to form containment systems, container vessels, shielding structures, and containment storage areas, all of which can be used to house radioactive waste. The preferred shielding system is in the form of a container for storage, transportation, and disposal of radioactive waste. In addition, improved methods for preparing uranium dioxide and uranium carbide microspheres for use in the radiation shielding materials are also provided.

Mirsky, Steven M. (Greenbelt, MD); Krill, Stephen J. (Arlington, VA); Murray, Alexander P. (Gaithersburg, MD)

2005-11-01T23:59:59.000Z

257

Radiation Shielding Materials and Containers Incorporating Same  

DOE Patents [OSTI]

An improved radiation shielding material and storage systems for radioactive materials incorporating the same. The PYRolytic Uranium Compound (''PYRUC'') shielding material is preferably formed by heat and/or pressure treatment of a precursor material comprising microspheres of a uranium compound, such as uranium dioxide or uranium carbide, and a suitable binder. The PYRUC shielding material provides improved radiation shielding, thermal characteristic, cost and ease of use in comparison with other shielding materials. The shielding material can be used to form containment systems, container vessels, shielding structures, and containment storage areas, all of which can be used to house radioactive waste. The preferred shielding system is in the form of a container for storage, transportation, and disposal of radioactive waste. In addition, improved methods for preparing uranium dioxide and uranium carbide microspheres for use in the radiation shielding materials are also provided.

Mirsky, Steven M.; Krill, Stephen J.; and Murray, Alexander P.

2005-11-01T23:59:59.000Z

258

Framework for a flexible, real-time controller for automated material transport systems  

E-Print Network [OSTI]

The Manager Module. 5. 5. 1 Configuration 1. . 5. 5. 2 Configurations 2 2k 3. 5. 5. 3 Configuratron 4. . 5. 5. 4 Error Handling and Recovery Routines. . . . . . 5. 6 The Dispatcher Module. . 5. 6. 1 Configurations I 2k 4 5. 6. 2 Configurations 2 & 3... for the manager module. MTC control structure. 25 28 43 61 16 17 19 20 Material transport system layout . Intermediate decision ports . . Intermediate MTS network representation. . Graph representation of the MTS. . . Basic flowchart for the MTC...

Edlabadkar, Abhay

1995-01-01T23:59:59.000Z

259

Mode-selective vibrational control of charge transport in $?$-conjugated molecular materials  

E-Print Network [OSTI]

The soft character of organic materials leads to strong coupling between molecular nuclear and electronic dynamics. This coupling opens the way to control charge transport in organic electronic devices by inducing molecular vibrational motions. However, despite encouraging theoretical predictions, experimental realization of such control has remained elusive. Here we demonstrate experimentally that photoconductivity in a model organic optoelectronic device can be controlled by the selective excitation of molecular vibrations. Using an ultrafast infrared laser source to create a coherent superposition of vibrational motions in a pentacene/C60 photoresistor, we observe that excitation of certain modes in the 1500-1700 cm$^{-1}$ region leads to photocurrent enhancement. Excited vibrations affect predominantly trapped carriers. The effect depends on the nature of the vibration and its mode-specific character can be well described by the vibrational modulation of intermolecular electronic couplings. Vibrational control thus presents a new tool for studying electron-phonon coupling and charge dynamics in (bio)molecular materials.

Artem A. Bakulin; Robert Lovrin?i?; Yu Xi; Oleg Selig; Huib J. Bakker; Yves L. A. Rezus; Pabitra K. Nayak; Alexandr Fonari; Veaceslav Coropceanu; Jean-Luc Brdas; David Cahen

2015-03-02T23:59:59.000Z

260

Application of United States Department of Transportation regulations to hazardous material and waste shipments on the Hanford Site  

SciTech Connect (OSTI)

All hazardous material and waste transported over roadways open to the public must be in compliance with the US Department of Transportation (DOT) regulations. The DOT states that the hazardous material regulations (HMR) also apply to government-owned, contractor-operated (GOCO) transportation operations over any US Department of Energy (DOE) site roadway where the public has free and unrestricted access. Hazardous material and waste in packages that do not meet DOE regulations must be transported on DOE site roadways in a manner that excludes the public and nonessential workers. At the DOE Richland Field Office (the Hanford Site), hazardous material and waste movements that do not meet DOE requirements are transported over public access roadways during off-peak hours with the roadways barricaded. These movements are accomplished using a transportation plan that involves the DOE, DOE contractors, and private utilities who operate on or near the Hanford Site. This method, which is used at the Hanford Site to comply with DOE regulations onsite, can be communicated to other DOE sites to provide a basis for achieving consistency in similar transportation operations.

Burnside, M.E.

1992-01-01T23:59:59.000Z

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


261

Measurements of D-T neutron induced radioactivity in plasma-facing materials and their role in qualification of activation cross-section libraries and codes  

SciTech Connect (OSTI)

USDOE/JAERI collaborative program on induced radioactivity measurements has been spread over last five years and has covered, among others, a large number of plasma facing materials of interest to D-T fusion reactors, including ITER and DEMO. The experiments have consisted of irradiation of high purity material samples in a range of neutron energy spectra in simulated fusion environments of prototypical blanket assemblies driven by D-T neutrons at FNS/JAERI. A typical sample measured 10 mm in diameter by 1 mm thickness, and the neutron fluence ranged from {approximately}10{sup 10} n/cm{sup 2} to {approximately}10{sup 14} n/cm{sup 2}, over an irradiation period of 30 m and 10 h. The irradiated samples were then cooled for varying times, from {approximately}10 m to {approximately}3 weeks, and their activity was derived by counting associated {gamma}-rays with intrinsic germanium detectors.

Kumar, A.; Abdou, M.A.; Youssef, M.Z. [Univ. of California, Los Angeles, CA (United States)] [and others

1994-12-31T23:59:59.000Z

262

Airborne radioactive material collection, measurement, and data storage for the Nuclear Science Center at Texas A&M University  

E-Print Network [OSTI]

REFERENCES AEC73 AEC Regulatory Guide 8. 2, 1973, "Guide for Administrative Practices in Radiation Monitoring". AEC74 AEC Regulatory Guide 1. 21, Rev. 1, 1974, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes, and Releases... System at the Nuclear Science Center (Texas AAM University) 38 VITA 66 LIST OF FIGURES FIGURE NUMBER Figure 1: FAM//I and FANF3 Sample Probe Orientation, PAGE Figure 2: FAM42, FAMR4, and FAMt6 Sample Probe Location . . 13 Figure 3; FAMF1 and FAM...

Jones, Melody Louise

1982-01-01T23:59:59.000Z

263

Proposed design requirements for high-integrity containers used to store, transport, and dispose of high-specific-activity, low-level radioactive wastes from Three Mile Island Unit II  

SciTech Connect (OSTI)

This report develops proposed design requirements for high integrity containers used to store, transport and/or dispose of high-activity, low-level radioactive wastes from Three Mile Island Unit II. The wastes considered are the dewatered resins produced by the EPICOR II waste treatment system used to clean-up the auxiliary building water. The radioactivity level of some of these EPICOR II liners is 1300 curies per container. These wastes may be disposed of in an intermediate depth burial (10 to 20 meter depth) facility. The proposed container design requirements are directed to ensure isolation of the waste and protection of the public health and safety.

Vigil, M.G.; Allen, G.C.; Pope, R.B.

1981-04-01T23:59:59.000Z

264

Transportation  

E-Print Network [OSTI]

Transportation in ancient Egypt entailed the use of boats2007 Land transport in Roman Egypt: A study of economics andDieter 1991 Building in Egypt: Pharaonic stone masonry. New

Vinson, Steve

2013-01-01T23:59:59.000Z

265

Development of long-term performance models for radioactive waste forms  

SciTech Connect (OSTI)

The long-term performance of solid radioactive waste is measured by the release rate of radionuclides into the environment, which depends on corrosion or weathering rates of the solid waste form. The reactions involved depend on the characteristics of the solid matrix containing the radioactive waste, the radionuclides of interest, and their interaction with surrounding geologic materials. This chapter describes thermo-hydro-mechanical and reactive transport models related to the long-term performance of solid radioactive waste forms, including metal, ceramic, glass, steam reformer and cement. Future trends involving Monte-Carlo simulations and coupled/multi-scale process modeling are also discussed.

Bacon, Diana H.; Pierce, Eric M.

2011-03-22T23:59:59.000Z

266

Transportation technology quick reference file  

SciTech Connect (OSTI)

This publication is a collection of items written by different authors on subjects relating to the transportation of radioactive materials. The purpose of the document is to meet the continuing need for information on specific subjects for dissemination to the public at their request. The subjects included were selected on the basis of the questions most often asked about radioactive materials and their transportation. Additional subjects are being considered and will be included in the future. The loose-leaf notebook format is used to facilitate the updating of this material. The data used in many of the papers represent the best available at time of publication and will be updated as more current information becomes available.

Shepherd, E.W. (ed.)

1981-05-01T23:59:59.000Z

267

Phosphine Oxide Based Electron Transporting and Hole Blocking Materials for Blue Electrophosphorescent Organic Light Emitting Devices  

SciTech Connect (OSTI)

We report the design, synthesis, thermal, and photophysical properties of two phosphine oxide based electron transport/hole blocking materials, 2,6-bis(4-(diphenylphosphoryl)phenyl)pyridine (BM-A11) and 2,4-bis(4-(diphenyl-phosphoryl)phenyl)pyridine (BM-A10) for blue electrophosphorescent organic light emitting devices (OLEDs). The use of these materials in blue OLED with iridium (III) bis[(4,6-difluorophenyl)-pyridinato-N,C2]picolinate (Firpic) as the phosphor was demonstrated. Using the dual host device architecture with BM-A10 as the ETM yields a maximum EQE of 8.9% with a power efficiency of 21.5 lm/W (4.0V and 35 cd/m2). When BM-A11 is used as the ETM, the maximum EQE and power efficiency improves to 14.9% and 48.4 lm/W, respectively (3.0V and 40 cd/m2).

Von Ruden, Amber L.; Cosimbescu, Lelia; Polikarpov, Evgueni; Koech, Phillip K.; Swensen, James S.; Wang, Liang; Darsell, Jens T.; Padmaperuma, Asanga B.

2010-10-26T23:59:59.000Z

268

Electronic and thermal transport in GeTe: A versatile base for thermoelectric materials  

DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

GeTe is a narrow-band gap semiconductor, where Ge vacancies generate free charge carriers, holes, forming a self-dopant degenerate system with p-type conductivity, and serves as a base for high-performance multicomponent thermoelectric materials. There is a significant discrepancy between the electronic and thermal transport data for GeTe-based materials reported in the literature, which obscures the baseline knowledge and prevents a clear understanding of the effect of alloying GeTe with various elements. A comprehensive study including XRD, SEM, EDS, Seebeck coefficient, electrical resistivity, thermal conductivity, and 125Te NMR of several GeTe samples was conducted. Similar Seebeck coefficient and electrical resistivity are observed for all GeTe samples used showing that the concentration of Ge vacancies generating charge carriers is constant along the ingot. Very short 125Te NMR spin-relaxation time agrees well with high carrier concentration obtained from the Hall effect measurements. Our data show that at ~700 K, GeTe has a very large power factor, 42 ?Wcm-1K-2, much larger than that of any high efficiency thermoelectric telluride at these temperatures. Electronic and thermal properties of GeTe are compared to PbTe, another well-known thermoelectric material, where free charge carriers, holes or electrons, are generated by vacancies on Pb or Te sites, respectively. Discrepancy in the data for GeTe reported in literature can be attributed to the variation in the Ge:Te ratio of solidified samples as well as to different conditions of measurements.

None

2013-08-29T23:59:59.000Z

269

Electronic and thermal transport in GeTe: A versatile base for thermoelectric materials  

SciTech Connect (OSTI)

GeTe is a narrow-band gap semiconductor, where Ge vacancies generate free charge carriers, holes, forming a self-dopant degenerate system with p-type conductivity, and serves as a base for high-performance multicomponent thermoelectric materials. There is a significant discrepancy between the electronic and thermal transport data for GeTe-based materials reported in the literature, which obscures the baseline knowledge and prevents a clear understanding of the effect of alloying GeTe with various elements. A comprehensive study including XRD, SEM, EDS, Seebeck coefficient, electrical resistivity, thermal conductivity, and 125Te NMR of several GeTe samples was conducted. Similar Seebeck coefficient and electrical resistivity are observed for all GeTe samples used showing that the concentration of Ge vacancies generating charge carriers is constant along the ingot. Very short 125Te NMR spin-relaxation time agrees well with high carrier concentration obtained from the Hall effect measurements. Our data show that at ~700 K, GeTe has a very large power factor, 42 ?Wcm-1K-2, much larger than that of any high efficiency thermoelectric telluride at these temperatures. Electronic and thermal properties of GeTe are compared to PbTe, another well-known thermoelectric material, where free charge carriers, holes or electrons, are generated by vacancies on Pb or Te sites, respectively. Discrepancy in the data for GeTe reported in literature can be attributed to the variation in the Ge:Te ratio of solidified samples as well as to different conditions of measurements.

None

2013-08-29T23:59:59.000Z

270

Deposition of hole-transport materials in solid-state dye-sensitized solar cells by doctor-blading  

E-Print Network [OSTI]

Deposition of hole-transport materials in solid-state dye-sensitized solar cells by doctor Accepted 19 April 2010 Available online xxxx Keywords: Dye-sensitized solar cells Organic semiconductors)-9,90 -spirobifluorene) in solid-state dye-sensitized solar cells. Doctor-blading is a roll

McGehee, Michael

271

Researchers at Montana State University and Idaho National Lab have developed a process to effectively and efficiently clean natural and man-made porous material of radioactive contamination. The system eliminates  

E-Print Network [OSTI]

to effectively and efficiently clean natural and man-made porous material of radioactive contamination. The system eliminates the practice of full demolition and removal of contaminated objects and can address contaminated substrate. Thus, building walls (interior or exterior), floors and ceilings can be remediated

Maxwell, Bruce D.

272

Transportation Services  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Transportation Services Transporting nuclear materials within the United States and throughout the world is a complicated and sometimes highly controversial effort requiring...

273

Corrective Action Decision Document/Closure Report for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0  

SciTech Connect (OSTI)

This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, in Areas 2, 3, 9, and 20 of the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (1996, as amended February 2008). Corrective Action Unit 545 is comprised of the following eight Corrective Action Sites (CASs): 02-09-01, Mud Disposal Area 03-08-03, Mud Disposal Site 03-17-01, Waste Consolidation Site 3B 03-23-02, Waste Disposal Site 03-23-05, Europium Disposal Site 03-99-14, Radioactive Material Disposal Area 09-23-02, U-9y Drilling Mud Disposal Crater 20-19-01, Waste Disposal Site While all eight CASs are addressed in this CADD/CR, sufficient information was available for the following three CASs; therefore, a field investigation was not conducted at these sites: For CAS 03-08-03, though the potential for subsidence of the craters was judged to be extremely unlikely, the data quality objective (DQO) meeting participants agreed that sufficient information existed about disposal and releases at the site and that a corrective action of close in place with a use restriction is recommended. Sampling in the craters was not considered necessary. For CAS 03-23-02, there were no potential releases of hazardous or radioactive contaminants identified. Therefore, the Corrective Action Investigation Plan for CAU 545 concluded that: Sufficient information exists to conclude that this CAS does not exist as originally identified. Therefore, there is no environmental concern associated with CAS 03-23-02. This CAS is closed with no further action. For CAS 03-23-05, existing information about the two buried sources and lead pig was considered to be sufficient, and safety concerns existed about the stability of the crater component. Therefore, a corrective action of close in place with a use restriction is recommended, and sampling at the site was not considered necessary. The purpose of this CADD/CR is to provide justification and documentation to support the recommendation for closure of CAU 545 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from August 20 through November 02, 2007, as set forth in the CAU 545 Corrective Action Investigation Plan. The purpose of the CAI was to fulfill the following data needs as defined during the DQO process: Determine whether contaminants of concern (COCs) are present. If COCs are present, determine their nature and extent. Provide sufficient information and data to complete appropriate corrective actions. The CAU 545 dataset from the investigation results was evaluated based on the data quality indicator parameters. This evaluation demonstrated the quality and acceptability of the dataset for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels established in this CADD/CR. The results of the CAI identified no COCs at the five CASs investigated in CAU 545. As a best management practice, repair of the fence enclosing CAS 03-08-03 has been completed. Therefore, the DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: Close in place COCs at CASs 03-08-03 and 03-23-05 with use restrictions. No further corrective action for CAU 545. No Corrective Action Plan. Corrective Action Unit 545 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order. A Notice of Completion to the DOE, National Nuclear Security Administration Nevada Site Office is requested from the Nevada Division of Environmental Protection for closure of CAU 545.

Alfred Wickline

2008-04-01T23:59:59.000Z

274

Assessing recycling versus incineration of key materials in municipal waste: The importance of efficient energy recovery and transport distances  

SciTech Connect (OSTI)

Highlights: Black-Right-Pointing-Pointer We model the environmental impact of recycling and incineration of household waste. Black-Right-Pointing-Pointer Recycling of paper, glass, steel and aluminium is better than incineration. Black-Right-Pointing-Pointer Recycling and incineration of cardboard and plastic can be equally good alternatives. Black-Right-Pointing-Pointer Recyclables can be transported long distances and still have environmental benefits. Black-Right-Pointing-Pointer Paper has a higher environmental benefit than recyclables found in smaller amounts. - Abstract: Recycling of materials from municipal solid waste is commonly considered to be superior to any other waste treatment alternative. For the material fractions with a significant energy content this might not be the case if the treatment alternative is a waste-to-energy plant with high energy recovery rates. The environmental impacts from recycling and from incineration of six material fractions in household waste have been compared through life cycle assessment assuming high-performance technologies for material recycling as well as for waste incineration. The results showed that there are environmental benefits when recycling paper, glass, steel and aluminium instead of incinerating it. For cardboard and plastic the results were more unclear, depending on the level of energy recovery at the incineration plant, the system boundaries chosen and which impact category was in focus. Further, the environmental impact potentials from collection, pre-treatment and transport was compared to the environmental benefit from recycling and this showed that with the right means of transport, recyclables can in most cases be transported long distances. However, the results also showed that recycling of some of the material fractions can only contribute marginally in improving the overall waste management system taking into consideration their limited content in average Danish household waste.

