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


1

Safety and Security Technologies for Radioactive Material Shipments...  

Office of Environmental Management (EM)

Safety and Security Technologies for Radioactive Material Shipments Safety and Security Technologies for Radioactive Material Shipments Safety and Security Technologies for...

2

Safety and Security Technologies for Radioactive Material Shipments  

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

and Security Technologies for and Security Technologies for Radioactive Material Shipments Safety & Security Technologies Study Started in 2005 with OCRWM Funding. OCRWM funding ended in 2009. EM gave CVSA funding to finish the report. CVSA Ad Hoc RAM/Security/ITS Committee Examined current and emerging technologies for safety and security of radioactive material shipments Site visits Product reviews HMCRP HM-04 report on emerging technologies Safety & Security Technologies Study Completed several site visits to look at current technologies being used. Technologies were broken down into five categories. 1. Inspection Technologies 2. Security Technologies 3. Radioactive Material Dose Rate Measurement and

3

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

4

ELUCIDATING THE DIFFERENCES BETWEEN ONSITE AND OFFSITE SHIPMENT OF RADIOACTIVE MATERIALS  

SciTech Connect

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

5

Enhancements to System for Tracking Radioactive Waste Shipments...  

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

now track shipments of radioactive materials and access transportation information on mobile devices. Transportation Tracking and Communication System users can now track...

6

Radioactive Material Transportation Practices  

Directives, Delegations, and Requirements

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

7

Enhancements to System for Tracking Radioactive Waste Shipments Benefit  

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

Enhancements to System for Tracking Radioactive Waste Shipments Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users January 30, 2013 - 12:00pm Addthis Transportation Tracking and Communication System users can now track shipments of radioactive materials and access transportation information on mobile devices. Transportation Tracking and Communication System users can now track shipments of radioactive materials and access transportation information on mobile devices. CARLSBAD, N.M. - EM's Carlsbad Field Office (CBFO) recently deployed a new version of the Transportation Tracking and Communication System (TRANSCOM) that is compatible with mobile devices, including smartphones. The recent enhancement, TRANSCOM version 3.0, improves the user interface

8

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...

9

Shipment of Small Quantities of Unspecified Radioactive Material in Chalfant Packagings  

SciTech Connect

In the post 6M era, radioactive materials package users are faced with the disciplined operations associated with use of Certified Type B packagings. Many DOE, commercial and academic programs have a requirement to ship and/or store small masses of poorly characterized or unspecified radioactive material. For quantities which are small enough to be fissile exempt and have low radiation levels, the materials could be transported in a package which provides the required containment level. Because their Chalfant type containment vessels meet the highest standard of containment (helium leak-tight), the 9975, 9977, and 9978 are capable of transporting any of these contents. The issues associated with certification of a high-integrity, general purpose package for shipping small quantities of unspecified radioactive material are discussed and certification of the packages for this mission is recommended.

Smith, Allen; Abramczyk, Glenn; Nathan, Steven; Bellamy, Steve

2009-06-12T23:59:59.000Z

10

Portsmouth Site Delivers First Radioactive Waste Shipment to...  

Office of Environmental Management (EM)

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas...

11

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal  

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

Delivers First Radioactive Waste Shipment to Delivers First Radioactive Waste Shipment to Disposal Facility in Texas Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas August 27, 2013 - 12:00pm Addthis Waste management and transportation personnel worked late to complete the first shipment to WCS. Through a contract with DOE, WCS will treat and accept potentially hazardous waste that has been at the Portsmouth site for decades. Pictured (from left) are Scott Fraser, Joe Hawes, Craig Herrmann, Jim Book, John Lee, John Perry, Josh Knipp, Melissa Dunsieth, Randy Barr, Rick Williams, Janet Harris, Maureen Fischels, Cecil McCoy, Trent Eckert, Anthony Howard and Chris Ashley. Waste management and transportation personnel worked late to complete the first shipment to WCS. Through a contract with DOE, WCS will treat and

12

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal  

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

Portsmouth Site Delivers First Radioactive Waste Shipment to Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas August 27, 2013 - 12:00pm Addthis Waste management and transportation personnel worked late to complete the first shipment to WCS. Through a contract with DOE, WCS will treat and accept potentially hazardous waste that has been at the Portsmouth site for decades. Pictured (from left) are Scott Fraser, Joe Hawes, Craig Herrmann, Jim Book, John Lee, John Perry, Josh Knipp, Melissa Dunsieth, Randy Barr, Rick Williams, Janet Harris, Maureen Fischels, Cecil McCoy, Trent Eckert, Anthony Howard and Chris Ashley. Waste management and transportation personnel worked late to complete the

13

Radioactive Material Transportation Practices Manual  

Directives, Delegations, and Requirements

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

14

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

SciTech Connect

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

15

Transporting & Shipping Hazardous Materials at LBNL: Radioactive Materials  

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

Radioactive Materials Radioactive Materials Refer to transportation guidelines in the applicable Radioactive Work Authorization (RWA). Contact the Radiation Protection Group (x7652) if transportation assistance is needed or if radioactive materials need to be shipped. Refer to RPG's Zone sheet to identifying the RCT or HP for your building: https://ehswprod.lbl.gov/rpg/who_to_call.shtml Need radioactive material shipped from LBNL? Please complete the request for shipment form online, print, sign, and forward to your building assigned RPG support person: RPG Transportation - Request for Shipment Form: http://www.lbl.gov/ehs/rpg/assets/docs/Transportation4.pdf Receiving radioactive material at LBNL? If receiving radioactive material at LBNL; radioactive material should be sent to the following address:

16

DOE - Safety of Radioactive Material Transportation  

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

What's their construction? Who uses them? Who makes rules? What are the requirements? Safety Record Radioactive materials are carried by road, rail, water, and air. There are strict regulations that originate from the International Atomic Energy Agency (IAEA) which cover the packaging and transportation of radioactive materials. Road Rail Water Air [Road transport] Click to view picture [Rail transport] Click to view picture [Sea transport] Click to view picture [Air transport] Click to view picture 1998 DOE Radioactive Shipments in the United States Out of the 3 million hazardous material shipments are made each year, DOE accounts for less than 1% of all radioactive materials shipments and 75% of the total curies shipped in the United States Ship 0 Train 308

17

DOE - Safety of Radioactive Material Transportation  

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

What are the requirements? What are the requirements? Safety Record Radioactive material has been shipped in the U. S. for more than 50 years with no occurrences of death or serious injury from exposure of the contents of these shipments. Hazardous Material Shipments for 1 Year Internationally 300 million United States 3 million DOE <1% or 5,000 (out of 3 million) [U.S. DOE NTP, 1999, Transporting Radioactive Materials] All radioactive shipments are regulated by the Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC). Since transport accidents cannot be prevented, the regulations are primarily designed to: Insure safety in routine handling situations for minimally hazardous material Insure integrity under all circumstances for highly dangerous materials

18

Ensuring Safe Shipment of Hazardous Materials | Department of Energy  

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

Ensuring Safe Shipment of Hazardous Materials Ensuring Safe Shipment of Hazardous Materials Ensuring Safe Shipment of Hazardous Materials March 28, 2013 - 12:00pm Addthis A truck carries a waste shipment from Brookhaven National Laboratory in New York. EM completed legacy cleanup activities at the site last year. A truck carries a waste shipment from Brookhaven National Laboratory in New York. EM completed legacy cleanup activities at the site last year. Emergency responders participate in a training exercise in the Transportation Emergency Preparedness Program (TEPP), which also recently released its annual report. Administered by EM’s Office of Packaging and Transportation, TEPP ensures federal, state, tribal and local responders have access to the plans, training and technical assistance necessary to safely, efficiently and effectively respond to radiological transportation accidents.

19

DOE - Safety of Radioactive Material Transportation  

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

How are they moved? What's their construction? Who uses them? Who makes rules? What are the requirements? Safety Record Packagings are used to safely transport radioactive materials across the United States in over 1.6 million shipments per year. [Weiner et. al., 1991, Risk Analysis, Vol. 11, No. 4, p. 663] Most shipments are destined for hospitals and medical facilities. Other destinations include industrial, research and manufacturing plants, nuclear power plants and national defense facilities. The last comprehensive survey showed that less than 1 percent of these shipments involve high-level radioactive material. [Javitz et. al., 1985, SAND84-7174, Tables 4 and 8] The types of materials transported include: Surface Contaminated Object (SCO) Low Specific Activity (LSA) materials, Low-Level Waste (LLW),

20

U.S. Department of Energy to Host Press Call on Radioactive Waste Shipment  

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

U.S. Department of Energy to Host Press Call on Radioactive Waste U.S. Department of Energy to Host Press Call on Radioactive Waste Shipment and Disposal U.S. Department of Energy to Host Press Call on Radioactive Waste Shipment and Disposal November 12, 2013 - 10:26am Addthis NEWS MEDIA CONTACT (202) 586-4940 LAS VEGAS, NV - On Tuesday, November 12, 2013, the U.S. Department of Energy (DOE) will host a press call to discuss Consolidated Edison Uranium Solidification Project (CEUSP) shipment and disposal plans in Nevada. Energy Chief of Staff Kevin Knobloch will host the call and will be joined by issue experts to address any questions. This press call is taking place the day before DOE starts public meetings on this issue in Las Vegas (Nov. 13 at Cashman Center) and Pahrump (Nov. 14 at NV Treasure RV Resort). More details on those meetings can be found

Note: This page contains sample records for the topic "radioactive material shipments" 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

Midwestern Radioactive Materials Transportation Committee Agenda...  

Office of Environmental Management (EM)

Midwestern Radioactive Materials Transportation Committee Agenda Midwestern Radioactive Materials Transportation Committee Agenda Midwestern Radioactive Materials Transportation...

22

Gamma monitor for assay of radioactive solid-waste shipments  

SciTech Connect

A gamma waste monitor has been developed and evaluated at the Savannah River Plant (SRP). The purpose of the monitor is to improve estimates of the radionuclides in solid wastes arriving at the plant's burial ground. This monitor, a computer-based spectrometer, quantitatively measures many radionuclides in SRP waste, including waste in heavily shielded shipping casks. Radionuclides emitting gamma rays of sufficient energy to penetrate the shipping container walls can be measured directly. Other radionuclides that are beta emitters or which emit gamma photons too weak to penetrate the walls of the waste containers can often be estimated by their association with measurable gamma photons. Development of the monitor was initiated to find a more accurate method of estimating the quantities of radioactive materials accumulated in the burial ground and to ensure compliance with burial limits imposed by SRP technical standards. Another benefit from the monitor is that it provides specific radionuclide data which are essential to environmental impact evaluations and decommissioning planning. The gamma waste monitor is described. (WHK)

Crawford, J H

1982-06-01T23:59:59.000Z

23

DOE - Safety of Radioactive Material Transportation  

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

When are they used? How are they moved? What's their construction? Who uses them? Who makes rules? What are the requirements? Safety Record A radioactive material (RAM) packaging is a container that is used to safely transport radioactive material from one location to another. In RAM transportation the container alone is called the Packaging. The packaging together with its contents is called the Package. Basic types of radioactive material packagings are: Excepted Packaging Industrial Packaging Type A Packaging Type B Packaging [EXCEPTED] Click to view picture [IP] Click to view picture [TYPE A] Click to view picture [TYPE B] Click to view picture Excepted Packagings are designed to survive normal conditions of transport. Excepted packagings are used for transportation of materials that are either Low Specific Activity (LSA) or Surface Contaminated Objects (SCO) and that are limited quantity shipments, instruments or articles, articles manufactured from natural or depleted uranium or natural thorium; empty packagings are also excepted (49CFR 173.421-428).

24

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

SciTech Connect

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

25

Hanford Site radioactive hazardous materials packaging directory  

SciTech Connect

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

26

Experiment Hazard Class 8.1 - Radioactive Materials/Samples  

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

1 - Radioactive Materials 1 - Radioactive Materials Applicability This hazard classification applies to all experiments involving radioactive materials as samples. The requirements of this hazard class also apply to sealed radioactive sources that are used as a sample (i.e. a target for x-ray radiation). Other hazard classifications and their associated hazard controls may also apply to experiments in this hazard class. The current requirements can be found in the APS Policy for Conducting Radioactive Sample Experiments in APS Experiment Enclosures. NOTE: The APS must be notified of shipment of any radioactive materials to the site well in advance of the proposed experiment. All radioactive materials must arrive through Argonne Receiving in Building 46 and the Argonne Materials Control & Accountability group (MC&A). Please contact

27

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

28

Annual Report - FY 2001, Radioactive Waste Shipments To and From the Nevada Test Site, February 2002  

SciTech Connect

In February 1997, the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office (NNSA/NV) 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). NNSA/NV 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 Sites (RWMSs) at Area 3 and Area 5. This document satisfies requirements with regard to low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) transported to or from the NTS during fiscal year (FY 2001).

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

2002-02-01T23:59:59.000Z

29

Evaluation of nuclear facility decommissioning projects: Summary status report: Three Mile Island Unit 2. Radioactive waste and laundry shipments  

SciTech Connect

This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. This report covers the period of April 9, 1979 through April 19, 1987. Included in this report are: waste disposal site locations, dose rates, curie content, waste description, container type and number, volumes and weights. This information is presented in two major categories: protective clothing (laundry) and radioactive waste. Each of the waste shipment reports is in chronological order.

Doerge, D. H.; Haffner, D. R.

1988-06-01T23:59:59.000Z

30

RH_SRS_Shipment  

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

WIPP Trucks Delivering First Remote-Handled Transuranic Waste WIPP Trucks Delivering First Remote-Handled Transuranic Waste from the Savannah River Site CARLSBAD, N.M., June 11, 2012- Photo caption: On June 7, 2012, Waste Isolation Pilot Plant (WIPP) trucks approach the WIPP facility near Carlsbad, New Mexico, with the first shipment of defense- related remote-handled transuranic (TRU) waste from Savannah River Site (SRS), near Aiken, South Carolina. TRU waste consists of materials contaminated with radioactive elements that have atomic numbers greater than uranium, including tools, rags, protective clothing, sludge and soil. That shipment and two contact- handled TRU waste shipments were released by SRS at the same time The three shipments consisted of (left to right) a TRUPACT-III, a RH-72B and one with

31

RADIOACTIVE MATERIALS SENSORS  

SciTech Connect

Providing technical means to detect, prevent, and reverse the threat of potential illicit use of radiological or nuclear materials is among the greatest challenges facing contemporary science and technology. In this short article, we provide brief description and overview of the state-of-the-art in sensor development for the detection of radioactive materials, as well as an identification of the technical needs and challenges faced by the detection community. We begin with a discussion of gamma-ray and neutron detectors and spectrometers, followed by a description of imaging sensors, active interrogation, and materials development, before closing with a brief discussion of the unique challenges posed in fielding sensor systems.

Mayo, Robert M.; Stephens, Daniel L.

2009-09-15T23:59:59.000Z

32

Preparing the Shipment 1. The material must be characterized.  

E-Print Network (OSTI)

' Health and Safety and the Environment Environmental Health & Safety (EHS) 490 10th St., 3rd Floor Atlanta Contact Number (404) 216-5237 Dangerous Goods Shipping Program EHS Role in Chemical/Biological Shipments Association (IATA) and a number of other agencies regulate the transport of dangerous goods. To ensure

Sherrill, David

33

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

Directives, Delegations, and Requirements

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

34

Radioactive waste shipments to Hanford Retrievable Storage from the General Electric Vallecitos Nuclear Center, Pleasanton, California  

SciTech Connect

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Approximately 3.8% of the TRU waste to be retrieved for shipment to WIPP was generated at the General Electric (GE) Vallecitos Nuclear Center (VNC) in Pleasanton, California and shipped to the Hanford Site for storage. The purpose of this report is to characterize these radioactive solid wastes using process knowledge, existing records, and oral history interviews. The waste was generated almost exclusively from the activities, of the Plutonium Fuels Development Laboratory and the Plutonium Analytical Laboratory. Section 2.0 provides further details of the VNC physical plant, facility operations, facility history, and current status. The solid radioactive wastes were associated with two US Atomic Energy Commission/US Department of Energy reactor programs -- the Fast Ceramic Reactor (FCR) program, and the Fast Flux Test Reactor (FFTR) program. These programs involved the fabrication and testing of fuel assemblies that utilized plutonium in an oxide form. The types and estimated quantities of waste resulting from these programs are discussed in detail in Section 3.0. A detailed discussion of the packaging and handling procedures used for the VNC radioactive wastes shipped to the Hanford Site is provided in Section 4.0. Section 5.0 provides an in-depth look at this waste including the following: weight and volume of the waste, container types and numbers, physical description of the waste, radiological components, hazardous constituents, and current storage/disposal locations.

Vejvoda, E.J.; Pottmeyer, J.A.; DeLorenzo, D.S.; Weyns-Rollosson, M.I. [Los Alamos Technical Associates, Inc., NM (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1993-10-01T23:59:59.000Z

35

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

36

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

37

Naturally Occurring Radioactive Materials (NORM)  

SciTech Connect

This paper discusses the broad problems presented by Naturally Occuring Radioactive Materials (NORM). Technologically Enhanced naturally occuring radioactive material includes any radionuclides whose physical, chemical, radiological properties or radionuclide concentration have been altered from their natural state. With regard to NORM in particular, radioactive contamination is radioactive material in an undesired location. This is a concern in a range of industries: petroleum; uranium mining; phosphorus and phosphates; fertilizers; fossil fuels; forestry products; water treatment; metal mining and processing; geothermal energy. The author discusses in more detail the problem in the petroleum industry, including the isotopes of concern, the hazards they present, the contamination which they cause, ways to dispose of contaminated materials, and regulatory issues. He points out there are three key programs to reduce legal exposure and problems due to these contaminants: waste minimization; NORM assesment (surveys); NORM compliance (training).

Gray, P. [ed.

1997-02-01T23:59:59.000Z

38

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

39

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

40

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

Note: This page contains sample records for the topic "radioactive material shipments" 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

Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2. Radioactive waste and laundry shipments. Volume 9. Summary status report  

SciTech Connect

This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. This report covers the period of April 9, 1979 to May 5, 1985. Included in this report are: waste disposal site locations, dose rates, curie content, waste description, container type and number, volumes and weights. This information is presented in two major categories: protective clothing (laundry) and radioactive waste. Each of the waste shipment reports is in chronological order.

Doerge, D. H.; Miller, R. L.; Scotti, K. S.

1986-05-01T23:59:59.000Z

42

Radioactive material package seal tests  

SciTech Connect

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

43

WIPP Receives 200th Shipment  

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

of defense- generated transuranic radioactive waste. The shipment came from DOE's Rocky Flats Environmental Technology Site (RFETS) in Colorado. "The arrival of the 200 th...

44

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

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

PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 The objective of this surveillance is to evaluate the effectiveness of the contractor's programs, policies, and procedures to transport radioactive and hazardous materials off-site or to receive such materials for routine operations, treatment, storage, or disposal. The Facility Representative observes preparation of materials for shipment and receipt of materials and reviews specific documents to determine compliance with requirements imposed by DOE and by applicable regulations from the U.S. Nuclear Regulatory Commission and the Department of Transportation. PTS13-01.doc More Documents & Publications Order Module--DOE O 460.1C, PACKAGING AND TRANSPORTATION SAFETY, DOE O

45

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

46

Radioactive Material Use at the EMSL Radiochemistry Annex  

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

The radioactive material must then be placed in inner packages that will prevent radioactive contamination during transportation. Dispersible radioactive material must be...

47

Surveillance Guides - PTS 13.1 Radioactive And Hazardous Material Transportation  

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

RADIOACTIVE AND HAZARDOUS MATERIALS TRANSPORTATION RADIOACTIVE AND HAZARDOUS MATERIALS TRANSPORTATION 1.0 Objective The objective of this surveillance is to evaluate the effectiveness of the contractor's programs, policies, and procedures to transport radioactive and hazardous materials off-site or to receive such materials for routine operations, treatment, storage, or disposal. The Facility Representative observes preparation of materials for shipment and receipt of materials and reviews specific documents to determine compliance with requirements imposed by DOE and by applicable regulations from the U.S. Nuclear Regulatory Commission and the Department of Transportation. 2.0 References DOE O 460.1A, Packaging and Transportation Safety DOE O 460.2, Chg1, Departmental Materials Transportation and Packaging

48

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

49

Diverter assembly for radioactive material  

DOE Patents (OSTI)

A diverter assembly for diverting a pneumatically conveyed holder for a radioactive material between a central conveying tube and one of a plurality of radially offset conveying tubes includes an airtight container. A diverter tube having an offset end is suitably mounted in the container for rotation. A rotary seal seals one end of the diverter tube during and after rotation of the diverter tube while a spring biased seal seals the other end of the diverter tube which moves between various offset conveying tubes. An indexing device rotatably indexes the diverter tube and this indexing device is driven by a suitable drive. The indexing mechanism is preferably a geneva-type mechanism to provide a locking of the diverter tube in place. 3 figs.

Andrews, K.M.; Starenchak, R.W.

1988-04-11T23:59:59.000Z

50

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

SciTech Connect

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

51

Radiation Sources and Radioactive Materials (Connecticut)  

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

52

Radiation Machines and Radioactive Materials (Iowa)  

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

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

53

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

SciTech Connect

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

54

Rocky Flats resumes shipments to WIPP  

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

Rocky Flats Resumes Shipments to WIPP CARLSBAD, N.M., March 11, 2000 - The U.S. Department of Energy (DOE) has resumed transuranic radioactive waste shipments from DOE's Rocky...

55

Radioactive Material or Multiple Hazardous Materials Decontamination  

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

The purpose of this procedure is to provide guidance for performing decontamination ofindividuals who have entered a hot zone during transportation incidents involving radioactive.

56

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

SciTech Connect

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

57

DOE - Safety of Radioactive Material Transportation  

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

SAFE are radioactive material transportations packages? SAFE are radioactive material transportations packages? RAM PACKAGES TESTING & CERTIFICATION REGULATIONS & GUIDANCE SITE MAP This graphic was generated from a computer analysis and shows the results from a regulatory puncture test of a stainless steel packaging dropping 40 inches (10 MPH) onto a 6 inch diameter steel spike. U.S. DOE | Office of Civilian Radioactive Waste Management (OCRWM) Sandia National Laboratories | Nuclear Energy & Fuel Cucle Programs © Sandia Corporation | Site Contact | Sandia Site Map | Privacy and Security An internationally recognized web-site from PATRAM 2001 - the 13th International Symposium on the Packaging and Transportation of Radioactive Material. Recipient of the AOKI AWARD. PATRAM, sponsored by the U.S. Department of Energy in cooperation with the International Atomic Energy Agency brings government and industry leaders together to share information on innovations, developments, and lessons learned about radioactive materials packaging and transportation.

58

Surveillance Guides - PTS 13.2 Packaging and Preparation for Shipment  

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

PACKAGING AND PREPARATION FOR SHIPMENT PACKAGING AND PREPARATION FOR SHIPMENT 1.0 Objective The objective of this surveillance is to evaluate the effectiveness of the contractor's programs for packaging radioactive and hazardous wastes for shipment. The Facility Representative examines packages ready for shipment, observes preparation of packages, and reviews documents that establish the acceptability of packages. The Facility Representative verifies compliance with DOE requirements including requirements established by the Department of Transportation and the U.S. Nuclear Regulatory Commission. 2.0 References 2.1 DOE 5480.3, Safety Requirements for the Packaging and Transportation of Hazardous Materials, Hazardous Substances, and Hazardous Wastes

59

Detection of radioactive materials at Astrakhan  

SciTech Connect

Astrakhan is the major Russian port on the Caspian Sea. Consequently, it is the node for significant river traffic up the Volga, as well as shipments to and from other seaports on the Caspian Sea. The majority of this latter trade across the Caspian Sea is with Iran. The Second Line of Defense and RF SCC identified Astrakhan as one of the top priorities for upgrading with modern radiation detection equipment. The purpose of the cooperative effort between RF SCC and DOE at Astrakhan is to provide the capability through equipment and training to monitor and detect illegal shipments of nuclear materials through Astrakhan. The first facility was equipped with vehicle and rail portal monitoring systems. The second facility was equipped with pedestrian, vehicle and rail portal monitoring systems. A second phase of this project will complete the equipping of Astrakhan by providing additional rail and handheld systems, along with completion of video systems. Associated with both phases is the necessary equipment and procedural training to ensure successful operation of the equipment in order to detect and deter illegal trafficking in nuclear materials. The presentation will described this project and its overall relationship to the Second Line of Defense Program.

Cantut, L; Dougan, A; Hemberger, P; Kravenchenko, Gromov, A; Martin, D; Pohl, B; Richardson, J H; Williams, H; York, R; Zaitsev, E

1999-07-01T23:59:59.000Z

60

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

Note: This page contains sample records for the topic "radioactive material shipments" 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 Samples / Materials at the APS  

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

Using Radioactive Samples / Materials at the APS Using Radioactive Samples / Materials at the APS The use of radioactive samples requires additional information for review and approval. All proposed experiments involving radioactive samples will be reviewed by the APS Radioactive Sample Safety Review Committee (RSSRC). The review will be on a graded basis. Hence, the experimenters are strongly advised to send in the experiment proposal in detail at least 2 months before the expected scheduled date of the experiment. Previously approved containment, isotopes and weights can be submitted as late as 2 weeks in advance. If your ESAF was submitted less than seven (7) days in advance of its scheduled start date you may be delayed to allow time for a safety review. The following guidelines are to be followed for all experiments with

62

PTS 13.1 Radioactive And Hazardous Material Transportation 4...  

Office of Environmental Management (EM)

PTS 13.1 Radioactive And Hazardous Material Transportation 41300 PTS 13.1 Radioactive And Hazardous Material Transportation 41300 The objective of this surveillance is to...

63

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

64

Uraninum-233 Inventory in Oak Ridge Lightened with First Shipment...  

Office of Environmental Management (EM)

Uraninum-233 Inventory in Oak Ridge Lightened with First Shipment of Material from Building 3019 Uraninum-233 Inventory in Oak Ridge Lightened with First Shipment of Material from...

65

PTS 13.2 Packaging and Preparation for Shipment 4/10/95 | Department of  

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

PTS 13.2 Packaging and Preparation for Shipment 4/10/95 PTS 13.2 Packaging and Preparation for Shipment 4/10/95 PTS 13.2 Packaging and Preparation for Shipment 4/10/95 The objective of this surveillance is to evaluate the effectiveness of the contractor's programs for packaging radioactive and hazardous wastes for shipment. The Facility Representative examines packages ready for shipment, observes preparation of packages, and reviews documents that establish the acceptability of packages. The Facility Representative verifies compliance with DOE requirements including requirements established by the Department of Transportation and the U.S. Nuclear Regulatory Commission. PTS13-02.doc More Documents & Publications PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 CMS 3.4 Temporary Changes, 4/10/95

66

DOE - Safety of Radioactive Material Transportation  

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

What are the requirements? Safety Record The Agencies that Generate Rules that Promulgate the Transport of Radioactive Materials: Regulations to control the transport of radioactive material were initiated about 1935 by the Postal Service. Over the years, the Interstate Commerce Commission (ICC) became involved and in 1948 promulgated regulations as Title 49 of the Code of Federal Regulations. In 1966, DOT received hazardous materials regulatory authority that had been exercised by the ICC, Federal Aviation Administration (FAA) and United States Costal Guard (USCG). Currently, five groups generate rules governing the transport of radioactive material -- the DOT, NRC, USPS, DOE, and various State agencies. Among these, DOT and NRC are the primary agencies issuing regulations based on the model regulations developed by the International Atomic Energy Agency (IAEA).

