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


1

Radioactive Material Transportation Practices  

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

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

2002-09-23T23:59:59.000Z

2

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...

3

Radioactive Material Transportation Practices Manual  

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

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

2008-06-04T23:59:59.000Z

4

DOE - Safety of Radioactive Material Transportation  

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

5

DOE - Safety of Radioactive Material Transportation  

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

6

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...

7

Transporting & Shipping Hazardous Materials at LBNL: Radioactive Materials  

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

8

DOE - Safety of Radioactive Material Transportation  

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

9

DOE - Safety of Radioactive Material Transportation  

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

10

DOE - Safety of Radioactive Material Transportation  

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

11

DOE - Safety of Radioactive Material Transportation  

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

12

Radioactive Materials Transportation and Incident Response  

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

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 _______

13

DOE - Safety of Radioactive Material Transportation  

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

14

EMERGENCY RESPONSE TO A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

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

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

15

Midwestern Radioactive Materials Transportation Committee Agenda  

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

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

16

DOE - Safety of Radioactive Material Transportation  

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

17

DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

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

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

18

DOE - Safety of Radioactive Material Transportation  

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

19

DOE - Safety of Radioactive Material Transportation  

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

20

DOE - Safety of Radioactive Material Transportation  

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

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


21

DOE - Safety of Radioactive Material Transportation  

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

22

Q A RADIOACTIVE MATERIALS Transportation Emergency Preparedness Program  

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

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 _______

23

DOE - Safety of Radioactive Material Transportation  

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

24

DOE - Safety of Radioactive Material Transportation  

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

25

DOE - Safety of Radioactive Material Transportation  

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

26

DOE - Safety of Radioactive Material Transportation  

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

27

THERMAL PERFORMANCE OF RADIOACTIVE MATERIAL PACKAGES IN TRANSPORT CONFIGURATION  

SciTech Connect (OSTI)

Drum type packages are routinely used to transport radioactive material (RAM) in the U.S. Department of Energy (DOE) complex. These packages are designed to meet the federal regulations described in 10 CFR 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

28

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

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

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

29

Surveillance Guides - PTS 13.1 Radioactive And Hazardous Material Transportation  

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

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

30

Applying Risk Communication to the Transportation of Radioactive Materials  

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

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

31

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...

32

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...

33

Radioactive Material Use at the EMSL Radiochemistry Annex  

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

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

34

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

35

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

SciTech Connect (OSTI)

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

36

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

SciTech Connect (OSTI)

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

37

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

SciTech Connect (OSTI)

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

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

1997-11-01T23:59:59.000Z

38

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

SciTech Connect (OSTI)

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

none,

1992-01-01T23:59:59.000Z

39

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

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

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

40

Radiation Sources and Radioactive Materials (Connecticut)  

Broader source: Energy.gov [DOE]

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

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


41

Radiation Machines and Radioactive Materials (Iowa)  

Broader source: Energy.gov [DOE]

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

42

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

43

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

SciTech Connect (OSTI)

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

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

2010-10-28T23:59:59.000Z

44

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

SciTech Connect (OSTI)

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

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

2010-01-01T23:59:59.000Z

45

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...

46

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

47

RADIOACTIVE MATERIALS SENSORS  

SciTech Connect (OSTI)

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

48

Radioactive Material or Multiple Hazardous Materials Decontamination  

Broader source: Energy.gov [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.

49

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

50

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

51

Naturally Occurring Radioactive Materials (NORM)  

SciTech Connect (OSTI)

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

52

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

53

Completion of the Radioactive Materials Packaging Handbook  

SciTech Connect (OSTI)

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

Shappert, L.B.

1998-02-01T23:59:59.000Z

54

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

55

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

56

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...

57

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...