Merrild, Hanna [Department of Environmental Engineering, Technical University of Denmark, Miljoevej, Building 113, DK-2800 Kongens Lyngby (Denmark); Larsen, Anna W., E-mail: awla@env.dtu.dk [Department of Environmental Engineering, Technical University of Denmark, Miljoevej, Building 113, DK-2800 Kongens Lyngby (Denmark); Christensen, Thomas H. [Department of Environmental Engineering, Technical University of Denmark, Miljoevej, Building 113, DK-2800 Kongens Lyngby (Denmark)

2012-05-15T23:59:59.000Z

275

Corrective Action Investigation Plan for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0  

SciTech Connect (OSTI)

Corrective Action Unit 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, consists of seven inactive sites located in the Yucca Flat area and one inactive site in the Pahute Mesa area. The eight CAU 545 sites consist of craters used for mud disposal, surface or buried waste disposed within craters or potential crater areas, and sites where surface or buried waste was disposed. The CAU 545 sites were used to support nuclear testing conducted in the Yucca Flat area during the 1950s through the early 1990s, and in Area 20 in the mid-1970s. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval.

Alfred Wickline

2007-06-01T23:59:59.000Z

276

Waste Isolation Pilot Plant Materials Interface Interactions Test: Papers presented at the Commission of European Communities workshop on in situ testing of radioactive waste forms and engineered barriers  

SciTech Connect (OSTI)

The three papers in this report were presented at the second international workshop to feature the Waste Isolation Pilot Plant (WIPP) Materials Interface Interactions Test (MIIT). This Workshop on In Situ Tests on Radioactive Waste Forms and Engineered Barriers was held in Corsendonk, Belgium, on October 13--16, 1992, and was sponsored by the Commission of the European Communities (CEC). The Studiecentrum voor Kernenergie/Centre D`Energie Nucleaire (SCK/CEN, Belgium), and the US Department of Energy (via Savannah River) also cosponsored this workshop. Workshop participants from Belgium, France, Germany, Sweden, and the United States gathered to discuss the status, results and overviews of the MIIT program. Nine of the twenty-five total workshop papers were presented on the status and results from the WIPP MIIT program after the five-year in situ conclusion of the program. The total number of published MIIT papers is now up to almost forty. Posttest laboratory analyses are still in progress at multiple participating laboratories. The first MIIT paper in this document, by Wicks and Molecke, provides an overview of the entire test program and focuses on the waste form samples. The second paper, by Molecke and Wicks, concentrates on technical details and repository relevant observations on the in situ conduct, sampling, and termination operations of the MIIT. The third paper, by Sorensen and Molecke, presents and summarizes the available laboratory, posttest corrosion data and results for all of the candidate waste container or overpack metal specimens included in the MIIT program.

Molecke, M.A.; Sorensen, N.R. [eds.] [Sandia National Labs., Albuquerque, NM (US); Wicks, G.G. [ed.] [Westinghouse Savannah River Technology Center, Aiken, SC (US)

1993-08-01T23:59:59.000Z

277

Role of chemical reactions of arylamine hole transport materials in operational degradation of organic light-emitting diodes  

SciTech Connect (OSTI)

We report that the representative arylamine hole transport materials undergo chemical transformations in operating organic light-emitting diode (OLED) devices. Although the underlying chemical mechanisms are too complex to be completely elucidated, structures of several identified degradation products point at dissociations of relatively weak carbon-nitrogen and carbon-carbon bonds in arylamine molecules as the initiating step. Considering the photochemical reactivities, the bond dissociation reactions of arylamines occur by the homolysis of the lowest singlet excited states formed by recombining charge carriers in the operating OLED device. The subsequent chemical reactions are likely to yield long-lived, stabilized free radicals capable of acting as deep traps--nonradiative recombination centers and fluorescence quenchers. Their presence in the hole transport layer results in irreversible hole trapping and manifests as a positive fixed charge. The extent and localization of chemical transformations in several exemplary devices suggest that the free radical reactions of hole transporting materials, arylamines, can be sufficient to account for the observed luminance efficiency loss and voltage rise in operating OLEDs. The relative bond strengths and excited state energies of OLED materials appear to have a determining effect on the operational stability of OLED devices.

Kondakov, Denis Y. [Eastman Kodak Company, Rochester, New York 14650-2103 (United States)

2008-10-15T23:59:59.000Z

278

Capital requirements for the transportation of energy materials: 1979 arc estimates  

SciTech Connect (OSTI)

Summaries of transportation investment requirements through 1990 are given for the low, medium and high scenarios. Total investment requirements for the three modes and the three energy commodities can accumulate to a $46.3 to $47.0 billion range depending on the scenario. The high price of oil, following the evidence of the last year, is projected to hold demand for oil below the recent past. Despite the overall decrease in traffic some investment in crude oil and LPG pipelines is necessary to reach new sources of supply. Although natural gas production and consumption is projected to decline through 1990, new investments in carrying capacity also are required due to locational shifts in supply. The Alaska Natural Gas Transportation System is the dominant investment for energy transportation in the next ten years. This year's report focuses attention on waterborne coal transportation to the northeast states in keeping with a return to significant coal consumption projected for this area. A resumption of such shipments will require a completely new fleet. The investment estimates given in this report identify capital required to transport projected energy supplies to market. The requirement is strategic in the sense that other reasonable alternatives do not exist or that a shared load of new growth can be expected. Not analyzed or forecasted are investments in transportation facilities made in response to local conditions. The total investment figures, therefore, represent a minimum necessary capital improvement to respond to changes in interregional supply conditions.

Not Available

1980-08-29T23:59:59.000Z

279

An evaluation of current hazardous material management procedures for the Texas Department of Transportation  

E-Print Network [OSTI]

Dealing with hazardous materials on a day-to-day basis requires a fine--tuned material management system to minimize risk of exposure or injury to workers or to the public. An effective hazardous material management system should also keep up...

Lovell, Cheryl Alane

1993-01-01T23:59:59.000Z

280

Zintl Phases as Thermoelectric Materials: Tuned Transport Properties of the Compounds CaxYb1xZn2Sb2**  

E-Print Network [OSTI]

Zintl Phases as Thermoelectric Materials: Tuned Transport Properties of the Compounds CaxYb1±xZn2Sb. Introduction Because of their ability to convert waste heat into electricity, thermoelectric materials have in efficiency, thermoelectric materials could pro- vide a substantial amount of electrical power from automotive

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


281

The Resource Handbook on DOE Transportation Risk Assessment  

SciTech Connect (OSTI)

In an attempt to bring forth increased efficiency and effectiveness in assessing transportation risks associated with radioactive materials or wastes, the U.S. Department of Energy's (DOE's) National Transportation Program (NTP) published a resource handbook in 2002. The handbook draws from the broad technical expertise among DOE national laboratories and industry, which reflects the extensive experience gained from DOE's efforts in conducting assessments (i.e., environmental impact assessments) within the context of the National Environmental Policy Act (NEPA) in the past 20 years. The handbook is intended to serve as a primary source of information regarding the approach and basis for conducting transportation risk assessments under normal or accidental conditions that are associated with shipping radioactive materials or wastes. It is useful as a reference to DOE managers, NEPA assessors, technical analysts, contractors, and also stakeholders. It provides a summary of pertinent U.S. policies and regulations on the shipment of radioactive materials, existing guidance on preparing transportation risk assessments, a review of previous transportation risk assessments by DOE and others, a description of comprehensive and generally accepted transportation risk assessment methodologies, and a compilation of supporting data, parameters, and assumptions. The handbook also provides a discussion paper on an issue that has been identified as being important in the past. The discussion paper focuses on cumulative impacts, illustrating the ongoing evolution of transportation risk assessment. The discussion may be expanded in the future as emerging issues are identified. The handbook will be maintained and periodically updated to provide current and accurate information.

Chen, S. Y.; Kapoor, A. K.

2003-02-27T23:59:59.000Z

282

Radioactive waste management in the former USSR  

SciTech Connect (OSTI)

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

Bradley, D.J.

1992-06-01T23:59:59.000Z

283

Transportation  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassiveSubmittedStatusButler TinaContact-Information-Transmission SignTransport

284

Type B Accident Investigation Board Report Subcontractor Radioactive...  

Energy Savers [EERE]

Subcontractor Radioactive Release During Transportation Activities on May 14, 2004, Bechtel Jacobs Company LLC, Oak Ridge, Tennessee (Amended) Type B Accident Investigation Board...

285

NMR and Transport Studies on Group IV Clathrates and Related Intermetallic Materials  

E-Print Network [OSTI]

challenge. In this work, Nuclear Magnetic Resonance (NMR), heat capacity and transport measurements have been used to study several clathrate systems, especially the well- known type-I Ba8Ga16Sn30, which has been reported to have one of the lowest thermal...

Zheng, Xiang

2012-10-19T23:59:59.000Z

286

Radioactive ion detector  

DOE Patents [OSTI]

Apparatus for detecting the presence, in aqueous media, of substances which emit alpha and/or beta radiation and determining the oxidation state of these radioactive substances, that is, whether they are in cationic or anionic form. In one embodiment, a sensor assembly has two elements, one comprised of an ion-exchange material which binds cations and the other comprised of an ion-exchange material which binds anions. Each ion-exchange element is further comprised of a scintillation plastic and a photocurrent generator. When a radioactive substance to which the sensor is exposed binds to either element and emits alpha or beta particles, photons produced in the scintillation plastic illuminate the photocurrent generator of that element. Sensing apparatus senses generator output and thereby indicates whether cationic species or anionic species or both are present and also provides an indication of species quantity. 2 figs.

Bower, K.E.; Weeks, D.R.

1997-08-12T23:59:59.000Z

287

Radioactive ion detector  

DOE Patents [OSTI]

Apparatus for detecting the presence, in aqueous media, of substances which emit alpha and/or beta radiation and determining the oxidation state of these radioactive substances, that is, whether they are in cationic or anionic form. In one embodiment, a sensor assembly has two elements, one comprised of an ion-exchange material which binds cations and the other comprised of an ion-exchange material which binds anions. Each ion-exchange element is further comprised of a scintillation plastic and a photocurrent generator. When a radioactive substance to which the sensor is exposed binds to either element and emits alpha or beta particles, photons produced in the scintillation plastic illuminate the photocurrent generator of that element. Sensing apparatus senses generator output and thereby indicates whether cationic species or anionic species or both are present and also provides an indication of species quantity.

Bower, Kenneth E. (Los Alamos, NM); Weeks, Donald R. (Saratoga, CA)

1997-01-01T23:59:59.000Z

288

Safety analysis report for packaging (onsite) sample pig transport system  

SciTech Connect (OSTI)

This Safety Analysis Report for Packaging (SARP) provides a technical evaluation of the Sample Pig Transport System as compared to the requirements of the U.S. Department of Energy, Richland Operations Office (RL) Order 5480.1, Change 1, Chapter III. The evaluation concludes that the package is acceptable for the onsite transport of Type B, fissile excepted radioactive materials when used in accordance with this document.

MCCOY, J.C.

1999-03-16T23:59:59.000Z

289

Understanding and engineering molecular interactions and electronic transport at 2D materials interfaces  

E-Print Network [OSTI]

2D materials are defined as solids with strong in-plane chemical bonds but weak out-of-plane, van der Waals (vdW) interactions. In order to realize potential applications of 2D materials in the areas of optoelectronics, ...

Shih, Chih-Jen, Ph. D. Massachusetts Institute of Technology

2014-01-01T23:59:59.000Z

290

Packaging and Transfer or Transportation of Materials of National Security Interest  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish requirements and responsibilities for offsite shipments of naval nuclear fuel elements, Category I and Category II special nuclear material, nuclear explosives, nuclear components, special assemblies, and other materials of national security interest. Cancels DOE O 461.1. Canceled by DOE O 461.1B and DOE O 461.2.

2004-04-26T23:59:59.000Z

291

Business and Finance Surplus Materials Disposal Policy # 4.51  

E-Print Network [OSTI]

and guidelines. B. Surplus property is defined as "equipment, furniture and other materials/supplies" no longer. Chemical recycling, second use of chemicals, and the disposal of unusable chemicals, radioactive are the responsibility of Transportation and Parking Services, 160 Bevis Hall, 1080 Carmack Road, 292-9341. B. Computer

292

E-Print Network 3.0 - artificial radioactive isotopes Sample...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

from an artificial source or from a radioactive substance containing naturally occurring... . This includes work with radioactive materials and that involving sources of...

293

Implementation of Benchmarking Transportation Logistics Practices and Future Benchmarking Organizations  

SciTech Connect (OSTI)

The purpose of the Office of Civilian Radioactive Waste Management's (OCRWM) Logistics Benchmarking Project is to identify established government and industry practices for the safe transportation of hazardous materials which can serve as a yardstick for design and operation of OCRWM's national transportation system for shipping spent nuclear fuel and high-level radioactive waste to the proposed repository at Yucca Mountain, Nevada. The project will present logistics and transportation practices and develop implementation recommendations for adaptation by the national transportation system. This paper will describe the process used to perform the initial benchmarking study, highlight interim findings, and explain how these findings are being implemented. It will also provide an overview of the next phase of benchmarking studies. The benchmarking effort will remain a high-priority activity throughout the planning and operational phases of the transportation system. The initial phase of the project focused on government transportation programs to identify those practices which are most clearly applicable to OCRWM. These Federal programs have decades of safe transportation experience, strive for excellence in operations, and implement effective stakeholder involvement, all of which parallel OCRWM's transportation mission and vision. The initial benchmarking project focused on four business processes that are critical to OCRWM's mission success, and can be incorporated into OCRWM planning and preparation in the near term. The processes examined were: transportation business model, contract management/out-sourcing, stakeholder relations, and contingency planning. More recently, OCRWM examined logistics operations of AREVA NC's Business Unit Logistics in France. The next phase of benchmarking will focus on integrated domestic and international commercial radioactive logistic operations. The prospective companies represent large scale shippers and have vast experience in safely and efficiently shipping spent nuclear fuel and other radioactive materials. Additional business processes may be examined in this phase. The findings of these benchmarking efforts will help determine the organizational structure and requirements of the national transportation system. (authors)

Thrower, A.W. [U.S. Department of Energy, Office of Civilian Radioactive Waste Management, Washington, DC (United States); Patric, J. [Booz Allen Hamilton, Washington, DC (United States); Keister, M. [Idaho National Laboratory, Idaho Falls, ID (United States)

2008-07-01T23:59:59.000Z

294

Microsoft Word - EMSL Rad Materials Use.r2.docx  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Dispersible radioactive material must be placed in rigid, leak-tight inner containers (e.g., durable screw-top sample jars). Non-dispersible radioactive material may...

295

Spent fuel integrity during transportation  

SciTech Connect (OSTI)

The conditions of recent shipments of light water reactor spent fuel were surveyed. The radioactivity level of cask coolant was examined in an attempt to find the effects of transportation on LWR fuel assemblies. Discussion included potential cladding integrity loss mechanisms, canning requirements, changes of radioactivity levels, and comparison of transportation in wet or dry media. Although integrity loss or degradation has not been identified, radioactivity levels usually increase during transportation, especially for leaking assemblies.

Funk, C.W.; Jacobson, L.D.

1980-01-01T23:59:59.000Z

296

Molten Salt Heat Transport Loop: Materials Corrosion and Heat Transfer Phenomena  

SciTech Connect (OSTI)

An experimental system for corrosion testing of candidate materials in molten FLiNaK salt at 850 degree C has been designed and constructed. While molten FLiNaK salt was the focus of this study, the system can be utilized for evaluation of materials in other molten salts that may be of interest in the future. Using this system, the corrosion performance of a number of code-certified alloys of interest to NGNP as well as the efficacy of Ni-electroplating have been investigated. The mechanisums underlying corrosion processes have been elucidated using scanning electron microscopy, x-ray diffraction, and x-ray photoelectron spectroscopy of the materials after the corrosion tests, as well as by the post-corrosion analysis of the salts using inductively coupled plasma (ICP) and neutron activation analysis (NAA) techniques.

Dr. Kumar Sridharan; Dr. Mark Anderson; Dr. Michael Corradini; Dr. Todd Allen; Luke Olson; James Ambrosek; Daniel Ludwig

2008-07-09T23:59:59.000Z

297

New Alkali Doped Pillared Carbon Materials Designed to Achieve Practical Reversible Hydrogen Storage for Transportation  

E-Print Network [OSTI]

and room temperature. This satisfies the DOE (Department of Energy) target of hydrogen-storage materials single-wall nanotubes can lead to a hydrogen-storage capacity of 6.0 mass% and 61:7 kg=m3 at 50 bars of roughly 1­20 bars and ambient temperature. Chen et al. reported remarkable hydrogen-storage capacities

Goddard III, William A.

298

Materials  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

2 MAG LAB REPORTS Volume 18 No. 1 CONDENSED MATTER SCIENCE Technique development, graphene, magnetism & magnetic materials, topological insulators, quantum fl uids & solids,...

299

Introduction to Nuclear Waste Management Nuclear Waste is a type of radioactive waste that is usually the by-product of  

E-Print Network [OSTI]

-Difficulty storing radioactive material -Waste disposal (heavy water, space jettison, underground) -Boat Transport -Impact water supply, nuclear fallout -6% world energy from nuclear energy, 14% world that is run through a turbine to produce energy. -Water or liquid metal are used to cool reactors. What

Auerbach, Scott M.