67

DOE - Safety of Radioactive Material Transportation  

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

Specific Activity Specific Activity Low Specific Activity (LSA) material means Class 7 (radioactive) material with limited specific activity which satisfies the descriptions and limits set forth below. Shielding materials surrounding the LSA material may not be considered in determining the estimated average specific activity of the package contents. LSA material must be in one of three groups: LSA-I (i) Ores containing only naturally occurring radionuclides (e.g., uranium, thorium) and uranium or thorium concentrates of such ores; or (ii) Solid unirradiated natural uranium or depleted uranium or natural thorium or their solid or liquid compounds or mixtures; or (iii) Class 7 (radioactive) material, other than fissile material, for which the A2 value is unlimited; or

68

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

SciTech Connect

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

69

Completion of the Radioactive Materials Packaging Handbook  

SciTech Connect

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

70

DOE - Safety of Radioactive Material Transportation  

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

Emergency Response Effects of Radiation History Gallery Glossary of Nuclear Terms [Majority from NRC] Contacts Comments & Questions Agencies U. S. Department of Transportation (DOT), U. S. Nuclear Regulatory Commission (NRC) Postal Services (USPS) U. S. Department of Energy (DOE), National Conference of State Legislatures - Environment, Energy and Transportation Program, Hazardous and Radioactive Materials International Atomic Energy Agency (IAEA) U. S. Environmental Protection Agency (EPA) Regulations Code of Federal Regulations: Title 10 - Energy Code of Federal Regulations: Title 10, PART 71 - Packaging and Transportation of Radioactive Material Code of Federal Regulations: Title 49 - Transportation Code of Federal Regulations: Title 49, PART 173 - Shippers - General

71

EMERGENCY RESPONSE TO A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

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

Emer Emer Emer Emer Emer Emergency Response to a T gency Response to a T gency Response to a T gency Response to a T gency Response to a Transportation ransportation ransportation ransportation ransportation Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond the scope of this video and requires either additional

72

Radioactive Material Use at the EMSL Radiochemistry Annex  

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

Material Use at the EMSL Radiochemistry Annex Material Use at the EMSL Radiochemistry Annex The EMSL Radiochemistry Annex, located in the 3410 Material Science and Technology Building, is authorized to work with small to moderate amounts of radioactive material. In order to work within 3410 facility radiological limits, potential users must provide detailed information about the type and quantity of radioactive material, the form and packaging of the material and the type of work that will be performed at the EMSL Radiochemistry Annex. Radioactive material includes both purchased radioactive material and samples that contain concentrations of radioactive material in excess of normal background levels. Please realize that some samples that may not be considered to be radioactive material at your institution will be managed as radioactive material at

73

Radioactive Materials Transportation and Incident Response  

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

FEMA 358, 05/10 FEMA 358, 05/10 Q A RADIOACTIVE MATERIALS Transportation Emergency Preparedness Program U.S. Department of Energy TRANSPORTATION AND INCIDENT RESPONSE Q&A About Incident Response Q Q Law Enforcement ____________________________________ Fire ___________________________________________ Medical ____________________________________________ State Radiological Assistance ___________________________ Local Government Official ______________________________ Local Emergency Management Agency ___________________ State Emergency Management Agency ___________________ HAZMAT Team ______________________________________ Water Pollution Control ________________________________ CHEMTEL (Toll-free US & Canada) 1-800-255-3924 _________ CHEMTREC (Toll-free US & Canada) 1-800-424-9300 _______

74

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

75

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

76

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

77

DOE - Safety of Radioactive Material Transportation  

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

Sources of Radiation Biological Responses Other Effects History Gallery Glossary of Nuclear Terms [Majority from NRC] Contacts Comments & Questions Radiation is all around us, occurring naturally in the environment. We are always exposed to radiation from: radon in the air uranium, radium and thorium in the earth cosmic rays from outer space and the sun radioactive potassium in our food and water naturally occuring radioactive material within our own bodies. This is commonly called "naturally-occurring background radiation." TYPES OF IONIZING RADIATION Alpha Alpha particles can be shielded by a sheet of paper or by human skin. If alpha emitters are inhaled, ingested, or enter the body through a cut, they can cause cancer. Beta Beta radiation can be stopped by a shield like aluminum foil or wood. If beta emitters are inhaled, ingested, or enter the body through a cut, they can cause cancer.

78

Study of gel materials as radioactive 222Rn gas detectors  

Science Journals Connector (OSTI)

......studied as radioactive radon gas detectors. The detection...diffusion of the radioactive gas in the gel material...easy handling and low cost of the gel material...and other radioactive gases. INTRODUCTION The objective...homogeneity of the device production, dimensions, almost......

G. Espinosa; J. I. Golzarri; J. Rickards; R. B. Gammage

2006-09-01T23:59:59.000Z

79

Midwestern Radioactive Materials Transportation Committee Agenda  

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

Council of State Governments Council of State Governments Midwestern Radioactive Materials Transportation Committee May 15, 2012 Knoxville, Tennessee Revised Agenda 9 - 9:45 am Welcome, Introductions, and Committee Reports Report from co-chairs Tim Runyon (Illinois) Project update Lisa Janairo, CSG Midwest Work group reports Integrated Spent Fuel Management Work Group Teri Engelhart (Wisconsin) NTSF-related reports Planning Committee Tim Runyon (Illinois) Communications Ad Hoc Working Group Jane Beetem (Missouri) WIPP Security Communications Protocol Major Lance Evans (Iowa) Ad Hoc Working Group Information and Communications Work Group Lisa Janairo 9:45 - 10:45 am Committee Discussion Blue Ribbon Commission final report: state reactions, next steps

80

RECLAMATION OF RADIOACTIVE MATERIAL PACKAGING COMPONENTS  

SciTech Connect

Radioactive material packages are withdrawn from use for various reasons; loss of mission, decertification, damage, replacement, etc. While the packages themselves may be decertified, various components may still be able to perform to their required standards and find useful service. The Packaging Technology and Pressurized Systems group of the Savannah River National Laboratory has been reducing the cost of producing new Type B Packagings by reclaiming, refurbishing, and returning to service the containment vessels from older decertified packagings. The program and its benefits are presented.

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

2011-06-06T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive material shipments" 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

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.

82

WIPP Receives First Shipment | National Nuclear Security Administratio...  

National Nuclear Security Administration (NNSA)

26, 1999 WIPP Receives First Shipment Carlsbad, NM After more than two decades of political, legal, and bureaucratic delays, the first truckload of radioactive waste from Los...

83

Study of gel materials as radioactive 222Rn gas detectors  

Science Journals Connector (OSTI)

......Commercial hair gel material (polyvinyl pyrolydone...radioactive gas in the gel material, and the subsequent...reproducibility of data, easy handling and low cost of the gel material. This detection...aerosols(7). The diagrams of the Marinelli......

G. Espinosa; J. I. Golzarri; J. Rickards; R. B. Gammage

2006-09-01T23:59:59.000Z

84

Introduction to naturally occurring radioactive material  

SciTech Connect

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

85

DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

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

Video User' s Guide Video User' s Guide DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond

86

DOE - Safety of Radioactive Material Transportation  

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

What are full-scale tests? What are scale-model tests? What is computer analysis? What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. A packaging is certified when it can survive a sequence of impact, crush, puncture, fire, and immersion tests designed to replicate transport accident conditions. Type B Packages must meet the testing requirements of: Compliance Testing, as defined in 10 CFR Part 71.85 and 10 CFR Part 71.87 Normal Conditions of Transport, Ten tests as defined in 10 CFR Part 71.71 Hypothetical Accident Conditions, Six tests as defined in 10 CFR Part 71.73 The ability of radioactive material packages to withstand testing environments can be demonstrated by full-scale testing, scale-model

87

DOE - Safety of Radioactive Material Transportation  

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

Other Effects History Gallery Glossary of Nuclear Terms [Majority from NRC] Contacts Comments & Questions Dose Rate Calculator Click to use calculator. This tool calculates a dose rate (DR) at 2 meters (about 6 ft) from the surface of a package containing radioactive material IF you know the dose rate at 1 meter (about 3 ft). It will also calculate the reverse; DR at 1 meter if you know the DR at 2 meters. These two distances are used by the Nuclear Regulatory Commission to define acceptable dose rates for packages. Dose (Rad) Biological Effect < 5 rad No immediate observable effects 5 - 50 rad Slight blood changes may be detected by medical evaluation 50 - 150 rad Slight blood changes will be noted and likely symptoms of nausea, fatigue, vomiting, etc.

88

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than  

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

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment of "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than 5,000 Cubic Meters of Nuclear Waste to WIPP "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than 5,000 Cubic Meters of Nuclear Waste to WIPP With the American Recovery and Reinvestment Act funding, Savannah River Site (SRS) continues to safely treat and dispose of radioactive waste created while producing materials for nuclear weapons throughout the Cold War. The DOE site in Aiken, S.C., is safely, steadily, and cost-effectively making progress to analyze, measure, and then carefully cleanup or dispose of legacy transuranic (TRU) waste remaining at SRS after the lengthy nuclear arms race. "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than

89

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than  

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

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment of "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than 5,000 Cubic Meters of Nuclear Waste to WIPP "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than 5,000 Cubic Meters of Nuclear Waste to WIPP With the American Recovery and Reinvestment Act funding, Savannah River Site (SRS) continues to safely treat and dispose of radioactive waste created while producing materials for nuclear weapons throughout the Cold War. The DOE site in Aiken, S.C., is safely, steadily, and cost-effectively making progress to analyze, measure, and then carefully cleanup or dispose of legacy transuranic (TRU) waste remaining at SRS after the lengthy nuclear arms race. "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than

90

Radioactive Materials at SSRL | Stanford Synchrotron Radiation Lightsource  

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

Radioactive Materials at SSRL Radioactive Materials at SSRL Contact Information SSRL Safety Officer (650) 926-3861 SSRL Radiation Protection Group (650) 926-4299 SSRLRadMat@SLAC.STANFORD.EDU Throughout the course of an SSRL Experimental Run, there are requests from users to transport and use small amounts of radioactive material in their experiments, either as stand alone samples or in a matrix of other materials. There is no minimum quantity for declaring the use of radioactive samples at SSRL. The purpose of this procedure is to enable Users, SSRL and SLAC staff to know what radiological controls will be implemented for these materials, based on the isotope, its toxicity risk and radiological controls. Radioactive materials at SSRL are classified into 4 classification Groups based on the radiotoxicity tables, see below.

91

MATERIALS COMPATIBILITY OF SNAP FUEL COMPONENTS DURING SHIPMENT IN 9975 PACKAGING  

SciTech Connect

Materials Science and Technology has evaluated materials compatibility for the SNAP (Systems for Nuclear Auxiliary Power) fuel for containment within a 9975 packaging assembly for a shipping period of one year. The evaluation included consideration for potential for water within the convenience can, corrosion from water, galvanic corrosion, tape degradation, and thermal expansion risk. Based on a review of existing literature and assumed conditions, corrosion and/or degradation of the 304 stainless steel (SS) Primary Containment Vessel (PCV) and the 304 stainless steel convenience cans containing the SNAP fuel is not significant to cause failure during the 1 year time shipping period in the 9975 packaging assembly. However, storage beyond the 1 year shipping period has not been validated.

Vormelker, P

2006-11-14T23:59:59.000Z

92

DOE - Safety of Radioactive Material Transportation  

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

What are examples of severe testing? What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. These full-scale tests, conducted at Sandia National Laboratories Transportation Programs, demonstrate how spent fuel casks perform in accident environments that are more similar to what may happen during actual shipments. Each of the tests included the transportation vehicle as well as the cask. The damage to the casks from these tests was less than the damage during the regulatory hypothetical accident tests, demonstrating that the regulatory tests are more severe. DESCRIPTION PHOTO DURING TEST PHOTO AFTER TEST PHOTO OF PACKAGE AFTER TEST VIDEO OF TEST CRASH TEST Cask rail car with a 74 ton Type B Package on it crashing into a 690 ton concrete block at 81 miles per hour [photo]

93

Naturally Occurring Radioactive Materials in Cargo at US Borders  

SciTech Connect

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

94

U.S. and Bahamian Governments to Cooperate on Detecting Illicit Shipments  

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

Bahamian Governments to Cooperate on Detecting Illicit Bahamian Governments to Cooperate on Detecting Illicit Shipments of Nuclear Material U.S. and Bahamian Governments to Cooperate on Detecting Illicit Shipments of Nuclear Material January 11, 2005 - 9:46am Addthis Bahamas to Become First Caribbean Country to Use Detection Equipment NASSAU, BAHAMAS -- In an effort to work together in the war on terrorism, the United States and the Commonwealth of the Bahamas recently signed an agreement to install special equipment at one of the Bahamas' busiest seaports to detect hidden shipments of nuclear and other radioactive material, Secretary of Energy Spencer Abraham announced today. The Bahamas will be the first country in the Caribbean to deploy this type of detection system. "Helping better protect the world's maritime shipping network from

95

High-Activity Radioactive Materials Removed From Mexico | National Nuclear  

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

High-Activity Radioactive Materials Removed From Mexico | National Nuclear High-Activity Radioactive Materials Removed From Mexico | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Press Releases > High-Activity Radioactive Materials Removed From Mexico Press Release High-Activity Radioactive Materials Removed From Mexico Nov 15, 2013 WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA)

96

NNSA: Securing Domestic Radioactive Material | National Nuclear Security  

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

NNSA: Securing Domestic Radioactive Material | National Nuclear Security NNSA: Securing Domestic Radioactive Material | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > NNSA: Securing Domestic Radioactive Material Fact Sheet NNSA: Securing Domestic Radioactive Material Apr 12, 2013 The Department of Energy's National Nuclear Security Administration (NNSA),

97

High-Activity Radioactive Materials Removed From Mexico | National Nuclear  

National Nuclear Security Administration (NNSA)

High-Activity Radioactive Materials Removed From Mexico | National Nuclear High-Activity Radioactive Materials Removed From Mexico | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Press Releases > High-Activity Radioactive Materials Removed From Mexico Press Release High-Activity Radioactive Materials Removed From Mexico Nov 15, 2013 WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA)

98

Sandia technology used to remove radioactive material at Fukushima |  

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

technology used to remove radioactive material at Fukushima | technology used to remove radioactive material at Fukushima | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Sandia technology used to remove radioactive material ... Sandia technology used to remove radioactive material at Fukushima Posted By Office of Public Affairs

99

NNSA Removes High-Activity Radioactive Materials from Boston | National  

National Nuclear Security Administration (NNSA)

Removes High-Activity Radioactive Materials from Boston | National Removes High-Activity Radioactive Materials from Boston | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Press Releases > NNSA Removes High-Activity Radioactive Materials from Boston Press Release NNSA Removes High-Activity Radioactive Materials from Boston Nov 22, 2013

100

Roadmapping the Resolution of Gas Generation Issues in Packages Containing Radioactive Waste/Materials  

SciTech Connect

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 materials. Transportation regulations prohibit shipment of explosives and radioactive materials together. 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 (NM), and spent nuclear fuels (SNF) programs within DOEs Environmental Management (EM) organization 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 "program level" roadmapping involves linking technology development (and deployment) efforts to the programs needs and requirements for dispositioning the material/waste that generates combustible gas through radiolysis and chemical decomposition. The roadmapping effort focused on needed technical & programmatic support to the baselines (and to alternatives to the baselines) where the probability of success is low (i.e., high uncertainty) and the consequences of failure are relatively high (i.e., high programmatic risk). A second purpose for roadmapping was to provide the basis for coordinating sharing of "lessons learned" from research and development (R&D) efforts across DOE programs to increase efficiency and effectiveness in addressing gas generation issues.

Luke, Dale Elden; Rogers, Adam Zachary; Hamp, S.

2001-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive material shipments" 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

Radioactive material in the West Lake Landfill: Summary report  

SciTech Connect

The West Lake Landfill is located near the city of St. Louis in Bridgeton, St. Louis County, Missouri. The site has been used since 1962 for disposing of municipal refuse, industrial solid and liquid wastes, and construction demolition debris. This report summarizes the circumstances of the radioactive material in the West Lake Landfill. The radioactive material resulted from the processing of uranium ores and the subsequent by the AEC of processing residues. Primary emphasis is on the radiological environmental aspects as they relate to potential disposition of the material. It is concluded that remedial action is called for. 8 refs., 2 figs., 1 tab.

none,

1988-06-01T23:59:59.000Z

102

NNSA: Securing Domestic Radioactive Material | National Nuclear...  

National Nuclear Security Administration (NNSA)

2011 In April 2009, President Obama outlined an ambitious agenda to secure vulnerable nuclear material around the world within four years, calling the danger of a terrorist...

103

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

SciTech Connect

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

104

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

SciTech Connect

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

105

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

106

Management of sewage sludge and ash containing radioactive materials.  

SciTech Connect

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

107

Hanford Site Shares Lessons Learned in Retrieving Highly Radioactive Material  

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

RICHLAND, Wash. EMs Richland Operations Office (Richland) and its contractor, CH2M HILL Plateau Remediation Company (CH2M HILL), welcomed staff from the Oak Ridge Office of Environmental Management Transuranic (TRU) waste processing team in Tennessee to the Hanford site recently to share lessons learned in the retrieval and processing of highly radioactive material, called sludge.

108

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

109

DOE - Safety of Radioactive Material Transportation  

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

Who makes rules? What are the requirements? Safety Record USERS OF PACKAGINGS CARRIER PACKAGE TYPE Hospitals and their suppliers common carrier Type A Industrial radiography companies private carrier Type B Soil testing laboratories private carrier Type B Food irradiators contract carrier Type B Medical supply sterilizers contract carrier Type B Academic research institutes common & contract carrier all types Nuclear energy fuel cycle facilities common & contract carrier all types Nuclear weapons complex contract & government carrier all types An agency or company that wants to ship RAM (shipper) often makes arrangements with a common or contract carrier or (where appropriate) a private carrier may transport the material. Packagings may be procured or

110

A manual for implementing residual radioactive material guidelines  

SciTech Connect

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

111

Digital Radiography of a Drop Tested 9975 Radioactive Materials Packaging  

SciTech Connect

This paper discusses the use of radiography as a tool for evaluating damage to radioactive material packaging subjected to regulatory accident conditions. The Code of Federal Regulations, 10 CFR 71, presents the performance based requirements that must be used in the development (design, fabrication and testing) of a radioactive material packaging. The use of various non-destructive examination techniques in the fabrication of packages is common. One such technique is the use of conventional radiography in the examination of welds. Radiography is conventional in the sense that images are caught one at a time on film stock. Most recently, digital radiography has been used to characterize internal damage to a package subjected to the 30-foot hypothetical accident conditions (HAC) drop. Digital radiography allows for real time evaluation of the item being inspected. This paper presents a summary discussion of the digital radiographic technique and an example of radiographic results of a 9975 package following the HAC 30-foot drop.

Blanton, P.S.

2001-05-30T23:59:59.000Z

112

Q A RADIOACTIVE MATERIALS Transportation Emergency Preparedness Program  

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

Q A RADIOACTIVE MATERIALS Transportation Emergency Preparedness Program U.S. Department of Energy TRANSPORTATION AND INCIDENT RESPONSE Q&A About Incident Response Q Q Law Enforcement ____________________________________ Fire ___________________________________________ Medical ____________________________________________ State Radiological Assistance ___________________________ Local Government Official ______________________________ Local Emergency Management Agency ___________________ State Emergency Management Agency ___________________ HAZMAT Team ______________________________________ Water Pollution Control ________________________________ CHEMTEL (Toll-free US & Canada) 1-800-255-3924 _________ CHEMTREC (Toll-free US & Canada) 1-800-424-9300 _______

113

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

114

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

SciTech Connect

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

115

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

116

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

117

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

118

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

119

SGP Shipment Notification Form  

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

PlainsShipment Notification Form PlainsShipment Notification Form SGP Related Links Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site Fact Sheet Images Information for Guest Scientists Contacts Shipment Notification Form Note: Red text indicates a required field. Your Notification Form has been submitted. Section 1 : Initiator Information Date Afilliation Name Phone Number Email Section 2 : Vendor Information Ship From Point of Contact Address Phone Section 3 : Carrier Information Shipping Company Tracking/AWB Number Number of Boxes Approximate Weight for EACH BOX Expected Ship Date Section 4 : Shipment List Description System/Instrument

120

WIPP - Shipment & Disposal Information  

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

February 11, 2014 Site Shipments Loaded Miles Argonne National Laboratory 193 331,333 Bettis Atomic Power Laboratory 5 10,955 GE Vallecitos Nuclear Center 32 44,800 Idaho National...

Note: This page contains sample records for the topic "radioactive material shipments" 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

Management of Naturally Occurring Radioactive Materials (NORM) in Canada  

Science Journals Connector (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 guidelineCanadian 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.

Anar S. Baweja; Bliss L. Tracy

2008-01-01T23:59:59.000Z

122

Management of Naturally Occurring Radioactive Materials (NORM) in Canada  

SciTech Connect

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

123

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

124

Best Practices for the Security of Radioactive Materials  

SciTech Connect

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

125

TYPE B RADIOACTIVE MATERIAL PACKAGE FAILURE MODES AND CONTENTS COMPLIANCE  

SciTech Connect

Type B radioactive material package failures can occur due to any one of the following: inadequate design, manufacture, and maintenance of packages, load conditions beyond those anticipated in the regulations, and improper package loading and operation. The rigorous package design evaluations performed in the certification process, robust package manufacture quality assurance programs, and demanding load conditions prescribed in the regulations are all well established. This paper focuses on the operational aspects of Type B package loading with respect to an overbatch which may cause a package failure.

Watkins, R; Steve Hensel, S; Allen Smith, A

2007-02-21T23:59:59.000Z

126

THERMAL UPGRADING OF 9977 RADIOACTIVE MATERIAL (RAM) TYPE B PACKAGE  

SciTech Connect

The 9977 package is a radioactive material package that was originally certified to ship Heat Sources and RTG contents up to 19 watts and it is now being reviewed to significantly expand its contents in support of additional DOE missions. Thermal upgrading will be accomplished by employing stacked 3013 containers, a 3013 aluminum spacer and an external aluminum sleeve for enhanced heat transfer. The 7th Addendum to the original 9977 package Safety Basis Report describing these modifications is under review for the DOE certification. The analyses described in this paper show that this well-designed and conservatively analyzed package can be upgraded to carry contents with decay heat up to 38 watts with some simple design modifications. The Model 9977 package has been designed as a replacement for the Department of Transportation (DOT) Fissile Specification 6M package. The 9977 package is a very versatile Type B package which is certified to transport and store a wide spectrum of radioactive materials. The package was analyzed quite conservatively to increase its usefulness and store different payload configurations. Its versatility is evident from several daughter packages such as the 9978 and H1700, and several addendums where the payloads have been modified to suit the Shipper's needs without additional testing.

Gupta, N.; Abramczyk, G.

2012-03-26T23:59:59.000Z

127

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

SciTech Connect

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

128

NEW APPROACH TO ADDRESSING GAS GENERATION IN RADIOACTIVE MATERIAL PACKAGING  

SciTech Connect

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

129

2011 Radioactive Materials Usage Survey for Unmonitored Point Sources  

SciTech Connect

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

130

THERMAL PERFORMANCE OF RADIOACTIVE MATERIAL PACKAGES IN TRANSPORT CONFIGURATION  

SciTech Connect

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 Part 71. The packages are transported in specially designed vehicles like Safe Secure Transport (SST) for safety and security. In the transport vehicles, the packages are placed close to each other to maximize the number of units in the vehicle. Since the RAM contents in the packagings produce decay heat, it is important that they are spaced sufficiently apart to prevent overheating of the containment vessel (CV) seals and the impact limiter to ensure the structural integrity of the package. This paper presents a simple methodology to assess thermal performance of a typical 9975 packaging in a transport configuration.

Gupta, N.

2010-03-04T23:59:59.000Z

131

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

SciTech Connect

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

132

January 23, 2007: WIPP receives first shipment of waste | Department of  

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

January 23, 2007: WIPP receives first shipment of waste January 23, 2007: WIPP receives first shipment of waste January 23, 2007: WIPP receives first shipment of waste January 23, 2007: WIPP receives first shipment of waste January 23, 2007 The Department's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, receives (pdf) its first shipment of remote-handled (RH) transuranic (TRU) radioactive waste. The waste, which consisted of three 30-gallon drums of radioactive debris waste and originated at DOE's Idaho National Laboratory, was transported inside a shielded RH-72B shipping cask, providing the same low radiation levels as the contact-handled (CH) TRU wastes that have been shipped to WIPP since 1999. "This first shipment of RH-TRU waste is particularly significant to DOE," notes DOE Assistant

133

Shipments in Idaho  

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

Radiological Training for Radiological Training for Emergency Responders in Idaho Doug Walker Senior Health Physicist Idaho Department of Environmental Quality Radiation Control Program 2 Initial Assessment * Evaluation of state-wide resources * Consideration for instrumentation * Implementation of state-based training 3 State - Wide Resources State - Wide Resources * Regional Haz-Mat Response Teams * Idaho State Police CVSA/Haz-Mat Radiation Control Program 4 Response Instrumentation * Standardized instrumentation * Annual calibration schedule 5 State Emergency Response Commission * Approval for standardizing instrumentation within the regional response structure * Adopted the DOE-MERRTT as the core training for radioactive materials * Assigned Radiation Control Program to manage the training program

134

Final Transuranic Waste Shipment Leaves Rocky Flats | Department of Energy  

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

Final Transuranic Waste Shipment Leaves Rocky Flats Final Transuranic Waste Shipment Leaves Rocky Flats Final Transuranic Waste Shipment Leaves Rocky Flats April 19, 2005 - 12:23pm Addthis Cleanup Ahead of Schedule, On Track to Save Taxpayers Billions GOLDEN, CO. - A major environmental victory was achieved at the Rocky Flats Site in Golden, Colo., today when the final remaining shipment of radioactive, transuranic (TRU) waste left the property on a truck bound for an underground waste repository in New Mexico. This major milestone is another step toward the final conversion of the site to a National Wildlife Refuge managed by the U.S. Fish and Wildlife Service. "This is great news for all of Colorado, and would not have been possible without hand-in-glove cooperation between the Department of Energy, the

135

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.

136

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

137

U.S. Department of Energy to Host Press Call on Radioactive Waste...  

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

Department of Energy to Host Press Call on Radioactive Waste Shipment and Disposal U.S. Department of Energy to Host Press Call on Radioactive Waste Shipment and Disposal November...

138

U.S. Department of Energy Guidelines for Residual Radioactive Material at  

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

U.S. Department of Energy Guidelines for Residual Radioactive U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites (Revision 2, March 1987) U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites (Revision 2, March 1987) More Documents & Publications

139

U.S. Department of Energy Guidelines for Residual Radioactive Material at  

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

U.S. Department of Energy Guidelines for Residual Radioactive U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites (Revision 2, March 1987) U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites (Revision 2, March 1987) More Documents & Publications

140

WIPP Receives 100th Shipment  

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

of Energy's (DOE) Waste Isolation Pilot Plant (WIPP). The shipment came from DOE's Rocky Flats Environmental Technology Site (RFETS) in Colorado. "This is a major milestone...

Note: This page contains sample records for the topic "radioactive material shipments" 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

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

SciTech Connect

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

142

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

143

Annual Transportation Report for Radioactive Waste Shipments...  

National Nuclear Security Administration (NNSA)

U.S. Department of Energy Office of Scientific and Technical Information P.O. Box 62 Oak Ridge, TN 37831-0062 Phone: 865.576.8401 Fax: 865.576.5728 Email:...

144

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

SciTech Connect

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

145

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

SciTech Connect

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

146

Storage systems and containers for radioactive materials. February 1971-November 1989 (a Bibliography from the US Patent data base). Report for February 1971-November 1989  

SciTech Connect

This bibliography contains citations of selected patents concerning container designs for storage, shipping, and handling of radioactive materials. Storage equipment and devices such as sheilding, racks, covers, seals, packing materials, and filling systems for containerized radioactive materials are considered. Radioactive materials considered include nuclear fuels, spent fuels, radioactive wastes, and radioactive research materials. High- and low-level radioactive materials are included. (Contains 139 citations fully indexed and including a title list.)

Not Available

1990-03-01T23:59:59.000Z

147

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

E-Print Network (OSTI)

This thesis addresses the problem of removal of Naturally Occurring Radioactive Materials, NORM, and describes an effective alternative to the current treatment method for their removal. High-pen-meability fracturing, recently established...

Demarchos, Andronikos Stavros

2012-06-07T23:59:59.000Z

148

LANL reaches waste shipment milestone  

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

LANL reaches waste shipment milestone LANL reaches waste shipment milestone LANL reaches waste shipment milestone The Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total. May 31, 2011 A shipment of transuranic waste on its way to the WIPP repository A shipment of transuranic waste on its way to the WIPP repository. Contact Fred deSousa Communicatons Office (505) 665-3430 Email LOS ALAMOS, New Mexico, May 31, 2011 - Los Alamos National Laboratory has reached an important milestone in its campaign to ship transuranic (TRU) waste from Cold War-era nuclear operations to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This month, the Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total.

149

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

150

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

SciTech Connect

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

151

Idaho Site Achieves Successful Nuclear Shipment on Newly Constructed Haul  

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

Achieves Successful Nuclear Shipment on Newly Achieves Successful Nuclear Shipment on Newly Constructed Haul Road Idaho Site Achieves Successful Nuclear Shipment on Newly Constructed Haul Road May 1, 2012 - 12:00pm Addthis The HFEF-6 cask is transported on the haul road. The HFEF-6 cask is transported on the haul road. IDAHO FALLS, Idaho - Close coordination among operations, security and transportation teams at the Idaho site helped ensure the recent success of the first nuclear shipment on a newly constructed haul road. The new road located between the Critical Infrastructure Test Range Complex (CITRC) and the Materials and Fuels Complex (MFC) is expected to help save significant time and cost over the life of the project by avoiding traffic disruptions on the public highway and increased cost associated with

152

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

153

U.S. Works With Kazakhstan to Stop Nuclear and Radioactive Material  

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

Works With Kazakhstan to Stop Nuclear and Radioactive Material Works With Kazakhstan to Stop Nuclear and Radioactive Material Smuggling U.S. Works With Kazakhstan to Stop Nuclear and Radioactive Material Smuggling May 6, 2006 - 10:34am Addthis WASHINGTON, DC - As part of the overall U.S. strategy to prevent nuclear and dangerous radiological materials from falling into the hands of terrorists, the Department of Energy's National Nuclear Security Administration (NNSA) announced today that an agreement with the government of Kazakhstan had been signed to create a partnership under the Second Line of Defense program. U.S. Ambassador Ordway joined Kazakhstan Customs Control Committee Chairman Askar Shakirov in signing the accord. The agreement will pave the way for NNSA to work collaboratively with the Kazakhstan Customs Control Committee

154

LANL Resumes Shipments to WIPP  

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

19, the U.S. Department of Energy's (DOE) Los Alamos National Laboratory (LANL) will resume shipments of transuranic waste to DOE's Waste Isolation Pilot Plant (WIPP). In March...