300

Theoretical Aspects of Science with Radioactive Nuclear Beams  

E-Print Network [OSTI]

Physics of radioactive nuclear beams is one of the main frontiers of nuclear science today. Experimentally, thanks to technological developments, we are on the verge of invading the territory of extreme N/Z ratios in an unprecedented way. Theoretically, nuclear exotica represent a formidable challenge for the nuclear many-body theories and their power to predict nuclear properties in nuclear terra incognita. It is important to remember that the lesson learned by going to the limits of the nuclear binding is also important for normal nuclei from the neighborhood of the beta stability valley. And, of course, radioactive nuclei are crucial astrophysically; they pave the highway along which the nuclear material is transported up in the proton and neutron numbers during the complicated synthesis process in stars.

Jacek Dobaczewski; Witold Nazarewicz

1997-07-28T23:59:59.000Z

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


301

Theoretical Aspects of Science with Radioactive Nuclear Beams  

E-Print Network [OSTI]

Physics of radioactive nuclear beams is one of the main frontiers of nuclear science today. Experimentally, thanks to technological developments, we are on the verge of invading the territory of extreme N/Z ratios in an unprecedented way. Theoretically, nuclear exotica represent a formidable challenge for the nuclear many-body theories and their power to predict nuclear properties in nuclear terra incognita. It is important to remember that the lesson learned by going to the limits of the nuclear binding is also important for normal nuclei from the neighborhood of the beta stability valley. And, of course, radioactive nuclei are crucial astrophysically; they pave the highway along which the nuclear material is transported up in the proton and neutron numbers during the complicated synthesis process in stars.

Dobaczewski, J; Dobaczewski, Jacek; Nazarewicz, Witold

1997-01-01T23:59:59.000Z

302

TRANSPORT THROUGH CRACKED CONCRETE: LITERATURE REVIEW  

SciTech Connect (OSTI)

Concrete containment structures and cement-based fills and waste forms are used at the Savannah River Site to enhance the performance of shallow land disposal systems designed for containment of low-level radioactive waste. Understanding and measuring transport through cracked concrete is important for describing the initial condition of radioactive waste containment structures at the Savannah River Site (SRS) and for predicting performance of these structures over time. This report transmits the results of a literature review on transport through cracked concrete which was performed by Professor Jason Weiss, Purdue University per SRR0000678 (RFP-RQ00001029-WY). This review complements the NRC-sponsored literature review and assessment of factors relevant to performance of grouted systems for radioactive waste disposal. This review was performed by The Center for Nuclear Waste Regulatory Analyses, San Antonio, TX, and The University of Aberdeen, Aberdeen Scotland and was focused on tank closure. The objective of the literature review on transport through cracked concrete was to identify information in the open literature which can be applied to SRS transport models for cementitious containment structures, fills, and waste forms. In addition, the literature review was intended to: (1) Provide a framework for describing and classifying cracks in containment structures and cementitious materials used in radioactive waste disposal, (2) Document the state of knowledge and research related to transport through cracks in concrete for various exposure conditions, (3) Provide information or methodology for answering several specific questions related to cracking and transport in concrete, and (4) Provide information that can be used to design experiments on transport through cracked samples and actual structures.

Langton, C.

2012-05-11T23:59:59.000Z

303

Impact of the deployment schedule of fast breeding reactors in the frame of French act for nuclear materials and radioactive waste management  

SciTech Connect (OSTI)

In the frame of the French Act of June 28, 2006 on 'a sustainable management of nuclear materials and radioactive waste' EDF R and D assesses various research scenarios of transition between the actual French fleet and a Generation IV fleet with a closed fuel cycle where plutonium is multi-recycled. The basic scenarios simulate a deployment of 60 GWe of Sodium-cooled Fast Reactors (SFRs) in two steps: one third from 2040 to 2050 and the rest from 2080 to 2100 (scenarios 2040). These research scenarios assume that SFR technology will be ready for industrial deployment in 2040. One of the many sensitivity analyses that EDF, as a nuclear power plant operator, must evaluate is the impact of a delay of SFR technology in terms of uranium consumptions, plutonium needs and fuel cycle utilities gauging. The sensitivity scenarios use the same assumptions as scenarios 2040 but they simulate a different transition phase: SFRs are deployed in one step between 2080 and 2110 (scenarios 2080). As the French Act states to conduct research on minor actinides (MA) management, we studied different options for 2040 and 2080 scenarios: no MA transmutation, americium transmutation in heterogeneous mode based on americium Bearing Blankets (AmBB) in SFRs and all MA transmutation in heterogeneous mode based on MA Bearing Blankets (MABB). Moreover, we studied multiple parameters that could impact the deployment of these reactors (SFR load factor, increase of the use of MOX in Light Water Reactors, increase of the cooling time in spent nuclear fuel storage...). Each scenario has been computed with the EDF R and D fuel cycle simulation code TIRELIRE-STRATEGIE and optimized to meet various fuel cycle constraints such as using the reprocessing facility with long period of constant capacity, keeping the temporary stored mass of plutonium and MA under imposed limits, recycling older assemblies first... These research scenarios show that the transition from the current PWR fleet to an equivalent fleet of Generation IV SFR can follow different courses. The design of SFR-V2B that we used in our studies needs a high inventory of plutonium resulting in tension on this resource. Several options can be used in order to loosen this tension: our results lead to favour the use of axial breeding blanket in SFR. Load factor of upcoming reactors has to be regarded with attention as it has a high impact on plutonium resource for a given production of electricity. The deployment of SFRs beginning in 2080 instead of 2040 following the scenarios we described creates higher tensions on reprocessing capacity, separated plutonium storage and spent fuel storage. In the frame of the French Act, we studied minor actinides transmutation. The flux of MA in all fuel cycle plants is really high, which will lead to decay heat, a and neutron emission related problems. In terms of reduction of MA inventories, the deployment of MA transmutation cycle must not delay the installation of SFRs. The plutonium production in MABB and AmBB does not allow reducing the use of axial breeding blankets. The impact of MA or Am transmutation over the high level waste disposal is more important if the SFRs are deployed later. Transmutation option (americium or all MA) does not have a significant impact on the number of canister produced nor on its long-term thermal properties. (authors)

Le Mer, J.; Garzenne, C.; Lemasson, D. [Electricite de France R and D, 1, Avenue du General De Gaulle, 92141 Clamart (France)

2012-07-01T23:59:59.000Z

304

WaterTransport in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing and Design Optimization  

SciTech Connect (OSTI)

Water management in Proton Exchange Membrane, PEM, Fuel Cells is challenging because of the inherent conflicts between the requirements for efficient low and high power operation. Particularly at low powers, adequate water must be supplied to sufficiently humidify the membrane or protons will not move through it adequately and resistance losses will decrease the cell efficiency. At high power density operation, more water is produced at the cathode than is necessary for membrane hydration. This excess water must be removed effectively or it will accumulate in the Gas Diffusion Layers, GDLs, between the gas channels and catalysts, blocking diffusion paths for reactants to reach the catalysts and potentially flooding the electrode. As power density of the cells is increased, the challenges arising from water management are expected to become more difficult to overcome simply due to the increased rate of liquid water generation relative to fuel cell volume. Thus, effectively addressing water management based issues is a key challenge in successful application of PEMFC systems. In this project, CFDRC and our partners used a combination of experimental characterization, controlled experimental studies of important processes governing how water moves through the fuel cell materials, and detailed models and simulations to improve understanding of water management in operating hydrogen PEM fuel cells. The characterization studies provided key data that is used as inputs to all state-of-the-art models for commercially important GDL materials. Experimental studies and microscopic scale models of how water moves through the GDLs showed that the water follows preferential paths, not branching like a river, as it moves toward the surface of the material. Experimental studies and detailed models of water and airflow in fuel cells channels demonstrated that such models can be used as an effective design tool to reduce operating pressure drop in the channels and the associated costs and weight of blowers and pumps to force air and hydrogen gas through the fuel cell. Promising improvements to materials structure and surface treatments that can potentially aid in managing the distribution and removal of liquid water were developed; and improved steady-state and freeze-thaw performance was demonstrated for a fuel cell stack under the self-humidified operating conditions that are promising for stationary power generation with reduced operating costs.

J. Vernon Cole; Abhra Roy; Ashok Damle; Hari Dahr; Sanjiv Kumar; Kunal Jain; Ned Djilai

2012-10-02T23:59:59.000Z

305

Electrostatics and radioactive aerosol behavior  

SciTech Connect (OSTI)

Radioactive aerosols differ from their nonradioactive counterparts by their ability to charge themselves by emitting charged particles during the radioactive decay process. Evidence that electrostatics, including this charging process, can affect the transport of the aerosols was summarized previously. Charge distributions and the mean charge for a monodisperse radioactive aerosol have been considered in detail. The principal results of theory to calculate charge distributions on a aerosol with a size distribution, changes to Brownian coagulation rates for an aerosol in a reactor containment, and possible changes to aerosol deposition resulting from the charging will be presented. The main purpose of the work has been to improve calculations of aerosol behavior in reactor containments, but behavior in less ionizing environments will be affected more strongly, and some problems remain to be solved in performing reliable calculations.

Clement, C.F.

1994-12-31T23:59:59.000Z

306

4.0 RISK FROM URANIUM MINING WASTE IN BUILDING In general, building materials contain low levels of radioactivity. For example, the range of  

E-Print Network [OSTI]

4.0 RISK FROM URANIUM MINING WASTE IN BUILDING MATERIALS In general, building materials contain low, especially in buildings constructed with materials containing uranium TENORM mine wastes. In the Grand the wastes from uranium mines have been removed from mining sites and used in local and nearby communities

307

Radioactive Threat Detection with Scattering Physics: A Model-Based Application  

SciTech Connect (OSTI)

The detection of radioactive contraband is a critical problem in maintaining national security for any country. Emissions from threat materials challenge both detection and measurement technologies especially when concealed by various types of shielding complicating the transport physics significantly. The development of a model-based sequential Bayesian processor that captures both the underlying transport physics including scattering offers a physics-based approach to attack this challenging problem. It is shown that this processor can be used to develop an effective detection technique.

Candy, J V; Chambers, D H; Breitfeller, E F; Guidry, B L; Verbeke, J M; Axelrod, M A; Sale, K E; Meyer, A M

2010-01-21T23:59:59.000Z

308

Radioactive Waste Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish policies and guidelines by which the Department of Energy (DOE) manages tis radioactive waste, waste byproducts, and radioactively contaminated surplus facilities.

1984-02-06T23:59:59.000Z

309

Survey of National Programs for Managing High-Level Radioactive  

E-Print Network [OSTI]

Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel-Level Radioactive Waste and Spent Nuclear Fuel A Report to Congress and the Secretary of Energy October 2009 #12 Safety (Germany) Peter De Preter: National Agency for Radioactive Waste and Enriched Fissile Materials

310

RADIOACTIVITY 1997 BNL Site Environmental Report 4 -1  

E-Print Network [OSTI]

of a few inches. Naturally occurring radioactive elements such as potassium-40 emit beta radiation. Gamma by materials such as paper and have a range in air of only an inch or so. Naturally occurring radioactive 4.3 Sources of Radiation Radioactivity and radiation are part of the earth's natural environment

311

Radioactive waste processing apparatus  

DOE Patents [OSTI]

Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container.

Nelson, Robert E. (Lombard, IL); Ziegler, Anton A. (Darien, IL); Serino, David F. (Maplewood, MN); Basnar, Paul J. (Western Springs, IL)

1987-01-01T23:59:59.000Z

312

Design and optimization of a multi-particle accelerator beam transport and delivery system for material irradiation in nuclear and fusion science  

E-Print Network [OSTI]

A beam delivery and transport system were designed for the use in MIT Materials Test Facility (M2TF). The purpose of this beam delivery system was to design a 36 MeV Proton Cyclotron for DPA accumulation and a 100 MeV ...

Sordelet, Tyler Christopher

2012-01-01T23:59:59.000Z

313

Materials  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recovery challenge fund LasDubey selectedContract Research Material

314

activity radioactive waste: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

315

aqueous radioactive waste: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

316

acidic radioactive waste: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

317

activities radioactive waste: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

318

activity radioactive wastes: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

is: not high-level radioactive waste or irradiated nuclear fuel not uranium, thorium or other ore tailings or waste from extraction and concentration for source material...

319

Alternative p-doped hole transport material for low operating voltage and high efficiency organic light-emitting diodes  

SciTech Connect (OSTI)

We investigate the properties of N,N?-[(Diphenyl-N,N?-bis)9,9,-dimethyl-fluoren-2-yl]-benzidine (BF-DPB) as hole transport material (HTL) in organic light-emitting diodes (OLEDs) and compare BF-DPB to the commonly used HTLs N,N,N?,N?-tetrakis(4-methoxyphenyl)-benzidine (MeO-TPD), 2,2?,7,7?-tetrakis(N,N?-di-p-methylphenylamino)-9,9?-spirobifluorene (Spiro-TTB), and N,N?-di(naphtalene-1-yl)-N,N?-diphenylbenzidine (NPB). The influence of 2,2?-(perfluoronaphthalene-2,6-diylidene)dimalononitrile (F6-TCNNQ p-dopant) concentration in BF-DPB on the operation voltage and efficiency of red and green phosphorescent OLEDs is studied; best results are achieved at 4?wt. % doping. Without any light extraction structure, BF-DPB based red (green) OLEDs achieve a luminous efficacy of 35?.1?lm/W (74?.0?lm/W) at 1000?cd/m{sup 2} and reach a very high brightness of 10?000 cd/m{sup 2} at a very low voltage of 3.2 V (3.1 V). We attribute this exceptionally low driving voltage to the high ionization potential of BF-DPB which enables more efficient hole injection from BF-DPB to the adjacent electron blocking layer. The high efficiency and low driving voltage lead to a significantly lower luminous efficacy roll-off compared to the other compounds and render BF-DPB an excellent HTL material for highly efficient OLEDs.

Murawski, Caroline, E-mail: caroline.murawski@iapp.de; Fuchs, Cornelius; Hofmann, Simone; Leo, Karl [Institut fr Angewandte Photophysik, Technische Universitt Dresden, George-Bhr-Str. 1, 01062 Dresden (Germany); Gather, Malte C. [Institut fr Angewandte Photophysik, Technische Universitt Dresden, George-Bhr-Str. 1, 01062 Dresden (Germany); SUPA, School of Physics and Astronomy, University of St Andrews, North Haugh, St Andrews, KY16 9SS Scotland (United Kingdom)

2014-09-15T23:59:59.000Z

320

EIS-0250-S1: Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada  

Broader source: Energy.gov [DOE]

The Proposed Action defined in the Yucca Mountain FEIS is to construct, operate, monitor, and eventually close a geologic repository at Yucca Mountain to dispose of spent nuclear fuel and high-level radioactive waste. The Proposed Action includes transportation of these materials from commercial and DOE sites to the repository.

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


321

Radioactive waste management in the former USSR. Volume 3  

SciTech Connect (OSTI)

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world`s largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

Bradley, D.J.

1992-06-01T23:59:59.000Z

322

Data and methods for the assessment of the risks associated with the maritime transport of radioactive materials: Results of the SeaRAM program studies. Volume 2 -- Appendices  

SciTech Connect (OSTI)

This report describes ship accident event trees, ship collision and ship fire frequencies, representative ships and shipping practices, a model of ship penetration depths during ship collisions, a ship fire spread model, cask to environment release fractions during ship collisions and fires, and illustrative consequence calculations. This report contains the following appendices: Appendix 1 -- Representative Ships and Shipping Practices; Appendix 2 -- Input Data for Minorsky Calculations; Appendix 3 -- Port Ship Speed Distribution; and Appendix 4 -- Cask-to-Environment Release Fractions.

Sprung, J.L.; Bespalko, S.J.; Kanipe, F.L. [and others

1998-05-01T23:59:59.000Z

323

A high integrity transportable supercompactor  

SciTech Connect (OSTI)

Current transportable equipment produced to utilize high force compaction to reduce the overall volume of drums containing solid radioactive material prior to disposal, were originally designed to standards which will eventually become obsolete. At the time these machines were produced, they were state-of-the-art, but are now indicating their weaknesses in operational and safety aspects. This paper formulates a concept for a Transportable Supercompactor for handling alpha and beta/gamma bearing wastes, low operator dose uptake, contamination and radiation control systems, liquids collection, the maintenance demands of a contained press, etc., taking into account the latest technical and safety considerations. The possibility of using the concept as a skid mounted fixed Supercompactor is also reviewed in this paper.

Sims, J.; Schmidt, G.

1993-12-31T23:59:59.000Z

324

Transportation System Requirements Document  

SciTech Connect (OSTI)

This Transportation System Requirements Document (Trans-SRD) describes the functions to be performed by and the technical requirements for the Transportation System to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from Purchaser and Producer sites to a Civilian Radioactive Waste Management System (CRWMS) site, and between CRWMS sites. The purpose of this document is to define the system-level requirements for Transportation consistent with the CRWMS Requirement Document (CRD). These requirements include design and operations requirements to the extent they impact on the development of the physical segments of Transportation. The document also presents an overall description of Transportation, its functions, its segments, and the requirements allocated to the segments and the system-level interfaces with Transportation. The interface identification and description are published in the CRWMS Interface Specification.

Not Available

1993-09-01T23:59:59.000Z

325

Radioactive Waste Management Procedures and Guidelines See Radiation Manual 1997 for further details  

E-Print Network [OSTI]

1-24-03 Radioactive Waste Management Procedures and Guidelines See Radiation Manual 1997 PART I. Radioactive Waste A. Dry Waste 1. Labs must request a box from the Radioactive Waste program, and use only this box for accumulating their waste. 2. Place only radioactive material contaminated

326

Center for Intermodal Transportation Safety  

E-Print Network [OSTI]

Center for Intermodal Transportation Safety and Security Panagiotis Scarlatos, Ph.D., Director Transportation Safety and Security #12;Center for Intermodal Transportation Safety and Security Partners #12 evacuations · Tracking systems for hazardous materials Center for Intermodal Transportation Safety

Fernandez, Eduardo

327

ANSI N14.5 source term licensing of spent-fuel transport cask containment  

SciTech Connect (OSTI)

American National Standards Institute (ANSI) standard N14.5 states that ``compliance with package containment requirements shall be demonstrated either by determination of the radioactive contents release rate or by measurement of a tracer material leakage rate.`` The maximum permissible leakage rate from the transport cask is equal to the maximum permissible release rate divided by the time-averaged volumetric concentration of suspended radioactivity within the cask. The development of source term methodologies at Sandia National Laboratories (SNL) provides a means to determine the releasable radionuclide concentrations within spent-fuel transport casks by estimating the probability of cladding breach, quantifying the amount of radioactive material released into the cask interior from the breached fuel rods, and quantifying the amount of radioactive material within the cask due to other sources. These methodologies are implemented in the Source Term Analyses for Containment Evaluations (STACE) software. In this paper, the maximum permissible leakage rates for the normal and hypothetical accident transport conditions defined by 10 CFR 71 are estimated using STACE for a given cask design, fuel assembly, and initial conditions. These calculations are based on defensible analysis techniques that credit multiple release barriers, including the cladding and the internal cask walls.

Seager, K.D. [Sandia National Labs., Albuquerque, NM (United States); Reardon, P.C. [GRAM, Inc., Albuquerque, NM (United States); James, R.J.; Foadian, H.; Rashid, Y.R. [ANATECH Research Corp., La Jolla, CA (United States)

1993-10-01T23:59:59.000Z

328

Waste gas combustion in a Hanford radioactive waste tank  

SciTech Connect (OSTI)

It has been observed that a high-level radioactive waste tank generates quantities of hydrogen, ammonia, nitrous oxide, and nitrogen that are potentially well within flammability limits. These gases are produced from chemical and nuclear decay reactions in a slurry of radioactive waste materials. Significant amounts of combustible and reactant gases accumulate in the waste over a 110- to 120-d period. The slurry becomes Taylor unstable owing to the buoyancy of the gases trapped in a matrix of sodium nitrate and nitrite salts. As the contents of the tank roll over, the generated waste gases rupture through the waste material surface, allowing the gases to be transported and mixed with air in the cover-gas space in the dome of the tank. An ignition source is postulated in the dome space where the waste gases combust in the presence of air resulting in pressure and temperature loadings on the double-walled waste tank. This analysis is conducted with hydrogen mixing studies HMS, a three-dimensional, time-dependent fluid dynamics code coupled with finite-rate chemical kinetics. The waste tank has a ventilation system designed to maintain a slight negative gage pressure during normal operation. We modeled the ventilation system with the transient reactor analysis code (TRAC), and we coupled these two best-estimate accident analysis computer codes to model the ventilation system response to pressures and temperatures generated by the hydrogen and ammonia combustion.

Travis, J.R.; Fujita, R.K.; Spore, J.W.

1994-07-01T23:59:59.000Z

329

Spent Nuclear Fuel Transportation: An Examination of Potential Lessons Learned From Prior Shipping Campaigns  

SciTech Connect (OSTI)

The Nuclear Waste Policy Act of 1982 (NWPA), as amended, assigned the Department of Energy (DOE) responsibility for developing and managing a Federal system for the disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for accepting, transporting, and disposing of SNF and HLW at the Yucca Mountain repository in a manner that protects public health, safety, and the environment; enhances national and energy security; and merits public confidence. OCRWM faces a near-term challengeto develop and demonstrate a transportation system that will sustain safe and efficient shipments of SNF and HLW to a repository. To better inform and improve its current planning, OCRWM has extensively reviewed plans and other documents related to past high-visibility shipping campaigns of SNF and other radioactive materials within the United States. This report summarizes the results of this review and, where appropriate, lessons learned.

Marsha Keister; Kathryn McBride

2006-08-01T23:59:59.000Z

330

Environmental Impacts of Transportation to the Potential Repository at Yucca Mountain  

SciTech Connect (OSTI)

The Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada analyzes a Proposed Action to construct, operate, monitor, and eventually close a geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste. As part of the Proposed Action, the EIS analyzes the potential impacts of transporting commercial and DOE spent nuclear fuel and high-level radioactive waste to Yucca Mountain from 77 sites across the United States. The analysis includes information on the comparative impacts of transporting these materials by truck and rail and discusses the impacts of building a rail line or using heavy-haul trucks to move rail casks from a mainline railroad in Nevada to the site. This paper provides an overview of the analyses and the potential impacts of these transportation activities. The potential transportation impacts were looked at from two perspectives: transportation of spent nuclear fuel and high-level radioactive waste by legal-weight truck or by rail on a national scale and impacts specific to Nevada from the transportation of these materials from the State borders to the Yucca Mountain site. In order to address the range of impacts that could result from the most likely modes, legal-weight truck and rail, the EIS employed two analytical scenarios--mostly legal-weight truck and mostly rail. Estimated national transportation impacts were based on 24 years of transportation activities. Approximately 8 fatalities could occur from all causes in the nationwide general population from incident-free transportation activities of the mostly legal-weight truck scenario and about 4 from the mostly rail scenario. The analysis examined the radiological consequences under the maximum foreseeable accident scenario and also overall accident risk. The overall accident risk over the 24 year period would be about 0.0002 latent cancer fatality for the mostly legal-weight truck scenario and about 0.0005 latent cancer fatality for the mostly rail scenario. The maximum reasonably foreseeable accident scenario resulted in 0.55 latent cancer fatality for the legal-weight truck case and 5 latent cancer fatalities in the case of mostly rail. The EIS also analyzed the impacts associated with the transportation of spent nuclear fuel and high-level radioactive waste in the State of Nevada. This included: constructing a branch rail line and using it to ship waste to the repository; upgrading highways in Nevada for use by heavy-haul trucks; constructing and operating an intermodal transfer station; and transporting personnel and materials to support construction and operation of the repository.

R.L. Sweeney; R. Best; P. Bolton; P. Adams

2002-01-03T23:59:59.000Z

331

Radioactive and chemotoxic wastes: Only radioactive wastes?  

SciTech Connect (OSTI)

Radioactive waste arising from Italian Nuclear Power Plants and Research Centers, classified as 1st and 2nd Category wastes, are managed only as radioactive wastes following the Technical Guide No. 26 issued by the Italian Regulatory Body: ENEA DISP on 1987. A very important Regulatory Regime revision for Italian Nuclear Activities started at the end of 1991. This paper considers the need to develop a new strategy dedicated to mixed waste in line with current international trends.

Eletti, G.F.; Tocci, M. [ENEA DISP, Rome (Italy)

1993-12-31T23:59:59.000Z

332

Routing of radioactive shipments in networks with time-varying costs and curfews  

SciTech Connect (OSTI)

This research examines routing of radioactive shipments in highway networks with time-dependent travel times and population densities. A time-dependent least-cost path (TDLCP) algorithm that uses a label-correcting approach is adapted to include curfews and waiting at nodes. A method is developed to estimate time-dependent population densities, which are required to estimate risk associated with the use of a particular highway link at a particular time. The TDLCP algorithm is implemented for example networks and used to examine policy questions related to radioactive shipments. It is observed that when only Interstate highway facilities are used to transport these materials, a shipment must go through many cities and has difficulty avoiding all of them during their rush hour periods. Decreases in risk, increased departure time flexibility, and modest increases in travel times are observed when primary and/or secondary roads are included in the network. Based on the results of the example implementation, the suitability of the TDLCP algorithm for strategic nuclear material and general radioactive material shipments is demonstrated.

Bowler, L.A.; Mahmassani, H.S. [Univ. of Texas, Austin, TX (United States). Dept. of Civil Engineering

1998-09-01T23:59:59.000Z

333

FABRICATION AND DEPLOYMENT OF THE 9979 TYPE AF RADIOACTIVE WASTE PACKAGING FOR THE DEPARTMENT OF ENERGY  

SciTech Connect (OSTI)

This paper summarizes the development, testing, and certification of the 9979 Type A Fissile Packaging that replaces the UN1A2 Specification Shipping Package eliminated from Department of Transportation (DOT) 49 CFR 173. The DOT Specification Package was used for many decades by the U.S. nuclear industry as a fissile waste container until its removal as an authorized container by DOT. This paper will discuss stream lining procurement of high volume radioactive material packaging manufacturing, such as the 9979, to minimize packaging production costs without sacrificing Quality Assurance. The authorized content envelope (combustible and non-combustible) as well as planned content envelope expansion will be discussed.

Blanton, P.; Eberl, K.

2013-10-10T23:59:59.000Z

334

Optimization of the Transport Shield for Neutrinoless Double Beta-decay Enriched Germanium  

SciTech Connect (OSTI)

This document presents results of an investigation of the material and geometry choice for the transport shield of germanium, the active detector material used in 76Ge neutrinoless double beta decay searches. The objective of this work is to select the optimal material and geometry to minimize cosmogenic production of radioactive isotopes in the germanium material. The design of such a shield is based on the calculation of the cosmogenic production rate of isotopes that are known to cause interfering backgrounds in 76Ge neutrinoless double beta decay searches.

Aguayo Navarrete, Estanislao; Kouzes, Richard T.; Orrell, John L.; Reid, Douglas J.; Fast, James E.

2012-04-15T23:59:59.000Z

335

A source-term method for determining spent-fuel transport cask containment requirements: Executive summary  

SciTech Connect (OSTI)

This Executive Summary presents the methodology for determining containment requirements for spent-fuel transport casks under normal and hypothetical accident conditions. Three sources of radioactive material are considered: (1) the spent fuel itself, (2) radioactive material, referred to as CRUD, attached to the outside surfaces of fuel rod cladding, and (3) residual contamination adhering to interior surfaces of the cask cavity. The methodologies for determining the concentrations of freely suspended radioactive materials within a spent-fuel transport cask for these sources are discussed in much greater detail in three companion reports: A Method for Determining the Spent-Fuel Contribution to Transport Cask Containment Requirements,'' Estimate of CRUD Contribution to Shipping Cask Containment Requirements,'' and A Methodology for Estimating the Residual Contamination Contribution to the Source Term in a Spent-Fuel Transport Cask.'' Examples of cask containment requirements that combine the individually determined containment requirements for the three sources are provided, and conclusions from the three companion reports to this Executive Summary are presented.

Sanders, T.L.; Seager, K.D. (Sandia National Labs., Albuquerque, NM (United States)); Reardon, P.C. (GRAM, Inc., Albuquerque, NM (United States))

1993-02-01T23:59:59.000Z

336

Conditioning and Repackaging of Spent Radioactive Cs-137 and Co-60 Sealed Sources in Egypt - 13490  

SciTech Connect (OSTI)

Radioactive Sealed sources (RSSs) are widely use all over the world in medicine, agriculture, industry, research, etc. The accidental misuse and exposure to RSSs has caused significant environmental contamination, serious injuries and many deaths. The high specific activity of the materials in many RSSs means that the spread of as little as microgram quantities can generate significant risk to human health and inhibit the use of buildings and land. Conditioning of such sources is a must to protect humans and environment from the hazard of ionizing radiation and contamination. Conditioning is also increase the security of these sources by decreasing the probability of stolen and/or use in terrorist attacks. According to the law No.7/2010, Egyptian atomic energy authority represented in the hot laboratories and waste management center (centralized waste facility, HLWMC) has the responsibility of collecting, conditioning, storing and management of all types of radioactive waste from all Egyptian territory including spent radioactive sealed sources (SRSSs). This paper explains the conditioning procedures for two of the most common SRSSs, Cs{sup 137} and Co{sup 60} sources which make up more than 90% of the total spent radioactive sealed sources stored in our centralized waste facility as one of the major activities of hot laboratories and waste management center. Conditioning has to meet three main objectives, be acceptable for storage, enable their safe transport, and comply with disposal requirements. (authors)

Hasan, M.A.; Selim, Y.T.; El-Zakla, T. [Hot Labs and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)] [Hot Labs and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)

2013-07-01T23:59:59.000Z

337

Radioactive Waste: 1. Radioactive waste from your lab is  

E-Print Network [OSTI]

Radioactive Waste: 1. Radioactive waste from your lab is collected by the RSO. 2. Dry radioactive waste must be segregated by isotope. 3. Liquid radioactive waste must be separated by isotope. 4. Liquid frequently and change them if contaminated. 5. Use radioactive waste container to collect the waste. 6. Check

Jia, Songtao

338

Electric transport properties of the pentatelluride materials HfTe{sub 5} and ZrTe{sub 5}  

SciTech Connect (OSTI)

The authors have measured the resistivity and thermopower of single crystals as well as polycrystalline pressed powders of the low-dimensional pentatelluride materials: HfTe{sub 5} and ZrTe{sub 5}. They have performed these measurements as a function of temperature between 5K and 320K. In the single crystals there is a peak in the resistivity for both materials at a peak temperature, T{sub p} where T{sub p} {approx} 80K for HfTe{sub 5} and T{sub p} {approx} 145K for ZrTe{sub 5}. Both materials exhibit a large p-type thermopower around room temperature which undergoes a change to n-type below the peak. These data are similar to behavior observed previously in these materials. They have also synthesized pressed powders of polycrystalline pentatelluride materials, HfTe{sub 5} and ZrTe{sub 5}. They have measured the resistivity and thermopower of these polycrystalline materials as a function of temperature between 5K and 320K. For the polycrystalline material, the room temperature thermopower for each of these materials is relatively high, +95 {micro}V/K and +65 {micro}V/K for HfTe{sub 5} and ZrTe{sub 5}, respectively. These values compare closely to thermopower values for single crystals of these materials. At 77 K, the thermopower is +55 {micro}V/K for HfTe{sub 5} and +35 {micro}V/K for ZrTe{sub 5}. In fact, the thermopower for the polycrystals decreases monotonically with temperature to T {approx} 5K, thus exhibiting p-type behavior over the entire range of temperature. As expected, the resistivity for the polycrystals is higher than the single crystal material, with values of 430 m{Omega}-cm and 24 m{Omega}-cm for HfTe{sub 5} and ZrTe{sub 5} respectively, compared to single crystal values of 0.35 m{Omega}-cm (HfTe{sub 5}) and 1.0 m{Omega}-cm (ZrTe{sub 5}). The authors have found that the peak in the resistivity evident in both single crystal materials is absent in these polycrystalline materials. They will discuss these materials in relation to their potential as candidates for thermoelectric applications.

Tritt, T.M.; Wilson, M.L.; Littleton, R.L. [and others

1997-07-01T23:59:59.000Z

339

Radioactive Waste Management Basis  

SciTech Connect (OSTI)

The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Perkins, B K

2009-06-03T23:59:59.000Z

340

Radioactivity in Food and the Environment, 2005  

E-Print Network [OSTI]

.............................................................................................. 0 .. Radioactive waste disposal from nuclear sites ........................................................................................................................... 9 . Disposals of radioactive waste............................................ .. Radioactive waste disposal at sea

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


341

ONSITE TRANSPORTATION AUTHORIZATION CHALLENGES AT THE SAVANNAH RIVER SITE  

SciTech Connect (OSTI)

Prior to 2008, transfers of radioactive material within the Savannah River Site (SRS) boundary, referred to as onsite transfers, were authorized by Transportation Safety Basis (TSB) documents that only required approval by the SRS contractor. This practice was in accordance with the existing SRS Transportation Safety Document (TSD). In 2008 the Department of Energy Savannah River Field Office (DOE-SR) requested that the SRS TSD be revised to require DOE-SR approval of all Transportation Safety Basis (TSB) documents. As a result, the primary SRS contractor embarked on a multi-year campaign to consolidate old or generate new TSB documents and obtain DOE-SR approval for each. This paper focuses on the challenges incurred during the rewriting or writing of and obtaining DOE-SR approval of all Savannah River Site Onsite Transportation Safety Basis documents.

Watkins, R.; Loftin, B.; Hoang, D.; Maxted, M.

2012-05-30T23:59:59.000Z

342

US Department of Energy automated transportation management system  

SciTech Connect (OSTI)

The US Department of Energy (DOE) has approximately 80 facilities throughout the United States that specialize in either scientific research, engineering, technology, production, and/or waste management activities. These facilities can best be described as Government Owned, Contractor Operated (GOCO) sites, and vary in size from very small laboratories to large industrial plant type facilities. Each of these GOCO`s have varying needs for transportation of materials into and/or out of their facility. Therefore, Traffic Management operations will differ from site to site due to size and the internal or site specific mission. The DOE Transportation Management Division (TMD) has the corporate responsibility to provide a well managed transportation management program for the safe, efficient, and economical transportation of all DOE-owned materials. To achieve this mission, TMD provides oversight, and when necessary, resources to assist in ensuring regulatory compliance in the packaging and shipment of DOE-owned materials. A large part of TMD`s responsibility is to develop, administer, and provide policies and guidance concerning department-wide transportation and packaging operations. This responsibility includes overall Transportation Management policies and programs for the packaging and movement of all DOE materials, including radioactive materials, other hazardous materials/substances, and hazardous wastes. TMD formulates policies and guidance that assist the DOE Field Elements and GOCO`s in meeting TMD`s goal for safe, efficient and economical transportation. Considering there are at least 80 shipping and receiving sites, the challenge encountered by TMD has been the difficulty in managing such a diverse transportation community.

Thomas, T.M. [Dept. of Energy, Germantown, MD (United States); Frost, D.M.; Lopez, C.A. [MELE Associates, Rockville, MD (United States)] [and others

1996-12-31T23:59:59.000Z

343

Materials Science and Materials Chemistry for Large Scale Electrochemi...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Science and Materials Chemistry for Large Scale Electrochemical Energy Storage: From Transportation to Electrical Grid Materials Science and Materials Chemistry for Large Scale...

344

Groundwater Impacts of Radioactive Wastes and Associated Environmental Modeling Assessment  

SciTech Connect (OSTI)

This article provides a review of the major sources of radioactive wastes and their impacts on groundwater contamination. The review discusses the major biogeochemical processes that control the transport and fate of radionuclide contaminants in groundwater, and describe the evolution of mathematical models designed to simulate and assess the transport and transformation of radionuclides in groundwater.