155

U.S. DEPARTMENT OF ENERGY GUIDELINES FOR RESIDUAL RADIOACTIVE MATERIAL AT  

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

I I U.S. DEPARTMENT OF ENERGY GUIDELINES FOR RESIDUAL RADIOACTIVE MATERIAL AT FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM AHD REMOTE SURPLUS FACILITIES MANAGEMENT PROGRAM SITES (Revision 2, March 1987) A. INTRODUCTION This document presents U.S. Department of Energy (DOE) radiological protection guidelines for cleanup of residual radioactive material and management of the resulting wastes and residues. It is applicable to si~es - "C-- identified by the Formerly Utilized Sites l{emedia1 Ac:tionProgram (FUSRAP) .and remote sites identified by the Surplus Facilities Management Program (SFMP).* The topics covered are basic dose limits, guidelines and authorized limits for allowable levels of residual radioactive material, and requirements for

156

Milestone reached: Waste shipment leaves Los Alamos National Laboratory  

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

Waste shipment leaves LANL Waste shipment leaves LANL Milestone reached: Waste shipment leaves Los Alamos National Laboratory The material, known as "remote-handled transuranic waste" (RH-TRU), has been stored at the Laboratory since 1995. June 2, 2009 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials. Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials.

157

Naval Spent Fuel Rail Shipment Accident Exercise Objectives ...  

Office of Environmental Management (EM)

Naval Spent Fuel Rail Shipment Accident Exercise Objectives Naval Spent Fuel Rail Shipment Accident Exercise Objectives Naval Spent Fuel Rail Shipment Accident Exercise Objectives...

158

West Valley Demonstration Project Low-Level Waste Shipment |...  

Office of Environmental Management (EM)

West Valley Demonstration Project Low-Level Waste Shipment West Valley Demonstration Project Low-Level Waste Shipment West Valley Demonstration Project Low-Level Waste Shipment...

159

Hanford Shipment Arrives Safely At Waste Isolation Pilot Plant  

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

63 shipments of transuranic waste. DOE has disposed of 41 shipments of waste from the Rocky Flats Environmental Technology Site (Boulder, Colorado), 17 shipments from Los...

160

Lab sets new record for waste shipments  

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

New record for waste shipments New record for waste shipments Lab sets new record for waste shipments LANL completing its 132nd transuranic (TRU) waste shipment of fiscal year 2010 to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. August 20, 2010 LANL's shipment of transuranic waste leaves Los Alamos. LANL's shipment of transuranic waste leaves Los Alamos. Contact Fred deSousa Communications Office (505) 500-5672 Email "Removing this waste from Los Alamos is crucial to our plans for overall cleanup." Each shipment moves LANL closer to cleanup LOS ALAMOS, New Mexico, August 20, 2010-Los Alamos National Laboratory set a new LANL record on Friday by completing its 132nd transuranic (TRU) waste shipment of fiscal year 2010 to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The shipment eclipsed last year's

Note: This page contains sample records for the topic "radioactive material shipments" 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

Fluorescent Functionalized Mesoporous Silica for Radioactive Material Extraction  

SciTech Connect

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

162

Gamma motes for detection of radioactive materials in shipping containers  

SciTech Connect

Shipping containers can be effectively monitored for radiological materials using gamma (and neutron) motes in distributed mesh networks. The mote platform is ideal for collecting data for integration into operational management systems required for efficiently and transparently monitoring international trade. Significant reductions in size and power requirements have been achieved for room-temperature cadmium zinc telluride (CZT) gamma detectors. Miniaturization of radio modules and microcontroller units are paving the way for low-power, deeply-embedded, wireless sensor distributed mesh networks.

Harold McHugh; William Quam; Stephan Weeks; Brendan Sever

2007-04-13T23:59:59.000Z

163

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

SciTech Connect

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

164

WIPP Receives 500th Waste Shipment  

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

transuranic waste. The 500 th shipment arrived at WIPP at 6:38 p.m. Saturday from DOE's Rocky Flats Environmental Technology Site in Colorado. It was the 282 nd shipment to WIPP...

165

First of Hanford's Highly Radioactive Sludge Moved Away from River |  

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

First of Hanford's Highly Radioactive Sludge Moved Away from First of Hanford's Highly Radioactive Sludge Moved Away from River First of Hanford's Highly Radioactive Sludge Moved Away from River July 13, 2012 - 12:00pm Addthis Media Contacts Geoff Tyree, DOE Geoffrey.Tyree@rl.doe.gov 509-376-4171 Dee Millikin, CH2M HILL Dee_Millikin@rl.doe.gov 509-376-1297 RICHLAND, Wash. - Workers have started moving highly radioactive material, called sludge, away from the Columbia River, marking a significant milestone in the U. S. Department of Energy (DOE)'s cleanup of the Hanford Site in Washington State. Today, DOE contractor CH2M HILL Plateau Remediation Company (CH2M HILL) safely transferred the first large container of highly radioactive sludge from a basin next to a former plutonium production reactor to dry storage in the center of the site. Today's transfer is the first of six shipments

166

Combustion aerosols formed during burning of radioactively contaminated materials: Experimental results  

SciTech Connect

Safety assessments and environmental impact statements for nuclear fuel cycle facilities require an estimate of potential airborne releases. Radioactive aerosols generated by fires were investigated in experiments in which combustible solids and liquids were contaminated with radioactive materials and burned. Uranium in powder and liquid form was used to contaminate five fuel types: polychloroprene, polystyrene, polymethylmethacrylate, cellulose, and a mixture of 30% tributylphosphate (TBP) in kerosene. Heat flux, oxygen concentration, air flow, contaminant concentration, and type of ignition were varied in the experiments. The highest release (7.1 wt %) came from burning TBP/kerosene over contaminated nitric acid. Burning cellulose contaminated with uranyl nitrate hexahydrate liquid gave the lowest release (0.01 wt %). Rate of release and particle size distribution of airborne radioactive particles were highly dependent on the type of fuel burned.

Halverson, M.A.; Ballinger, M.Y.; Dennis, G.W.

1987-03-01T23:59:59.000Z

167

APPLICATION FO FLOW FORMING FOR USE IN RADIOACTIVE MATERIAL PACKAGING DESIGNS  

SciTech Connect

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

168

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

SciTech Connect

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

169

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

170

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

171

Closed source experimental system for soft x-ray spectroscopy of radioactive materials  

Science Journals Connector (OSTI)

An instrumental and experimental setup for soft x-rayspectroscopy meeting the requirements of a closed source for radioactivity is described. The system consists of a vacuum sealed cell containing the sample mounted on a tubing system to ensure compatibility with most standard manipulators. The soft x rays penetrate a thin x-ray window separating the interior of the cell from the vacuum in the experimental chamber. Our first results for single crystal PuO 2 confirm the feasibility of experiments using the setup. The results are consistent with results of first principles calculations and previously recorded spectra obtained using a standard open source setup. The results show that the closed source experimental system can be used to collect valuable experimental data from radioactive materials.

A. Modin; S. M. Butorin; J. Vegelius; A. Olsson; C.-J. Englund; J. Andersson; L. Werme; J. Nordgren; T. Kmbre; G. Skarnemark; B. E. Burakov

2008-01-01T23:59:59.000Z

172

Savannah River Site offsite hazardous waste shipment data validation report. Revision 1  

SciTech Connect

The objective of this data validation is to verify that waste shipments reported in response to the US Department of Energy Headquarters data request are properly categorized according to DOE-HQ definitions. This report documents all findings and actions resulting from the independent review of the Savannah River Site data submittal, and provides a summary of the SRS data submittal and data validation strategy. The overall hazardous waste management and offsite release process from 1987--1991 is documented, along with an identification and description of the hazardous waste generation facilities. SRS did not ship any hazardous waste offsite before 1987. Sampling and analysis and surface surveying procedures and techniques used in determining offsite releasability of the shipments are also described in this report. SRS reported 150 manifested waste shipments from 1984 to 1991 that included 4,755 drums or lab packs and 13 tankers. Of these waste items, this report categorizes 4,251 as clean (including 12 tankers), 326 as likely clean, 138 as likely radioactive, and 55 as radioactive (including one tanker). Although outside the original scope of this report, 14 manifests from 1992 and 1993 are included, covering 393 drums or lab packs and seven tankers. From the 1992--1993 shipments, 58 drums or lab packs are categorized as radioactive and 16 drums are categorized as likely radioactive. The remainder are categorized as clean.

Casey, C.; Kudera, D.E.; Page, L.A.; Rohe, M.J.

1995-05-01T23:59:59.000Z

173

Irradiated test fuel shipment plan for the LWR MOX fuel irradiation test project  

SciTech Connect

This document outlines the responsibilities of DOE, DOE contractors, the commercial carrier, and other organizations participating in a shipping campaign of irradiated test specimen capsules containing mixed-oxide (MOX) fuel from the Idaho National Engineering and Environmental Laboratory (INEEL) to the Oak Ridge National Laboratory (ORNL). The shipments described here will be conducted according to applicable regulations of the US Department of Transportation (DOT), US Nuclear Regulatory Commission (NRC), and all applicable DOE Orders. This Irradiated Test Fuel Shipment Plan for the LWR MOX Fuel Irradiation Test Project addresses the shipments of a small number of irradiated test specimen capsules and has been reviewed and agreed to by INEEL and ORNL (as participants in the shipment campaign). Minor refinements to data entries in this plan, such as actual shipment dates, exact quantities and characteristics of materials to be shipped, and final approved shipment routing, will be communicated between the shipper, receiver, and carrier, as needed, using faxes, e-mail, official shipping papers, or other backup documents (e.g., shipment safety evaluations). Any major changes in responsibilities or data beyond refinements of dates and quantities of material will be prepared as additional revisions to this document and will undergo a full review and approval cycle.

Shappert, L.B.; Dickerson, L.S.; Ludwig, S.B.

1998-10-16T23:59:59.000Z

174

" Row: NAICS Codes, Value of Shipments...  

U.S. Energy Information Administration (EIA) Indexed Site

2 Capability to Switch Natural Gas to Alternative Energy Sources, 2010;" " Level: National and Regional Data;" " Row: NAICS Codes, Value of Shipments and Employment Sizes;" "...

175

" Row: NAICS Codes, Value of Shipments...  

U.S. Energy Information Administration (EIA) Indexed Site

6 Capability to Switch Electricity to Alternative Energy Sources, 2010; " " Level: National and Regional Data;" " Row: NAICS Codes, Value of Shipments and Employment Sizes;" "...

176

Moab Resumes Rail Shipments After Rockslide  

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

MOAB, Utah EMs Moab Uranium Mill Tailings Remedial Action Project recently resumed rail shipments after an almost two-month halt due to a major rockslide.

177

Alternatives for the disposal of NORM (naturally occurring radioactive materials) wastes in Texas  

SciTech Connect

Some of the Texas wastes containing naturally occurring radioactive materials (NORM) have been disposed of in a uranium mill tailings impoundment. There is currently no operating disposal facility in Texas to accept these wastes. As a result, some wastes containing extremely small amounts of radioactivity are sent to elaborate disposal sites at extremely high costs. The Texas Low-Level Radioactive Waste Disposal Authority has sponsored a study to investigate lower cost, alternative disposal methods for certain wastes containing small quantities of NORM. This paper presents the results of a multipathway safety analysis of various scenarios for disposing of wastes containing limited quantities of NORM in Texas. The wastes include pipe scales and sludges from oil and gas production, residues from rare-earth mineral processing, and water treatment resins, but exclude large-volume, diffuse wastes (coal fly ash, phosphogypsum). The purpose of the safety analysis is to define concentration and quantity limits for the key nuclides of NORM that will avoid dangerous radiation exposures under different waste disposal scenarios.

Nielson, K.K.; Rogers, V.C. (Rogers Associates Engineering Corporation, Salt Lake City, UT (USA)); Pollard, C.G. (Texas Low-Level Radioactive Waste Disposal Authority, Austin (USA))

1989-11-01T23:59:59.000Z

178

Radiological Dose Assessment Related to Management of Naturally Occurring Radioactive Materials Generated by the Petroleum Industry  

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

Tebes is affiliated with the University of Illinois. Tebes is affiliated with the University of Illinois. ANL/EAD-2 Radiological Dose Assessment Related to Management of Naturally Occurring Radioactive Materials Generated by the Petroleum Industry by K.P. Smith, D.L. Blunt, G.P. Williams, and C.L. Tebes * Environmental Assessment Division Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 September 1996 Work sponsored by the United States Department of Energy, Office of Policy iii CONTENTS ACKNOWLEDGMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii NOTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . viii ABSTRACT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

179

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

SciTech Connect

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

180

Removing nuclear waste, one shipment at a time  

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

Removing nuclear waste, one shipment at a time Removing nuclear waste, one shipment at a time The Lab's 1,000th shipment of transuranic waste recently left Los Alamos, on its way...

Note: This page contains sample records for the topic "radioactive material shipments" 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

E-Print Network 3.0 - administered radioactive material Sample...  

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

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

182

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

SciTech Connect

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

183

APPLICATION OF POLYURETHANE FOAM FOR IMPACT ABSORPTION AND THERMAL INSULATION FOR GENERAL PURPOSE RADIOACTIVE MATERIALS PACKAGINGS  

SciTech Connect

Polyurethane foam has been employed in impact limiters for large radioactive materials packagings since the early 1980's. Its consistent crush response, controllable structural properties and excellent thermal insulating characteristics have made it attractive as replacement for the widely used cane fiberboard for smaller, drum size packagings. Accordingly, polyurethane foam was chosen for the overpack material for the 9977 and 9978 packagings. The study reported here was undertaken to provide data to support the analyses performed as part of the development of the 9977 and 9978, and compared property values reported in the literature with published property values and test results for foam specimens taken from a prototype 9977 packaging. The study confirmed that, polyurethane foam behaves in a predictable and consistent manner and fully satisfies the functional requirements for impact absorption and thermal insulation.

Smith, A; Glenn Abramczyk, G; Paul Blanton, P; Steve Bellamy, S; William Daugherty, W; Sharon Williamson, S

2009-02-18T23:59:59.000Z

184

GOLDSIM models of long-term radiation impact of conditionally cleared radioactive material  

Science Journals Connector (OSTI)

Abstract Management of waste materials from the decommissioning of nuclear installations offers opportunities for optimization. Large amounts of waste materials with low contents of various radionuclides could be recycled to save financial resources or repository capacity. The increase of the share of recycled materials compared to the current practice could be accomplished by applying the conditional clearance concept. Conditional clearance, as up to now is an unproven theoretical concept, demands utilization of the cleared material for the previously defined purpose (e.g., building construction). Safety studies needed for realization of this practice have to prove that conditionally cleared material will not cause radiation impact exceeding levels prescribed in health and safety regulations. Safety studies assess radiation impact during all manipulations with low level radioactive material (e.g., melting, component manufacturing, building of construction, etc.) as well as its impact on inhabitants living near the construction built using conditionally cleared material. The article is focused on modeling and calculation of long-term radiation impact on inhabitants living near the constructions. Models (scenarios) of various building applications were simulated using GOLDSIM software with Radionuclide Transport Module. Scenarios were selected according to information from the civil engineering business to cover the types of buildings most suitable for application of conditionally cleared material. The results of the calculations showed that conditional clearance represents no significant safety issue in the long-term. Calculated individual effective doses received by inhabitants did not exceed the given dose constraint (10?Sv/year) in case of any scenario evaluated. Detailed and transparent studies of the long-term impact of conditionally cleared materials are important especially for winning of public acceptance.

Michal Panik; Vladimir Necas

2013-01-01T23:59:59.000Z

185

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

SciTech Connect

Six alloys are being considered as possible materials for the fabrication of containers for the disposal of high-level radioactive waste. Three of these candidate materials are copper-based alloys: CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni). The other three are iron- to nickel-based austenitic materials: Types 304L and 316L stainless steels and Alloy 825. Radioactive waste will include spent-fuel assemblies from reactors as well as waste in borosilicate glass and will be sent to the prospective site at Yucca Mountain, Nevada, for disposal. The waste-package containers must maintain substantially complete containment for at least 300 yr and perhaps as long as 1000 yr. During the first 50 yr after emplacement, the containers must be retrievable from the disposal site. Shortly after emplacement of the containers in the repository, they will be exposed to high temperatures and high gamma radiation fields from the decay of high-level waste. This radiation will promote the radiolytic decomposition of moist air to hydrogen. This volume surveys the available data on the effects of hydrogen on the six candidate alloys for fabrication of the containers. For copper, the mechanism of hydrogen embrittlement is discussed, and the effects of hydrogen on the mechanical properties of the copper-based alloys are reviewed. The solubilities and diffusivities of hydrogen are documented for these alloys. For the austenitic materials, the degradation of mechanical properties by hydrogen is documented. The diffusivity and solubility of hydrogen in these alloys are also presented. For the copper-based alloys, the ranking according to resistance to detrimental effects of hydrogen is: CDA 715 (best) > CDA 613 > CDA 102 (worst). For the austenitic alloys, the ranking is: Type 316L stainless steel {approx} Alloy 825 > Type 304L stainless steel (worst). 87 refs., 19 figs., 8 tabs.

Gdowski, G.E.; Bullen, D.B. (Science and Engineering Associates, Inc., Pleasanton, CA (USA))

1988-08-01T23:59:59.000Z

186

The Evolution of U.S. Transportation Regulations for Radioactive Materials?A Retrospective  

SciTech Connect

The discussion in this Chapter is a highly condensed version of the information presented previously in Chapter 52 of the 2nd Edition of the Companion Guide to the ASME Boiler & Pressure Vessel Code.[1] The full text of the previous Chapter 52, i.e., Development of U.S. Regulations for the Transportation of Radioactive Materials - A Look Back over the Past 40 Years, could not be reproduced here. Therefore, this Chapter offers a high-level overview of the information presented previously, including all of the appropriate references. For the most part, the material that was not included in this version of Chapter 52 is available in the public domain. Due to the sheer volume of the information, readers interested in the preamble-only versions of the material referenced in this Chapter are redirected to Reference [1]. Readers interested in the full-text versions of the material referenced in this Chapter are redirected to the appropriate Federal Register and/or U.S. Nuclear Regulatory Commission (NRC) websites. Because some of the material dates back to pre-website times, readers interested in the full-text versions of some of the references may have to rely on the services of their local libraries.

Hafner, R

2008-04-28T23:59:59.000Z

187

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

SciTech Connect

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

188

Lessons Learned from a Regional Approach to Route Selection for Spent Nuclear Fuel Shipments to Yucca Mountain  

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

Midwestern Route Identification Project Midwestern Route Identification Project Sarah K. Wochos Policy Analyst Council of State Governments - Midwest Approach Why Regional? * States need to know the routes as soon as possible * Regions develop and use the criteria that is important to them * States have a better feel for routes that run through their jurisdictions * States felt that EIS routes were a poor starting point for discussions * Regional framework has worked well on other issues Why a Suite of Routes? * Better variety and thus perhaps better security? * Flexibility during construction, bad weather or special events * Inevitable further winnowing through national discussion Methodology Primary Factors - from U.S. DOT's Guidelines for Selecting Preferred Highway Routes for Highway Route Controlled Shipments of Radioactive Materials

189

Ion implantation effects in insulators and the long-term stability of radioactive waste storage materials  

Science Journals Connector (OSTI)

Most insulator materials so far proposed for storing high-level radioactive wastes, such as glass and and the constituent minerals of ceramics are nuclear track detectors. Lead ion implantation experiments show that such materials should be transformed into giant nuclear tracks, when the internal fluence of heavy recoils emitted during the ?-decay of actinide elements stored in them exceeds a critical value, which corresponds to an equivalent storage period of a few thousand years for the wastes expected from a pressurized water reactor. In contrast, actinide bearing minerals are much more stable against ?-recoil damage. As nuclear tracks are extremely chemical reactive, ?-recoil damage is expected to shorten the lifetime of storage materials such as glass and ceramics against dissolution in ground waters. Fortunately new nuclear track concepts are already yielding guidelines for predicting and improving the long-term stability of storage materials. The results of the present studies also bear on the physics of ion implantation phenomena an insulator targets exposed to high fluences of low energy ions.

J.C. Dran; Y. Langevin; M. Maurette; J.C. Petit; B. Vassent

1981-01-01T23:59:59.000Z

190

Background in the context of land contaminated with naturally occurring radioactive material  

Science Journals Connector (OSTI)

The financial implications of choosing a particular threshold for clearance of radioactively contaminated land are substantial, particularly when one considers the volume of naturally occurring radioactive material (NORM) created each year by the production and combustion of fossil fuels and the exploitation of industrial minerals. Inevitably, a compromise needs to be reached between the level of environmental protection sought and the finite resources available for remediation. In the case of natural series radionuclides, any anthropogenic input is always superimposed on the inventory already present in the soil; this 'background' inventory is conventionally disregarded when assessing remediation targets. Unfortunately, the term is not well defined and the concept of 'background dose' is open to alternative interpretations. In this paper, we address the issue of natural background from a geochemical rather than from a solely radiological perspective, illustrating this with an example from the china clay industry. We propose a simple procedure for decision making based on activity concentrations of primordial radionuclides and their progeny. Subsequent calculations of dose need to take into account the mineralogical and chemical characteristics of the contamination, which in the case of NORM are invariably reflected in uranium series disequilibrium.

D Read; G D Read; M C Thorne

2013-01-01T23:59:59.000Z

191

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

SciTech Connect

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

192

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) ...  

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

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) A transuranic (TRU) waste shipment makes its way to the...

193

Study on release and transport of aerial radioactive materials in reprocessing plants  

SciTech Connect

The release and transport characteristics of radioactive materials at a boiling accident of the high active liquid waste (HALW) in a reprocessing plant have been studied for improving experimental data of source terms of the boiling accident. In the study, a heating test and a thermogravimetry and differential thermal analysis (TG-DTA) test were conducted. In the heating test using a simulated HALW, it was found that ruthenium was mainly released into the air in the form of gas and that non-volatile elements were released into the air in the form of mist. In the TG-DTA test, the rate constants and reaction heat of thermal decomposition of ruthenium nitrosyl nitrate were obtained from TG and DTA curves. (authors)

Amano, Y.; Tashiro, S.; Uchiyama, G.; Abe, H.; Yamane, Y.; Yoshida, K. [Japan Atomic Energy Agency, 2-4 Shirane, Shirakata, Tokai-mura, Naka-gun, Ibaraki, 319-1195 (Japan); Kodama, T. [Japan Nuclear Fuel Ltd., 4-108 Okitsuke, Obuchi, Rokkasho-mura, Kamikita-gun, Aomori, 039-3212 (Japan)

2013-07-01T23:59:59.000Z

194

INVESTIGATION OF THE PRESENCE OF DRUGSTORE BEETLES WITHIN CELOTEX ASSEMBLIES IN RADIOACTIVE MATERIAL PACKAGINGS  

SciTech Connect

During normal operations at the Department of Energy's Hanford Site in Hanford, WA, drugstore beetles, (Stegobium paniceum (L.) Coleoptera: Anobiidae), were found within the fiberboard subassemblies of two 9975 Shipping Packages. Initial indications were that the beetles were feeding on the Celotex{trademark} assemblies within the package. Celotex{trademark} fiberboard is used in numerous radioactive material packages serving as both a thermal insulator and an impact absorber for both normal conditions of transport and hypothetical accident conditions. The Department of Energy's Packaging Certification Program (EM-63) directed a thorough investigation to determine if the drugstore beetles were causing damage that would be detrimental to the safety performance of the Celotex{trademark}. The Savannah River National Laboratory is conducting the investigation with entomological expertise provided by Clemson University. The two empty 9975 shipping packages were transferred to the Savannah River National Laboratory in the fall of 2007. This paper will provide details and results of the ongoing investigation.

Loftin, B; Glenn Abramczyk, G

2008-06-04T23:59:59.000Z

195

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

SciTech Connect

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

196

APPLICATION OF POLYURETHANE FOAM FOR IMPACT ABSORPTION AND THERMAL INSULATION FOR RADIOACTIVE MATERIALS PACKAGINGS.  

SciTech Connect

Polyurethane foam has been widely used as an impact absorbing and thermal insulating material for large radioactive materials packages, since the 1980's. With the adoption of the regulatory crush test requirement, for smaller packages, polyurethane foam has been adopted as a replacement for cane fiberboard, because of its ability to withstand the crush test. Polyurethane foam is an engineered material whose composition is much more closely controlled than that of cane fiberboard. In addition, the properties of the foam can be controlled by controlling the density of the foam. The conditions under which the foam is formed, whether confined or unconfined have an affect on foam properties. The study reported here reviewed the application of polyurethane foam in RAM packagings and compared property values reported in the literature with published property values and test results for foam specimens taken from a prototype 9977 packaging. The study confirmed that, polyurethane foam behaves in a predictable and consistent manner and fully satisfies the functional requirements for impact absorption and thermal insulation.

Smith, A; Glenn Abramczyk, G; Paul Blanton, P; Steve Bellamy, S; William Daugherty, W; Sharon Williamson, S

2007-05-15T23:59:59.000Z

197

IMPACT OF TARGET MATERIAL ACTIVATION ON PERSONNEL EXPOSURE AND RADIOACTIVE CONTAMINATION IN THE NATIONAL IGNITION FACILITY  

SciTech Connect

Detailed activation analyses are performed for the different materials under consideration for use in the target capsules and hohlraums used during the ignition campaign on the National Ignition Facility. Results of the target material activation were additionally used to estimate the levels of contamination within the NIF target chamber and the workplace controls necessary for safe operation. The analysis examined the impact of using Be-Cu and Ge-doped CH capsules on the external dose received by workers during maintenance activities. Five days following a 20 MJ shot, dose rates inside the Target Chamber (TC) due to the two proposed capsule materials are small ({approx} 1 {micro}rem/h). Gold and depleted-uranium (DU) are considered as potential hohlraum materials. Following a shot, gold will most probably get deposited on the TC first wall. On the other hand, while noble-gas precursors from the DU are expected to stay in the TC, most of the noble gases are pumped out of the chamber and end up on the cryopumps. The dose rates inside the TC due to activated gold or DU, at 5 days following a 20 MJ shot, are about 1 mrem/h. Dose rates in the vicinity of the cryo-pumps (containing noble 'fission' gases) drop-off to about 1 mrem/h during the first 12 hours following the shot. Contamination from activation of NIF targets will result in the NIF target chamber exceeding DOE surface contamination limits. Objects removed from the TC will need to be managed as radioactive material. However, the results suggest that airborne contamination from resuspension of surface contamination will not be significant and is at levels that can be managed by negative ventilation when accessing the TC attachments.

Khater, H; Epperson, P; Thacker, R; Beale, R; Kohut, T; Brereton, S

2009-06-30T23:59:59.000Z

198

Materials performance in a high-level radioactive waste vitrification system  

SciTech Connect

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

199

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

SciTech Connect

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

200

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

SciTech Connect

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

Note: This page contains sample records for the topic "radioactive material shipments" 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

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. The chamber may be formed by placing a removable extension over the top of the container. The extension communicates with the apparatus so that such vapors are contained within the container, extension and solution feed apparatus. A portion of the chamber includes coolant which condenses the vapors. The resulting condensate is returned to the container by the force of gravity.

Nelson, R.E.; Ziegler, A.A.; Serino, D.F.; Basnar, P.J.

1985-08-30T23:59:59.000Z

202

NR-SRS TRU Waste Shipments Milestone June 4 2013.docx  

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

June 4, 2013 June 4, 2013 Bill Taylor, DOE-SR, (803) 952-8564 bill.taylor@srs.gov DT Townsend, SRNS, (803) 952-7566 Dt-lawrence.townsend@srs.gov Savannah River Site Exceeds Waste Shipment Goals AIKEN, S.C. - During the month of April, the Savannah River Site met two new milestone records towards analyzing, preparing, packaging and shipping radioactive transuranic (TRU) waste bound for a

203

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

SciTech Connect

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

204

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

SciTech Connect

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

205

Microsoft Word - 10000th_shipment.doc  

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

For Immediate Release For Immediate Release The Department of Energy Announces Major Cold War Legacy Waste Cleanup Milestone Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, N.M., September 28, 2011 - The U.S. Department of Energy today announced that the Waste Isolation Pilot Plant (WIPP) received its 10,000th shipment of transuranic (TRU) waste over the weekend. This marks an important milestone in DOE's mission to clean up the country's Cold War legacy. "This accomplishment reflects the hard work and dedication of our workers and contractors," said Energy Secretary Steven Chu. "It also demonstrates the Department's commitment to future generations as we continue our cleanup mission as safely and quickly as possible." The 10,000th shipment, which consisted of defense-generated contact-handled

206

Enhancing Railroad Hazardous Materials Transportation Safety  

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

Railroad Hazardous g Railroad Hazardous g Materials Transportation Safety Kevin R. Blackwell Kevin R. Blackwell Kevin R. Blackwell Kevin R. Blackwell Radioactive Materials Program Manager Radioactive Materials Program Manager H d M t i l Di i i H d M t i l Di i i Hazmat Hazardous Materials Division Hazardous Materials Division Federal Railroad Administration Federal Railroad Administration Presentation for the Presentation for the DOE NTSF Meeting DOE NTSF Meeting May 10 May 10- -12, 2011 12, 2011 Our Regulated Community * More than 550 l d railroads * 170,000 miles of track * 220,000 employees * 1.3 million railcars * 20,000 locomotives Hazmat * 3,500 chemical shippers * Roughly 2 Million Roughly 2 Million annual HM shipments HM-232E Introduction * Notice of Proposed Rulemaking d b * Issued December 21, 2006 * Interim Final Rule

207

Overseas shipments of 48Y cylinders  

SciTech Connect

This paper describes experiences with two incidents of overseas shipments of uranium hexafluoride (UF{sub 6}) cylinders. The first incident involved nine empty UF{sub 6} cylinders in enclosed sea containers. Three UF{sub 6} cylinders broke free from their tie-downs and damaged and contaminated several sea containers. This paper describes briefly how decontamination was carried out. The second incident involved a shipment of 14 full UF{sub 6} cylinders. Although the incident did not cause an accident, the potential hazard was significant. The investigation of the cause of the near accident is recounted. Recommendations to alleviate future similar incidents for both cases are presented.