Ma, Rui; Zheng, Chunmiao; Liu, Chongxuan

2012-11-01T23:59:59.000Z

345

Automated Transportation Management System (ATMS) Software Project Management Plan (SPMP). Revision 2  

SciTech Connect (OSTI)

As a cabinet level federal agency with a diverse range of missions and an infrastructure spanning the United States, the US Department of Energy (DOE) has extensive freight transportation requirements. Performance and management of this freight activity is a critical function. DOE`s Transportation Management Division (TMD) has an agency-wide responsibility for overseeing transportation activities. Actual transportation operations are handled by government or contractor staff at the field locations. These staff have evolved a diverse range of techniques and procedures for performing transportation functions. In addition to minimizing the economic impact of transportation on programs, facility transportation staff must be concerned with the increasingly complex task of complying with complex shipment safety regulations. Maintaining the department`s safety record for shipping hazardous and radioactive materials is a primary goal. Use of automation to aid transportation functions is not widespread within DOE, though TMD has a number of software systems designed to gather and analyze data pertaining to field transportation activities. These systems are not integrated. Historically, most field facilities have accomplished transportation-related tasks manually or with minimal computer assistance. At best, information and decision support systems available to transportation staffs within the facilities are fragmented. In deciding where to allocate resources for automation, facility managers have not tended to give the needs of transportation departments a high priority. This diversity causes TMD significant difficulty in collecting data for use in managing department-wide transportation activities.

Weidert, R.S.

1995-05-26T23:59:59.000Z

346

The New Orphaned Radioactive Sources Program in the United States International Conference on the Safety of Radiation Sources and the Security of Radioactive  

E-Print Network [OSTI]

of contamination in metals: contaminated metal from foreign countries, and sealed radioactive sources, both1 The New Orphaned Radioactive Sources Program in the United States International Conference on the Safety of Radiation Sources and the Security of Radioactive Materials. September 14-18, 1998 Neil Naraine

347

Recovering Radioactive Materials with ORSP Team  

ScienceCinema (OSTI)

The National Nuclear Security Administration sponsors a program, executed by Los Alamos National Laboratory, to recover radioisotopes used by industry and academia and no longer needed. Called the "Offsite Source Recovery Program (OSRP), it has recovered more than 16,000 orphan sources as of 2008.

LANL

2009-09-01T23:59:59.000Z

348

Recovering Radioactive Materials with OSRP team  

ScienceCinema (OSTI)

The National Nuclear Security Administration sponsors a program, executed by Los Alamos National Laboratory, to recover radioisotopes used by industry and academia and no longer needed. Called the "Offsite Source Recovery Program (OSRP), it has recovered

None

2010-01-08T23:59:59.000Z

349

Emergency Responder Radioactive Material Quick Reference Sheet  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergy CooperationRequirementsDraft EnvironmentalRoadDepartment5-CE-14020)BUILDING

350

ETEC - Radioactive Handling Materials Facility (RMHF) Leachfield |  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power SystemsResources DOE ZeroThreeEnergyDepartment0:Energy 2: ActionsEPActDepartment of

351

Radioactive Materials Emergencies Course Presentation | Department of  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAXBalancedDepartment ofColumbus HTS1,Geologic Disposal= J .MEASUREMENT

352

Transportation of radionuclides in urban environs: draft environmental assessment  

SciTech Connect (OSTI)

This report assesses the environmental consequences of the transportation of radioactive materials in densely populated urban areas, including estimates of the radiological, nonradiological, and social impacts arising from this process. The chapters of the report and the appendices which follow detail the methodology and results for each of four causative event categories: incident free transport, vehicular accidents, human errors or deviations from accepted quality assurance practices, and sabotage or malevolent acts. The numerical results are expressed in terms of the expected radiological and economic impacts from each. Following these discussions, alternatives to the current transport practice are considered. Then, the detailed analysis is extended from a limited area of New York city to other urban areas. The appendices contain the data bases and specific models used to evaluate these impacts, as well as discussions of chemical toxicity and the social impacts of radioactive material transport in urban areas. The latter are evaluated for each causative event category in terms of psychological, sociological, political, legal, and organizational impacts. The report is followed by an extensive bibliography covering the many fields of study which were required in performing the analysis.

Finley, N.C.; Aldrich, D.C.; Daniel, S.L.; Ericson, D.M.; Henning-Sachs, C.; Kaestner, P.C.; Ortiz, N.R.; Sheldon, D.D.; Taylor, J.M.

1980-07-01T23:59:59.000Z

353

RADIOACTIVE WASTE DISPOSAL IN GRANITE  

E-Print Network [OSTI]

RADIOACTIVE WASTE DISPOSAL IN GRANITE Paul A. WitherspoonRADIOACTIVE WASTE DISPOSAL IN GRANITE Paul A. Wither spoona repository site in granite are to evaluate the suitability

Witherspoon, P.A.

2010-01-01T23:59:59.000Z

354

Electronic transport in Lithium Nickel Manganese Oxide, a high-voltage cathode material for Lithium-Ion batteries  

E-Print Network [OSTI]

Potential routes by which the energy densities of lithium-ion batteries may be improved abound. However, the introduction of Lithium Nickel Manganese Oxide (LixNi1i/2Mn3/2O4, or LNMO) as a positive electrode material appears ...

Ransil, Alan Patrick Adams

2013-01-01T23:59:59.000Z

355

Packaging and Transportation Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes safety requirements for the proper packaging and transportation of offsite shipments and onsite transfers of hazardous materials andor modal transport. Cancels DOE 1540.2 and DOE 5480.3

1995-09-27T23:59:59.000Z

356

Packaging and Transportation Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes safety requirements for the proper packaging and transportation of Department of Energy (DOE) offsite shipments and onsite transfers of hazardous materials and for modal transport. Canceled by DOE 460.1A

1995-09-27T23:59:59.000Z

357

Packaging and Transportation Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Establishes safety requirements for the proper packaging and transportation of Department of Energy (DOE) offsite shipments and onsite transfers of hazardous materials and for modal transport. Cancels DOE O 460.1.

1996-10-02T23:59:59.000Z

358

Radioactive Waste Management Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. The purpose of the Manual is to catalog those procedural requirements and existing practices that ensure that all DOE elements and contractors continue to manage DOE's radioactive waste in a manner that is protective of worker and public health and safety, and the environment. Does not cancel other directives.

1999-07-09T23:59:59.000Z

359

RADIOACTIVE ELEMENT REMOVAL FROM WATER USING GRAPHENE OXIDE (GO)  

E-Print Network [OSTI]

and may release significant amounts of radioactive material into the environment resulting in the potential for widespread exposure. These industries include mining, phosphate processing, metal ore processing, heavy mineral sand processing, titanium...

Concklin, Joshua Paul

2013-12-19T23:59:59.000Z

360

Modelling of long-term diffusionreaction in a bentonite barrier for radioactive waste confinement  

E-Print Network [OSTI]

Modelling of long-term diffusion­reaction in a bentonite barrier for radioactive waste confinement in geological disposal facilities for radioactive waste. This material is expected to fill up by swelling transformations; Solute diffusion 1. Introduction The radioactive waste confinement in deep geolo- gical laye

Montes-Hernandez, German

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


361

Investigations to site a radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4  

E-Print Network [OSTI]

Investigations to site a radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4 Radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4 s the UK radioactive waste legacy comprises difficult material which is complex, of mixed origin

362

E-Print Network 3.0 - alkaline radioactive liquid Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

with Conventional Uranium Milling Introduction Summary: Radioactive Materials from Uranium Mining. Volume 1: Mining and Reclamation Background" by U.S. EPA (2006... as an...

363

Puncture detecting barrier materials  

DOE Patents [OSTI]

A method and apparatus for continuous real-time monitoring of the integrity of protective barrier materials, particularly protective barriers against toxic, radioactive and biologically hazardous materials has been developed. Conductivity, resistivity or capacitance between conductive layers in the multilayer protective materials is measured by using leads connected to electrically conductive layers in the protective barrier material. The measured conductivity, resistivity or capacitance significantly changes upon a physical breach of the protective barrier material. 4 figs.

Hermes, R.E.; Ramsey, D.R.; Stampfer, J.F.; Macdonald, J.M.

1998-03-31T23:59:59.000Z

364

Dynamic radioactive particle source  

DOE Patents [OSTI]

A method and apparatus for providing a timed, synchronized dynamic alpha or beta particle source for testing the response of continuous air monitors (CAMs) for airborne alpha or beta emitters is provided. The method includes providing a radioactive source; placing the radioactive source inside the detection volume of a CAM; and introducing an alpha or beta-emitting isotope while the CAM is in a normal functioning mode.

Moore, Murray E.; Gauss, Adam Benjamin; Justus, Alan Lawrence

2012-06-26T23:59:59.000Z

365

Radioactive Waste Management Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07.

1999-07-09T23:59:59.000Z

366

Quality assurance for radioactive waste packages -- A general approach  

SciTech Connect (OSTI)

Radioactive waste packages must fulfill the requirements resulting from regulations concerning handling, treatment, conditioning, transportation, storage and disposal so that the goal of radioactive waste management can be achieved. Usually in different parts of waste management different quality systems are used, and different quality assurance measures are performed. In the paper, these problems ar elucidated and it is explained by means of the quality assurance performed for the disposal of radioactive waste in Germany how the fulfillment of the requirements of the repository can be ensured.

Martens, B.R. [Bundesamt fuer Strahlenschutz, Saltzgitter (Germany)

1993-12-31T23:59:59.000Z

367

Concluding Remarks In this work, we have explored in depth many types of radioactive contamination that are  

E-Print Network [OSTI]

Concluding Remarks In this work, we have explored in depth many types of radioactive contamination as radiopurity testing facilities, capable of measuring the radioactivity levels of materials to be used

368

Radioactive tank waste remediation focus area  

SciTech Connect (OSTI)

EM`s Office of Science and Technology has established the Tank Focus Area (TFA) to manage and carry out an integrated national program of technology development for tank waste remediation. The TFA is responsible for the development, testing, evaluation, and deployment of remediation technologies within a system architecture to characterize, retrieve, treat, concentrate, and dispose of radioactive waste stored in the underground stabilize and close the tanks. The goal is to provide safe and cost-effective solutions that are acceptable to both the public and regulators. Within the DOE complex, 335 underground storage tanks have been used to process and store radioactive and chemical mixed waste generated from weapon materials production and manufacturing. Collectively, thes tanks hold over 90 million gallons of high-level and low-level radioactive liquid waste in sludge, saltcake, and as supernate and vapor. Very little has been treated and/or disposed or in final form.

NONE

1996-08-01T23:59:59.000Z

369

Wide range radioactive gas concentration detector  

DOE Patents [OSTI]

A wide range radioactive gas concentration detector and monitor which is capable of measuring radioactive gas concentrations over a range of eight orders of magnitude. The device of the present invention is designed to have an ionization chamber which is sufficiently small to give a fast response time for measuring radioactive gases but sufficiently large to provide accurate readings at low concentration levels. Closely spaced parallel plate grids provide a uniform electric field in the active region to improve the accuracy of measurements and reduce ion migration time so as to virtually eliminate errors due to ion recombination. The parallel plate grids are fabricated with a minimal surface area to reduce the effects of contamination resulting from absorption of contaminating materials on the surface of the grids. Additionally, the ionization chamber wall is spaced a sufficient distance from the active region of the ionization chamber to minimize contamination effects.

Anderson, David F. (Los Alamos, NM)

1984-01-01T23:59:59.000Z

370

EIS-0250-S2: Supplemental EIS for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada- Nevada Rail Transportation Corridor  

Broader source: Energy.gov [DOE]

This SEIS is to evaluate the potential environmental impacts of constructing and operating a railroad for shipments of spent nuclear fuel and high-level radioactive waste from an existing rail line in Nevada to a geologic repository at Yucca Mountain. The purpose of the evaluation is to assist the Department in deciding whether to construct and operate a railroad in Nevada, and if so, in which corridor and along which specific alignment within the selected corridor.

371

Recent Theoretical Results for Advanced Thermoelectric Materials...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Materials Recent Theoretical Results for Advanced Thermoelectric Materials Transport theory and first principles calculations applied to oxides, chalcogenides and...

372

HIGHWAY INFRASTRUCTURE FOCUS AREA NEXT-GENERATION INFRASTRUCTURE MATERIALS VOLUME I - TECHNICAL PROPOSAL & MANAGEMENTENHANCEMENT OF TRANSPORTATION INFRASTRUCTURE WITH IRON-BASED AMORPHOUS-METAL AND CERAMIC COATINGS  

SciTech Connect (OSTI)

The infrastructure for transportation in the United States allows for a high level of mobility and freight activity for the current population of 300 million residents, and several million business establishments. According to a Department of Transportation study, more than 230 million motor vehicles, ships, airplanes, and railroads cars were used on 6.4 million kilometers (4 million miles) of highways, railroads, airports, and waterways in 1998. Pipelines and storage tanks were considered to be part of this deteriorating infrastructure. The annual direct cost of corrosion in the infrastructure category was estimated to be approximately $22.6 billion in 1998. There were 583,000 bridges in the United States in 1998. Of this total, 200,000 bridges were steel, 235,000 were conventional reinforced concrete, 108,000 bridges were constructed using pre-stressed concrete, and the balance was made using other materials of construction. Approximately 15 percent of the bridges accounted for at this point in time were structurally deficient, primarily due to corrosion of steel and steel reinforcement. Iron-based amorphous metals, including SAM2X5 (Fe{sub 49.7}Cr{sub 17.7}Mn{sub 1.9}Mo{sub 7.4}W{sub 1.6}B{sub 15.2}C{sub 3.8}Si{sub 2.4}) and SAM1651 (Fe{sub 48}Mo{sub 14}Cr{sub 15}Y{sub 2}C{sub 15}B{sub 6}) have been developed, and have very good corrosion resistance. These materials have been prepared as a melt-spun ribbons, as well as gas atomized powders and thermal-spray coatings. During electrochemical testing in several environments, including seawater at 90 C, the passive film stabilities of these materials were found to be comparable to that of more expensive high-performance alloys, based on electrochemical measurements of the passive film breakdown potential and general corrosion rates. These materials also performed very well in standard salt fog tests. Chromium (Cr), molybdenum (Mo) and tungsten (W) provided corrosion resistance, and boron (B) enabled glass formation. The high boron content of this particular amorphous metal made it an effective neutron absorber, and suitable for criticality control applications. These amorphous alloys appear to maintain their corrosion resistance up to the glass transition temperature. Visionary research is proposed to extend the application of corrosion-resistant iron-based amorphous metal coatings, and variants of these coatings, to protection of the Nation's transportation infrastructure. Specific objectives of the proposed work are: (1) fabrication of appropriate test samples for evaluation of concept; (2) collection of production and test data for coated steel reinforcement bars, enabling systematic comparison of various coating options, based upon performance and economic considerations; and (3) construction and testing of concrete structures with coated steel reinforcement bars, thereby demonstrating the value of amorphous-metal coatings. The benefits of ceramic coatings as thermal barriers will also be addressed.

Farmer, J C

2007-12-04T23:59:59.000Z

373

Radioactivity in food crops  

SciTech Connect (OSTI)

Published levels of radioactivity in food crops from 21 countries and 4 island chains of Oceania are listed. The tabulation includes more than 3000 examples of 100 different crops. Data are arranged alphabetically by food crop and geographical origin. The sampling date, nuclide measured, mean radioactivity, range of radioactivities, sample basis, number of samples analyzed, and bibliographic citation are given for each entry, when available. Analyses were reported most frequently for /sup 137/Cs, /sup 40/K, /sup 90/Sr, /sup 226/Ra, /sup 228/Ra, plutonium, uranium, total alpha, and total beta, but a few authors also reported data for /sup 241/Am, /sup 7/Be, /sup 60/Co, /sup 55/Fe, /sup 3/H, /sup 131/I, /sup 54/Mn, /sup 95/Nb, /sup 210/Pb, /sup 210/Po, /sup 106/Ru, /sup 125/Sb, /sup 228/Th, /sup 232/Th, and /sup 95/Zr. Based on the reported data it appears that radioactivity from alpha emitters in food crops is usually low, on the order of 0.1 Bq.g/sup -1/ (wet weight) or less. Reported values of beta radiation in a given crop generally appear to be several orders of magnitude greater than those of alpha emitters. The most striking aspect of the data is the great range of radioactivity reported for a given nuclide in similar food crops with different geographical origins.

Drury, J.S.; Baldauf, M.F.; Daniel, E.W.; Fore, C.S.; Uziel, M.S.

1983-05-01T23:59:59.000Z

374

Transportation Baseline Schedule  

SciTech Connect (OSTI)

The 1999 National Transportation Program - Transportation Baseline Report presents data that form a baseline to enable analysis and planning for future Department of Energy (DOE) Environmental Management (EM) waste/material transportation. The companion 1999 Transportation Barriers Analysis analyzes the data and identifies existing and potential problems that may prevent or delay transportation activities based on the data presented. The 1999 Transportation Baseline Schedule (this report) uses the same data to provide an overview of the transportation activities of DOE EM waste/materials. This report can be used to identify areas where stakeholder interface is needed, and to communicate to stakeholders the quantity/schedule of shipments going through their area. Potential bottlenecks in the transportation system can be identified; the number of packages needed, and the capacity needed at receiving facilities can be planned. This report offers a visualization of baseline DOE EM transportation activities for the 11 major sites and the Geologic Repository Disposal site (GRD).