Tanaka, R.T.; Furlan, A.S. [Cameco Corp., Port Hope, Ontario (Canada)

1991-12-31T23:59:59.000Z

208

First Oak Ridge Remote-Handled Transuranic Waste Shipment Arrives...  

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

First Oak Ridge Remote-Handled Transuranic Waste Shipment Arrives Safely at WIPP First Oak Ridge Remote-Handled Transuranic Waste Shipment Arrives Safely at WIPP March 2, 2009 -...

209

Confidentiality and the Desire for Open Communication in the Transport of Radioactive Material to a National Repository  

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

Confidentiality, Security and Confidentiality, Security and Confidentiality, Security and Confidentiality, Security and the Desire for Open the Desire for Open Communication in the Communication in the Transport of Radioactive Transport of Radioactive Material to a National Material to a National Repository Repository A presentation to the A presentation to the DOE Transportation External Coordination (TEC) DOE Transportation External Coordination (TEC) Working Group Meeting Working Group Meeting Albuquerque, NM Albuquerque, NM 21 21 - - 23 April 2004 23 April 2004 Ronald B. Pope Consultant April 2004 April 2004 Confidentiality Confidentiality - - TEC Working TEC Working Group Group - - Albuquerque Albuquerque 2 2 Objectives Objectives Address and prompt TEC discussion on issues Address and prompt TEC discussion on issues

210

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

SciTech Connect

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

211

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

212

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

SciTech Connect

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

213

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

SciTech Connect

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

214

Benchmark studies of induced radioactivity produced in LHC materials, part II: remanent dose rates  

Science Journals Connector (OSTI)

......production of radioactive isotopes as well as their decay...carbon composites, boron nitride, aluminium...step (calculation of isotopes), the FLUKA implementation...benchmark(6,7). Isotope information was written...uncertainty for the determination of the effective centre......

M. Brugger; H. Khater; S. Mayer; A. Prinz; S. Roesler; L. Ulrici; H. Vincke

2005-12-20T23:59:59.000Z

215

STATEMENT OF TRAINING AND EXPERIENCE (Radioactive Material User) Print Name: _______________________________________________ Permit Supervisor: ___________________________________  

E-Print Network (OSTI)

and Practices of Radiation Protection [ ] YES [ ] NO Radioactivity measurement, monitoring techniques [ ] STAFF [ ] GRADUATE STUDENT [ ] POST DOC [ ] UNDERGRADUATE STUDENT I plan to use (check all that apply. [Radiation Safety Courses at other institutions and lectures on the topics as part of college level

Firestone, Jeremy

216

Microsoft Word - ORNL_first_shipment  

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

WIPP Receives First Shipment From Oak Ridge National Laboratory CARLSBAD, N.M., September 25, 2008 - Oak Ridge National Laboratory (ORNL) in Tennessee has become the latest site to ship defense-related transuranic waste directly to the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP). A truck with three loaded TRUPACT-II shipping containers departed ORNL yesterday and arrived at WIPP this morning - the 6,894th safe shipment to WIPP since the project opened in 1999. "Safe, responsible cleanup is the bottom line," said DOE Carlsbad Field Office Manager Dr. Dave Moody. "While we make steady progress every day at WIPP, it is milestones like this that highlight the overall success of the DOE clean-up effort. I applaud

217

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

SciTech Connect

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

218

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

SciTech Connect

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

219

RADIOACTIVE MATERIAL SHIPPING PACKAGINGS AND METAL TO METAL SEALS FOUND IN THE CLOSURES OF CONTAINMENT VESSELS INCORPORATING CONE SEAL CLOSURES  

SciTech Connect

The containment vessels for the Model 9975 radioactive material shipping packaging employ a cone-seal closure. The possibility of a metal-to-metal seal forming between the mating conical surfaces, independent of the elastomer seals, has been raised. It was postulated that such an occurrence would compromise the containment vessel hydrostatic and leakage tests. The possibility of formation of such a seal has been investigated by testing and by structural and statistical analyses. The results of the testing and the statistical analysis demonstrate and procedural changes ensure that hydrostatic proof and annual leakage testing can be accomplished to the appropriate standards.

Loftin, B; Glenn Abramczyk, G; Allen Smith, A

2007-06-06T23:59:59.000Z

220

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

Note: This page contains sample records for the topic "radioactive material shipments" 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

Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste  

SciTech Connect

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation.

NONE

1994-12-31T23:59:59.000Z

222

Removing nuclear waste, one shipment at a time  

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

Stories » Stories » Removing nuclear waste, one shipment at a time Removing nuclear waste, one shipment at a time The Lab's 1,000th shipment of transuranic waste recently left Los Alamos, on its way to a permanent repository near Carlsbad, NM. June 26, 2012 Governor Martinez applauding the 1014th TRU waste shipment New Mexico Governor Susana Martinez and other dignitaries applaud as the 1,014th shipment of transuranic waste leaves Los Alamos National Laboratory. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email "The milestone we're celebrating is one that has been a long-term environmental commitment." Removing nuclear waste, one shipment at a time Elected officials and other dignitaries recently gathered at Los Alamos

223

Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility |  

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

Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility Final Hanford Offsite Waste Shipment Leaves Idaho Treatment Facility August 18, 2011 - 12:00pm Addthis Idaho State Patrol Troopers Rick Stouse and Tony Anderson inspected the TRUPACTS, containers which contain TRU waste, and trailer containing the final shipment of Hanford offsite waste. The Idaho State Patrol officers have played an important role in AMWTP's success by inspecting every one of AMWTP's nearly 3,900 shipments. Idaho State Patrol Troopers Rick Stouse and Tony Anderson inspected the TRUPACTS, containers which contain TRU waste, and trailer containing the final shipment of Hanford offsite waste. The Idaho State Patrol officers have played an important role in AMWTP's success by inspecting every one of

224

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

SciTech Connect

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

225

Level: National and Regional Data; Row: Values of Shipments and...  

Gasoline and Diesel Fuel Update (EIA)

Level: National and Regional Data; Row: Values of Shipments and Employment Sizes; Column: Energy-Consumption Ratios; Unit: Varies. Consumption Consumption per Dollar Consumption...

226

Level: National and Regional Data; Row: Values of Shipments and...  

U.S. Energy Information Administration (EIA) Indexed Site

2 Electricity: Components of Net Demand, 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes; Column: Electricity Components; Unit: Million...

227

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

228

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

SciTech Connect

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

229

WIPP Receives First Shipment | National Nuclear Security Administration  

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

WIPP Receives First Shipment | National Nuclear Security Administration WIPP Receives First Shipment | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > WIPP Receives First Shipment WIPP Receives First Shipment March 26, 1999 Carlsbad, NM WIPP Receives First Shipment After more than two decades of political, legal, and bureaucratic delays,

230

Portsmouth, Paducah Project Leaps Past Shipment Milestone, Delivering  

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

Portsmouth, Paducah Project Leaps Past Shipment Milestone, Portsmouth, Paducah Project Leaps Past Shipment Milestone, Delivering Economic Benefit to U.S. Portsmouth, Paducah Project Leaps Past Shipment Milestone, Delivering Economic Benefit to U.S. September 1, 2012 - 12:00pm Addthis Pictured here are railcars carrying tanks of hydrofluoric acid for shipment from the Portsmouth site to Solvay Fluorides for industrial use. Pictured here are railcars carrying tanks of hydrofluoric acid for shipment from the Portsmouth site to Solvay Fluorides for industrial use. LEXINGTON, Ky. - The company that operates DOE's depleted uranium hexafluoride (DUF6) conversion facilities marked a milestone in September when it shipped the one millionth gallon of hydrofluoric acid. Babcock & Wilcox Conversion Services (BWCS) continues to deliver more of

231

Thermal Analysis and Test Results for the Overpack of a Typical Radioactive Materials Package  

SciTech Connect

In the course of the development and certification of the 9975 Package, extensive thermal analyses were performed and the package subjected to the regulatory HAC thermal test. The results of the thermal analysis and materials tests of the cane fiberboard overpack material were evaluated in comparison with the package HAC thermal test results. The evaluation confirmed that the thermal analysis correctly predicted the performance of the 9975 in the HAC fire test. The post test examination revealed that the heat affected region of the Celotex(R) overpack correlated well with the calculated temperature distribution

Smith, A.C.

2003-05-06T23:59:59.000Z

232

Assuring Access to Low-Level Radioactive Waste Disposal Facilities for Non-DOE Users of Radioactive Materials: Solutions -Outside the Box  

SciTech Connect

This paper proposes both near-term and long-term solutions for disposal of low-level radioactive waste (LLRW) Classes B and C generated by non-DOE organizations in thirty-six states that will lose access to the Barnwell, SC disposal facility on July 1, 2008. The solutions proposed here call for the federal government, specifically the US Department of Energy (DOE), to play a key role and are outside the existing interstate compact framework established by the Low-Level Radioactive Waste Policy Act of 1980 (amended in 1985) and subsequent state ratification and Congressional consent statutes. (authors)

Pasternak, A.D. [Ph.D. California Radioactive Materials Management Forum, Lafayette, CA (United States)

2008-07-01T23:59:59.000Z

233

Application of a passive electrochemical noise technique to localized corrosion of candidate radioactive waste container materials  

SciTech Connect

One of the key engineered barriers in the design of the proposed Yucca Mountain repository is the waste canister that encapsulates the spent fuel elements. Current candidate metals for the canisters to be emplaced at Yucca Mountain include cast iron, carbon steel, Incoloy 825 and titanium code-12. This project was designed to evaluate passive electrochemical noise techniques for measuring pitting and corrosion characteristics of candidate materials under prototypical repository conditions. Experimental techniques were also developed and optimized for measurements in a radiation environment. These techniques provide a new method for understanding material response to environmental effects (i.e., gamma radiation, temperature, solution chemistry) through the measurement of electrochemical noise generated during the corrosion of the metal surface. In addition, because of the passive nature of the measurement the technique could offer a means of in-situ monitoring of barrier performance.

Korzan, M.A.

1994-05-01T23:59:59.000Z

234

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

SciTech Connect

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

235

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

SciTech Connect

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

236

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

SciTech Connect

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

237

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

SciTech Connect

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

238

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

239

Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range  

SciTech Connect

A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products.

NONE

1997-06-01T23:59:59.000Z

240

Los Alamos National Laboratory Accelerates Transuranic Waste Shipments:  

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

Los Alamos National Laboratory Accelerates Transuranic Waste Los Alamos National Laboratory Accelerates Transuranic Waste Shipments: Spurred by a major wildfire in 2011, Los Alamos National Laboratory's TRU Waste Program accelerates shipments of transuranic waste stored aboveground to the Waste Isolation Pilot Plan Los Alamos National Laboratory Accelerates Transuranic Waste Shipments: Spurred by a major wildfire in 2011, Los Alamos National Laboratory's TRU Waste Program accelerates shipments of transuranic waste stored aboveground to the Waste Isolation Pilot Plan July 2, 2012 - 12:00pm Addthis New Mexico Governor Susana Martinez greets Terry Aguilar, governor of San Ildefonso Pueblo, while Frank Marcinowski (lower right), EM deputy assistant secretary of waste management, and Dan Cox, LANL associate deputy director for environmental affairs, look on.

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


241

Naval Spent Fuel Rail Shipment Accident Exercise Objectives  

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

NAVAL SPENT FUEL RAIL SHIPMENT NAVAL SPENT FUEL RAIL SHIPMENT ACCIDENT EXERCISE OBJECTIVES * Familiarize stakeholders with the Naval spent fuel ACCIDENT EXERCISE OBJECTIVES Familiarize stakeholders with the Naval spent fuel shipping container characteristics and shipping practices * Gain understanding of how the NNPP escorts who accompany the spent fuel shipments will interact with civilian emergency services representatives g y p * Allow civilian emergency services agencies the opportunity to evaluate their response to a pp y p simulated accident * Gain understanding of how the communications links that would be activated in an accident involving a Naval spent fuel shipment would work 1 NTSF May 11 ACCIDENT EXERCISE TYPICAL TIMELINE * Conceptual/Organizational Meeting - April 6 E R T i d it t t d TYPICAL TIMELINE

242

Microsoft Word - INL Waste Stream Cleared for Shipment to WIPP...  

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

2006 - The U.S. Department of Energy (DOE) has authorized the Idaho National Laboratory (INL) to restart shipments from the waste stream that was suspended from transport to the...

243

Milestone Shipment Arrives at WIPP | Department of Energy  

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

WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs DOE Completes TRU Waste Cleanup at Bettis DOE Completes Disposal Operations In Panel 5 of the WIPP Underground...

244

Microsoft Word - First LANL Shipment Arrives at WCS  

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

NWP Media Contacts: Donavan Mager Nuclear Waste Partnership LLC (575) 234-7586 www.wipp.energy.gov For Immediate Release First LANL Shipment Arrives at Waste Control Specialists...

245

Estimating carbon emissions from less-than-truckload (LTL) shipments  

E-Print Network (OSTI)

Less-than-truckload (LTL) is a $32-billion sector of the trucking industry that focuses on moving smaller shipments, typically with weights between 100 and 10,000 pounds, that do not require a full trailer to be moved. ...

Veloso de Aguiar, Guilherme

2014-01-01T23:59:59.000Z

246

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

SciTech Connect

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

247

Results of the European Commission Marina II Study Part IIeffects of discharges of naturally occurring radioactive material  

Science Journals Connector (OSTI)

Enhanced levels of naturally occurring radioactive materials (NORM) are produced through various industrial operations and may lead to discharges to the marine environment. A recent study, called MARINA II, carried out for the European Commission considered discharges of radionuclides from the NORM industries to north European marine waters and their consequences. There are two main sources that were considered in the study. The use of phosphogypsum during the production of phosphoric acid by the fertiliser industry and the pumping of oil and gas from the continental shelf in the North Sea which produces large quantities of water contaminated with enhanced levels of naturally occurring radionuclides. Discharges of alpha emitting radionuclides from these two industries have contributed significantly to the total input of alpha emitters to north European waters over the period 19812000 (data were not available prior to 1981). Discharges due to the use of phosphogypsum have declined since the early 1990s and are now very low. Discharges from the oil and gas industries stabilised in the second half of the 1990s and are now the major contributor to alpha discharges to the region. As most European countries do not report discharges of radioactivity with the water produced during extraction, there is considerable uncertainty in the discharges used in the study. The impact of the discharges has been estimated both in terms of the effect on non-human biota and the radiological impact for people. In the 1980s the radiation dose rates to marine biota in the region around a phosphate plant on the north-west coast of England were as high due to the discharges from the phosphate plant as those near to the Sellafield reprocessing plant due to its discharges. In recent years the additional dose to marine biota in this region due to the past NORM discharges is of the same order of magnitude as the natural background. The collective dose rate was estimated to determine the radiological impact on people. The peak collective dose rate from the NORM industries occurred in 1984 and was just over 600 manSv y?1. The collective dose rate fell with time as discharges from the phosphate industry reduced and was estimated as under 200 manSv y?1 in 2000.

M. Betti; L. Aldave de las Heras; A. Janssens; E. Henrich; G. Hunter; M. Gerchikov; M. Dutton; A.W. van Weers; S. Nielsen; J. Simmonds; A. Bexon; T. Sazykina

2004-01-01T23:59:59.000Z

248

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

249

REEVALUATION OF WATERBORNE RELEASES OF RADIOACTIVE MATERIALS FROM THE MAYAK PRODUCTION ASSOCIATION INTO THE TECHA RIVER IN 1949-1951  

SciTech Connect

The Mayak Production Association was the first site for the production of weapon-grade plutonium in Russia. Early operations led to the waterborne release of large amounts of radioactive materials into the small Techa River. Residents living downstream used river water for drinking and other purposes. The releases and subsequent flooding resulted in the deposition of sediments along the shoreline and on floodplain soil. Primary routes of exposure were external dose from the deposited sediments and the ingestion of 90Sr and other radionuclides. Study of the Techa River Cohort has revealed an increased incidence of leukemia and solid cancers. These epidemiologic studies are supported by extensive dose-reconstruction activities that have led to the creation of various versions of a Techa River Dosimetry System (TRDS). The correctness of the TRDS has been challenged by the allegation that releases of short-lived radionuclides were much larger than those used in the TRDS. Although the dosimetry system depends more upon the measurements of 90Sr in humans and additional measurements of radionuclides and of exposure rates in the environment, a major activity has been undertaken to define more precisely the time-dependent rates of release and radionuclide composition of the releases. The major releases occurred during 1950-1951. In addition to routine releases major accidental releases occurred. The re-evaluated amount of total release is 114 PBq, about half of which was from accidents that occurred in late 1951. The composition of the radionuclides released has also been re-evaluated; this composition changed with time.

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

2012-01-01T23:59:59.000Z

250

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

SciTech Connect

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

251

Proposal for Qualification of Gas-Generating Radioactive Payloads for Transportation within a Type B Package  

SciTech Connect

Characterization data describing radioactive materials (RAM) in storage are likely those associated with the processes that produced the materials or with the mission for which they were produced. Along with impurity data, often absent or unknown as a result of post-processing storage environment is moisture content. Radiolysis of moisture may lead to a hydrogen flammability hazard within a closed volume such as a storage can or a transportation package. This paper offers a practical means of qualifying payloads of unknown moisture content for shipment within Type B packaging, while supporting the DOE program to maintain radworker dose as low as reasonable achievable (ALARA). Specifically, the paper discusses part of a qualification program carried out at the Savannah River Site for onsite shipment of legacy RAM within the DDF-1 package. The DDF-1 is an onsite-only prototype of the currently certified 9975 package. Measurement of storage-can lid bulge can provide an upper bound for pressure within a storage can. Subsequent belljar testing can measure the rate of gas leakage from a storage can. These actions are shown sufficient to ensure that the performance of the 9975 containment vessels can accommodate the deflagration energy from flammable gas mixtures within Normal Conditions of Transport, and, and the consequences of a detonation shock wave within Hypothetical Accident Conditions.

Houghtaling, T.K.

2002-06-07T23:59:59.000Z

252

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

253

National Transportation Stakeholders Forum (NTSF) | Department...  

Energy Savers (EERE)

at a national level with states and tribes about the Department's shipments of radioactive waste and materials, as well as occasional high-visibility shipments that are...

254

Applying Risk Communication to the Transportation of Radioactive...  

Office of Environmental Management (EM)

Applying Risk Communication to the Transportation of Radioactive Materials Applying Risk Communication to the Transportation of Radioactive Materials Participants should expect to...

255

DOE Seeks Trucking Services for Transuranic Waste Shipments | Department of  

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

Trucking Services for Transuranic Waste Shipments Trucking Services for Transuranic Waste Shipments DOE Seeks Trucking Services for Transuranic Waste Shipments March 30, 2011 - 12:00pm Addthis Media Contact Bill Taylor 513-246-0539 william.taylor@emcbc.doe.gov Cincinnati -- The Department of Energy (DOE) today will issue a Request for Proposals for the continuation of carrier services to transport transuranic waste (TRU) between DOE sites and the Waste Isolation Pilot Plant (WIPP) site, near Carlsbad, New Mexico. The transportation of TRU waste is accomplished by contracted trucking carriers that ship the waste via public highways on custom designed trailers. The contract will be an Indefinite Delivery/ Indefinite Quantity (ID/IQ) contract using firm-fixed- price delivery task orders. The estimated contract cost is $80-$100 million over a five-year contract

256

Stability of Appalachian coal shipments under policy variation  

SciTech Connect

A quadratic programming transportation model and a nonparametric statistical procedure are used to investigate how Appalachian coal-supply flows vary in response to changes in national coal markets and policies, with emphasis on the relative stability of traditional flows. The results show that the relative stability of coal shipments is preserved under small and moderate random shocks, suggesting that coal-shipment patterns remain relatively stable despite changes in the absolute level. The tendency for traditional routes to continue has occurred because of the region's access to transportation networks and its low fixed mining costs. Environmental restriction could change shipment patterns by terminating coal production in some regions. Some areas of instability may require freight subsidies. Increased taxes or changes in mining capital or generating costs could also alter the pattern. Policies to stabilize freight rates and production costs are indicated. 10 references, 8 tables.

Yang, C.W. (Clarion State Coll., PA); Labys, W.C.

1981-07-01T23:59:59.000Z

257

Pipe overpack container for trasuranic waste storage and shipment  

DOE Patents (OSTI)

A Pipe Overpack Container for transuranic waste storage and shipment. The system consists of a vented pipe component which is positioned in a vented, insulated 55 gallon steel drum. Both the vented pipe component and the insulated drum are capable of being secured to prevent the contents from leaving the vessel. The vented pipe component is constructed of 1/4 inch stainless steel to provide radiation shielding. Thus, allowing shipment having high Americium-241 content. Several Pipe Overpack Containers are then positioned in a type B, Nuclear Regulatory Commission (NRC) approved, container. In the current embodiment, a TRUPACT-II container was employed and a maximum of fourteen Pipe Overpack Containers were placed in the TRUPACT-II. The combination received NRC approval for the shipment and storage of transuranic waste.

Geinitz, Richard R. (Arvada, CO); Thorp, Donald T. (Broomfield, CO); Rivera, Michael A. (Boulder, CO)

1999-01-01T23:59:59.000Z

258

Waste Shipment Tracking Technology Lowers Costs, Increases Efficiency |  

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

Shipment Tracking Technology Lowers Costs, Increases Shipment Tracking Technology Lowers Costs, Increases Efficiency Waste Shipment Tracking Technology Lowers Costs, Increases Efficiency February 27, 2013 - 12:00pm Addthis This graphic shows how the radiofrequency identification technology tracks and monitors packages in transport, in-transit stops and storage. This graphic shows how the radiofrequency identification technology tracks and monitors packages in transport, in-transit stops and storage. The technology developed by EM’s Office of Packaging and Transportation Packaging Certification Program technology development team was selected by the RFID Journal as the "Most Innovated Use of RFIDs.” Team members pictured here include Dr. John Lee, Dr. Yung Liu, Dr. Jim Shuler, Dr. Hanchung Tsai and John Anderson. Team members not pictured are Brian Craig and Dr. Kun Chen.

259

SR-08-03 _LEU Shipments_.doc  

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

DOE Media CONTACTS: For Immediate Release DOE Media CONTACTS: For Immediate Release Jim Giusti, (803) 952-7697 October, 2, 2008 james-r.giusti@srs.gov DOE's Savannah River Site Fulfills Uranium Shipment Contract with TVA Aiken, SC - The U.S. Department of Energy's (DOE) Savannah River Site (SRS) this week safely sent its final shipment of Cold War era uranium to the Tennessee Valley Authority (TVA), marking a significant step toward achieving the Department's goal of safely cleaning up the Site.

260

Level: National Data; Row: Values of Shipments within NAICS Codes;  

Gasoline and Diesel Fuel Update (EIA)

3 Consumption Ratios of Fuel, 2010; 3 Consumption Ratios of Fuel, 2010; Level: National Data; Row: Values of Shipments within NAICS Codes; Column: Energy-Consumption Ratios; Unit: Varies. Consumption Consumption per Dollar Consumption per Dollar of Value NAICS per Employee of Value Added of Shipments Code(a) Economic Characteristic(b) (million Btu) (thousand Btu) (thousand Btu) Total United States 311 - 339 ALL MANUFACTURING INDUSTRIES Value of Shipments and Receipts (million dollars) Under 20 405.4 4.0 2.1 20-49 631.3 4.7 2.2 50-99 832.0 4.9 2.3 100-249 1,313.4 6.2 2.8 250-499 1,905.2 7.4 3.6 500 and Over 4,225.4 7.5 3.1 Total 1,449.6 6.4 2.8 311 FOOD Value of Shipments and Receipts (million dollars) Under 20 576.6 5.9

Note: This page contains sample records for the topic "radioactive material shipments" 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

Level: National Data; Row: Values of Shipments within NAICS Codes;  

U.S. Energy Information Administration (EIA) Indexed Site

3 Consumption Ratios of Fuel, 2006; 3 Consumption Ratios of Fuel, 2006; Level: National Data; Row: Values of Shipments within NAICS Codes; Column: Energy-Consumption Ratios; Unit: Varies. Consumption Consumption per Dollar Consumption per Dollar of Value NAICS per Employee of Value Added of Shipments Code(a) Economic Characteristic(b) (million Btu) (thousand Btu) (thousand Btu) Total United States 311 - 339 ALL MANUFACTURING INDUSTRIES Value of Shipments and Receipts (million dollars) Under 20 330.6 3.6 2.0 20-49 550.0 4.5 2.2 50-99 830.1 5.9 2.7 100-249 1,130.0 6.7 3.1 250-499 1,961.4 7.6 3.6 500 and Over 3,861.9 9.0 3.6 Total 1,278.4 6.9 3.1 311 FOOD Value of Shipments and Receipts (million dollars) Under 20 979.3 10.3

262

WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs |  

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

First Remote-Handled Waste Shipment From Sandia Labs First Remote-Handled Waste Shipment From Sandia Labs WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs December 21, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. - The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) has received the first of eight planned defense-related remote-handled transuranic (RH-TRU) waste shipments from Sandia National Laboratories (SNL) in Albuquerque. The shipment arrived December 16 for permanent disposal in WIPP's underground repository. DOE National TRU Program Director J.R. Stroble said the shipment is significant to WIPP. "Our goal is to reduce the nation's nuclear waste footprint and we routinely receive shipments from around the country,"

263

Naturally occurring radioactive material (NORM V): proceedings of an international symposium, Seville, Spain, 1922 March 2007  

Science Journals Connector (OSTI)

......their decay chain members in rare earth minerals is often enough...occupational exposure during rare earth production gives rise...variety of monazite mining and rare earth recovery industries...environmental weathering of stacked phosphogypsum waste materials, with observed......

William E. Kennedy; Jr.

2010-03-01T23:59:59.000Z

264

10,000th Waste Shipment Milestone is All in the Family | Department of  

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

10,000th Waste Shipment Milestone is All in the Family 10,000th Waste Shipment Milestone is All in the Family 10,000th Waste Shipment Milestone is All in the Family August 29, 2011 - 12:00pm Addthis A Waste Isolation Pilot Plant facility shift manager inspects the shipping manifest of the 10,000th safe shipment to roll through the gates at the Department of Energy’s Waste Isolation Pilot Plant on Sept. 24, 2011. A Waste Isolation Pilot Plant facility shift manager inspects the shipping manifest of the 10,000th safe shipment to roll through the gates at the Department of Energy's Waste Isolation Pilot Plant on Sept. 24, 2011. Idaho's Advanced Mixed Waste Treatment Project employees prepare to send the 10,000th shipment to the Waste Isolation Pilot Plant. Idaho's Advanced Mixed Waste Treatment Project employees prepare to send

265

WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs  

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

For immediate release WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs CARLSBAD, N.M., December 21, 2011 - The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) has received the first of eight planned defense-related remote- handled transuranic (RH-TRU) waste shipments from Sandia National Laboratories (SNL) in Albuquerque. The shipment arrived December 16 for permanent disposal in WIPP's underground repository. DOE National TRU Program Director J.R. Stroble said the shipment is significant to WIPP. "Our goal is to reduce the nation's nuclear waste footprint and we routinely receive shipments from around the country," said Stroble. "This first shipment of RH-TRU waste from

266

JOINT UNITED STATES/IAEA PROPOSED APPROACH FOR SAFEGUARDS DURING PLUTONIUM STABILIZATION, PACKAGING, AND SHIPMENT  

SciTech Connect

For safety reasons, the U.S. Department of Energy (DOE) is preparing to stabilize and package plutonium oxide currently subject to International Atomic Energy Agency safeguards at the Rocky Flats Environmental Technology Site (RFETS) beginning in the year 2001. The Hanford Site will also stabilize and package plutonium materials under IAEA safeguards. The U.S. and the IAEA began consultations in late 1996 to develop an approach to the application of safeguards during stabilization and packaging. With the plans to ship RFETS plutonium to Savannah River for interim storage prior to final disposition, this work has been extended to include safeguards during shipment. This paper will discuss the elements of a joint U.S./IAEA proposal for this task.

L. KWEI; B. SMITH; ET AL

2001-02-01T23:59:59.000Z

267

E-Print Network 3.0 - atms tracking shipments Sample Search Results  

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

in which the tuna were caught; (3) listing the numbers for the associated Tuna Tracking Forms which contain... to document U.S. domestic landings and shipments of...

268

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.

269

" Row: Selected SIC Codes; Column: Energy Sources and Shipments;"  

U.S. Energy Information Administration (EIA) Indexed Site

2. First Use of Energy for All Purposes (Fuel and Nonfuel), 1998;" 2. First Use of Energy for All Purposes (Fuel and Nonfuel), 1998;" " Level: National Data; " " Row: Selected SIC Codes; Column: Energy Sources and Shipments;" " Unit: Trillion Btu." " "," "," "," "," "," "," "," "," "," "," ",," " " "," "," ",," "," ",," "," ",," ","Shipments","RSE" "SIC"," ",,"Net","Residual","Distillate",,"LPG and",,"Coke and"," ","of Energy Sources","Row"

270

" Row: Selected SIC Codes; Column: Energy Sources and Shipments;"  

U.S. Energy Information Administration (EIA) Indexed Site

1. First Use of Energy for All Purposes (Fuel and Nonfuel), 1998;" 1. First Use of Energy for All Purposes (Fuel and Nonfuel), 1998;" " Level: National Data; " " Row: Selected SIC Codes; Column: Energy Sources and Shipments;" " Unit: Physical Units or Btu." " "," "," "," "," "," "," "," "," "," "," ",," " " "," "," ",," "," ",," "," ","Coke and"," ","Shipments"," " " "," ",,"Net","Residual","Distillate","Natural Gas(e)","LPG and","Coal","Breeze"," ","of Energy Sources","RSE"

271

Enhancing Railroad Hazardous Materials Transportation Safety...  