Fawcett, Ricky Lee; John, Mark Earl

2000-01-01T23:59:59.000Z

375

An overview of the Radioisotope Thermoelectric Generator Transportation System Program  

SciTech Connect (OSTI)

Radioisotope Thermoelectric Generators (RTG) convert the heat generated by radioactive decay to electricity using thermocouples. RTGs have a long operating life, are reasonably lightweight, and require little or no maintenance once assembled and tested. These factors make RTGs particularly attractive for use in spacecraft. However, because RTGs contain significant quantities of radioactive materials, normally plutonium-238 and its decay products, they must be transported in packages built in accordance with Title 10, Code of Federal Regulations, Part 71. The U.S. Department of Energy assigned the Radioisotope Thermoelectric Generator Transportation System (RTGTS) Program to Westinghouse Hanford Company in 1988 to develop a system meeting the regulatory requirements. The program objective was to develop a transportation system that would fully comply with 10 CFR 71 while protecting RTGs from adverse environmental conditions during normal conditions of transport (e.g., shock and heat). The RTGTS is scheduled for completion in December 1996 and will be available to support the National Aeronautics and Space Administration{close_quote}s Cassini mission to Saturn in October 1997. This paper provides an overview of the RTGTS and discusses the hardware being produced. Additionally, various program management innovations mandated by recent major changes in the U.S. Department of Energy structure and resources will be outlined. {copyright} {ital 1996 American Institute of Physics.}

McCoy, J.C.; Becker, D.L. [Westinghouse Hanford Company, P.O. Box 1970, Richland, Washington 99352 (United States)

1996-03-01T23:59:59.000Z

376

Cosmic Ray Interactions in Shielding Materials  

SciTech Connect (OSTI)

This document provides a detailed study of materials used to shield against the hadronic particles from cosmic ray showers at Earths surface. This work was motivated by the need for a shield that minimizes activation of the enriched germanium during transport for the MAJORANA collaboration. The materials suitable for cosmic-ray shield design are materials such as lead and iron that will stop the primary protons, and materials like polyethylene, borated polyethylene, concrete and water that will stop the induced neutrons. The interaction of the different cosmic-ray components at ground level (protons, neutrons, muons) with their wide energy range (from kilo-electron volts to giga-electron volts) is a complex calculation. Monte Carlo calculations have proven to be a suitable tool for the simulation of nucleon transport, including hadron interactions and radioactive isotope production. The industry standard Monte Carlo simulation tool, Geant4, was used for this study. The result of this study is the assertion that activation at Earths surface is a result of the neutronic and protonic components of the cosmic-ray shower. The best material to shield against these cosmic-ray components is iron, which has the best combination of primary shielding and minimal secondary neutron production.

Aguayo Navarrete, Estanislao; Kouzes, Richard T.; Ankney, Austin S.; Orrell, John L.; Berguson, Timothy J.; Troy, Meredith D.

2011-09-08T23:59:59.000Z

377

Quality assurance in the transport of UF{sub 6}  

SciTech Connect (OSTI)

Edlow International`s primary business is the international transportation of radioactive materials. Therefore, Edlow has the responsibility to ensure that shipments are performed in compliance with regulatory requirements. In this regard, Edlow maintains a Quality Assurance (QA) Program. A major part of this Program is the establishment and use of QA Procedures. This paper addresses QA procedural requirements and how they are applied to a routine international shipment of low enriched UF{sub 6}. Only the major requirements for scheduling shipments will be addressed.

Ravenscroft, N.L. [Edlow International Company, Washington, DC (United States)

1991-12-31T23:59:59.000Z

378

Radioactive mixed waste disposal  

SciTech Connect (OSTI)

Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste.

Jasen, W.G.; Erpenbeck, E.G.

1993-02-01T23:59:59.000Z

379

Radioactive Waste Management Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07. Admin Chg 2, dated 6-8-11, cancels DOE M 435.1-1 Chg 1.

1999-07-09T23:59:59.000Z

380

Management of Transuranic Contaminated Material  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish guidelines for the generation, treatment, packaging, storage, transportation, and disposal of transuranic (TRU) contaminated material.

1982-09-30T23:59:59.000Z

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


381

Radioactive Waste Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The objective of this Order is to ensure that all Department of Energy (DOE) radioactive waste is managed in a manner that is protective of worker and public health and safety and the environment. Cancels DOE O 5820.2A

1999-07-09T23:59:59.000Z

382

Sealed Radioactive Source Accountability  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish Department of Energy (DOE) interim policy and to provide guidance for sealed radioactive source accountability. The directive does not cancel any directives. Extended by DOE N 5400.10 to 12-24-93 & Extended by DOE N 5400.12 to 12-24-94.

1991-12-24T23:59:59.000Z

383

Radioactive Waste Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The objective of this Order is to ensure that all Department of Energy (DOE) radioactive waste is managed in a manner that is protective of worker and public health and safety and the environment. Cancels DOE O 5820.2A. Chg 1 dated 8-28-01. Certified 1-9-07.

1999-07-09T23:59:59.000Z

384

Sealed Radioactive Source Accountability  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Notice extends DOE N 5400.9, Sealed Radioactive Source Accountability, of 12-24-91, until 12-24-95, unless sooner superseded or rescinded. The contents of DOE N 5400.9 will be updated and incorporated in the revised DOE O 5480.11, Radiation Protection for Occupational Workers.

1994-12-22T23:59:59.000Z

385

Radioactive Contamination of Danish Territory  

E-Print Network [OSTI]

Risø-R-462 Radioactive Contamination of Danish Territory after Core-melt Accidents at the Barsebäck;#12;RIS0-R-462 RADIOACTIVE CONTAMINATION OF DANISH TERRITORY AFTER CORE-MELT ACCIDENTS AT THE BARSEBACK. An assessment is made of the radioactive contamination of Danish territory in the event of a core-melt accident

386

Radioactive Contamination of Danish Territory  

E-Print Network [OSTI]

» & Risø-R-462 Radioactive Contamination of Danish Territory after Core-melt Accidents 1982 Risø National Laboratory, DK-4000 Roskilde, Denmark #12;RIS?-R-462 RADIOACTIVE CONTAMINATION. Heikel Vinther, L. Warming and A. Aarkrog Abstract. An assessment is made of the radioactive

387

Low-level radioactive waste regulation: Science, politics and fear  

SciTech Connect (OSTI)

An inevitable consequence of the use of radioactive materials is the generation of radioactive wastes and the public policy debate over how they will be managed. In 1980, Congress shifted responsibility for the disposal of low-level radioactive wastes from the federal government to the states. This act represented a sharp departure from more than 30 years of virtually absolute federal control over radioactive materials. Though this plan had the enthusiastic support of the states in 1980, it now appears to have been at best a chimera. Radioactive waste management has become an increasingly complicated and controversial issue for society in recent years. This book discusses only low-level wastes, however, because Congress decided for political reasons to treat them differently than high-level wastes. The book is based in part on three symposia sponsored by the division of Chemistry and the Law of the American Chemical Society. Each chapter is derived in full or in part from presentations made at these meetings, and includes: (1) Low-level radioactive wastes in the nuclear power industry; (2) Low-level radiation cancer risk assessment and government regulation to protect public health; and (3) Low-level radioactive waste: can new disposal sites be found.

Burns, M.E. (ed.)

1988-01-01T23:59:59.000Z

388

Hazardous Material Security (Maryland)  

Broader source: Energy.gov [DOE]

All facilities processing, storing, managing, or transporting hazardous materials must be evaluated every five years for security issues. A report must be submitted to the Department of the...

389

Fifty years of federal radioactive waste management: Policies and practices  

SciTech Connect (OSTI)

This report provides a chronological history of policies and practices relating to the management of radioactive waste for which the US Atomic Energy Commission and its successor agencies, the Energy Research and Development Administration and the Department of Energy, have been responsible since the enactment of the Atomic Energy Act in 1946. The defense programs and capabilities that the Commission inherited in 1947 are briefly described. The Commission undertook a dramatic expansion nationwide of its physical facilities and program capabilities over the five years beginning in 1947. While the nuclear defense activities continued to be a major portion of the Atomic Energy Commission`s program, there was added in 1955 the Atoms for Peace program that spawned a multiplicity of peaceful use applications for nuclear energy, e.g., the civilian nuclear power program and its associated nuclear fuel cycle; a variety of industrial applications; and medical research, diagnostic, and therapeutic applications. All of these nuclear programs and activities generated large volumes of radioactive waste that had to be managed in a manner that was safe for the workers, the public, and the environment. The management of these materials, which varied significantly in their physical, chemical, and radiological characteristics, involved to varying degrees the following phases of the waste management system life cycle: waste characterization, storage, treatment, and disposal, with appropriate transportation linkages. One of the benefits of reviewing the history of the waste management program policies and practices if the opportunity it provides for identifying the lessons learned over the years. Examples are summarized at the end of the report and are listed in no particular order of importance.

Bradley, R.G.

1997-04-01T23:59:59.000Z

390

Material transport method and apparatus  

DOE Patents [OSTI]

An electrospray apparatus uses a microchannel formed in a microchip. Fluid is pumped through the channel to an outlet orifice using either hydraulic or electrokinetic means. An electrospray is generated by establishing a sufficient potential difference between the fluid at the outlet orifice and a target electrode spaced from the outlet orifice. Electrokinetic pumping is also utilized to provide additional benefits to microchip devices.

Ramsey, J. Michael (Knoxville, TN); Ramsey, Roswitha S. (Knoxville, TN)

2001-01-01T23:59:59.000Z

391

Material transport method and apparatus  

DOE Patents [OSTI]

An electrospray apparatus uses a microchannel formed in a microchip. Fluid is pumped through the channel to an outlet orifice using either hydraulic or electrokinetic means. An electrospray is generated by establishing a sufficient potential difference between the fluid at the outlet orifice and a target electrode spaced from the outlet orifice. Electrokinetic pumping is also utilized to provide additional benefits to microchip devices.

Ramsey, J. Michael (Knoxville, TN); Ramsey, Roswitha S. (Knoxville, TN)

2000-01-01T23:59:59.000Z

392

Incineration of radioactive waste in shaft furnace  

SciTech Connect (OSTI)

Development of nuclear technology depends greatly on solving the problems, concerning the treatment of waste, arising from power station activity. A great deal of waste will arise in the process of atomic power station decommissioning. One of the methods for radioactive waste treatment is a method of combustion. The volume reduction factor of the final product is 60--100. In the process of combustion, the organic radwaste is transported into gaseous wastes and ash. For better environmental protection, one must achieve the minimal release of nuclides from partially burned products in the gaseous phase, and maximize the waste in ash form suitable for final disposal.

Dmitriev, S.A.; Knyasev, I.A.; Kobelev, A.P. [Moscow SIA Radon, Sergiev Posad (Russian Federation). Dept. of Engineering Supply

1993-12-31T23:59:59.000Z

393

Draft Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada  

SciTech Connect (OSTI)

The Proposed Action addressed in this EIS is to construct, operate and monitor, and eventually close a geologic repository at Yucca Mountain in southern Nevada for the disposal of spent nuclear fuel and high-level radioactive waste currently in storage at 72 commercial and 5 DOE sites across the United States. The EIS evaluates (1) projected impacts on the Yucca Mountain environment of the construction, operation and monitoring, and eventual closure of the geologic repository; (2) the potential long-term impacts of repository disposal of spent nuclear fuel and high-level radioactive waste; (3) the potential impacts of transporting these materials nationally and in the State of Nevada; and (4) the potential impacts of not proceeding with the Proposed Action.

N /A

1999-08-13T23:59:59.000Z

394

THE USE OF POLYMERS IN RADIOACTIVE WASTE PROCESSING SYSTEMS  

SciTech Connect (OSTI)

The Savannah River Site (SRS), one of the largest U.S. Department of Energy (DOE) sites, has operated since the early 1950s. The early mission of the site was to produce critical nuclear materials for national defense. Many facilities have been constructed at the SRS over the years to process, stabilize and/or store radioactive waste and related materials. The primary materials of construction used in such facilities are inorganic (metals, concrete), but polymeric materials are inevitably used in various applications. The effects of aging, radiation, chemicals, heat and other environmental variables must therefore be understood to maximize service life of polymeric components. In particular, the potential for dose rate effects and synergistic effects on polymeric materials in multivariable environments can complicate compatibility reviews and life predictions. The selection and performance of polymeric materials in radioactive waste processing systems at the SRS are discussed.

Skidmore, E.; Fondeur, F.

2013-04-15T23:59:59.000Z

395

Membrane Treatment of Liquid Salt Bearing Radioactive Wastes  

SciTech Connect (OSTI)

The main fields of introduction and application of membrane methods for preliminary treatment and processing salt liquid radioactive waste (SLRW) can be nuclear power stations (NPP) and enterprises on atomic submarines (AS) utilization. Unlike the earlier developed technology for the liquid salt bearing radioactive waste decontamination and concentrating this report presents the new enhanced membrane technology for the liquid salt bearing radioactive waste processing based on the state-of-the-art membrane unit design, namely, the filtering units equipped with the metal-ceramic membranes of ''TruMem'' brand, as well as the electrodialysis and electroosmosis concentrators. Application of the above mentioned units in conjunction with the pulse pole changer will allow the marked increase of the radioactive waste concentrating factor and the significant reduction of the waste volume intended for conversion into monolith and disposal. Besides, the application of the electrodialysis units loaded with an ion exchange material at the end polishing stage of the radioactive waste decontamination process will allow the reagent-free radioactive waste treatment that meets the standards set for the release of the decontaminated liquid radioactive waste effluents into the natural reservoirs of fish-farming value.

Dmitriev, S. A.; Adamovich, D. V.; Demkin, V. I.; Timofeev, E. M.

2003-02-25T23:59:59.000Z

396

Solar Powered Radioactive Air Monitoring Stations  

SciTech Connect (OSTI)

Environmental monitoring of ambient air for radioactive material is required as stipulated in the PNNL Site radioactive air license. Sampling ambient air at identified preferred locations could not be initially accomplished because utilities were not readily available. Therefore, solar powered environmental monitoring systems were considered as a possible option. PNNL purchased two 24-V DC solar powered environmental monitoring systems which consisted of solar panels, battery banks, and sampling units. During an approximate four month performance evaluation period, the solar stations operated satisfactorily at an on-site test location. They were subsequently relocated to their preferred locations in June 2012 where they continue to function adequately under the conditions found in Richland, Washington.

Barnett, J. M.; Bisping, Lynn E.; Gervais, Todd L.

2013-10-30T23:59:59.000Z

397

Radioactive waste management strategy in the Republic of Croatia  

SciTech Connect (OSTI)

Environmental preservation and human health protection have been proclaimed by the Croatian Government as priority actions. Hence, all organized actions toward this aim are expected to be supported by the State. Radioactive waste management plays a significant role in controlling materials that could harm the environment. Strategy in handling radioactive wastes is a prerequisite for well-organized radwaste management. It should be applied to all radioactive wastes that have already been produced in various industries, medical institutions, and scientific laboratories. Additionally, radioactive wastes that are being generated in the Krsko NPP must not be neglected, as well as possible future nuclear program needs in Croatia. For all considered actions, world-wide experiences and safety requirements should be strictly respected.

Subasic, D.; Saler, A.; Skanata, D. [Javno poduzece za zbrinjavanje radioaktivnog otpada, Zagreb (Croatia)

1993-12-31T23:59:59.000Z

398

Induced Radioactivity and Waste Classification of Reactor Zone Components of the Chernobyl Nuclear Power Plant Unit 1 After Final Shutdown  

SciTech Connect (OSTI)

The dismantlement of the reactor core materials and surrounding structural components is a major technical concern for those planning closure and decontamination and decommissioning of the Chernobyl Nuclear Power Plant (NPP). Specific issues include when and how dismantlement should be accomplished and what the radwaste classification of the dismantled system would be at the time it is disassembled. Whereas radiation levels and residual radiological characteristics of the majority of the plant systems are directly measured using standard radiation survey and radiochemical analysis techniques, actual measurements of reactor zone materials are not practical due to high radiation levels and inaccessibility. For these reasons, neutron transport analysis was used to estimate induced radioactivity and radiation levels in the Chernobyl NPP Unit 1 reactor core materials and structures.Analysis results suggest that the optimum period of safe storage is 90 to 100 yr for the Unit 1 reactor. For all of the reactor components except the fuel channel pipes (or pressure tubes), this will provide sufficient decay time to allow unlimited worker access during dismantlement, minimize the need for expensive remote dismantlement, and allow for the dismantled reactor components to be classified as low- or medium-level radioactive waste. The fuel channel pipes will remain classified as high-activity waste requiring remote dismantlement for hundreds of years due to the high concentration of induced {sup 63}Ni in the Zircaloy pipes.

Bylkin, Boris K. [Russian Research Center 'Kurchatov Institute' (Russian Federation); Davydova, Galina B. [Russian Research Center 'Kurchatov Institute' (Russian Federation); Zverkov, Yuri A. [Russian Research Center 'Kurchatov Institute' (Russian Federation); Krayushkin, Alexander V. [Russian Research Center 'Kurchatov Institute' (Russian Federation); Neretin, Yuri A. [Chernobyl Nuclear Power Plant (Ukraine); Nosovsky, Anatoly V. [Slavutych Division of the International Chernobyl Center (Ukraine); Seyda, Valery A. [Chernobyl Nuclear Power Plant (Ukraine); Short, Steven M. [Pacific Northwest National Laboratory (United States)

2001-10-15T23:59:59.000Z

399

RADIONUCLIDE TRANSPORT MODELS UNDER AMBIENT CONDITIONS  

SciTech Connect (OSTI)

The purpose of this model report is to document the unsaturated zone (UZ) radionuclide transport model, which evaluates, by means of three-dimensional numerical models, the transport of radioactive solutes and colloids in the UZ, under ambient conditions, from the repository horizon to the water table at Yucca Mountain, Nevada.