Office of Environmental Management (EM)

Enhancing Railroad Hazardous Materials Transportation Safety Enhancing Railroad Hazardous Materials Transportation Safety Presented by Kevin R. Blackwell, Radioactive Materials...

272

First TRUPACT-III Shipment Arrives Safely at the Waste Isolation Pilot  

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

TRUPACT-III Shipment Arrives Safely at the Waste Isolation TRUPACT-III Shipment Arrives Safely at the Waste Isolation Pilot Plant First TRUPACT-III Shipment Arrives Safely at the Waste Isolation Pilot Plant August 29, 2011 - 12:00pm Addthis Media Contact Lauren Milone lauren.milone@em.doe.gov 301-903-3731 Washington, D.C. - The U.S. Department of Energy (DOE) announced today that the first shipment of transuranic waste using the newly approved shipping package known as the TRUPACT-III safely arrived at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The shipment, which originated at the Savannah River Site (SRS) in South Carolina, arrived at WIPP on August 25. The new shipping package - the Transuranic Package Transporter Model 3 or TRUPACT-III - allows the Department to package and ship large-sized transuranic waste in a single box that would otherwise

273

First TRUPACT-III Shipment Arrives Safely at the Waste Isolation Pilot  

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

First TRUPACT-III Shipment Arrives Safely at the Waste Isolation First TRUPACT-III Shipment Arrives Safely at the Waste Isolation Pilot Plant First TRUPACT-III Shipment Arrives Safely at the Waste Isolation Pilot Plant August 29, 2011 - 12:00pm Addthis Media Contact Lauren Milone lauren.milone@em.doe.gov 301-903-3731 Washington, D.C. - The U.S. Department of Energy (DOE) announced today that the first shipment of transuranic waste using the newly approved shipping package known as the TRUPACT-III safely arrived at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The shipment, which originated at the Savannah River Site (SRS) in South Carolina, arrived at WIPP on August 25. The new shipping package - the Transuranic Package Transporter Model 3 or TRUPACT-III - allows the Department to package and ship large-sized transuranic waste in a single box that would otherwise

274

Upcoming Pipeline Capacity Additions Will Facilitate Continued Growth in Crude Oil Shipments from Midwest to Gulf Coast  

Reports and Publications (EIA)

Upcoming Pipeline Capacity Additions Will Facilitate Continued Growth in Crude Oil Shipments from Midwest to Gulf Coast

2013-01-01T23:59:59.000Z

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

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

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

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) | Department of  

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

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) A transuranic (TRU) waste shipment makes its way to the Waste Isolation Pilot Plant in Carlsbad, N.M. A transuranic (TRU) waste shipment makes its way to the Waste Isolation Pilot Plant in Carlsbad, N.M. On February 17, 2011, DOE issued the Draft Environmental Impact Statement (EIS) for the Disposal of Greater-Than-Class C (GTCC) Low-Level Radioactive Waste (LLRW) and GTCC-Like Waste (Draft EIS, DOE/EIS-0375D) for public review and comment. DOE is inviting public comments on this Draft EIS during a 120-day public comment period, from the date of publication of the EIS's Notice of Availability in the Federal Register. During the comment

278

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

SciTech Connect

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

279

Accident analysis of railway transportation of low-level radioactive and hazardous chemical wastes: Application of the /open quotes/Maximum Credible Accident/close quotes/ concept  

SciTech Connect

The maximum credible accident (MCA) approach to accident analysis places an upper bound on the potential adverse effects of a proposed action by using conservative but simplifying assumptions. It is often used when data are lacking to support a more realistic scenario or when MCA calculations result in acceptable consequences. The MCA approach can also be combined with realistic scenarios to assess potential adverse effects. This report presents a guide for the preparation of transportation accident analyses based on the use of the MCA concept. Rail transportation of contaminated wastes is used as an example. The example is the analysis of the environmental impact of the potential derailment of a train transporting a large shipment of wastes. The shipment is assumed to be contaminated with polychlorinated biphenyls and low-level radioactivities of uranium and technetium. The train is assumed to plunge into a river used as a source of drinking water. The conclusions from the example accident analysis are based on the calculation of the number of foreseeable premature cancer deaths the might result as a consequence of this accident. These calculations are presented, and the reference material forming the basis for all assumptions and calculations is also provided.

Ricci, E.; McLean, R.B.

1988-09-01T23:59:59.000Z

280

Uranium Compounds and Other Natural Radioactivities  

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

radioactive materials and global fallout as it exists in the environment (such as from testing of nuclear explosive devices.) However, any action that has been taken to separate...

Note: This page contains sample records for the topic "radioactive material shipments" 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

Stakeholder Transportation Scorecard: Reviewing Nevada's Recommendations for Enhancing the Safety and Security of Nuclear Waste Shipments - 13518  

SciTech Connect

As a primary stakeholder in the Yucca Mountain program, the state of Nevada has spent three decades examining and considering national policy regarding spent nuclear fuel and high-level radioactive waste transportation. During this time, Nevada has identified 10 issues it believes are critical to ensuring the safety and security of any spent nuclear fuel transportation program, and achieving public acceptance. These recommendations are: 1) Ship the oldest fuel first; 2) Ship mostly by rail; 3) Use dual-purpose (transportable storage) casks; 4) Use dedicated trains for rail shipments; 5) Implement a full-scale cask testing program; 6) Utilize a National Environmental Policy Act (NEPA) process for the selection of a new rail spur to the proposed repository site; 7) Implement the Western Interstate Energy Board (WIEB) 'straw man' process for route selection; 8) Implement Section 180C assistance to affected States, Tribes and localities through rulemaking; 9) Adopt safety and security regulatory enhancements proposed states; and 10) Address stakeholder concerns about terrorism and sabotage. This paper describes Nevada's proposals in detail and examines their current status. The paper describes the various forums and methods by which Nevada has presented its arguments and sought to influence national policy. As of 2012, most of Nevada's recommendations have been adopted in one form or another, although not yet implemented. If implemented in a future nuclear waste program, the State of Nevada believes these recommendations would form the basis for a successful national transportation plan for shipments to a geologic repository and/or centralized interim storage facility. (authors)

Dilger, Fred C. [Black Mountain Research, Henderson, NV 81012 (United States)] [Black Mountain Research, Henderson, NV 81012 (United States); Ballard, James D. [Department of Sociology, California State University, Northridge, CA 91330 (United States)] [Department of Sociology, California State University, Northridge, CA 91330 (United States); Halstead, Robert J. [State of Nevada Agency for Nuclear Projects, Carson City, NV 80906 (United States)] [State of Nevada Agency for Nuclear Projects, Carson City, NV 80906 (United States)

2013-07-01T23:59:59.000Z

282

Proposed risk evaluation guidelines for use by the DOE-AL Nuclear Explosive Safety Division in evaluating proposed shipments of nuclear components  

SciTech Connect

The licensing requirements of 10 CFR 71 (US Code of Federal Regulations) are the primary criteria used to license proposed US Department of Energy (DOE) shipments of nuclear components. However, if a shipment cannot meet 10 CFR 71 requirements, a Transportation System Risk Assessment (TSRA) is prepared to document: (1) the degree of compliance of proposed DOE shipments of nuclear components with applicable federal regulations, and (2) the risk associated with the proposed shipments. The Nuclear Explosive Safety Division (NESD) of the Department of Energy, Albuquerque Area Office (DOE-AL) is responsible for evaluating TSRAs and for preparing Safety Evaluation Reports (SERs) to authorize the off-site transport. Hazards associated with the transport may include the presence of fissile material, chemically and radiologically toxic uranium, and ionizing radiation. The Nuclear Regulatory Commission (NRC) has historically considered only radiological hazards in licensing the transport of radiological material because the US Department of Transportation considers licensing requirements of nonradiological (i.e., chemically toxic) hazards. The requirements of 10 CFR 71 are based primarily on consideration of radiological hazards. For completeness, this report provides information for assessing the effects of chemical toxicity. Evaluating the degree of compliance with the requirements of 10 CFR 71 is relatively straightforward. However, there are few precedents associated with developing TSRA risk assessments for packages that do not comply with all of the requirements of 10 CFR 71. The objective of the task is to develop Risk Evaluation Guidelines for DOE-AL to use when evaluating a TSRA. If the TSRA shows that the Risk Evaluation Guidelines are not exceeded, then from a risk perspective the TSRA should be approved if there is evidence that the ALARA (as low as reasonably achievable) principle has been applied.

Just, R.A.; Love, A.F.

1997-10-01T23:59:59.000Z

283

50th Anniversary of First Fuel Shipment Highlights EM's Role | Department  

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

50th Anniversary of First Fuel Shipment Highlights EM's Role 50th Anniversary of First Fuel Shipment Highlights EM's Role 50th Anniversary of First Fuel Shipment Highlights EM's Role August 12, 2013 - 12:00pm Addthis A view of the first cask of reactor fuel from Sweden being unloaded from the m.s. Odensholm on July 21, 1963 in Savannah, Ga. A view of the first cask of reactor fuel from Sweden being unloaded from the m.s. Odensholm on July 21, 1963 in Savannah, Ga. Checking a shipment of reactor fuel are, left to right, Samuel Edlow, U.S. Representative for Aktiebolaget Atomenergi of Sweden; S.D. Smiley, offsite fuels coordinator for the Du Pont Company at Savannah River; S.D. Tatalovich, Atomic Energy Commission international affairs representative; and Robert L. Chandler, chemical engineer with the Savannah River Operations Office.

284

10,000th Shipment Celebrated at WIPP | Department of Energy  

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

10,000th Shipment Celebrated at WIPP 10,000th Shipment Celebrated at WIPP 10,000th Shipment Celebrated at WIPP October 24, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. - Approximately 130 people gathered at the U.S. Department of Energy's (DOE's) Waste Isolation Pilot Plant (WIPP) on October 22, to celebrate the 10,000th shipment of transuranic (TRU) waste to WIPP, which arrived safely late last month. The event was attended by elected and appointed officials, state and local leaders, WIPP employees and representatives of the carriers who transport TRU waste to WIPP. People in D.C. absolutely understand the service you provide the nation,‖ said U.S. Congressman Steve Pearce. -We need to solve political problems in this industry because modern economies depend on good fuel and good

285

LANL Reaches Waste Shipment Milestone: Waste from Cold War-era weapons  

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

Reaches Waste Shipment Milestone: Waste from Cold War-era Reaches Waste Shipment Milestone: Waste from Cold War-era weapons production being shipped to WIPP LANL Reaches Waste Shipment Milestone: Waste from Cold War-era weapons production being shipped to WIPP May 31, 2011 - 12:00pm Addthis Media Contact Fred deSousa 505-665-3430 fdesousa@lanl.gov LOS ALAMOS, New Mexico - Los Alamos National Laboratory has reached an important milestone in its campaign to ship transuranic (TRU) waste from Cold War-era nuclear operations to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This month, the Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total. The waste, sent from LANL to WIPP in more than 750 shipments since 1999,

286

Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Inspections  

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

Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Inspections Tasked for the Transportation of Spent Nuclear Fuel Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Inspections Tasked for the Transportation of Spent Nuclear Fuel Task: Identify Shortline Railroads Serving Nuclear Power Plants Establish Contact Information with Railroads Officials Field Review of each Railroad's Physical and Operational Infrastructure Facilitate Upgrades to Meet Safe Acceptable Standards Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Inspections Tasked for the Transportation of Spent Nuclear Fuel More Documents & Publications TEC Meeting Summaries - February 2008 Presentations TEC Meeting Summaries - July 2007 Presentations TEC Meeting Summaries - September 2006

287

50th Anniversary of First Fuel Shipment Highlights EM's Role | Department  

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

50th Anniversary of First Fuel Shipment Highlights EM's Role 50th Anniversary of First Fuel Shipment Highlights EM's Role 50th Anniversary of First Fuel Shipment Highlights EM's Role August 12, 2013 - 12:00pm Addthis A view of the first cask of reactor fuel from Sweden being unloaded from the m.s. Odensholm on July 21, 1963 in Savannah, Ga. A view of the first cask of reactor fuel from Sweden being unloaded from the m.s. Odensholm on July 21, 1963 in Savannah, Ga. Checking a shipment of reactor fuel are, left to right, Samuel Edlow, U.S. Representative for Aktiebolaget Atomenergi of Sweden; S.D. Smiley, offsite fuels coordinator for the Du Pont Company at Savannah River; S.D. Tatalovich, Atomic Energy Commission international affairs representative; and Robert L. Chandler, chemical engineer with the Savannah River Operations Office.

288

Under U.S.-Russia Partnership, Final Shipment of Fuel Converted...  

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

U.S.-Russia Partnership, Final Shipment of Fuel Converted From 20,000 Russian Nuclear Warheads Arrives in United States and Will Be Used for U.S. Electricity Under U.S.-Russia...

289

"NAICS",,"per Employee","of Value Added","of Shipments" "Code...  

U.S. Energy Information Administration (EIA) Indexed Site

Dollar","of Value" "NAICS",,"per Employee","of Value Added","of Shipments" "Code(a)","Economic Characteristic(b)","(million Btu)","(thousand Btu)","(thousand Btu)" ,,"Total United...

290

Assessing the level of service for shipments originating or terminating on short line railroads  

E-Print Network (OSTI)

This thesis measures railroad freight trip time and trip time reliability for freight rail shipments involving short lines in 2006. It is based on an underlying MIT study commissioned by members of the short line railroading ...

Alpert, Steven M

2007-01-01T23:59:59.000Z

291

" Row: NAICS Codes; Column: Energy Sources and Shipments;"  

U.S. Energy Information Administration (EIA) Indexed Site

.1. Number of Establishments by First Use of Energy for All Purposes (Fuel and Nonfuel), 1998;" .1. Number of Establishments by First Use of Energy for All Purposes (Fuel and Nonfuel), 1998;" " Level: National Data; " " Row: NAICS Codes; Column: Energy Sources and Shipments;" " Unit: Establishment Counts." " "," "," "," "," "," "," "," "," "," "," ",," " " "," ","Any",," "," ",," "," ",," ","Shipments","RSE" "NAICS"," ","Energy","Net","Residual","Distillate",,"LPG and",,"Coke and"," ","of Energy Sources","Row"

292

Radiation Exposures Associated with Shipments of Foreign Research Reactor Spent Nuclear Fuel  

SciTech Connect

Experience has shown that the analyses of marine transport of spent fuel in the Environmental Impact Statement (EIS) were conservative. It is anticipated that for most shipments. The external dose rate for the loaded transportation cask will be more in line with recent shipments. At the radiation levels associated with these shipments, we would not expect any personnel to exceed radiation exposure limits for the public. Package dose rates usually well below the regulatory limits and personnel work practices following ALARA principles are keeping human exposures to minimal levels. However, the potential for Mure shipments with external dose rates closer to the exclusive-use regulatory limit suggests that DOE should continue to provide a means to assure that individual crew members do not receive doses in excess of the public dose limits. As a minimum, the program will monitor cask dose rates and continue to implement administrative procedures that will maintain records of the dose rates associated with each shipment, the vessel used, and the crew list for the vessel. DOE will continue to include a clause in the contract for shipment of the foreign research reactor spent nuclear fuel requiring that the Mitigation Action Plan be followed.

MASSEY,CHARLES D.; MESSICK,C.E.; MUSTIN,T.

1999-11-01T23:59:59.000Z

293

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

294

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

295

Radioactivity and Radiation  

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

Radioactivity and Radiation Radioactivity and Radiation Uranium and Its Compounds line line What is Uranium? Chemical Forms of Uranium Properties of Uranium Compounds Radioactivity and Radiation Uranium Health Effects Radioactivity and Radiation Discussion of radioactivity and radiation, uranium and radioactivity, radiological health risks of uranium isotopes and decay products. Radioactivity Radioactivity is the term used to describe the natural process by which some atoms spontaneously disintegrate, emitting both particles and energy as they transform into different, more stable atoms. This process, also called radioactive decay, occurs because unstable isotopes tend to transform into a more stable state. Radioactivity is measured in terms of disintegrations, or decays, per unit time. Common units of radioactivity

296

Materials  

NLE Websites -- All DOE Office Websites (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,...

297

Under U.S.-Russia Partnership, Final Shipment of Fuel Converted From 20,000  

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

Under U.S.-Russia Partnership, Final Shipment of Fuel Converted Under U.S.-Russia Partnership, Final Shipment of Fuel Converted From 20,000 Russian Nuclear Warheads Arrives in United States and Will Be Used for U.S. Electricity Under U.S.-Russia Partnership, Final Shipment of Fuel Converted From 20,000 Russian Nuclear Warheads Arrives in United States and Will Be Used for U.S. Electricity December 10, 2013 - 2:50pm Addthis News Media Contact (202) 586-4940 WASHINGTON, D.C. - The United States and Russia are today commemorating the completion of the 1993 U.S.-Russia HEU Purchase Agreement, commonly known as the Megatons to Megawatts Program, with this week's off-loading of the final shipment of low enriched uranium (LEU) at the Port of Baltimore in Baltimore, Maryland, from Russia. The shipment was the last of the LEU converted from more than 500 metric tons of weapons-origin highly enriched

298

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

SciTech Connect

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

299

SHIPMENT OF NON-TRADITIONAL CONTENTS IN THE 9977 TYPE B PACKAGE  

SciTech Connect

The 9977 is a certified Type B Packaging authorized to ship uranium and plutonium in metal and oxide forms. These materials are typically confined within metallic containers designed for ease of handling and to prevent the spread of contamination. The Pacific Northwest National Laboratory (PNNL) uses Pu and U sources for the training of domestic and international customs agents in the identification and detection of radioactive materials (RAM). These materials are packed in polycarbonate containers which permit the trainees to view the RAM. The safety basis was made to authorize the use of these unusual containers. The inclusion of the PNNL Training Source Contents into the 9977 Packaging imposed unique conditions previously unanalyzed. The use of polycarbonate as a content container material, while different from any configuration previously considered, does not raise any safety issues with the package which continues to operate with a large safety margin for temperatures, pressures, containment, dose rates, and subcriticality.

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

2011-06-06T23:59:59.000Z

300

Microsoft Word - MCA-60-pg2 _9-10_.doc  

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

Per the general instructions of the Nuclear Material Users Manual, section 10.1, all nuclear and radioactive material shipments that are not considered waste, leaving the...

Note: This page contains sample records for the topic "radioactive material shipments" 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

Moab Mill Tailings Removal Project Plans to Resume Train Shipments in  

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

Plans to Resume Train Shipments Plans to Resume Train Shipments in March; All of the Laid Off Workers Will Return Moab Mill Tailings Removal Project Plans to Resume Train Shipments in March; All of the Laid Off Workers Will Return February 25, 2013 - 12:00pm Addthis Media Contacts Donald Metzler, donald.metzler@gjem.doe.gov 970-257-2115 Jeff Biagini, jeff.biagini@gjemrac.doe.gov 970-257-2117 Wendee Ryan, wryan@gjemtac.doe.gov 970-257-2145 Grand Junction, CO - All 27 employees of the Remedial Action Contractor (RAC) to the U.S. Department of Energy will return to work on the Uranium Mill Tailings Remedial Action Project on March 4, following a 3-month planned furlough. Project shipping and disposal operations have been shut down, as planned, since late November 2012, but are scheduled to resume

302

RUSSIAN-ORIGIN HIGHLY ENRICHED URANIUM SPENT NUCLEAR FUEL SHIPMENT FROM BULGARIA  

SciTech Connect

In July 2008, the Global Threat Reduction Initiative and the IRT 2000 research reactor in Sofia, Bulgaria, operated by the Institute for Nuclear Research and Nuclear Energy (INRNE), safely shipped 6.4 kilograms of Russian origin highly enriched uranium (HEU) spent nuclear fuel (SNF) to the Russian Federation. The shipment, which resulted in the removal of all HEU from Bulgaria, was conducted by truck, barge, and rail modes of transport across two transit countries before reaching the final destination at the Production Association Mayak facility in Chelyabinsk, Russia. This paper describes the work, equipment, organizations, and approvals that were required to complete the spent fuel shipment and provides lessons learned that might assist other research reactor operators with their own spent nuclear fuel shipments.

Kelly Cummins; Igor Bolshinsky; Ken Allen; Tihomir Apostolov; Ivaylo Dimitrov

2009-07-01T23:59:59.000Z

303

Current Situation for Management of Disused Sealed Radioactive Sources in Japan - 13025  

SciTech Connect

As for the Sealed Radioactive Source currently used in Japan, many of them are imported from overseas. The U.S., Canada, Germany, the Netherlands, Belgium and Czech Republic are the main exporting States. Many of disused sealed radioactive sources are being returned to exporting States. The sealed radioactive sources which cannot be returned to exporting States are appropriately kept in the domestic storage facility. So, there are not main problem on the long term management of disused sealed radioactive sources in Japan. However, there are some difficulties on repatriate. One is reservation of a means of transport. The sea mail which conveys radioactive sources owing to reduction of movement of international cargo is decreasing in number. And there is a denial of shipment. Other one is that the manufacturer has already resigned from the work and cannot return disused sealed radioactive sources, or a manufacturer cannot specify and disused sources cannot be returned. The disused sealed radioactive source which cannot be repatriated is a little in term of radioactivity. As for the establishment of national measure of final disposal facility for disused sealed radioactive sources, in Japan, it is not yet installed with difficulty. Since there are many countries for which installation of a final disposal facility for disused sealed radioactive sources is difficult, the source manufacture country should respond positively to return the source which was manufactured and sold in the past. (authors)

Kusama, Keiji; Miyamoto, Yoichi [Japan Radioisotope Association, Radiopharmaceutical and Radioisotope Supply Business Promotion Department (Japan)] [Japan Radioisotope Association, Radiopharmaceutical and Radioisotope Supply Business Promotion Department (Japan)

2013-07-01T23:59:59.000Z

304

22 - Radioactive waste disposal  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses the disposal of radioactive wastes that arise from a great variety of sources, including the nuclear fuel cycle, beneficial uses of isotopes, and radiation by institutions. Spent fuel contains uranium, plutonium, and highly radioactive fission products. The spent fuel is accumulating, awaiting the development of a high-level waste repository. It is anticipated that a multi-barrier system involving packaging and geologic media will provide protection of the public over the centuries. The favored method of disposal is in a mined cavity deep underground. In some countries, reprocessing the fuel assemblies permits recycling of materials and disposal of smaller volumes of solidified waste. Transportation of wastes is done by casks and containers designed to withstand severe accidents. Low-level wastes come from research and medical procedures and from a variety of activation and fission sources at a reactor site. They generally can be given near-surface burial. Isotopes of special interest are cobalt-60 and cesium-137. Transuranic wastes are being disposed of in the Waste Isolation Pilot Plant. Decommissioning of reactors in the future will contribute a great deal of low-level radioactive waste.

Raymond L. Murray

2001-01-01T23:59:59.000Z

305

Radioactive waste storage issues  

SciTech Connect

In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

Kunz, D.E.

1994-08-15T23:59:59.000Z

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

Materials  

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

Materials Materials and methods are available as supplementary materials on Science Online. 16. W. Benz, A. G. W. Cameron, H. J. Melosh, Icarus 81, 113 (1989). 17. S. L. Thompson, H. S. Lauson, Technical Rep. SC-RR-710714, Sandia Nat. Labs (1972). 18. H. J. Melosh, Meteorit. Planet. Sci. 42, 2079 (2007). 19. S. Ida, R. M. Canup, G. R. Stewart, Nature 389, 353 (1997). 20. E. Kokubo, J. Makino, S. Ida, Icarus 148, 419 (2000). 21. M. M. M. Meier, A. Reufer, W. Benz, R. Wieler, Annual Meeting of the Meteoritical Society LXXIV, abstr. 5039 (2011). 22. C. B. Agnor, R. M. Canup, H. F. Levison, Icarus 142, 219 (1999). 23. D. P. O'Brien, A. Morbidelli, H. F. Levison, Icarus 184, 39 (2006). 24. R. M. Canup, Science 307, 546 (2005). 25. J. J. Salmon, R. M. Canup, Lunar Planet. Sci. XLIII, 2540 (2012). Acknowledgments: SPH simulation data are contained in tables S2 to S5 of the supplementary materials. Financial support

308

Radioactive Waste Management  

Directives, Delegations, and Requirements

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

Level: National and Regional Data; Row: Values of Shipments and Employment Sizes  

U.S. Energy Information Administration (EIA) Indexed Site

1.3 First Use of Energy for All Purposes (Fuel and Nonfuel), 2006; 1.3 First Use of Energy for All Purposes (Fuel and Nonfuel), 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes Column: Energy Sources and Shipments; Unit: Trillion Btu. Shipments Economic Net Residual Distillate LPG and Coke and of Energy Sources Characteristic(a) Total(b) Electricity(c) Fuel Oil Fuel Oil(d) Natural Gas(e) NGL(f) Coal Breeze Other(g) Produced Onsite(h) Total United States Value of Shipments and Receipts (million dollars) Under 20 1,166 367 23 48 540 15 41 3 140 12 20-49 1,209 333 20 26 550 8 104 5 182 20 50-99 1,507 349 51 19 575 98 190 9 256 40 100-249 2,651 607 53 20 1,091 23 310 53 566 73 250-499 2,362 413 52 13 754 158 247 9 732 16 500 and Over

310

Bacteria eats radioactive waste  

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

Bacteria eats radioactive waste Bacteria eats radioactive waste Name: deenaharper Status: N/A Age: N/A Location: N/A Country: N/A Date: Around 1993 Question: In my studies, I have found that everything in this world is balanced. When something dies it is converted into life. Is there anything out there that could convert radioactive material into a harmless substance? Some sort of bacteria that consumes radiation? Replies: The reason why radiation is so harmful is that is produces free radicals in living tissue, that is, it de-stabilizes molecules by tearing off electrons due to intense energies. These free radicals start a chain reaction of destruction, de-stabilizing neighboring molecules. If this continues unchecked, cells die, genetic material are mutated, and tissue aging accelerates. It is somewhat like being burned. Fire oxidizes by a similar free radical reaction. (Hence the term "sun burn.") The natural defenses against free radical reactions in biological systems are antioxidants, which are enzymes, nutrients, and other chemicals, which quench free radical reactions. Without them, life would very quickly cease. To my knowledge, no microorganism has an antioxidant capacity great enough to withstand even minimal exposure to any type of radiation. Microorganisms are actually very susceptible to radiation, which is why heat and gamma irradiation are used to sterilize food, instruments, etc. However, you raise an interesting possibility in that perhaps one can be genetically engineered to have super- antioxidant capacity, but that may be beyond current technology. Plus, if any got loose, given the exponential rate of reproduction, they may become an uncontrollable health hazard, as it would be very difficult to destroy them!

311

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

312

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

313

Moab Mill Tailings Removal Project Plans to Resume Train Shipments...  

Energy Savers (EERE)

result in a cost savings to the project over the long term. Made of -inch durable plastic, the liners will prevent the tailings material, which tends to be sticky, from...

314

Alloy of depleted uranium: Material for ?-protection of shipment packing sets  

Science Journals Connector (OSTI)

The effect of thermal action on the structure and physical and mechanical properties of an alloy based on depleted uranium and used for biological protection from ionizing...

V. K. Orlov; V. M. Sergeev; A. G. Semenov; V. V. Noskov

315

Microsoft PowerPoint - Advances_Taylor  

Office of Environmental Management (EM)

MSP Airport Mall of America Bloomington, Minnesota WHAT is TRANSCOM? * Unclassified web-based tracking and communication system * Monitor radioactive material shipments at...

316

Radioactive Waste Incineration: Status Report  

SciTech Connect

Incineration is generally accepted as a method of reducing the volume of radioactive waste. In some cases, the resulting ash may have high concentrations of materials such as Plutonium or Uranium that are valuable materials for recycling. Incineration can also be effective in treating waste that contains hazardous chemicals as well as radioactive contamination. Despite these advantages, the number of operating incinerators currently in the US currently appears to be small and potentially declining. This paper describes technical, regulatory, economic and political factors that affect the selection of incineration as a preferred method of treating radioactive waste. The history of incinerator use at commercial and DOE facilities is summarized, along with the factors that have affected each of the sectors, thus leading to the current set of active incinerator facilities. In summary: Incineration has had a long history of use in radioactive waste processing due to their ability to reduce the volume of the waste while destroying hazardous chemicals and biological material. However, combinations of technical, regulatory, economic and political factors have constrained the overall use of incineration. In both the Government and Private sectors, the trend is to have a limited number of larger incineration facilities that treat wastes from a multiple sites. Each of these sector is now served by only one or two incinerators. Increased use of incineration is not likely unless there is a change in the factors involved, such as a significant increase in the cost of disposal. Medical wastes with low levels of radioactive contamination are being treated effectively at small, local incineration facilities. No trend is expected in this group. (authors)

Diederich, A.R.; Akins, M.J. [WorleyParsons, Reading, PA (United States)

2008-07-01T23:59:59.000Z

317

FORM EIA-63B ANNUAL PHOTOVOLTAIC CELL/MODULE SHIPMENTS REPORT  

U.S. Energy Information Administration (EIA) Indexed Site

CELL/MODULE SHIPMENTS REPORT For Reporting Year ( ) OMB No. 1905-0129 Approval Expires: 12/31/2016 Burden: 5 hours GENERAL INFORMATION AND INSTRUCTIONS I. Purpose Form EIA-63B is designed to provide the data necessary for the U.S. Energy Information Administration (EIA), a part of the U.S. Department of Energy (DOE), to carry out its responsibilities tracking photovoltaic cell/module shipments in the photovoltaic industry and reporting information concerning the size and status of the industry. The data collected will be published a nnu a lly in the S o la r Phot o vo lt ai c C el l/ Mo du le Sh ip m ent s R epor t a nd be available through EIA's Internet site at http://www.eia.gov/renewable/annual/solar_photo/. II. Who Should Respond to This Survey

318

Effects of shipment on diffusive dosimetry recovery efficiency for pentane, hexane and heptane  

E-Print Network (OSTI)

Sciences College of Pharmacy Chairman of' Advisory Committee: Mr. Charles L. Gilmore The effects of' shipment on recovery was investigated for three aliphatic hydrocarbons adsorbed on the 3M Company's $3500 Organic Vapor Monitor and the Scientific Kit... of the contaminant compound of interest and the adsorptive properties of the adsorbing (3-6) medium, activated charcoal, for collection. The diffusive dosimeter is easy to use and can be placed on the worker by the first line supervisor each day at the beginning...

Read, Ronald Bruce

2012-06-07T23:59:59.000Z

319

APS Radioactive Sample Safety Review Committee  

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

Radioactive Sample Safety Review Committee Radioactive Sample Safety Review Committee March 6, 2012 1. Purpose The APS Safety Radioactive Sample Safety Review Committee (RSSRC) advises the AES Division Director on the radioactive samples to be used at the APS and the adequacy of controls in place for the duration of their use. The RSSRC reviews the radioactive material samples proposed to be run at the APS to ensure that they fall within established safety envelopes of the APS. 2. Membership The RSSRC members are appointed by the AES Division Director. The current members of the RSRC are: B. Glagola AES - Chair S. Davey AES G. Pile AES L. Soderholm CHM J. Vacca RSO W. VanWingeren AES M. Beno XSD E. Alp XSD M. Rivers PUC 3. Method The AES User Safety Coordinator will notify the RSSRC of any samples

320

Level: National and Regional Data; Row: Values of Shipments and Employment Sizes;  

U.S. Energy Information Administration (EIA) Indexed Site

2 Consumption Ratios of Fuel, 2006; 2 Consumption Ratios of Fuel, 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes; Column: Energy-Consumption Ratios; Unit: Varies. Consumption Consumption per Dollar Consumption per Dollar of Value Economic per Employee of Value Added of Shipments Characteristic(a) (million Btu) (thousand Btu) (thousand Btu) Total United States Value of Shipments and Receipts (million dollars) Under 20 330.6 3.6 2.0 20-49 550.0 4.5 2.2 50-99 830.1 5.9 2.7 100-249 1,130.0 6.7 3.1 250-499 1,961.4 7.6 3.6 500 and Over 3,861.9 9.0 3.6 Total 1,278.4 6.9 3.1 Employment Size Under 50 562.6 4.7 2.4 50-99 673.1 5.1 2.4 100-249 1,072.8 6.5 3.0 250-499 1,564.3 7.7 3.6 500-999 2,328.9

Note: This page contains sample records for the topic "radioactive material shipments" 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

CRAD, Packaging and Transfer of Hazardous Materials and Materials of  

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

Packaging and Transfer of Hazardous Materials and Materials Packaging and Transfer of Hazardous Materials and Materials of National Security Interest Assessment Plan CRAD, Packaging and Transfer of Hazardous Materials and Materials of National Security Interest Assessment Plan Performance Objective: Verify that packaging and transportation safety requirements of hazardous materials and materials of national security interest have been established and are in compliance with DOE Orders 461.1 and 460.1B Criteria: Verify that safety requirements for the proper packaging and transportation of DOE/NNSA offsite shipments and onsite transfers of hazardous materials and for modal transport have been established [DOE O 460.1B, 1, "Objectives"]. Verify that the contractor transporting a package of hazardous materials is in compliance with the requirements of the Hazardous Materials

322

Radioactive Waste Management (Minnesota)  

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

323

Chapter 22 - Radioactive Waste Disposal  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses safe disposal of radioactive waste in order to provide safety to workers and the public. Radioactive wastes arise from a great variety of sources, including the nuclear fuel cycle, and from beneficial uses of isotopes and radiation by institutions. Spent fuel contains uranium, plutonium, and highly radioactive fission products. In the United States spent fuel is accumulating, awaiting the development of a high-level waste repository. A multi-barrier system involving packaging and geological media will provide protection of the public over the centuries the waste must be isolated. The favored method of disposal is in a mined cavity deep underground. In other countries, reprocessing the fuel assemblies permits recycling of materials and disposal of smaller volumes of solidified waste. Transportation of wastes is by casks and containers designed to withstand severe accidents. Low-level wastes (LLWs) come from research and medical procedures and from a variety of activation and fission sources at a reactor site. They generally can be given near-surface burial. Isotopes of special interest are cobalt-60 and cesium-137. Transuranic wastes are being disposed of in the Waste Isolation Pilot Plant. Establishment of regional disposal sites by interstate compacts has generally been unsuccessful in the United States. Decontamination of defense sites will be long and costly. Decommissioning of reactors in the future will contribute a great deal of low-level radioactive waste.

Raymond L. Murray

2009-01-01T23:59:59.000Z

324

EM Waste and Materials Disposition & Transportation | Department...  

Office of Environmental Management (EM)

EM Waste and Materials Disposition & Transportation EM Waste and Materials Disposition & Transportation DOE's Radioactive Waste Management Priorities: Continue to manage waste...

325

Final 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  

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

Contents Contents CR-iii TABLE OF CONTENTS Section Page 8. Transportation Modes, Routes, Affected Environment, and Impacts............................................ CR8-1 8.1 General Opposition to Transporting Spent Nuclear Fuel and High-Level Radioactive Waste ............................................................................................................ CR8-6 8.2 Number of Shipments ..................................................................................................... CR8-37 8.3 Transportation Modes and Routes .................................................................................. CR8-41 8.3.1 State Highway 127, Hoover Dam, Nevada Department of Transportation Alternatives ..............................................................................................................

326

What are Spent Nuclear Fuel and High-Level Radioactive Waste ?  

SciTech Connect

Spent nuclear fuel and high-level radioactive waste are materials from nuclear power plants and government defense programs. These materials contain highly radioactive elements, such as cesium, strontium, technetium, and neptunium. Some of these elements will remain radioactive for a few years, while others will be radioactive for millions of years. Exposure to such radioactive materials can cause human health problems. Scientists worldwide agree that the safest way to manage these materials is to dispose of them deep underground in what is called a geologic repository.

DOE

2002-12-01T23:59:59.000Z

327

RH-TRU Waste Shipments from Battelle Columbus Laboratories to the Hanford Nuclear Facility for Interim Storage  

SciTech Connect

Battelle Columbus Laboratories (BCL), located in Columbus, Ohio, must complete decontamination and decommissioning (D&D) activities for nuclear research buildings and grounds by 2006, as directed by Congress. Most of the resulting waste (approximately 27 cubic meters [m3]) is remote-handled (RH) transuranic (TRU) waste destined for disposal at the Waste Isolation Pilot Plant (WIPP). The BCL, under a contract to the U.S. Department of Energy (DOE) Ohio Field Office, has initiated a plan to ship the TRU waste to the DOE Hanford Nuclear Facility (Hanford) for interim storage pending the authorization of WIPP for the permanent disposal of RH-TRU waste. The first of the BCL RH-TRU waste shipments was successfully completed on December 18, 2002. This BCL shipment of one fully loaded 10-160B Cask was the first shipment of RH-TRU waste in several years. Its successful completion required a complex effort entailing coordination between different contractors and federal agencies to establish necessary supporting agreements. This paper discusses the agreements and funding mechanisms used in support of the BCL shipments of TRU waste to Hanford for interim storage. In addition, this paper presents a summary of the efforts completed to demonstrate the effectiveness of the 10-160B Cask system. Lessons learned during this process are discussed and may be applicable to other TRU waste site shipment plans.

Eide, J.; Baillieul, T. A.; Biedscheid, J.; Forrester, T,; McMillan, B.; Shrader, T.; Richterich, L.

2003-02-26T23:59:59.000Z

328

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

329

Packaging and Transportation | Department of Energy  

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

Packaging and Transportation Packaging and Transportation Packaging and Transportation Packaging and Transportation Radiological shipments are accomplished safely. Annually, about 400 million hazardous materials shipments occur in the United States by rail, air, sea, and land. Of these shipments, about three million are radiological shipments. Since Fiscal Year (FY) 2004, EM has completed over 150,000 shipments of radioactive material/waste. Please click here to see Office of Packaging and Transportation Fiscal Year 2012 Annual Report. SUPPORTING PROGRAMS SAFE TRANSPORTATION OF RADIOLOGICAL SHIPMENTS Transportation Emergency Preparedness Program (TEPP) TEPP provides the tools for planning, training and exercises, and technical assistance to assist State and Tribal authorities in preparing for response

330

Upgrading the Radioactive Waste Management Infrastructure in Azerbaijan  

SciTech Connect

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

331

Level: National Data; Row: NAICS Codes; Column: Energy Sources and Shipments;  

Gasoline and Diesel Fuel Update (EIA)

1.4 Number of Establishments by First Use of Energy for All Purposes (Fuel and Nonfuel), 2010; 1.4 Number of Establishments by First Use of Energy for All Purposes (Fuel and Nonfuel), 2010; Level: National Data; Row: NAICS Codes; Column: Energy Sources and Shipments; Unit: Establishment Counts. Any Shipments NAICS Energy Net Residual Distillate LPG and Coke and of Energy Sources Code(a) Subsector and Industry Source(b) Electricity(c) Fuel Oil Fuel Oil(d) Natural Gas(e) NGL(f) Coal Breeze Other(g) Produced Onsite(h) Total United States 311 Food 13,269 13,265 151 2,494 10,376 4,061 64 7 1,668 W 3112 Grain and Oilseed Milling 602 602 9 201 490 286 30 0 165 W 311221 Wet Corn Milling 59 59 W 26 50 36 15 0 29 0 31131 Sugar Manufacturing 73 73 3 36 67 13 11 7 15 0 3114 Fruit and Vegetable Preserving and Specialty Foods 987 987

332

Level: National and Regional Data; Row: Values of Shipments and Employment Sizes;  

U.S. Energy Information Administration (EIA) Indexed Site

6 Electricity: Sales to Utility and Nonutility Purchasers, 2006; 6 Electricity: Sales to Utility and Nonutility Purchasers, 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes; Column: Utility and Nonutility Purchasers; Unit: Million Kilowatthours. Total of Economic Sales and Utility Nonutility Characteristic(a) Transfers Offsite Purchaser(b) Purchaser(c) Total United States Value of Shipments and Receipts (million dollars) Under 20 28 28 0 20-49 307 227 80 50-99 2,218 1,673 545 100-249 2,647 1,437 1,210 250-499 3,736 2,271 1,464 500 and Over 10,814 5,665 5,149 Total 19,750 11,301 8,449 Employment Size Under 50 516 230 287 50-99 1,193 1,180 13 100-249 3,825 3,231 594 250-499 3,796 2,675 1,120 500-999 4,311 1,921 2,390

333

Level: National and Regional Data; Row: Values of Shipments and Employment Sizes;  

U.S. Energy Information Administration (EIA) Indexed Site

4 Electricity: Components of Onsite Generation, 2006; 4 Electricity: Components of Onsite Generation, 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes; Column: Onsite-Generation Components; Unit: Million Kilowatthours. Renewable Energy (excluding Wood Economic Total Onsite and Characteristic(a) Generation Cogeneration(b) Other Biomass)(c) Other(d) Total United States Value of Shipments and Receipts (million dollars) Under 20 1,447 450 Q Q 20-49 5,220 5,106 29 Q 50-99 3,784 3,579 29 Q 100-249 17,821 17,115 484 222 250-499 28,464 27,202 334 927 500 and Over 86,249 85,028 106 1,114 Total 142,986 138,480 1,030 3,476 Employment Size Under 50 2,193 1,177 Q Q 50-99 6,617 6,438 13 166 100-249 12,403 12,039 266 98 250-499

334

Level: National and Regional Data; Row: Values of Shipments and Employment Sizes  

U.S. Energy Information Administration (EIA) Indexed Site

2.3 Nonfuel (Feedstock) Use of Combustible Energy, 2006; 2.3 Nonfuel (Feedstock) Use of Combustible Energy, 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes Column: Energy Sources Unit: Trillion Btu Economic Residual Distillate LPG and Coke and Characteristic(a) Total Fuel Oil Fuel Oil(b) Natural Gas(c) NGL(d) Coal Breeze Other(e) Total United States Value of Shipments and Receipts (million dollars) Under 20 47 0 3 5 Q 20 1 17 20-49 112 7 Q 20 1 12 1 64 50-99 247 29 Q 26 88 33 * 68 100-249 313 28 1 97 12 48 43 85 250-499 297 * * 121 154 3 5 13 500 and Over 2,547 * * 130 2,043 301 6 66 Not Ascertained (f) 3,399 0 0 0 0 0 0 3,399 Total 6,962 64 17 398 2,299 417 56 3,711 Employment Size Under 50 161 4 Q 48 15 19 0 64 50-99 390 41 1 97 145 27 1 77 100-249

335

Level: National Data; Row: NAICS Codes; Column: Energy Sources and Shipments  

U.S. Energy Information Administration (EIA) Indexed Site

1.4 Number of Establishments by First Use of Energy for All Purposes (Fuel and Nonfuel), 2006; 1.4 Number of Establishments by First Use of Energy for All Purposes (Fuel and Nonfuel), 2006; Level: National Data; Row: NAICS Codes; Column: Energy Sources and Shipments Unit: Establishment Counts. Any Shipments NAICS Energy Net Residual Distillate LPG and Coke and of Energy Sources Code(a) Subsector and Industry Source(b) Electricity(c) Fuel Oil Fuel Oil(d) Natural Gas(e) NGL(f) Coal Breeze Other(g) Produced Onsite(h) Total United States 311 Food 14,128 14,113 326 1,475 11,399 2,947 67 15 1,210 W 3112 Grain and Oilseed Milling 580 580 15 183 449 269 35 0 148 W 311221 Wet Corn Milling 47 47 W 17 44 19 18 0 18 0 31131 Sugar Manufacturing 78 78 11 45 61 35 26 15 45 0 3114 Fruit and Vegetable Preserving and Specialty Food 1,125

336

Level: National and Regional Data; Row: Values of Shipments and Employment Sizes;  

U.S. Energy Information Administration (EIA) Indexed Site

3.3 Fuel Consumption, 2006; 3.3 Fuel Consumption, 2006; Level: National and Regional Data; Row: Values of Shipments and Employment Sizes; Column: Energy Sources; Unit: Trillion Btu. Economic Net Residual Distillate LPG and Coke and Characteristic(a) Total Electricity(b) Fuel Oil Fuel Oil(c) Natural Gas(d) NGL(e) Coal Breeze Other(f) Total United States Value of Shipments and Receipts (million dollars) Under 20 1,139 367 23 45 535 14 21 3 131 20-49 1,122 333 13 19 530 8 93 5 122 50-99 1,309 349 22 17 549 10 157 8 197 100-249 2,443 607 25 19 994 11 263 10 512 250-499 2,092 413 53 13 633 4 244 3 730 500 and Over 7,551 781 115 17 2,271 31 240 344 3,752 Total 15,657 2,851 251 129 5,512 79 1,016 374 5,445 Employment Size Under 50 1,103 334 10 45 550 10

337

Present experience of NRI REZ with preparation of spent nuclear fuel shipment to Russian Federation  

SciTech Connect

The Nuclear Research Institute Rez plc (NRI) jointed the Russian Research Reactor Fuel Return (RRRFR) programme under the US-Russian Global Threat Reduction Initiative (GTRI) initiative and started the preparation of the spent nuclear fuel (SNF) shipment from the LVR-15 research reactor back to the Russian Federation (RF). The transport of 16 SKODA VPVR/M casks with EK-10, IRT-2M 80 %, and IRT-2M 36% fuel types is planned for the autumn of 2007. The paper describes the experience gained so far during the preparatory works for the SNF shipment (facility equipment modification, cask licenses) and the actual preparation of the SNF for transport, in particular its checking, repacking in a hot cell, loading into the VPVR/M casks, drying, manipulation, completion of the transport documentation, etc., including its transport to the SNF storage facility at the NRI before it is shipped to the RF. The paper also briefly describes a regulatory framework for these activities with a focus on legislative and methodological aspects of the return of vitrified waste back to the Czech Republic. (author)

Svitak, F.; Broz, V.; Hrehor, M.; Marek, M.; Novosad, P.; Podlaha, J.; Rychecky, J. [Nuclear Research Institute Rez plc, Husinec 130, CZ-25068 (Czech Republic)

2008-07-15T23:59:59.000Z

338

Evaluation of Shortline Railroads & SNF/HLW Rail Shipment Inspections Tasked for the Transportation of Spent Nuclear Fuel  

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

Transportation Transportation Stakeholders National Transportation Stakeholders National Transportation Stakeholders National Transportation Stakeholders Forum Forum 2011 Annual Meeting 2011 Annual Meeting 2011 Annual Meeting 2011 Annual Meeting May 11, 2011 May 11, 2011 Evaluation of Shortline Railroads Evaluation of Shortline Railroads & & & & SNF/HLW Rail Shipment Inspections SNF/HLW Rail Shipment Inspections Tasked for the Transportation of Spent Nuclear Fuel Tasked for the Transportation of Spent Nuclear Fuel Evaluation of Shortline Railroads Evaluation of Shortline Railroads Evaluation of Shortline Railroads Evaluation of Shortline Railroads Task: Task: Task: Task: Identify Shortline Railroads Serving Nuclear Power Plants Identify Shortline Railroads Serving Nuclear Power Plants

339

DOE - Safety of Radioactive Material Transportation  

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

What is computer analysis? What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. Accurate determination of package behavior for impact and puncture accidents can be obtained by testing sub-scale models. This technique is frequently used in conjunction with full-scale tests and computer analyses. Full-scale spent fuel packages can weigh 250,000 pounds (three fully loaded semi-trucks) or more, therefore the ability to determine the behavior with scale-models improves testing safety and reduces testing costs. *** 1/4 Scale Free Drop Test 1/4 Scale Component Free Drop Test 1/3 Scale Puncture Test 1/2 Scale Puncture Test 1/8 Scale Rail Crush Test [scale model DROP test] Click to view picture [scale model component test]

340

DOE - Safety of Radioactive Material Transportation  

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

Package Certification Using Computer Analysis Package Certification Using Computer Analysis Engineering Principles Established by Three Early Scientists Engineering Principles Applied to Ancient Structures Description of Computer Model in Computer Analysis Engineered Structures Built WITHOUT the Use of Computer Analysis Structures Analyzed WITH the Use of Computer Analysis What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. Computer analysis is an application of known engineering principles that take advantage of high-power computing capabilities in solving the response of computer models to various environments with complex mathematical calculations. Computer analysis can be used for package certification by generating a

Note: This page contains sample records for the topic "radioactive material shipments" 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

DOE - Safety of Radioactive Material Transportation  

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

Free Drop Comparison Crush Comparison Puncture Comparison Fire Comparison Immersion Comparison Demonstrating target hardness. Hypothetical Accident Conditions: Six tests as defined in 10 CFR Part 71.73 of the NRC transportation regulations were established to provide repeatable and definable conditions that encompass most real-life accidents. The real-life accidents on this page are comparisons to the environments that the regulatory hypothetical accidents protect against. The collision forces or fire temperature and duration that were present in each accident are similar to the conditions that spent fuel casks are designed to survive. Passenger Train and Semi-truck Trailer Collision [DROP scenario] Mack Truck and Subaru Collision [CRUSH scenario] Freight Train and Freight Train Collision

342

DOE - Safety of Radioactive Material Transportation  

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

Comments & Questions Gary Lanthrum, DOE/NTP Albuquerque, NM E-mail: glanthrum@doeal.gov Phone: (505) 845-5277 Fax: (505) 845-5508 Ashok K. Kapoor, DOE/NTP Albuquerque, NM E-mail: akapoor@doeal.gov Phone: (505) 845-4574 Fax: (505) 845-5508 David R. Miller, SNL/TP Manager, Albuquerque, NM E-mail: drmille@sandia.gov Phone: (505) 284-2574 Fax: (505) 844-2829 Mona L. Aragon, SNL/TP Advanced Visualization, Albuquerque, NM E-mail: mlrage@sandia.gov Phone: (505) 844-2541 Fax: (505) 844-0244 Doug Ammerman, SNL/TP Structural Analysis, Albuquerque, NM E-mail: djammer@sandia.gov Phone: (505) 845-8158 Fax: (505) 844-0244 Fran Kanipe, SNL/TP Computer Programming, Albuquerque, NM E-mail: flkanip@sandia.gov Phone: (505) 844-1121 Fax: (505) 844-0244 Carlos Lopez, SNL/TP Thermal Analysis, Albuquerque, NM

343

DOE - Safety of Radioactive Material Transportation  

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

Glossary of Nuclear Terms [Majority from NRC] Contacts Comments & Questions Photos 30-Foot Free Drop Test jpeg, 788K [photo] Click to view picture 1100-Pound Crush Test jpeg, 448K [photo] Click to view picture 40-Inch Puncture Test jpeg, 912K [photo] Click to view picture 30-Minute Pool Fire Test jpeg, 88K [photo] Click to view picture 8-Hour Immersion Test jpeg, 416K [photo] Click to view picture Graphics Unyielding Target jpeg, 144K [graphic] Click to view graphic title jpeg, 000K [graphic] Click to view graphic title jpeg, 000K [graphic] Click to view graphic title jpeg, 000K [graphic] Click to view graphic title jpeg, 000K [graphic] Click to view graphic Movies 30-Foot Free Drop Test AVI, 4.5 MB [movie] Click to view movie 1/3-Scale Puncture Test AVI, 3.3 MB [movie] Click to view movie 30-Minute

344

DOE - Safety of Radioactive Material Transportation  

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

Crush Comparison Puncture Comparison Fire Comparison Immersion Comparison Demonstrating target hardness. Comparison of the Free Drop Test to a Passenger Train and Semi-truck Trailer Collision Free Drop Test 3,000,000 lbs of force present in this package certification test. [DROP test] Click to view picture Real-life Accident Comparison 1,000,000 lbs of force present in this real-life accident. [DROP scenario] Click to view picture Real-life scenarios that are encompassed by the above test include: the package being struck by a train traveling 60 MPH the package falling off of a 30-foot high bridge onto solid rock or from a higher bridge onto a highway or railroad the package running into a bridge support or rock slope at 45 MPH. Packages are transported onboard trucks or rail cars, which absorb some of the impact energy, reducing the resulting damage to the packages from the accident. On May 2, 1995, an O&J Gordon Trucking Company truck consisting of a tractor and a lowbed semitrailer became lodged on a high-profile (hump) railroad grade crossing near Sycamore, South Carolina. About 35 minutes later, the truck was struck by southbound Amtrak train No. 81, Silver Star, en route from New York City to Tampa, Florida.

345

DOE - Safety of Radioactive Material Transportation  

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

REGULATIONS & GUIDANCE SEARCH SITE MAP SITE MAP SAFE HOME Search Site RAM PACKAGES What are they? When are they used? How are they moved? What's their construction? Who uses them? Who makes rules? What are the requirements? Safety Record TESTING & CERTIFICATION How are packages certified? What are full-scale tests? What are scale-model tests? What is computer analysis? Package Certification Using Computer Analysis Engineering Principles Established by Three Early Scientists Engineering Principles Applied to Ancient Structures Description of Computer Model in Computer Analysis Engineered Structures Built WITHOUT the Use of Computer Analysis Structures Analyzed WITH the Use of Computer Analysis What are examples of severe testing? How do the certification tests compare to real-life accidents?

346

DOE - Safety of Radioactive Material Transportation  

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

Puncture Comparison Fire Comparison Immersion Comparison Demonstrating target hardness. Comparison of the Free Drop Test to a Mack Truck and Subaru Collision Crush Test 200,000 lbs of force present in this package certification test. [CRUSH test] Click to view picture Real-life Accident Comparison 60,000 lbs of force present in this real-life accident. [CRUSH scenario] Click to view picture Real-life scenarios that the above test* is designed to protect against include: the package being under a vehicle during a pile-up accident the package being pinned between two vehicles during a collision. The 55 gallon drum is an overpack for a smaller (6-inch diameter x 18-inch long, 1/4-inch thick stainless steel walled) package that is inside. Note*: This test is ONLY for packages weighing less than 500 kg (1100 lbs). On April 25, 1996, a Mack truck with a concrete mixer body, unable to stop, proceeded through an intersection at the bottom of an exit ramp. It collided with and overrode a Subaru passenger car near Plymouth Meeting, Pennsylvania.

347

DOE - Safety of Radioactive Material Transportation  

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

What are examples of severe testing? What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. Purpose Background Results References Demonstrating Target Hardness between an Unyielding Target vs. Concrete Target During 30-foot Drop Tests. 30-foot 1/2 scale DHLW (Defense High-Level Waste) cask drop onto an unyielding target click to play, avi 4.7MB 30-foot 1/2 scale DHLW (Defense High-Level Waste) cask drop onto a 1/2 scale (5 1/2 inch) concrete pad click to play, avi 2.5MB 30-foot van drop onto an unyielding target click to play, avi 3.7MB 30-foot van drop onto an 11 inch concrete pad click to play, avi 3.4MB Purpose [ Back to top of page ] The purpose of this series of tests is to visually demonstrate the severity of the Type B Hypothetical Accident Condition impact test (10 CFR Part

348

DOE - Safety of Radioactive Material Transportation  

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

Immersion Comparison Demonstrating target hardness. Comparison of the Fire Test to a Gasoline Tanker and Sedan collision under an Overpass Fire Test [FIRE test] Click to view picture Real-life Accident Comparison [FIRE scenario] Click to view picture Real-life scenarios that the above test is designed to protect against include being involved in an accident with a gasoline tanker truck, causing the gasoline contents to burn the package. The amount of fuel being burned is approximately 5000 gallons in a pool 30 feet in diameter. During this test, the package is fully engulfed in the fire and is not protected by a transporting vehicle. On October 9, 1997, a truck tractor pulling a cargo tank semitrailer was going under an overpass of the New York State Thruway in Yonkers, New York when it was struck by a sedan. The car hit the right side of the cargo tank in the area of the tank's external loading/unloading lines, releasing the 8800 gallons of gasoline they contained.

349

Emergency Responder Radioactive Material Quick Reference Sheet  

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

This job aid is a quick reference to assist emergency responders in identifying preliminary safety precautions that should be taken during the initial response phase after arrival at the scene of...

350

Radioactive Materials Transportation and Incident Response  

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

This booklet was written to answer questions most frequently asked by fire fighters, law enforcement officers, and emergency medical services personnel. The booklet is not intended as a substitute...

351

ETEC - Radioactive Handling Materials Facility (RMHF) Leachfield...  

Office of Environmental Management (EM)

of Plume (acres): 2 Plume Status: Plume expanding but not expected to migrate offsite Remedial Approach Remedy Name Status Start Date End Date Groundwater Use Exit Strategy...

352

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

353

NNSA: Securing Domestic Radioactive Material | National Nuclear...  

National Nuclear Security Administration (NNSA)

established the Global Threat Reduction Initiative (GTRI) in the Office of Defense Nuclear Nonproliferation to, as quickly as possible, identify, secure, remove andor...

354

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

355

DOE - Safety of Radioactive Material Transportation  

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

Structures Analyzed WITH the Use of Computer Analysis Structures Analyzed WITH the Use of Computer Analysis What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. Structural Analysis and Thermal Analysis of RAM Packaging Sandia National Laboratories jpeg, 24K Click to view picture AVI, 344K Click to view movie jpeg, 100K Click to view picture AVI, 1.5 MB Click to view movie C-1500 Truck Model Crash Analysis National Crash Analysis Center jpeg, 60K Click to view picture AVI, 616K Click to view movie AVI, 1.4 MB Click to view movie AVI, 368K Click to view movie Ship-to-Ship Collision Sandia National Laboratories Simulation Testing of Tire Designs Sandia National Laboratories jpeg, 72K Click to view picture AVI, 6.9 MB Click to view movie jpeg, 88K

356

DOE - Safety of Radioactive Material Transportation  

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

Biological Responses Other Effects History Gallery Glossary of Nuclear Terms [Majority from NRC] Contacts Comments & Questions [RAD Pie Chart] Exposure Source Average annual dose to an individual in the United States (millirem) Natural sources (including radon) - Ground, cosmic, and terrestrial - Internal radiation 200 mrem 100 mrem Occupational 0.9 mrem Nuclear Fuel Cycle 0.05 mrem Consumer Products - Tobacco - Other (i.e., smoke detectors, exit signs, luminous watch dials) Dose to lungs ~16,000 mrem 5 - 13 mrem Environmental Sources 0.06 mrem Medical - Diagnostic X-rays - Nuclear Medicine 39 mrem 14 mrem Approximate Annual Total 360 mrem [Radiation] Everyone in the world is continuously exposed to naturally-occuring background radiation. The average radiation dose received by the United

357

Measurement of natural radioactivity from soil samples of Sind, Pakistan  

Science Journals Connector (OSTI)

......Gnbold G., Ganhimeg G. Natural Radioactivity of Some Mongolian Building Materials (2000) National University of Mongolia. INIS Electronic Form No. E16-20002-46. 14 Baeza A. , Del-Rio M., Miro C. Natural radioactivity in soils of the Province......