S. Magnuson

2004-11-01T23:59:59.000Z

400

Nevada potential repository preliminary transportation strategy: Study 1  

SciTech Connect (OSTI)

Limited feasible options exist when considering the shipment of spent nuclear fuel and high-level radioactive waste. These options are rail or truck; because of the weight associated with transportation casks (68.0 to 113.4 tonnes/75 to 125 tons), heavy-haul trucks are also considered. Yucca Mountain currently lacks rail service or an existing right-of-way for rail; it also lacks a dedicated highway suitable for heavy-haul trucks. Approximately 11,230 shipments by rail are planned from waste producer sites to Nevada, with an additional 1,041 shipments by legal-weight truck from four reactor sites not capable of upgrading for rail shipment. This study identifies the reasonable alternatives for waste transport to the potential repository site, describes the evaluation process performed to identify those alternatives, and discusses the reasons for elimination of transportation routes deemed to be not reasonable. The study concluded that heavy haul truck transportation is feasible-cost is very favorable when compared to rail-but route restrictions must be further evaluated. In addition to restrictions due to seasonal weather conditions, specific routes have additional restrictions, including no travel on holidays or weekends, and travel during daylight hours only. Further restrictions will be imposed by the U.S. Department of Transportation based on routing of radioactive materials by highway. Operation and maintenance costs for heavy-haul over a 24-year period, based on preliminary information, were calculated on an estimated operational cost of $15,000 per trip, with an estimated 468 trips per year average (11,230 total trips), for an estimated cost of $171 million to $173 million, depending on the route used. Because the initial costs and the total system life cycle costs of heavy-haul are approximately 50 percent lower than the lowest rail cost, this option will continue to be evaluated.

NONE

1995-04-01T23:59:59.000Z

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


401

RSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 RADIOACTIVE WASTE DISPOSAL  

E-Print Network [OSTI]

RSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 CHAPTER 7 RADIOACTIVE WASTE DISPOSAL PAGE I. Radioactive Waste Disposal ............................................................................................ 7-2 II. Radiation Control Technique #2 Instructions for Preparation of Radioactive Waste

Slatton, Clint

402

__________________________________ Environment, Health, & Safety ________________________________ Training Program  

E-Print Network [OSTI]

commercial drivers license endorsement to transport radioactive or hazardous waste. Course Objectives: After ________________________________ Training Program EHS0476~ Radioactive Materials Driver Training Subject Category: Radioactive Materials function specific drivers training for LBNL personnel who transport radioactive materials, via government

Eisen, Michael

403

Standard practice for prediction of the long-term behavior of materials, including waste forms, used in engineered barrier systems (EBS) for geological disposal of high-level radioactive waste  

E-Print Network [OSTI]

1.1 This practice describes test methods and data analyses used to develop models for the prediction of the long-term behavior of materials, such as engineered barrier system (EBS) materials and waste forms, used in the geologic disposal of spent nuclear fuel (SNF) and other high-level nuclear waste in a geologic repository. The alteration behavior of waste form and EBS materials is important because it affects the retention of radionuclides by the disposal system. The waste form and EBS materials provide a barrier to release either directly (as in the case of waste forms in which the radionuclides are initially immobilized), or indirectly (as in the case of containment materials that restrict the ingress of groundwater or the egress of radionuclides that are released as the waste forms and EBS materials degrade). 1.1.1 Steps involved in making such predictions include problem definition, testing, modeling, and model confirmation. 1.1.2 The predictions are based on models derived from theoretical considerat...

American Society for Testing and Materials. Philadelphia

2007-01-01T23:59:59.000Z

404

Handling Radioactive Waste from the Proton Accelerator Facility at the Paul Scherrer Institut (PSI) - Always Surprising? - 13320  

SciTech Connect (OSTI)

The Paul Scherrer Institut (PSI) is the largest national research centre in Switzerland. Its multidisciplinary research is dedicated to a wide field in natural science and technology as well as particle physics. In this context, PSI is operating, amongst others, a large proton accelerator facility since more than 30 years. In two cyclotrons, protons are accelerated to high speeds and then guided along roughly 100 m of beam line to three different target stations to produce secondary particles like mesons and neutrons for experiments and a separately beam line for UCN. The protons induce spallation processes in the target materials, and also at other beam loss points along the way, with emission of protons, neutrons, hydrogen, tritium, helium, heavier fragments and fission processes. In particular the produced neutrons, due to their large penetration depth, will then interact also with the surrounding materials. These interactions of radiation with matter lead to activation and partly to contamination of machine components and the surrounding infrastructures. Maintenance, operation and decommissioning of installations generate inevitably substantial amounts of radioactive operational and dismantling waste like targets, magnets, collimators, shielding (concrete, steel) and of course secondary waste. To achieve an optimal waste management strategy for interim storage or final disposal, radioactive waste has to be characterized, sorted and treated. This strategy is based on radiation protection demands, raw waste properties (size, material, etc.), and requirements to reduce the volume of waste, mainly for legal and economical reasons. In addition, the radiological limitations for transportation of the waste packages to a future disposal site have to be taken into account, as well as special regulatory demands. The characterization is a task of the waste producer. The conditioning processes and quality checks for radioactive waste packages are part of an accredited waste management process of PSI, especially of the Section Dismantling and Waste Management. Strictly proven and accepted methods needed to be developed and enhanced for safe treatment, transport, conditioning and storage. But in the field of waste from research activities, individual and new solutions have to be found in an increasingly growing administrative environment. Furthermore, a wide variety of components, with a really large inventory of radioactive nuclides, has to be handled. And there are always surprising challenges concerning the unusual materials or the nuclide inventory. In case of the operational and dismantling radioactive accelerator waste, the existing conditioning methods are in the process of a continuous enhancement - technically and administratively. The existing authorized specifications of conditioning processes have to be extended to optimize and fully describe the treatment of the inevitably occurring radioactive waste from the accelerator facility. Additional challenges are the changes with time concerning the legal and regulatory requirements - or do we have to consider it as business as usual? This paper gives an overview of the current practices in radioactive waste management and decommissioning of the existing operational accelerator waste. (authors)

Mueth, Joachim [Paul Scherrer Institute, CH-5232 Villigen (Switzerland)] [Paul Scherrer Institute, CH-5232 Villigen (Switzerland)

2013-07-01T23:59:59.000Z

405

NREL: Transportation Research Home Page  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

to heavy-duty freight trucks. Female researcher holding coin cell battery. NREL's transportation research spans from the materials to the systems level. Fuel cell electric sports...

406

A compendium of the radioisotope thermoelectric generator transportation system and recent programmatic changes  

SciTech Connect (OSTI)

Because RTGs contain significant quantities of radioactive materials, usually plutonium-238 and its decay products, they must be transported in packages built in accordance with 10 CFR 71 (1994). To meet these regulatory requirements, US DOE commissioned Westinghouse Hanford Co. in 1988 to develop a Radioisotope Thermoelectric Generator Transportation System (RTGTS) that would fully comply while protecting RTGs from adverse environmental conditions during normal transport conditions (eg, mainly shock and heat). RTGTS is scheduled for completion Dec. 1996 and will be available to support NASA`s Cassini mission to Saturn in Oct. 1997. This paper provides an overview of the RTGTS project, discusses the hardware being produced, and summarizes various programmatic and management innovations required by recent changes at DOE.

Becker, D.L.; McCoy, J.C.

1996-03-01T23:59:59.000Z

407

DEVELOPMENT OF THE HS99 AIR TRANSPORT TYPE A FISSILE PACKAGE  

SciTech Connect (OSTI)

An air-transport Type A Fissile radioactive shipping package for the transport of special form uranium sources has been developed by the Savannah River National Laboratory (SRNL) for the Department of Homeland Security. The Package model number is HS99 for Homeland Security Model 99. This paper presents the major design features of the HS99 and highlights engineered materials necessary for meeting the design requirements for this light-weight Type AF packaging. A discussion is provided demonstrating how the HS99 complies with the regulatory safety requirements of the Nuclear Regulatory Commission. The paper summarizes the results of structural testing to specified in 10 CFR 71 for Normal Conditions of Transport and Hypothetical Accident Conditions events. Planned and proposed future missions for this packaging are also addressed.

Blanton, P.; Eberl, K.

2012-07-10T23:59:59.000Z

408

CHERNOBYL DATA BASE ENVIRONMENTAL RADIOACTIVITY  

E-Print Network [OSTI]

MAY 1990 THE NORDIC CHERNOBYL DATA BASE ENVIRONMENTAL RADIOACTIVITY MEASUREMENTS Nordic liaison CHERNOBYL DATA BASE ENVIRONMENTAL RADIOACTIVITY MEASUREMENTS Final Report of the NKA Project AKT 242 Edited the members of the working group. Graphic Systems AB, Malmo 1990 #12;111 ABSTRACT. The NORDIC CHERNOBYL DATA

409

Properties of Natural Radiation and Radioactivity  

SciTech Connect (OSTI)

Ubiquitous natural sources of radiation and radioactive material (naturally occurring radioactive material, NORM) have exposed humans throughout history. To these natural sources have been added technologically-enhanced naturally occurring radioactive material (TENORM) sources and human-made (anthropogenic) sources. This chapter describes the ubiquitous radiation sources that we call background, including primordial radionuclides such as 40K, 87Rb, the 232Th series, the 238U series, and the 235U series; cosmogenic radionuclides such as 3H and 14C; anthropogenic radionuclides such as 3H, 14C, 137Cs, 90Sr, and 129I; radiation from space; and radiation from technologically-enhanced concentrations of natural radionuclides, particularly the short-lived decay products of 222Rn ("radon") and 220Rn ("thoron") in indoor air. These sources produce radiation doses to people principally via external irradiation or internal irradiation following intakes by inhalation or ingestion. The effective doses from each are given, with a total of 3.11 mSv y-1 (311 mrem y-1) to the average US resident. Over 2.5 million US residents receive over 20 mSv y-1 (2 rem y-1), primarily due to indoor radon. Exposure to radiation from NORM and TENORM produces the largest fraction of ubiquitous background exposure to US residents, on the order of 2.78 mSv (278 mrem) or about 89%. This is roughly 45% of the average annual effective dose to a US resident of 6.2 mSv y-1 (620 mrem y-1) that includes medical (48%), consumer products and air travel (2%), and occupational and industrial (0.1%). Much of this chapter is based on National Council on Radiation Protection and Measurements (NCRP) Report No. 160, "Ionizing Radiation Exposure of the Population of the United States," for which the author chaired the subcommittee that wrote Chapter 3 on "Ubiquitous Background Radiation."

Strom, Daniel J.

2009-07-13T23:59:59.000Z

410

Packaging and Transportation Safety  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish safety requirements for the proper packaging and transportation of Department of Energy (DOE)/National Nuclear Security Administration (NNSA) offsite shipments and onsite transfers of hazardous materials and for modal transport. Cancels DOE O 460.1A. Canceled by DOE O 460.1C.

2003-04-04T23:59:59.000Z

411

MSE 410: Materials Foundations for Energy Applications MSE 810: Materials for Energy Applications  

E-Print Network [OSTI]

; materials for future wind energy needs; thermoelectric materials for solid state energy conversion II: thermoelectric materials Introduction; the design of thermoelectric materials Morelli Jan 31, Feb 2 Module II: thermoelectric materials Thermal and electrical transport properties; model systems

412

Enclosure 3 DOE Response to EPA Question Regarding "High-Level Liquid Radioactive Waste"  

E-Print Network [OSTI]

to date, which is from the definitions in the Nuclear Waste Policy Act: The term "high-level radioactive waste" means-- (A) the highly radioactive material resulting from the reprocessing of spent nuclear fuel of waste streams as from the applicable definition of HLW in the Nuclear Waste Policy Act. 5/11/20051 #12

413

Bonded carbon or ceramic fiber composite filter vent for radioactive waste  

DOE Patents [OSTI]

Carbon bonded carbon fiber composites as well as ceramic or carbon bonded ceramic fiber composites are very useful as filters which can separate particulate matter from gas streams entraining the same. These filters have particular application to the filtering of radioactive particles, e.g., they can act as vents for containers of radioactive waste material.

Brassell, Gilbert W. (13237 W. 8th Ave., Golden, CO 80401); Brugger, Ronald P. (Lafayette, CO)

1985-02-19T23:59:59.000Z

414

CHAPTER 4: CONCEPTS OF RADIOACTIVITY 1998 SITE ENVIRONMENTAL REPORT4-1  

E-Print Network [OSTI]

a range in air of only an inch or so. Naturally occurring radioactive elements such as radon emit alpha by materials such as aluminum foil. They have a range in air of a few inches. Naturally occurring radioactive-rays are essen- tially a form of gamma radiation. Figure 4-1. Typical Annual Radiation Doses from Natural and Man

415

Radioactivity in Food and the Environment, 2009  

E-Print Network [OSTI]

................................................................................................................22 1.2.1 Radioactive waste disposal from nuclear sites ............................................................................................................................22 1.2 Disposals of radioactive waste ..............................................................................................................27 1.2.5 Solid radioactive waste disposal at sea

416

Radioactivity in Food and the Environment, 2006  

E-Print Network [OSTI]

................................................................................................................22 1.2.1 Radioactive waste disposal from nuclear sites .............................................................................................................................22 1.2 Disposals of radioactive waste.......................................................................................................25 1.2.5 Solid radioactive waste disposal at sea

417

A method for determining the spent-fuel contribution to transport cask containment requirements  

SciTech Connect (OSTI)

This report examines containment requirements for spent-fuel transport containers that are transported under normal and hypothetical accident conditions. A methodology is described that estimates the probability of rod failure and the quantity of radioactive material released from breached rods. This methodology characterizes the dynamic environment of the cask and its contents and deterministically models the peak stresses that are induced in spent-fuel cladding by the mechanical and thermal dynamic environments. The peak stresses are evaluated in relation to probabilistic failure criteria for generated or preexisting ductile tearing and material fractures at cracks partially through the wall in fuel rods. Activity concentrations in the cask cavity are predicted from estimates of the fraction of gases, volatiles, and fuel fines that are released when the rod cladding is breached. Containment requirements based on the source term are calculated in terms of maximum permissible volumetric leak rates from the cask. Calculations are included for representative cask designs.

Sanders, T.L.; Seager, K.D. [Sandia National Labs., Albuquerque, NM (United States); Rashid, Y.R.; Barrett, P.R. [ANATECH Research Corp., La Jolla, CA (United States); Malinauskas, A.P. [Oak Ridge National Lab., TN (United States); Einziger, R.E. [Pacific Northwest Lab., Richland, WA (United States); Jordan, H. [EG and G Rocky Flats, Inc., Golden, CO (United States). Rocky Flats Plant; Duffey, T.A.; Sutherland, S.H. [APTEK, Inc., Colorado Springs, CO (United States); Reardon, P.C. [GRAM, Inc., Albuquerque, NM (United States)

1992-11-01T23:59:59.000Z

418

Particle beam generator using a radioactive source  

DOE Patents [OSTI]

The apparatus of the present invention selects from particles emitted by a radioactive source those particles having momentum within a desired range and focuses the selected particles in a beam having at least one narrow cross-dimension, and at the same time attenuates potentially disruptive gamma rays and low energy particles. Two major components of the present invention are an achromatic bending and focusing system, which includes sector magnets and quadrupole, and a quadrupole doublet final focus system. Permanent magnets utilized in the apparatus are constructed of a ceramic (ferrite) material which is inexpensive and easily machined.

Underwood, David G. (Naperville, IL)

1993-01-01T23:59:59.000Z

419

Particle beam generator using a radioactive source  

DOE Patents [OSTI]

The apparatus of the present invention selects from particles emitted by a radioactive source those particles having momentum within a desired range and focuses the selected particles in a beam having at least one narrow cross-dimension, and at the same time attenuates potentially disruptive gamma rays and low energy particles. Two major components of the present invention are an achromatic bending and focusing system, which includes sector magnets and quadrupole, and a quadrupole doublet final focus system. Permanent magnets utilized in the apparatus are constructed of a ceramic (ferrite) material which is inexpensive and easily machined.

Underwood, D.G.

1993-03-30T23:59:59.000Z

420

RISKIND: An enhanced computer code for National Environmental Policy Act transportation consequence analysis  

SciTech Connect (OSTI)

The RISKIND computer program was developed for the analysis of radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel (SNF) or other radioactive materials. The code is intended to provide scenario-specific analyses when evaluating alternatives for environmental assessment activities, including those for major federal actions involving radioactive material transport as required by the National Environmental Policy Act (NEPA). As such, rigorous procedures have been implemented to enhance the code`s credibility and strenuous efforts have been made to enhance ease of use of the code. To increase the code`s reliability and credibility, a new version of RISKIND was produced under a quality assurance plan that covered code development and testing, and a peer review process was conducted. During development of the new version, the flexibility and ease of use of RISKIND were enhanced through several major changes: (1) a Windows{sup {trademark}} point-and-click interface replaced the old DOS menu system, (2) the remaining model input parameters were added to the interface, (3) databases were updated, (4) the program output was revised, and (5) on-line help has been added. RISKIND has been well received by users and has been established as a key component in radiological transportation risk assessments through its acceptance by the U.S. Department of Energy community in recent environmental impact statements (EISs) and its continued use in the current preparation of several EISs.

Biwer, B.M.; LePoire, D.J.; Chen, S.Y.

1996-03-01T23:59:59.000Z

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


421

Over-the-road shock and vibration testing of the radioisotope thermoelectric generator transportation system  

SciTech Connect (OSTI)

Radioisotope Thermoelectric Generators (RTG) convert heat generated by radioactive decay into electricity through the use of thermocouples. The RTGs have a long operating life, are reasonably lightweight, and require little or no maintenance, which make them particularly attractive for use in spacecraft. However, because RTGs contain significant quantities of radioactive materials, normally plutonium-238 and its decay products, they must be transported in packages built in accordance with Title 10, Code of Federal Regulations, Part 71 (10 CFR 71). To meet these regulations, a RTG Transportation System (RTGTS) that fully complies with 10 CFR 71 has been developed, which protects RTGs from adverse environmental conditions during normal conditions of transport (e.g., shock, vibration, and heat). To ensure the protection of RTGs from shock and vibration loadings during transport, extensive over-the-road testing was conducted on the RTG`S to obtain real-time recordings of accelerations of the air-ride suspension system trailer floor, packaging, and support structure. This paper provides an overview of the RTG`S, a discussion of the shock and vibration testing, and a comparison of the test results to the specified shock response spectra and power spectral density acceleration criteria.

Becker, D.L.