S. A. Mujahid; S. Hussain

2011-06-01T23:59:59.000Z

358

Natural radioactivity in soil in the Baluchistan province of Pakistan  

Science Journals Connector (OSTI)

......Gnbold G., Ganhimeg G. Natural radioactivity of some Mongolian building materials. (2000) National University of Mongolia, INIS Electronic Form No. E16-20002-46. 17 Baeza A. , Del-Rio M., Miro C. Natural radioactivity in soils of the Province......

S. A. Mujahid; S. Hussain

2010-08-01T23:59:59.000Z

359

E-Print Network 3.0 - alpha contaminated material Sample Search...  

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

possible. Radioactively Contaminated... consumption by removing levels of naturally occurring radioactive materials found in raw water supplies... . As large quantities of water...

360

Walk the Line: The Development of Route Selection Standards for Spent Nuclear Fuel and High-level Radioactive Waste in the United States - 13519  

SciTech Connect

Although storage facilities for spent nuclear fuel (SNF) and high-level radioactive waste (HLRW) are widely dispersed throughout the United States, these materials are also relatively concentrated in terms of geographic area. That is, the impacts of storage occur in a very small geographic space. Once shipments begin to a national repository or centralized interim storage facility, the impacts of SNF and HLRW will become more geographically distributed, more publicly visible, and almost certainly more contentious. The selection of shipping routes will likely be a major source of controversy. This paper describes the development of procedures, regulations, and standards for the selection of routes used to ship spent nuclear fuel and high-level radioactive waste in the United States. The paper begins by reviewing the circumstances around the development of HM-164 routing guidelines. The paper discusses the significance of New York City versus the Department of Transportation and application of HM-164. The paper describes the methods used to implement those regulations. The paper will also describe the current HM-164 designated routes and will provide a summary data analysis of their characteristics. This analysis will reveal the relatively small spatial scale of the effects of HM 164. The paper will then describe subsequent developments that have affected route selection for these materials. These developments include the use of 'representative routes' found in the Department of Energy (DOE) 2008 Supplemental Environmental Impact Statement for the formerly proposed Yucca Mountain geologic repository. The paper will describe recommendations related to route selection found in the National Academy of Sciences 2006 report Going the Distance, as well as recommendations found in the 2012 Final Report of the Blue Ribbon Commission on America's Nuclear Future. The paper will examine recently promulgated federal regulations (HM-232) for selection of rail routes for hazardous materials transport. The paper concludes that while the HM 164 regime is sufficient for certain applications, it does not provide an adequate basis for a national plan to ship spent nuclear fuel and high-level radioactive waste to centralized storage and disposal facilities over a period of 30 to 50 years. (authors)

Dilger, Fred [Black Mountain Research, Henderson, NV 81012 (United States)] [Black Mountain Research, Henderson, NV 81012 (United States); Halstead, Robert J. [State of Nevada Agency for Nuclear Projects, Carson City, NV 80906 (United States)] [State of Nevada Agency for Nuclear Projects, Carson City, NV 80906 (United States); Ballard, James D. [Department of Sociology, California State University, Northridge, CA 91330 (United States)] [Department of Sociology, California State University, Northridge, CA 91330 (United States)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive material shipments" 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

Coordinating production and shipment decisions in a two-stage supply chain with time-sensitive demand  

Science Journals Connector (OSTI)

This paper investigates a supply chain system consisting of one manufacturer who receives an order from a single retailer and then coordinates a production and shipment schedule to fulfill the retailer's order as quickly and cost effectively as possible. ... Keywords: Direct shipping, Inventory control, Supply chain responsiveness

Emmett J. Lodree, Jr.; Christopher D. Geiger; Kandace N. Ballard

2010-03-01T23:59:59.000Z

362

Radioactive Waste Management Manual  

Directives, Delegations, and Requirements

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

363

Packaging and Transfer or Transportation of Materials of National Security Interest  

Directives, Delegations, and Requirements

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

364

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

365

EIA Energy Efficiency-Table 3a. Value of Shipments by Selected Industries,  

Gasoline and Diesel Fuel Update (EIA)

a a Page Last Modified: May 2010 Table 3a. Value of Shipments 1 by Selected Industries, 1998, 2002, and 2006 (Current Billion Dollars) MECS Survey Years NAICS Subsector and Industry 1998 2002 2006 311 Food Manufacturing 428 457 538 312 Beverage and Tobacco Product Manufacturing 102 104 125 313 Textile Mills 57 45 39 314 Textile Product Mills 31 32 33 315 Apparel Manufacturing 65 45 30 316 Leather and Allied Product Manufacturing 10 7 6 321 Wood Product Manufacturing 91 88 112 322 Paper Manufacturing 155 153 170 323 Printing and Related Support Activities 100 96 100 324 Petroleum and Coal Products Manufacturing 138 216 549 325 Chemical Manufacturing 417 454 658 326 Plastics and Rubber Products Manufacturing 164 173 211

366

EIA Energy Efficiency-Table 4a. Value of Shipments by Selected Industries,  

Gasoline and Diesel Fuel Update (EIA)

Table 4a Table 4a Page Last Modified: May 2010 Table 4a. Value of Shipments1 by Selected Industries, 1998, 2002, and 2006 (Billion 2000 Dollars ) MECS Survey Years NAICS Subsector and Industry 1998 2002 2006 311 Food Manufacturing 430 448 472 312 Beverage and Tobacco Product Manufacturing 121 96 109 313 Textile Mills 56 47 37 314 Textile Product Mills 31 32 30 315 Apparel Manufacturing 65 45 30 316 Leather and Allied Product Manufacturing 10 6 6 321 Wood Product Manufacturing 92 89 100 322 Paper Manufacturing 168 156 153 323 Printing and Related Support Activities 103 93 92 324 Petroleum and Coal Products Manufacturing 227 242 265 325 Chemical Manufacturing 440 452 509 326 Plastics and Rubber Products Manufacturing 168 171 175

367

The maritime shipment of LNG to Europe: dynamics in markets, ships and terminal projects  

Science Journals Connector (OSTI)

The aim of this paper is to explore how the maritime shipment of liquefied natural gas (LNG) to Europe has developed over the last decade, given the growing usage of natural gas and increasing seaborne trade volume of LNG over the world. This paper presents the current situation of the LNG trade flows in Europe and also investigates the dynamics of the LNG shipping market, fleet development and import terminal projects in Europe, which are all indispensable to transport LNG to the European market. It is found that Europe increases LNG imports largely in recent years in order to secure its gas supply for seasonal fluctuations. Responding to such rising import volume, many new facilities are being built and planned in the region, including the ordering of new ships and the construction of new regasification terminals.

Siyuan Wang; Theo Notteboom

2012-01-01T23:59:59.000Z

368

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

369

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

370

Radioactive Waste Management Manual  

Directives, Delegations, and Requirements

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

371

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  

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

372

Radioactive Dust from Nuclear Detonations  

Science Journals Connector (OSTI)

...than the dose received from natural radioactivity in a period of...radioactive particles. The natural radioactivity of the atmosphere...curies/liter. This radioactive gas is present in equilibrium with...With an approximation of the natural radiation dose to the lung as...

Merril Eisenbud; John H. Harley

1953-02-13T23:59:59.000Z

373

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

374

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

NLE Websites -- All DOE Office Websites (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...

375

Radioactive residues associated with water treatment, use and disposal in Australia.  

E-Print Network (OSTI)

??Water resources are known to contain radioactive materials, either from natural or anthropogenic sources. Treatment, including wastewater treatment, of water for drinking, domestic, agricultural and (more)

Kleinschmidt, Ross Ivan

2011-01-01T23:59:59.000Z

376

E-Print Network 3.0 - automated radioactive particle Sample Search...  

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

OF TARGET MATERIAL RECYCLING AS WASTE MANAGEMENT ALTERNATIVE Summary: , requires remote handling, adds radioactive storage fa- cilities, and increases the cost and...

377

Radioactive Nickel-63 - ORNL Neutron Sciences  

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

Making Radioactive Nickel-63 Making Radioactive Nickel-63 ORNL-Supplied Nickel-63 Enables High-Sensitivity Explosives, Chemical Weapons, and Narcotics Detectors at Airports Explosives and narcotics detector. Detectors based on ion mobility spectrometry using ORNL 63Ni can now satisfy enhanced Homeland Security requirements at airports and other sensitive locations. When Transportation Security Administration (TSA) inspectors swipe a cloth over your luggage and then place it in an analyzer to check for explosives residue, they are using a device containing 63Ni, a radioactive isotope of nickel, made at ORNL. ORNL is the exclusive producer for 63Ni in North America and perhaps worldwide. "Our only competition would probably be Russia. They have high-flux research reactors and may well be supplying the material also,"

378

Public involvement in radioactive waste management decisions  

SciTech Connect

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

379

Fernald vacuum transfer system for uranium materials repackaging  

SciTech Connect

The Fernald Environmental Management Project (FEMP) is the site of a former Department of Energy (DOE) uranium processing plant. When production was halted, many materials were left in an intermediate state. Some of this product material included enriched uranium compounds that had to be repackaged for shipment of off-site storage. This paper provides an overview, technical description, and status of a new application of existing technology, a vacuum transfer system, to repackage the uranium bearing compounds for shipment. The vacuum transfer system provides a method of transferring compounds from their current storage configuration into packages that meet the Department of Transportation (DOT) shipping requirements for fissile materials. This is a necessary activity, supporting removal of nuclear materials prior to site decontamination and decommissioning, key to the Fernald site's closure process.

Kaushiva, Shirley; Weekley, Clint; Molecke, Martin; Polansky, Gary

2002-02-24T23:59:59.000Z

380

The basics in transportation of low-level radioactive waste  

SciTech Connect

This bulletin gives a basic understanding about issues and safety standards that are built into the transportation system for radioactive material and waste in the US. An excellent safety record has been established for the transport of commercial low-level radioactive waste, or for that matter, all radioactive materials. This excellent safety record is primarily because of people adhering to strict regulations governing the transportation of radioactive materials. This bulletin discusses the regulatory framework as well as the regulations that set the standards for packaging, hazard communications (communicating the potential hazard to workers and the public), training, inspections, routing, and emergency response. The excellent safety record is discussed in the last section of the bulletin.

Allred, W.E.

1998-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive material shipments" 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

Radioactivity in food crops  

SciTech Connect

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

382

Hazardous Material Packaging for Transport - Administrative Procedures  

Directives, Delegations, and Requirements

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

383

Radioactive Waste Management Manual  

Directives, Delegations, and Requirements

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

384

Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)  

SciTech Connect

In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

D'Amico, E. L [Washington TRU Solutions (United States); Edmiston, D. R. [John Hart and Associates (United States); O'Leary, G. A. [CH2M-WG Idaho, LLC (United States); Rivera, M. A. [Aspen Resources Ltd., Inc. (United States); Steward, D. M. [Boulder Research Enterprises, LLC (United States)

2006-07-01T23:59:59.000Z

385

University of Hawaii TABLE OF CONTENTS  

E-Print Network (OSTI)

Spills 3-1 C. Injuries to Personnel 3-2 D. Fires Involving Radioactive Materials 3-2 Part IV: Waste Shipments App. A-11 Radioactive Waste Pickup Form Instructions App. A-12 Radioactive Waste Pickup Request Instructions for Cruise Radioactive Waste App. A-16 Radioactive Waste Pick-Up Request form for R/V cruises App

Browder, Tom

386

Security for Radioactive Sources: Fact Sheet | National Nuclear Security  

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

for Radioactive Sources: Fact Sheet | National Nuclear Security for Radioactive Sources: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Security for Radioactive Sources: Fact Sheet Fact Sheet Security for Radioactive Sources: Fact Sheet Mar 23, 2012 Radioactive materials are a critical and beneficial component of global

387

Level: National and Regional Data; Row: NAICS Codes; Column: Energy Sources and Shipments;  

U.S. Energy Information Administration (EIA) Indexed Site

Coke and Shipments Net Residual Distillate Natural LPG and Coal Breeze of Energy Sources NAICS Total(b) Electricity(c) Fuel Oil Fuel Oil(d) Gas(e) NGL(f) (million (million Other(g) Produced Onsite(h) Code(a) Subsector and Industry (trillion Btu) (million kWh) (million bbl) (million bbl) (billion cu ft) (million bbl) short tons) short tons) (trillion Btu) (trillion Btu) Total United States RSE Column Factors: 0.9 1 1.2 1.8 1 1.6 0.8 0.9 1.2 0.4 311 Food 1,123 67,521 2 3 567 1 8 * 89 0 311221 Wet Corn Milling 217 6,851 * * 59 * 5 0 11 0 31131 Sugar 112 725 * * 22 * 2 * 46 0 311421 Fruit and Vegetable Canning 47 1,960 * * 35 * 0 0 1 0 312 Beverage and Tobacco Products 105 7,639 * * 45 * 1 0 11 0 3121 Beverages 85 6,426 * * 41 * * 0 10 0 3122 Tobacco 20 1,213 * * 4 * * 0 1 0 313 Textile Mills 207 25,271 1 * 73 * 1 0 15 0 314

388

Sealed Radioactive Source Accountability  

Directives, Delegations, and Requirements

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

389

Sealed Radioactive Source Accountability  

Directives, Delegations, and Requirements

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

390

Vacuuming radioactive sludge  

SciTech Connect

Vacuuming an estimated 55 cubic yards of radioactive sludge from the floor of Hanford's K East Basin was a complicated process. Workers stood on grates suspended above the 20-foot deep basin and manipulated vacuuming equipment at the end of long poles--using underwater cameras to guide their work.

2006-10-16T23:59:59.000Z

391

Radioactive Waste Management  

Directives, Delegations, and Requirements

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

392

Questions and Answers - How does the radioactivity of an atom affect the  

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

How is radioactivity measured? How is radioactivity measured? Previous Question (How is radioactivity measured?) Questions and Answers Main Index Next Question (Why do we use radioactivity to destroy cancers?) Why do we use radioactivityto destroy cancers? How does the radioactivity of an atom affect the body? You've asked a very broad question, so we'll have to split it up into smaller chunks in order to give you a reasonable answer. This is a topic that is very much misunderstood by most people and it's hard to give a short answer. You may know that all of us have radioactive material in our bodies naturally. There has always been radioactive material on earth (in fact, a million years ago, there was more present than there is today), and people have therefore always been exposed to it. There has also always been cosmic

393

2005 TEPP Annual Report | Department of Energy  

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

5 TEPP Annual Report 5 TEPP Annual Report 2005 TEPP Annual Report During FY 2005, the Office of Environmental Management completed over 21,000 shipments of radioactive material and waste. Hazardous material shipments continue to be of concern to communities. This is particularly true for radioactive material. An underlying concern is the adequacy of emergency preparedness along DOE shipping corridors. Within the DOE Office of Environmental Management, the Office of Transportation implements the complex-wide Transportation Emergency Preparedness Program (TEPP) to address preparedness issues for radioactive material and waste shipments. As an element of the DOE Comprehensive Emergency Management System, TEPP provides support to Federal, state, tribal, and local authorities to

394

Finding Aids: Radioactive Fallout  

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

A Guide to Archival Collections Relating to Radioactive Fallout from Nuclear Weapon Testing A Guide to Archival Collections Relating to Radioactive Fallout from Nuclear Weapon Testing Table of Contents INTRODUCTION Argonne National Laboratory Bancroft Library, University of California Boeing Aircraft Company Brookhaven National Laboratory Coordination and Information Center (CIC) Eastman Kodak EG&G, Energy Measurements Holmes and Narver Lawrence Livermore National Laboratory Los Alamos National Laboratory Manuscript Division, Library of Congress National Academy of Sciences Archives Oak Ridge National Laboratory Pacific Northwest Laboratory Sandia National Laboratories Scripps Institution of Oceanography Archives Smithsonian Institution Archives U.S. Air Force Brooks Air Force Base Kirtland Air Force Base USAF Historical Research Center U.S. Army Chemical Corps (Aberdeen Proving Ground)

395

Shipping Radioactive Waste by Rail from Brookhaven National Laboratory...  

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

Documents & Publications West Valley Demonstration Project Low-Level Waste Shipment Nuclear Fuel Storage and Transportation Planning Project Overview Prairie Island Indian...

396

2004 TEPP Annual Report  

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

During FY 2004, the Office of Environmental Management completed over 23,000 shipments of radioactive material and waste. In recent years, the transport of all types of hazardous materials has...

397

Office of Civilian Radioactive Waste Management fiscal year 1996 annual report to Congress  

SciTech Connect

In Fiscal Year 1996 a revised program strategy was developed that reflects Administration policy and responds to sharply reduced funding and congressional guidance while maintaining progress toward long-term objectives. The program is on track, working toward an early, comprehensive assessment of the viability of the Yucca Mountain site; more closely determining what will be required to incorporate defense waste into the waste management system; pursuing a market-driven strategy for waste acceptance, storage, and transportation; and preserving the core capability to respond to an interim storage contingency. Overall, the elements of an integrated system for managing the Nation`s spent fuel and high-level radioactive waste are emerging, more soundly conceived, and more modestly designed, as the OCRWM works toward the physical reality of waste shipments to Federal facilities.

NONE

1997-05-01T23:59:59.000Z

398

THE USE OF POLYMERS IN RADIOACTIVE WASTE PROCESSING SYSTEMS  

SciTech Connect

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

399

"NAICS",,"per Employee","of Value Added","of Shipments"  

U.S. Energy Information Administration (EIA) Indexed Site

1 Relative Standard Errors for Table 6.1;" 1 Relative Standard Errors for Table 6.1;" " Unit: Percents." ,,,,"Consumption" ,,,"Consumption","per Dollar" ,,"Consumption","per Dollar","of Value" "NAICS",,"per Employee","of Value Added","of Shipments" "Code(a)","Subsector and Industry","(million Btu)","(thousand Btu)","(thousand Btu)" ,,"Total United States" 311,"Food",3.8,4.3,4.1 3112," Grain and Oilseed Milling",8.2,5.8,5.6 311221," Wet Corn Milling",0,0,0 31131," Sugar Manufacturing",0,0,0 3114," Fruit and Vegetable Preserving and Specialty Foods ",7.3,6.7,6.2

400

Solar Powered Radioactive Air Monitoring Stations  

SciTech Connect

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

Note: This page contains sample records for the topic "radioactive material shipments" 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

EA-1599: Disposition of Radioactively Contaminated Nickel Located at the  

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

99: Disposition of Radioactively Contaminated Nickel Located 99: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications EA-1599: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications Summary This EA was being prepared to evaluate potential environmental impacts of a proposal to dispose of nickel scrap that is volumetrically contaminated with radioactive materials and that DOE recovered from equipment it had used in uranium enrichment. This EA is on hold. Public Comment Opportunities No public comment opportunities at this time.

402

Radioactivities in Solution by Particle Radiation can Increase Sister  

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

Radioactivities in Solution by Particle Radiation can Increase Sister Radioactivities in Solution by Particle Radiation can Increase Sister Chromatid Exchanges Junko Maeda Colorado State University Abstract Introduction Non-radioactive atoms can become radioactive from a nuclear reaction when atoms are hit by other high energy particles. These radioactivations are observed in nuclear facilities and may result in health effects in humans. Protons, carbon-ions, and iron-ions are tested to verify this hypothesis. Materials and Methods Protons were accelerated to 70MeV in cyclotron (NIRS-930) at National Institute of Radiological Sciences (NIRS). Carbon-ions and iron-ions were accelerated to 290MeV/n and 500MeV/n respectively, in HIMAC (Heavy ion Medical Accelerator in Chiba) at NIRS. 60ml of sterilized Milli-Q ultra pure water or PBS were filled in Falcon T25 flasks and exposed to ionizing

403

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

404

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

405

Environmental assessment for the manufacture and shipment of nuclear reactor fuel from the United States to Canada  

SciTech Connect

The US Department of Energy (DOE) has declared 41.9 tons (38 metric tons) of weapons-usable plutonium surplus to the United States` defense needs. A DOE Programmatic Environmental Impact Statement analyzed strategies for plutonium storage and dispositioning. In one alternative, plutonium as a mixed oxide (MOX) fuel would be irradiated (burned) in a reengineered heavy-water-moderated reactor, such as the Canadian CANDU design. In an Environmental Assessment (EA), DOE proposes to fabricate and transport to Canada a limited amount of MOX fuel as part of the Parallex (parallel experiment) Project. MOX fuel from the US and Russia would be used by Canada to conduct performance tests at Chalk River Laboratories. MOX fuel would be fabricated at Los Alamos National Laboratory and transported in approved container(s) to a Canadian port(s) of entry on one to three approved routes. The EA analyzes the environmental and human health effects from MOX fuel fabrication and transportation. Under the Proposed Action, MOX fuel fabrication would not result in adverse effects to the involved workers or public. Analysis showed that the shipment(s) of MOX fuel would not adversely affect the public, truck crew, and environment along the transportation routes.

Rangel, R.C.

1999-02-01T23:59:59.000Z

406

FAQ 5-Is uranium radioactive?  

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

Is uranium radioactive? Is uranium radioactive? Is uranium radioactive? All isotopes of uranium are radioactive, with most having extremely long half-lives. Half-life is a measure of the time it takes for one half of the atoms of a particular radionuclide to disintegrate (or decay) into another nuclear form. Each radionuclide has a characteristic half-life. Half-lives vary from millionths of a second to billions of years. Because radioactivity is a measure of the rate at which a radionuclide decays (for example, decays per second), the longer the half-life of a radionuclide, the less radioactive it is for a given mass. The half-life of uranium-238 is about 4.5 billion years, uranium-235 about 700 million years, and uranium-234 about 25 thousand years. Uranium atoms decay into other atoms, or radionuclides, that are also radioactive and commonly called "decay products." Uranium and its decay products primarily emit alpha radiation, however, lower levels of both beta and gamma radiation are also emitted. The total activity level of uranium depends on the isotopic composition and processing history. A sample of natural uranium (as mined) is composed of 99.3% uranium-238, 0.7% uranium-235, and a negligible amount of uranium-234 (by weight), as well as a number of radioactive decay products.

407

Properties of Natural Radiation and Radioactivity  

SciTech Connect

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

408

Radioactive waste management in the former USSR  

SciTech Connect

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

409

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

410

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

411

Radiation levels on empty cylinders containing heel material  

SciTech Connect

Empty UF{sub 6} cylinders containing heel material were found to emit radiation levels in excess of 200 mr/hr, the maximum amount stated in ORO-651. The radiation levels were as high as 335 mr/hr for thick wall (48X and 48Y) cylinders and 1050 mr/hr for thin wall (48G and 48H) cylinders. The high readings were found only on the bottom of the cylinders. These radiation levels exceeded the maximum levels established in DOT 49 CFR, Part 173.441 for shipment of cylinders. Holding periods of four weeks for thick-wall cylinders and ten weeks for thin-wall cylinders were established to allow the radiation levels to decay prior to shipment.

Shockley, C.W. [Martin Marietta Energy Systems, Inc., Paducah, KY (United States)

1991-12-31T23:59:59.000Z

412

Most Viewed Documents for Materials: September 2014 | OSTI, US...  

Office of Scientific and Technical Information (OSTI)

based design for radioactive material transport packagings -- Historical review Smith, J.A.; Salzbrenner, D.; Sorenson, K.; McConnell, P. (1998) 61 Charpy impact test...

413

SPRU Removes High-Risk Radioactive Waste  

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

NISKAYUNA, N.Y. EMs Separations Process Research Unit (SPRU) Disposition Project completed a significant waste-treatment campaign in February that involved the solidification of approximately 9,700 gallons of contaminated sludge and 14 shipments of the waste off-site for permanent disposal.

414

Civilian Radioactive Waste Management System Requirements Document...  

Office of Environmental Management (EM)

Civilian Radioactive Waste Management System Requirements Document Civilian Radioactive Waste Management System Requirements Document This document specifies the top-level...

415

Radioactive Waste Management Complex Wide Review | Department...  

Office of Environmental Management (EM)

Radioactive Waste Management Complex Wide Review Radioactive Waste Management Complex Wide Review The main goal of this complex-wide review was to obtain feedback from DOE sites...

416

5 - Fukushima Radioactivity Impact  

Science Journals Connector (OSTI)

Abstract Huge amounts of radioactivity have been released to the environment because of the Fukushima Dai-ichi Nuclear Power Plant (NPP) accident. In order to implement adequate protective actions and to assess the impact of the Fukushima radioactivity on the environment, an environmental monitoring has been conducted by national and local governments, research institutes and universities in Japan and over the world. The environmental monitoring revealed that heavy radioactivity-contaminated areas appeared within about 50 km of the Fukushima Dai-ichi NPP, controlled by land topography as do meteorological factors. The Fukushima-derived radionuclides, in which dominant nuclides were 131I, 134Cs and 137Cs, contaminated food stuffs. The radionuclide levels exceeded the regulation values in a part of food stuffs produced within about 500 km off Fukushima. Based on the comprehensive monitoring data, we describe here levels of the Fukushima-derived radionuclides in terrestrial and marine environments and in food products in Japan and over the globe. Temporal and spatial distributions of Fukushima-derived radionuclides in aerosols revealed the presence of two dominant radionuclide maxima which were observed throughout the Europe with decreasing amplitudes from the North to the South, which were associated with different air masses present in the European air. Modeled forward and backward trajectories indicated a preferential transport of air masses between Fukushima and Europe at 500 hPa (5000 m a. s. l.) air heights. The Lagrangian dispersion modeling showed that the horizontal dispersion in the Europe reached about 4000-km-wide belt, however, the entire world has been labeled with the Fukushima radionuclides, although at very low levels. A typical travel time between Fukushima and Europe has been estimated to be of 1015 days, with an average speed of the plume of 5070 km/h. An average 131I concentration, which was measured over the Europe (?1 mBq/m3), would result in the total amount of dispersed 131I of about 1 PBq. Although this represents a high release rate (almost 1% of the total amount of 131I released from the Fukushima NPP), as it was distributed over a huge area, it has not been of any radiological significance for European citizens. 134Cs and 137Cs were released to the North Pacific Ocean by two major likely pathways, direct discharge from the Fukushima Dai-ichi NPP site and atmospheric deposition off Honshu Islands of Japan, east and northeast of the site. High-density observations of 134Cs and 137Cs in the surface water were carried out by 17 cruises of cargo ships and several research-vessel cruises since March 2011 till March 2012. Main body of radioactive surface plume whose activity exceeded 10 Bq/m3 had been traveling along 40 N, and reached International Date Line on March 2012, 1 year after the accident. A zonal speed of the radioactive plume was estimated to be about 8 cm/s which was consistent with the zonal speed derived by Argo floats and satellite observations at the region. The dispersion of Fukushima-derived 137Cs in surface seawater of the North Pacific Ocean was carried out using an ocean global circulation model. The traveling time from the Fukushima coast to the US west coast was estimated to be 45 years, and the predicted 137Cs levels will reach ?3 Bq/m3, which are by about a factor of three higher than the present global fallout background levels. After 10 years, the 137Cs in the North Pacific Ocean will not be distinguishable over the global fallout background of 1 Bq/m3. The maximum predicted 137Cs activity concentrations in 2012 in the open western North Pacific Ocean will be around 20 Bq/m3, which will be comparable to that observed during the early 1960s after atmospheric nuclear weapons tests. However, after 10 years this concentration will be similar to that from global fallout. The open Pacific Ocean radionuclide concentrations will not pose therefore any radiation risk to the world population from consumption of seafood collected in this region.

Pavel P. Povinec; Katsumi Hirose; Michio Aoyama

2013-01-01T23:59:59.000Z

417

The Measurement of Body Radioactivity: Conference at Leeds  

Science Journals Connector (OSTI)

... Thames water (since this has a considerably lower radioactivity than Stockholm water) and the radon content of the air is reduced by forced ventilation. With these precautions to reduce ... all the differences in radium content. Dr. Hultqvist also described a survey of the radon and thoron content of air in Swedish homes of various building materials3, and showed ...

G. W. REED

1956-07-28T23:59:59.000Z

418

ORDER  

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

6-2010 6-2010 PACKAGING AND TRANSPORTATION FOR OFFSITE SHIPMENT OF MATERIALS OF NATIONAL SECURITY INTEREST NATIONAL NUCLEAR SECURITY ADMINISTRATION Office of Defense Programs DOE O 461.1B DOE O 461.1B 1 12-16-2010 PACKAGING AND TRANSPORTATION FOR OFFSITE SHIPMENT OF MATERIALS OF NATIONAL SECURITY INTEREST 1. PURPOSE. The Department of Energy (DOE) has broad authority under the Atomic Energy Act of 1954, as amended (AEA), to regulate all aspects of activities involving radioactive materials that are undertaken by DOE or on its behalf, including the transportation of radioactive materials. DOE exercises this authority to regulate certain DOE shipments, such as shipments of materials of national security interest undertaken by governmental employees or shipments involving special circumstances. The National

419

Summary of radioactive solid waste received in the 200 Areas during calendar year 1992  

SciTech Connect

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

420

Summary of radioactive solid waste received in the 200 Areas during calendar year 1994  

SciTech Connect

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

Note: This page contains sample records for the topic "radioactive material shipments" 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

Summary of radioactive solid waste received in the 200 Areas during calendar year 1993  

SciTech Connect

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

422

Kevin Blackwell, FRA Mike Butler, UETC Sandy Covi, UPRR Steve...  

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

for the Topic Group to discuss DOE's process for mode selection, the use of dedicated trains in spent fuel shipments, the feasibility of shipping low-level radioactive materials...

423

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

424

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

425

Radioactive Kr Isotopes  

Science Journals Connector (OSTI)

A radioactive isotope of 1.1-hour half-life has been produced in krypton by alpha-particle bombardment of Se74, enriched electromagnetically from 0.9 percent to 14.1 percent. Assignment of the isotope is made to Kr77. Aluminum absorption measurements indicate a positron end point of 1.7 Mev. In addition to annihilation radiation, gamma-rays and K-capture have been observed. The ratio of K-capture to positron emission from the Se74(?,n) reaction is computed as 2.6. The krypton 1.42-day isotope has been produced by an ?,n reaction on electromagnetically enriched Se76. The isotope is located as Kr79 and its half-life confirmed. A positron end point of 1.0 Mev is determined by aluminum absorption measurements. In addition to annihilation radiation, gamma-rays and K-capture have been observed. The ratio of K-capture to positron emission from the Se76(?,n) reaction is computed to be 50. The cross-section ratio for formation of Kr77 compared to Kr79 by alpha-particle bombardment of selenium is computed as 1.4. The 4.6-hour Kr85 isotope has been produced by a Se(?,n) reaction.

L. L. Woodward; D. A. Mccown; M. L. Pool

1948-10-01T23:59:59.000Z

426

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

427

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

428

Microsoft Word - Last Legacy Waste Shipment for EM Weekly 4-7...  

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

site lead for the U.S. Department of Energy (DOE). "It reduces the cost of long-term storage, surveillance, and maintenance of waste materials. It frees up space on the site to...

429

The largest radioactive waste glassification  

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

largest radioactive waste glassification largest radioactive waste glassification plant in the nation, the Defense Waste Processing Facility (DWPF) converts the liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for treating liquid nuclear waste. By immobilizing the radioactivity in glass, the DWPF reduces the risks associated with the continued storage of liquid nuclear waste at SRS and prepares the waste for final disposal in a federal repository. About 38 million gallons of liquid nuclear wastes are now stored in 49 underground carbon-steel tanks at SRS. This waste has about 300 million curies of radioactivity, of which the vast majority

430

Radioactivity of the Cooling Water  

DOE R&D Accomplishments (OSTI)

The most important source of radioactivity at the exit manifold of the pile will be due to O{sup 19}, formed by neutron absorption of O{sup 18}. A recent measurement of Fermi and Weil permits to estimate that it will be safe to stay about 80 minutes daily close to the exit manifolds without any shield. Estimates are given for the radioactivities from other sources both in the neighborhood and farther away from the pile.

Wigner, E. P.

1943-03-01T23:59:59.000Z

431

Radioactive and mixed waste - risk as a basis for waste classification. Symposium proceedings No. 2  

SciTech Connect

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

432

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

SciTech Connect

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

433

CHAPTER 5-RADIOACTIVE WASTE MANAGEMENT  

SciTech Connect

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

434

SCO shipments from Rocky Flats - Experience and current practice [Surface Contaminated Object  

SciTech Connect

Decommissioning activities at Rocky Flats Environmental Technology Site (RFETS) are expected to generate approximately 251,000 cubic meters of low-level radioactive waste. Almost half of this will be characterized and shipped as the Department of Transportation ''Surface Contaminated Object'' (SCO) shipping class. In the 2 years since an SCO characterization method was implemented, almost 11,000 of the 18,000 cubic meters of low-level waste were SCO. RFETS experience to-date using an SCO waste characterization method has shown significant time and cost savings, reduced errors, and enhanced employee safety. SCO waste is characterized prior to packaging, near the point of generation, by any of the site's 300 Radiological Control Technicians using inexpensive radiological control survey instruments. This reduces on-site waste container moves and eliminates radiometric analysis at centrally located drum or crate counters. Containers too large for crate counters can also be characterized. Current instrumentation is not adequate to take full advantage of the SCO regulations. Future improvements in the SCO characterization and shipping process are focused on use of larger and/or reusable containers, extended-range instruments, and additional statistical methods, so that the full extent of the SCO regulations can be used.

Bracken, Gary; Morris, Robert L.

2001-01-10T23:59:59.000Z

435

REMOVAL OF LEGACY PLUTONIUM MATERIALS FROM SWEDEN  

SciTech Connect

U.S. Department of Energys National Nuclear Security Administration (NNSA) Office of Global Threat Reduction (GTRI) recently removed legacy plutonium materials from Sweden in collaboration with AB SVAFO, Sweden. This paper details the activities undertaken through the U.S. receiving site (Savannah River Site (SRS)) to support the characterization, stabilization, packaging and removal of legacy plutonium materials from Sweden in 2012. This effort was undertaken as part of GTRIs Gap Materials Program and culminated with the successful removal of plutonium from Sweden as announced at the 2012 Nuclear Security Summit. The removal and shipment of plutonium materials to the United States was the first of its kind under NNSAs Global Threat Reduction Initiative. The Environmental Assessment for the U.S. receipt of gap plutonium material was approved in May 2010. Since then, the multi-year process yielded many first time accomplishments associated with plutonium packaging and transport activities including the application of the of DOE-STD-3013 stabilization requirements to treat plutonium materials outside the U.S., the development of an acceptance criteria for receipt of plutonium from a foreign country, the development and application of a versatile process flow sheet for the packaging of legacy plutonium materials, the identification of a plutonium container configuration, the first international certificate validation of the 9975 shipping package and the first intercontinental shipment using the 9975 shipping package. This paper will detail the technical considerations in developing the packaging process flow sheet, defining the key elements of the flow sheet and its implementation, determining the criteria used in the selection of the transport package, developing the technical basis for the package certificate amendment and the reviews with multiple licensing authorities and most importantly integrating the technical activities with the Swedish partners.

Dunn, Kerry A. [Savannah River National Laboratory; Bellamy, J. Steve [Savannah River National Laboratory; Chandler, Greg T. [Savannah River National Laboratory; Iyer, Natraj C. [U.S. Department of Energy, National Nuclear Security Administration, Office of; Koenig, Rich E.; Leduc, D. [Savannah River National Laboratory; Hackney, B. [Savannah River National Laboratory; Leduc, Dan R. [Savannah River National Laboratory

2013-08-18T23:59:59.000Z

436

Questions and Answers - Do radioactive things glow in the dark?  

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

Someone told me that Cherenkov radiationis analogous to breaking the sound barrier... Someone told me that Cherenkov radiation<br>is analogous to breaking the sound barrier... Previous Question (Someone told me that Cherenkov radiation is analogous to breaking the sound barrier...) Questions and Answers Main Index Next Question (If energy is formed by a generator, how does it form the energy?) If energy is formed by a generator,how does it form the energy? Do radioactive things glow in the dark? The short answer to your question is "no," radioactive things do not glow in the dark - not by themselves anyway. Radiation emitted by radioactive materials is not visible to the human eye. However, there are ways to"convert" this invisible energy to visible light. Many substances will emit visible light if "stimulated" by the ionizing radiation from

437

Application of microwave solidification technology to radioactive waste  

SciTech Connect

The EPA has declared vitrification to be the Best Available Demonstrated Technology (BDAT) for High Level Radioactive Waste (40 CFR 268.42). Vitrification has been chosen as the method of choice for treating a number of radioactive residues and wastes in the DOE complex. Vitrification offers advantages of waste volume reduction, the ability to handle changing waste forms, and a stable, nonleachable final waste form. Microwave heating is a superior method for vitrification of radioactive wastes. Advantages of microwave heating include: (1) direct waste heating, eliminates need for electrodes, refractories and other consumables; (2) ``in-can`` processing allows for treatment of the material in its final container, (3) a mechanically simple system where the microwaves are generated away from the treatment area and transmitted to the treatment applicator by a wave guide, thus minimizing worker exposure to radiation; (4) easier equipment maintenance; and (5) a high degree of public acceptance.

Harris, M.; Sprenger, G.; Roushey, B.; Fenner, G.; Nieweg, R.

1995-09-28T23:59:59.000Z

438

Material Balance Report NRC 742u  

National Nuclear Security Administration (NNSA)

2*** 2*** Company Name and Address License Number RIS A 10/01/2007 09/30/2008 20 / E4 1 1 1 COMPANY NAME RIS A 2 1 1 DATE SIGNATURE (See instructions for provisions on confidentiality) TITLE 54. SHIPMENTS -- MISC 65. ROUNDING ADJUSTMENT 58. DONATED MATERIAL -- TO U.S. GOVT BY OTHERS 59. DONATED MATERIAL -- TO OTHERS BY U.S. GOVT a. ICT b. ICT 72. DECAY 75. ACCIDENTAL LOSSES 73. FISSION AND TRANSMUTATION 74. NORMAL OPERATIONAL LOSSES/MEASURED DISCARDS 77. INVENTORY DIFFERENCE 82. TOTAL (lines 41-81) 80. ENDING INVENTORY -- U.S. GOVT OWNED 81. ENDING INVENTORY -- NOT U.S. GOVT OWNED MATERIAL ACCOUNTABILITY SECTION A (Continued) FOREIGN OBLIGATIONS SECTION B CERTIFICATION SECTION C To the best of my knowledge and belief, the information given above and in any attached schedules is true, complete, and correct.

439

Material Balance Report NRC 742u  

National Nuclear Security Administration (NNSA)

*** *** Company Name and Address License Number RIS 10/01/2007 09/30/2008 20 / E4 A 1 COMPANY NAME RIS A 2 1 1 1 1 DATE SIGNATURE (See instructions for provisions on confidentiality) TITLE 54. SHIPMENTS -- MISC 65. ROUNDING ADJUSTMENT 58. DONATED MATERIAL -- TO U.S. GOVT BY OTHERS 59. DONATED MATERIAL -- TO OTHERS BY U.S. GOVT a. ICT b. ICT 72. DECAY 75. ACCIDENTAL LOSSES 73. FISSION AND TRANSMUTATION 74. NORMAL OPERATIONAL LOSSES/MEASURED DISCARDS 77. INVENTORY DIFFERENCE 82. TOTAL (lines 41-81) 80. ENDING INVENTORY -- U.S. GOVT OWNED 81. ENDING INVENTORY -- NOT U.S. GOVT OWNED MATERIAL ACCOUNTABILITY SECTION A (Continued) FOREIGN OBLIGATIONS SECTION B CERTIFICATION SECTION C To the best of my knowledge and belief, the information given above and in any attached schedules is true, complete, and correct.

440

Material Balance Report NRC 742u  

National Nuclear Security Administration (NNSA)

*** *** Company Name and Address License Number RIS A 10/01/2007 09/30/2008 20 / E4 1 1 1 Company 1 RIS A 2 1 1 COMPANY NAME RIS A 3 1 1 DATE SIGNATURE (See instructions for provisions on confidentiality) TITLE 54. SHIPMENTS -- MISC 65. ROUNDING ADJUSTMENT 58. DONATED MATERIAL -- TO U.S. GOVT BY OTHERS 59. DONATED MATERIAL -- TO OTHERS BY U.S. GOVT a. ICT b. ICT 72. DECAY 75. ACCIDENTAL LOSSES 73. FISSION AND TRANSMUTATION 74. NORMAL OPERATIONAL LOSSES/MEASURED DISCARDS 77. INVENTORY DIFFERENCE 82. TOTAL (lines 41-81) 80. ENDING INVENTORY -- U.S. GOVT OWNED 81. ENDING INVENTORY -- NOT U.S. GOVT OWNED MATERIAL ACCOUNTABILITY SECTION A (Continued) FOREIGN OBLIGATIONS SECTION B CERTIFICATION SECTION C To the best of my knowledge and belief, the information given above and in any attached schedules is true, complete, and correct.

Note: This page contains sample records for the topic "radioactive material shipments" 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

Material Balance Report NRC 742u  

National Nuclear Security Administration (NNSA)

Example 4 *** Example 4 *** Company Name and Address License Number RIS A 10/01/2007 09/30/2008 20 / E4 1 1 1 A 2 1 1 DATE SIGNATURE (See instructions for provisions on confidentiality) TITLE 54. SHIPMENTS -- MISC 65. ROUNDING ADJUSTMENT 58. DONATED MATERIAL -- TO U.S. GOVT BY OTHERS 59. DONATED MATERIAL -- TO OTHERS BY U.S. GOVT a. ICT b. ICT 72. DECAY 75. ACCIDENTAL LOSSES 73. FISSION AND TRANSMUTATION 74. NORMAL OPERATIONAL LOSSES/MEASURED DISCARDS 77. INVENTORY DIFFERENCE 82. TOTAL (lines 41-81) 80. ENDING INVENTORY -- U.S. GOVT OWNED 81. ENDING INVENTORY -- NOT U.S. GOVT OWNED MATERIAL ACCOUNTABILITY SECTION A (Continued) FOREIGN OBLIGATIONS SECTION B CERTIFICATION SECTION C To the best of my knowledge and belief, the information given above and in any attached schedules is true, complete, and correct.

442

Analysis of International Commodity Shipping Data and the Shipment of NORM to the United States  

SciTech Connect

As part of the Spreader Bar Radiation Detector project, PNNL analyzed US import data shipped through US ports collected over the 12 months of 2006 (over 4.5 million containers). Using these data, we extracted a variety of distributions that are of interest to modelers and developers of active and passive detection systems used to 'scan' IMCCs for potential contraband. This report expands on some of the analysis presented in an earlier report from LLNL, by investigation the foreign port distribution of commodities shipped to the US. The majority of containers shipped to the United States are 40 ft containers ({approx}70%); about 25% are 20 ft; and about 3.6% are 45 ft containers. A small fraction (<1%) of containers are of other more specialized sizes, and very few ports actually ship these unique size containers (a full distribution for all foreign ports is shown in Appendix A below). The primary foreign ports that ship the largest fraction of each container are shown in the table below. Given that 45 ft containers comprise 1 of out every 27 containers shipped to the US, and given the foreign ports from which they are shipped, they should not be ignored in screening; further testing and analysis of radiation measurements for national security with this size container is warranted. While a large amount of NORM is shipped in IMCCs, only a few specific commodities are shipped with enough frequency to present potential issues in screening IMCCs at ports. The majority of containers with NORM will contain fertilizers (5,700 containers), granite (59,000 containers), or ceramic (225,000 containers) materials. Fertilizers were generally shipping in either 20- or 40 ft containers with equal frequency. While granite is mostly shipped in 20 ft containers, ceramic materials can be shipped in either 20- or 40 ft containers. The size of container depended on the specific use of the ceramic or porcelain material. General construction ceramics (such as floor and roofing tiles) tend to be shipped in 20 ft containers. Consumer products made from ceramic materials (e.g., tableware, sinks, and toilets) are generally shipped in 40 ft containers. This distinct discrepancy is due in large part to the packaging of the commodity. Consumer products are generally shipped packed in a box loaded with Styrofoam or other packing material to protect the product from breakage. Construction ceramic materials are generally shipped in less packing material, many times consisting of only a cardboard or wooden box. Granite is almost always shipped in a 20 ft container, given its very high density.

Baciak, James E.; Ely, James H.; Schweppe, John E.; Sandness, Gerald A.; Robinson, Sean M.

2011-10-01T23:59:59.000Z

443

Radioactive Liquid Waste Treatment Facility Discharges in 2011  

SciTech Connect

This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2011. During 2011, three pathways were available for the discharge of treated water to the environment: discharge as water through NPDES Outfall 051 into Mortandad Canyon, evaporation via the TA50 cooling towers, and evaporation using the newly-installed natural-gas effluent evaporator at TA50. Only one of these pathways was used; all treated water (3,352,890 liters) was fed to the effluent evaporator. The quality of treated water was established by collecting a weekly grab sample of water being fed to the effluent evaporator. Forty weekly samples were collected; each was analyzed for gross alpha, gross beta, and tritium. Weekly samples were also composited at the end of each month. These flow-weighted composite samples were then analyzed for 37 radioisotopes: nine alpha-emitting isotopes, 27 beta emitters, and tritium. These monthly analyses were used to estimate the radioactive content of treated water fed to the effluent evaporator. Table 1 summarizes this information. The concentrations and quantities of radioactivity in Table 1 are for treated water fed to the evaporator. Amounts of radioactivity discharged to the environment through the evaporator stack were likely smaller since only entrained materials would exit via the evaporator stack.

Del Signore, John C. [Los Alamos National Laboratory

2012-05-16T23:59:59.000Z

444

Radioactive waste disposal sites. January 1984-August 1989 (Citations from Pollution Abstracts). Report for January 1984-August 1989  

SciTech Connect

This bibliography contains citations concerning disposal sites for radioactive waste materials. Studies on potential sites for nuclear waste disposal include environmental surveys, trace element migration studies, groundwater characterization, rock mechanics, public opinion, pilot studies, and economic considerations. Safety aspects and risks associated with radioactive waste disposal are also considered. Radioactive waste processing and containerization are referenced in related published bibliographies. (Contains 155 citations fully indexed and including a title list.)

Not Available

1990-01-01T23:59:59.000Z

445

Transfer of excess nuclear material from Los Alamos to Savannah River site for long-term disposition  

SciTech Connect

Los Alamos National Laboratory is preparing excess nuclear material for shipment to Savannah River Site (SRS) for final disposition. Prior to shipment the nuclear material will be stabilized and packaged to meet strict criteria. The criterion that must be met include: (1) the DOE stabilization, packaging and storage requirements for plutonium bearing materials, DOE-STD-3013, (2) shipping container packaging requirements, (3) SRS packaging and storage criteria, and (4) DOE Material Disposition criteria for either immobilization or MOX reactor fuel. Another issue in preparing for this transfer is the DOE certification of shipping containers and the availability of shipping containers. This transfer of the nuclear material is fully supported by the EM, DP and NN Sections of the DOE, as well as, by LANL and SRS, yet a strong collaboration is needed to meet all established requirements relating to stabilization, packaging, shipment, storage and final disposition. This paper will present the overall objectives, the issues and the planned strategy to accomplish this nuclear material transfer.

Hoth, C. W. (Carl W.); Yarbro, T. F. (Tresa F.); Foster, Lynn A.

2001-06-01T23:59:59.000Z

446

Testing atomic mass models with radioactive beams  

SciTech Connect

Significantly increased yields of new or poorly characterized exotic isotopes that lie far from beta-decay stability can be expected when radioactive beams are used to produce these nuclides. Measurements of the masses of these new species are very important. Such measurements are motivated by the general tendency of mass models to diverge from one another upon excursions from the line of beta-stability. Therefore in these regions (where atomic mass data are presently nonexistent or sparse) the models can be tested rigorously to highlight the features that affect the quality of their short-range and long-range extrapolation properties. Selection of systems to study can be guided, in part, by a desire to probe those mass regions where distinctions among mass models are most apparent and where yields of exotic isotopes, produced via radioactive beams, can be optimized. Identification of models in such regions that have good predictive properties will aid materially in guiding the selection of additional experiments which ultimately will provide expansion of the atomic mass database for further refinement of the mass models. 6 refs., 5 figs.

Haustein, P.E.

1989-01-01T23:59:59.000Z

447

DOE Comments on Radioactive Waste | Department of Energy  

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

on Radioactive Waste DOE Comments on Radioactive Waste 1. Summary Comments on Draft Branch Technical Position on a Performance Assessment Methodology for Low-Level Radioactive...

448

Northeast High-Level Radioactive Waste Transportation Task Force...  

Office of Environmental Management (EM)

Northeast High-Level Radioactive Waste Transportation Task Force Agenda Northeast High-Level Radioactive Waste Transportation Task Force Agenda Northeast High-Level Radioactive...

449

Maine State Briefing Book on low-level radioactive waste management  

SciTech Connect

The Maine State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and Federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Maine. The profile is the result of a survey of radioactive material licensees in Maine. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested partices including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant goverment agencies and activities, all of which may impact management practices in Maine.

Not Available

1981-08-01T23:59:59.000Z

450

17 - Immobilisation of Radioactive Waste in Glass  

Science Journals Connector (OSTI)

Radionuclide immobilisation mechanisms are examined for vitreous wasteforms. Both borosilicate and phosphate glasses are described in detail, including the ability of cations to enter into the glass network structure. The role of various cations is considered, including boron, intermediates, and modifiers and elements difficult to immobilise. Selection rules for designing nuclear wasteform silicate glasses are outlined. Glass composite materials to immobilise glass-immiscible waste components are discussed. Both one- and two-stage vitrification technologies are described. An overview is given of the development of vitrification technology, including current operational data on radioactive waste vitrification facilities. Calcination processes are considered in detail, including typical properties of waste calcination products. Recent developments in vitrification are given, including descriptions of cold crucible induction-heated melters and in situ vitrification. Limitations caused by radionuclide volatility are examined. Acceptance criteria are given for vitreous wasteforms.

M.I. Ojovan; W.E. Lee

2014-01-01T23:59:59.000Z

451

Reporting of Radioactive Sealed Sources  

Directives, Delegations, and Requirements

To establish U.S. Department of Energy requirements for inventory reporting, transaction reporting, verification of reporting, and assign responsibilities for reporting of radioactive sealed sources. DOE N 251.86 extends this notice until 5-6-11. No cancellations. Canceled by DOE O 231.1B

2008-02-27T23:59:59.000Z

452

(Revised May 25, 2012) Radioactivity  

E-Print Network (OSTI)

(Revised May 25, 2012) Radioactivity GOALS (1) To gain a better understanding of naturally-occurring. (3) To measure the amount of "background radiation" from natural sources. (4) To test whether and man-made radiation sources. (2) To use a Geiger-Mueller tube to detect both beta and gamma radiation

Collins, Gary S.

453

Internal and External Radioactive Backgrounds  

E-Print Network (OSTI)

.6 Table 3.1: Naturally occurring radioactive isotopes [89]. The elemental abundance is the total amount words the signal to noise ratio should be greater than one, S/N > 1. Naturally, the larger S/N is to be distinguished from beta particles or gamma radiation. The big challenge for the Borexino experiment is to deal

454

Radioactive waste at Ward Valley  

Science Journals Connector (OSTI)

...Data Base for 1992: U.S. Spent Fuel and Radioactive Waste Inventories, Projections and Characteristics, publi. DOE/RW-0006, Rev. 8 (U.S. Department of Energy, Washington, DC, 1989), p. 113. 2. T. Taylor, quoted by S. Salesky...

Earl Budin

1995-09-22T23:59:59.000Z

455

The Radioactive Beam Program at Argonne  

E-Print Network (OSTI)

In this talk I will present selected topics of the ongoing radioactive beam program at Argonne and discuss the capabilities of the CARIBU radioactive ion production facility as well as plans for construction of a novel superconducting solenoid spectrometer.

B. B. Back

2006-06-06T23:59:59.000Z

456

Fusion Reactions Involving Radioactive Beams at GANIL  

Science Journals Connector (OSTI)

......February 2004 research-article Articles Fusion Reactions Involving Radioactive Beams...been used to produce exotic nuclei via fusion evaporation or to study reaction mechanisms...Physics Supplement No. 154, 2004 113 Fusion Reactions Involving Radioactive Beams......

Gilles de France

2004-02-01T23:59:59.000Z

457

Emergency Response to a Transportation Accident Involving Radioactive  

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

Response to a Transportation Accident Involving Response to a Transportation Accident Involving Radioactive Material Emergency Response to a Transportation Accident Involving Radioactive Material The purpose of this User's Guide is to provide instructors with an overview of the key points covered in the video. The Student Handout portion of this Guide is designed to assist the instructor in reviewing those points with students. The Student Handout should be distributed to students after the video is shown and the instructor should use the Guide to facilitate a discussion on each response disciplines' activities or duties at the scene. During this discussion, the instructor can present response scenarios, each of which would have a different discipline arriving first at the accident scene. The purpose of this discussion

458

Spent fuel and radioactive waste inventories, projections, and characteristics  

SciTech Connect

Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy (DOE) radioactive wastes were compiled through December 31, 1983, based on the most reliable information available from government sources and the open literature, technical reports, and direct contacts. Future waste and spent fuel to be generated over the next 37 years and characteristics of these materials are also presented, consistent with the latest DOE/Energy Information Administration (EIA) or projection of US commercial nuclear power growth and expected defense-related and private industrial and institutional activities. Materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, airborne waste, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated, based on reported or calculated isotopic compositions. 48 figures, 107 tables.

Not Available

1984-09-01T23:59:59.000Z

459

Radioactive isotopes in Danish drinking water  

E-Print Network (OSTI)

Radioactive isotopes in Danish drinking water Sven P. Nielsen Risø National Laboratory Working OF INVESTIGATION 11 3 DESCRIPTION OF INVESTIGATION 12 4 RADIOACTIVITY IN DRINKING WATER 13 5 SAMPLING 15 6 27 #12;4 #12;5 Preface This project for investigation of radioactivity in drinking water shall

460

Development of long-term performance models for radioactive waste forms  

SciTech Connect

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

Note: This page contains sample records for the topic "radioactive material shipments" 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.


461

DESIGN OF A CONTAINMENT VESSEL CLOSURE FOR SHIPMENT OF TRITIUM GAS  

SciTech Connect

This paper presents a design summary of the containment vessel closure for the Bulk Tritium Shipping Package (BTSP). This new package is a replacement for a package that has been used to ship tritium in a variety of content configurations and forms since the early 1970s. The new design is based on changes in the regulatory requirements. The BTSP design incorporates many improvements over its predecessor by implementing improved testing, handling, and maintenance capabilities, while improving manufacturability and incorporating new engineered materials that enhance the package's ability to withstand dynamic loading and thermal effects. This paper will specifically summarize the design philosophy and engineered features of the BTSP containment vessel closure. The closure design incorporates a concave closure lid, metallic C-Ring seals for containing tritium gas, a metal bellows valve and an elastomer O-Ring for leak testing. The efficient design minimizes the overall vessel height and protects the valve housing from damage during postulated drop and crush scenarios. Design features will be discussed.

Eberl, K; Paul Blanton, P

2007-07-03T23:59:59.000Z

462

Applying Risk Communication to the Transportation of Radioactive Materials  

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

Spokesperson Training 6/3/2010 Spokesperson Training 6/3/2010 May 2010 1 National Transportation Stakeholder Forum Chicago, Illinois May 2010 y May 2010 Page 1 Applying Risk Communication Principles Presented by: Ron Edmond Oak Ridge Institute for Science and Education May 2010 Page 2 Spokesperson Training 6/3/2010 May 2010 2  Participants should expect to gain the following skills: following skills:  How to recognize how the stakeholders prefer to receive information  How to integrate risk communication principles into individual communication  How to recognize the importance of earning trust and credibility y  How to identify stakeholders  How to answer questions using a variety of templates designed to keep messages focused May 2010 Page 3 The Chinese word for crisis contains two

463

Rubber membrane liner confines low level radioactive material  

SciTech Connect

One of the most sophisticated membrane lining projects in the world was undertaken in 1979 by the Cotter Corporation, Canon City, Colorado, producers of vanadium and uranium, when a new tailings pond was built to handle mill tailings and effluents. To comply with local, state and federal regulations, Cotter sought maximum protection for downstream residents. The lining was designed to keep leakage near zero and withstand tailings and water pressure at the deepest part of the pond. Other considerations were compatibility with alkalis and acids and durability and effectiveness of the lining beyond the life of the mill. ''We had to be sure the impoundment would outlast the mill because of the need for long-term isolation of the tailings,'' said Joseph McCluskey, Cotter's executive vice presient. Gotter chose an industrial grade sheeting made of Hypalon synthetic rubber, a chlorosulfonated polyethylene, that has an exposed life expectancy of 40 years; however, once covered with earth and tailings, it will last much longer. The sheeting consists of a reinforced scrim sandwiched between two sheets of Hypalon. The rubber comprises nearly 50 percent of the total linear weight, and the reinforcement is a 10' x 10' 1000D polyester scrim whose open weave allows the rubber to penetrate the fabric and create excellent adhesion between the layers. After two years, the impoundment contains approximately 1400 acre feet of liquid. Currently, about one half of the pond consists of run-off with tailings and liquids from the new mill making up the difference.

Not Available

1982-03-01T23:59:59.000Z

464

Regulation of naturally occurring radioactive materials in Australia  

Science Journals Connector (OSTI)

......implement those standards. In order to...competency standards, Codes of Practice, Standards and guidance...associated with uranium (and thorium...provision for plans to manage occupational...commissioned a review of operations......

Cameron Jeffries; Riaz Akber; Andrew Johnston; Brad Cassels

2011-07-01T23:59:59.000Z

465

Regulation of naturally occurring radioactive materials in Australia  

Science Journals Connector (OSTI)

......provide an overview of the regulatory approach to managing...been variation in the regulatory approach to implement...makes provision for plans to manage occupational...ARPANSA commissioned a review of operations involving...process to identify when regulatory control is appropriate......

Cameron Jeffries; Riaz Akber; Andrew Johnston; Brad Cassels

2011-07-01T23:59:59.000Z

466

Regulation of naturally occurring radioactive materials in Australia  

Science Journals Connector (OSTI)

......implement those standards. In order to...competency standards, Codes of Practice, Standards and guidance...protection in mining and mineral processing...provision for plans to manage occupational...commissioned a review of operations......

Cameron Jeffries; Riaz Akber; Andrew Johnston; Brad Cassels

2011-07-01T23:59:59.000Z

467

DOE/NNSA Recovers One Millionth Curie of Radioactive Material...  

National Nuclear Security Administration (NNSA)

Twitter, Tumblr, YouTube and Flickr. Established by Congress in 2000, NNSA is a semi-autonomous agency within the U.S. Department of Energy responsible for enhancing national...

468

REPORT NO. 5 background material  

E-Print Network (OSTI)

of atmospheric testing of nuclear weapons in 1961 and 1962 the question arose as to the possible need for protec from such events as: (1) an industrial accident, possibly involving a nuclear reactor or a nuclear fuel processing plant, and (2) release of radioactive materials from the detonation of nuclear weapons or other

469

Hazardous Materials Incident Response Procedure | Department of Energy  

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

Hazardous Materials Incident Response Procedure Hazardous Materials Incident Response Procedure Hazardous Materials