1997-05-01T23:59:59.000Z

422

Effect of Saltstone Vault Roof Configuration on the Rate of Contaminant Transport  

SciTech Connect (OSTI)

At the Savannah River Site, low-level radioactive decontaminated salt solution is mixed with slag, flyash, and cement to form a grout-like material called ``Saltstone``. The Saltstone is poured into concrete vaults constructed at the Saltstone Disposal Facility (SDF). The impact of SDF on groundwater has been studied in a radiological performance assessment (PA). Sophisticated groundwater models were used to predict the groundwater flow and contaminant transport problems. The modeling effort was divided into two parts: the unsaturated-zone model and the saturated zone model. One of the major performance objectives is to show that the impacted groundwater will be in compliance with the Safe Drinking Water Act.

Hsu, R.H.; Yu, A.D.; Lam, Poh-Sang

1994-12-28T23:59:59.000Z

423

Information management and collection for US DOE's packaging and transportation needs in the 90's  

SciTech Connect (OSTI)

The Transportation Assessment and Integration (TRAIN) Project (US DOE, 1992) was established to provide a systematic approach to identify the problems and needs that will affect the capability of the United States Department of Energy (US DOE) to provide itself with cost-effective, efficient, and coordinated transportation services during the 1990s. Eight issue areas were identified to be included in the TRAIN Project, with one principal investigator assigned to each. The eight areas are as follows: (1) Packaging and Transportation Needs (PATN) in the 1990s; (2) Institutional and Outreach Programs; (3) Regulatory Impacts on Transportation Management; (4) Traffic and Packaging Operations; (5) Research and Development Requirements; (6) Training Support; (7) Emergency Preparedness Requirements; and (8) US DOE-EM 561 Roles and Responsibilities. This paper focuses on the results of the PATN activity of TRAIN. The objective of PATN is to prepare the US DOE, in general, and US DOE-EM 561 (Environmental Restoration and Waste Management (EM), Office of Technology Development, Transportation) in particular, respond to the transportation needs of program elements in the Department. One of the first tasks in evaluating these needs was to formulate the potential for transportation of radioactive materials in the next decade.

Wheeler, T. A.; Luna, Robert E.; McClure, J. D. [Sandia National Labs., Albuquerque, NM (United States); Quinn, Geoffrey [Wastren, Inc., Germantown, MD (United States)

1991-01-01T23:59:59.000Z

424

Summary of radioactive solid waste received in the 200 Areas during calendar year 1992  

SciTech Connect (OSTI)

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1991. This report does not include solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms, or backlog wastes. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, (WHC 1988), liquid waste data are not included in this document.

Anderson, J.D.; Hagel, D.L.

1992-05-01T23:59:59.000Z

425

Summary of radioactive solid waste received in the 200 Areas during calendar year 1994  

SciTech Connect (OSTI)

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive material that has been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1994. This report does not include backlog waste: solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria (WHC 1988), liquid waste data are not included in this document.

Anderson, J.D.; Hagel, D.L.

1995-08-01T23:59:59.000Z

426

Summary of radioactive solid waste received in the 200 Areas during calendar year 1993  

SciTech Connect (OSTI)

Westinghouse Hanford Company manages and operates the Hanford Site 200 Areas radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Areas radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1993. This report does not include backlog waste, solid radioactive waste in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, ``Hanford Site Solid Waste Acceptance Criteria,`` (WHC 1988), liquid waste data are not included in this document.

Anderson, J.D.; Hagel, D.L.

1994-09-01T23:59:59.000Z

427

Bagless transfer process and apparatus for radioactive waste confinement  

DOE Patents [OSTI]

A process and apparatus is provided for removing radioactive material from a glovebox, placing the material in a stainless steel storage vessel in communication with the glovebox, and sealing the vessel with a welded plug. The vessel is then severed along the weld, a lower half of the plug forming a closure for the vessel. The remaining welded plug half provides a seal for the remnant portion of the vessel and thereby maintains the sealed integrity of the glovebox.

Maxwell, David N. (Aiken, SC); Hones, Robert H. (Evans, GA); Rogers, M. Lane (Aiken, SC)

1998-01-01T23:59:59.000Z

428

Bagless transfer process and apparatus for radioactive waste confinement  

DOE Patents [OSTI]

A process and apparatus are provided for removing radioactive material from a glovebox, placing the material in a stainless steel storage vessel in communication with the glovebox, and sealing the vessel with a welded plug. The vessel is then severed along the weld, a lower half of the plug forming a closure for the vessel. The remaining welded plug half provides a seal for the remnant portion of the vessel and thereby maintains the sealed integrity of the glovebox. 7 figs.

Maxwell, D.N.; Hones, R.H.; Rogers, M.L.

1998-04-14T23:59:59.000Z

429

SIMPLIFIED PROCEDURE FOR CERTAIN USERS OF SEALED SOURCES, SHORT HALF-LIFE MATERIALS,  

E-Print Network [OSTI]

authority with a minimum of: (1) a certification that no residual radioactive contamination attributable, AND SMALL QUANTITIES A large number of users of radioactive materials may use a simplified procedure that qualify for simplified decommissioning procedures are those where radioactive materials have been used

430

Data and methods for the assessment of the risks associated with the maritime transport of radioactive materials: Results of the SeaRAM program studies. Volume 1 -- Main report  

SciTech Connect (OSTI)

This report describes ship accident event trees, ship collision and ship fire frequencies, representative ships and shipping practices, a model of ship penetration depths during ship collisions, a ship fire spread model, cask to environment release fractions during ship collisions and fires, and illustrative consequence calculations.

Sprung, J.L.; Bespalko, S.J.; Kanipe, F.L. [and others

1998-05-01T23:59:59.000Z

431

Low-level radioactive waste technology: a selected, annotated bibliography  

SciTech Connect (OSTI)

This annotated bibliography of 447 references contains scientific, technical, economic, and regulatory information relevant to low-level radioactive waste technology. The bibliography focuses on environmental transport, disposal site, and waste treatment studies. The publication covers both domestic and foreign literature for the period 1952 to 1979. Major chapters selected are Chemical and Physical Aspects; Container Design and Performance; Disposal Site; Environmental Transport; General Studies and Reviews; Geology, Hydrology and Site Resources; Regulatory and Economic Aspects; Transportation Technology; Waste Production; and Waste Treatment. Specialized data fields have been incorporated into the data file to improve the ease and accuracy of locating pertinent references. Specific radionuclides for which data are presented are listed in the Measured Radionuclides field, and specific parameters which affect the migration of these radionuclides are presented in the Measured Parameters field. In addition, each document referenced in this bibliography has been assigned a relevance number to facilitate sorting the documents according to their pertinence to low-level radioactive waste technology. The documents are rated 1, 2, 3, or 4, with 1 indicating direct applicability to low-level radioactive waste technology and 4 indicating that a considerable amount of interpretation is required for the information presented to be applied. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. Indexes are provide for (1) author(s), (2) keywords, (3) subject category, (4) title, (5) geographic location, (6) measured parameters, (7) measured radionuclides, and (8) publication description.

Fore, C.S.; Vaughan, N.D.; Hyder, L.K.

1980-10-01T23:59:59.000Z

432

Hanford Site Wide Transportation Safety Document [SEC 1 Thru 3  

SciTech Connect (OSTI)

This safety evaluation report (SER) documents the basis for the US Department of Energy (DOE), Richland Operations Office (RL) to approve the Hanford Sitewide Transportation Safety Document (TSD) for onsite Transportation and Packaging (T&P) at Hanford. Hanford contractors, on behalf of DOE-RL, prepared and submitted the Hanford Sitewide Transportation Safety Document, DOE/RL-2001-0036, Revision 0, (DOE/RL 2001), dated October 4, 2001, which is referred to throughout this report as the TSD. In the context of the TSD, Hanford onsite shipments are the activities of moving hazardous materials, substances, and wastes between DOE facilities and over roadways where public access is controlled or restricted and includes intra-area and inter-area movements. The TSD sets forth requirements and standards for onsite shipment of radioactive and hazardous materials and wastes within the confines of the Hanford Site on roadways where public access is restricted by signs, barricades, fences, or other means including road closures and moving convoys controlled by Hanford Site security forces.

MCCALL, D L

2002-06-01T23:59:59.000Z

433

Radioactive decay data tables  

SciTech Connect (OSTI)

The estimation of radiation dose to man from either external or internal exposure to radionuclides requires a knowledge of the energies and intensities of the atomic and nuclear radiations emitted during the radioactive decay process. The availability of evaluated decay data for the large number of radionuclides of interest is thus of fundamental importance for radiation dosimetry. This handbook contains a compilation of decay data for approximately 500 radionuclides. These data constitute an evaluated data file constructed for use in the radiological assessment activities of the Technology Assessments Section of the Health and Safety Research Division at Oak Ridge National Laboratory. The radionuclides selected for this handbook include those occurring naturally in the environment, those of potential importance in routine or accidental releases from the nuclear fuel cycle, those of current interest in nuclear medicine and fusion reactor technology, and some of those of interest to Committee 2 of the International Commission on Radiological Protection for the estimation of annual limits on intake via inhalation and ingestion for occupationally exposed individuals.

Kocher, D.C.

1981-01-01T23:59:59.000Z

434

Room air monitor for radioactive aerosols  

DOE Patents [OSTI]

A housing assembly for use with a room air monitor for simultaneous collection and counting of suspended particles includes a casing containing a combination detector-preamplifier system at one end, a filter system at the other end, and an air flow system consisting of an air inlet formed in the casing between the detector-preamplifier system and the filter system and an air passageway extending from the air inlet through the casing and out the end opposite the detector-preamplifier combination. The filter system collects suspended particles transported directly through the housing by means of the air flow system, and these particles are detected and examined for radioactivity by the detector-preamplifier combination. 2 figs.

Balmer, D.K.; Tyree, W.H.

1987-03-23T23:59:59.000Z

435

Standard guide for sampling radioactive tank waste  

E-Print Network [OSTI]

1.1 This guide addresses techniques used to obtain grab samples from tanks containing high-level radioactive waste created during the reprocessing of spent nuclear fuels. Guidance on selecting appropriate sampling devices for waste covered by the Resource Conservation and Recovery Act (RCRA) is also provided by the United States Environmental Protection Agency (EPA) (1). Vapor sampling of the head-space is not included in this guide because it does not significantly affect slurry retrieval, pipeline transport, plugging, or mixing. 1.2 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2011-01-01T23:59:59.000Z

436

Radioactive Waste Management Complex performance assessment: Draft  

SciTech Connect (OSTI)

A radiological performance assessment of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory was conducted to demonstrate compliance with appropriate radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the general public. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the general public via air, ground water, and food chain pathways. Projections of doses were made for both offsite receptors and individuals intruding onto the site after closure. In addition, uncertainty analyses were performed. Results of calculations made using nominal data indicate that the radiological doses will be below appropriate radiological criteria throughout operations and after closure of the facility. Recommendations were made for future performance assessment calculations.

Case, M.J.; Maheras, S.J.; McKenzie-Carter, M.A.; Sussman, M.E.; Voilleque, P.

1990-06-01T23:59:59.000Z

437

Radioactive and mixed waste - risk as a basis for waste classification. Symposium proceedings No. 2  

SciTech Connect (OSTI)

The management of risks from radioactive and chemical materials has been a major environmental concern in the United states for the past two or three decades. Risk management of these materials encompasses the remediation of past disposal practices as well as development of appropriate strategies and controls for current and future operations. This symposium is concerned primarily with low-level radioactive wastes and mixed wastes. Individual reports were processed separately for the Department of Energy databases.

NONE

1995-06-21T23:59:59.000Z

438

Nanoengineered membranes for controlled transport  

DOE Patents [OSTI]

A nanoengineered membrane for controlling material transport (e.g., molecular transport) is disclosed. The membrane includes a substrate, a cover definining a material transport channel between the substrate and the cover, and a plurality of fibers positioned in the channel and connected to an extending away from a surface of the substrate. The fibers are aligned perpendicular to the surface of the substrate, and have a width of 100 nanometers or less. The diffusion limits for material transport are controlled by the separation of the fibers. In one embodiment, chemical derivitization of carbon fibers may be undertaken to further affect the diffusion limits or affect selective permeability or facilitated transport. For example, a coating can be applied to at least a portion of the fibers. In another embodiment, individually addressable carbon nanofibers can be integrated with the membrane to provide an electrical driving force for material transport.

Doktycz, Mitchel J. (Oak Ridge, TN) [Oak Ridge, TN; Simpson, Michael L. (Knoxville, TN) [Knoxville, TN; McKnight, Timothy E. (Greenback, TN) [Greenback, TN; Melechko, Anatoli V. (Oak Ridge, TN) [Oak Ridge, TN; Lowndes, Douglas H. (Knoxville, TN) [Knoxville, TN; Guillorn, Michael A. (Knoxville, TN) [Knoxville, TN; Merkulov, Vladimir I. (Oak Ridge, TN) [Oak Ridge, TN

2010-01-05T23:59:59.000Z

439

3.205 Thermodynamics and Kinetics of Materials, Fall 2003  

E-Print Network [OSTI]

Laws of thermodynamics applied to materials and materials processes. Solution theory. Equilibrium diagrams. Overview of fluid transport processes. Kinetics of processes that occur in materials, including diffusion, phase ...

Allen, Samuel M.

440

Update to ANSI/ANS-6.4.3-1991 for low-Z and compound materials and review of particle transport theory.  

E-Print Network [OSTI]

??The ANSI/ANS-6.4.3-1991 Gamma-Ray Attenuation Coefficients and Buildup Factors for Engineering Materials Standard (herein known as ANS Standard), contains derived gamma-ray attenuation coefficients and buildup factors (more)

Durani, Luis

2009-01-01T23:59:59.000Z

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


441

CHAPTER 5-RADIOACTIVE WASTE MANAGEMENT  

SciTech Connect (OSTI)

The ore pitchblende was discovered in the 1750's near Joachimstal in what is now the Czech Republic. Used as a colorant in glazes, uranium was identified in 1789 as the active ingredient by chemist Martin Klaproth. In 1896, French physicist Henri Becquerel studied uranium minerals as part of his investigations into the phenomenon of fluorescence. He discovered a strange energy emanating from the material which he dubbed 'rayons uranique.' Unable to explain the origins of this energy, he set the problem aside. About two years later, a young Polish graduate student was looking for a project for her dissertation. Marie Sklodowska Curie, working with her husband Pierre, picked up on Becquerel's work and, in the course of seeking out more information on uranium, discovered two new elements (polonium and radium) which exhibited the same phenomenon, but were even more powerful. The Curies recognized the energy, which they now called 'radioactivity,' as something very new, requiring a new interpretation, new science. This discovery led to what some view as the 'golden age of nuclear science' (1895-1945) when countries throughout Europe devoted large resources to understand the properties and potential of this material. By World War II, the potential to harness this energy for a destructive device had been recognized and by 1939, Otto Hahn and Fritz Strassman showed that fission not only released a lot of energy but that it also released additional neutrons which could cause fission in other uranium nuclei leading to a self-sustaining chain reaction and an enormous release of energy. This suggestion was soon confirmed experimentally by other scientists and the race to develop an atomic bomb was on. The rest of the development history which lead to the bombing of Hiroshima and Nagasaki in 1945 is well chronicled. After World War II, development of more powerful weapons systems by the United States and the Soviet Union continued to advance nuclear science. It was this defense application that formed the basis for the commercial nuclear power industry.

Marra, J.

2010-05-05T23:59:59.000Z

442

An issue paper on the use of hydrogen getters in transportation packaging  

SciTech Connect (OSTI)

The accumulation of hydrogen is usually an undesirable occurrence because buildup in sealed systems pose explosion hazards under certain conditions. Hydrogen scavengers, or getters, can avert these problems by removing hydrogen from such environments. This paper provides a review of a number of reversible and irreversible getters that potentially could be used to reduce the buildup of hydrogen gas in containers for the transport of radioactive materials. In addition to describing getters that have already been used for such purposes, novel getters that might find application in future transport packages are also discussed. This paper also discusses getter material poisoning, the use of getters in packaging, the effects of radiation on getters, the compatibility of getters with packaging, design considerations, regulatory precedents, and makes general recommendations for the materials that have the greatest applicability in transport packaging. At this time, the Pacific Northwest National Laboratory composite getter, DEB [1,4-(phenylethylene)benzene] or similar polymer-based getters, and a manganese dioxide-based getter appear to be attractive candidates that should be further evaluated. These getters potentially can help prevent pressurization from radiolytic reactions in transportation packaging.

NIGREY,PAUL J.

2000-02-01T23:59:59.000Z

443

Standardization of Transport Properties Measurements: Internal Energy Agency (IEA-AMT) Annex on Thermoelectric  

Broader source: Energy.gov [DOE]

Thermoelectric materials transport properties measurements improvement and standardization is undertaken by new IEA annex under the Advanced Materials for Transportation implementing agreement

444

US Department of Energy, Westinghouse Hanford Company ARECO cesium transportation plan  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) is committed to the safe, efficient, and cost-effective transportation of all materials that support its various programs and activities. DOE strives to ensure that hazardous materials (particularly radioactive),hazardous substances, and hazardous mixed waste are handled and transported in compliance with all applicable federal, state,tribal, and local rules and regulations. This plan outlines the activities and responsibilities of DOE and other agencies that will be followed to conclude a significant movement of radioactive cesium (Cs) chloride capsules in a safe and uneventful manner. DOE-Headquarters (DOE-HQ) has directed that Cs capsules manufactured at the Waste Encapsulation and Storage Facility (WESF) be returned to WESF, located at DOE`s Hanford Site in southeast Washington State. Currently, there are 25 Cs capsules at the Applied Radiant Energy Corporation (ARECO)facility utilized for the polymerization of wood products in Lynchburg, Virginia, that requires removal as part of the overall Cs capsule return effort. This plan has been prepared in cooperation with member states of the Western Governors` Association (WGA) and the Southern States Energy Board (SSEB);the Council of State Governments Midwestern Office; and the Confederated Tribes of the Umatilla Indian