58

The basics in transportation of low-level radioactive waste  

SciTech Connect (OSTI)

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

59

Radioactive material package seal tests  

SciTech Connect (OSTI)

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

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

1990-01-01T23:59:59.000Z

60

Radioactive Materials at SSRL | Stanford Synchrotron Radiation Lightsource  

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

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


61

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

62

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

63

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

64

Transporting & Shipping Hazardous Materials at LBNL  

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

EHSS EHSS Industrial Hygiene Group HazMat Transport/Shipping Home Biological & Infectious Substances Chemicals Compressed Gas Cryogens Dry Ice Engineered Nanomaterials Gasoline Lithium Betteries Radioactive Materials Waste: Hazardous, Biohazardous, Medical or Radioactive Mixed Hazardous Materials Personal/Rental Vehicles HazMat Transport/Shipping Transporting and shipping hazardous materials can be dangerous, but both activities can be done safely - much of it by the researchers themselves. Each of the items below is subject to some transportation or shipping restrictions. Click on the applicable hazardous material icon below to learn how you can safely (and legally) transport that hazardous material and to learn what laboratory resources are available to you for your shipping needs.

65

Materials Transportation Testing & Analysis at Sandia National Laboratories  

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

RMIR (Radioactive Materials Incident Report) Database Transportation RMIR (Radioactive Materials Incident Report) Database Transportation Accident and Incident Experience,1971-1999 Access Hazardous Materials Information System (HMIS) the primary source of national data for the Federal, state, and local governmental agencies responsible for the safety of hazardous materials transportation. Rail Transport Highway Transport Air Transport The Radioactive Material Incident Report (RMIR) Database was developed in 1981 at the Transportation Technology Center of Sandia National Laboratories (SNL) to support its research and development activities for the U.S. Department of Energy (DOE). This database contains information about radioactive materials transportation incidents that have occurred in the U.S. from 1971 through 1999. These data were drawn from the U.S.

66

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

67

Emergency Response to a Transportation Accident Involving Radioactive  

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

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

68

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

69

Radioactive Samples / Materials at the APS  

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

70

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...

71

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

72

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

SciTech Connect (OSTI)

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

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

1998-08-01T23:59:59.000Z

73

Department of Transportation Pipeline and Hazardous Materials Safety Administration Activities  

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

DOT/PHMSA DOT/PHMSA A ti iti Activities Michael Conroy U S Department of Transportation - 1 - U.S. Department of Transportation Pipeline and Hazardous Materials Safety Administration Office of Hazardous Materials Safety Radioactive Materials U.S. Department of Transportation Pipeline and Hazardous Materials Safety Administration Overview * Harmonization with International Regulations * Update on Revisions to International Regulations * Recent Letters of Interpretation * Update on Rulemakings * PHMSA Information Resources - 2 - * PHMSA Information Resources 2 U.S. Department of Transportation Pipeline and Hazardous Materials Safety Administration HM-230 Harmonized with 2000 Version of IAEA's 1996 Edition - 3 - U.S. Department of Transportation Pipeline and Hazardous Materials Safety Administration

74

Enhancing Railroad Hazardous Materials Transportation Safety  

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

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

75

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

Broader source: Energy.gov [DOE]

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

76

Radioactive Material Use at the EMSL Radiochemistry Annex  

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

77

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

78

Hanford Site radioactive hazardous materials packaging directory  

SciTech Connect (OSTI)

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

McCarthy, T.L.

1995-12-01T23:59:59.000Z

79

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

80

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

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


81

Materials Transportation Testing & Analysis at Sandia National Laboratories  

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

Materials Characterization Materials Characterization Paul McConnell, (505) 844-8361 The purpose of hazardous and radioactive materials, i.e., mixed waste, packaging is to enable this waste type to be transported without posing a threat to the health or property of the general public. To achieve this goal, regulations have been written establishing general design requirement for such packagings. Based on these regulatory requirements, a Mixed Waste Chemical Compatibility Testing Program is intended to assure regulatory bodies that the issue of packaging compatibility towards hazardous and radioactive materials has been addressed. Such a testing program has been developed in the Transportation Systems Department at Sandia National Laboratories. Materials Characterization Capabilities

82

Department of Transportation Pipeline and Hazardous Materials...  

Office of Environmental Management (EM)

Department of Transportation Pipeline and Hazardous Materials Safety Administration Activities Department of Transportation Pipeline and Hazardous Materials Safety Administration...

83

EM Waste and Materials Disposition & Transportation  

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

On Closure Success On Closure Success 1 EM Waste and Materials Disposition & Transportation National Transportation Stakeholders Forum Chicago, Illinois May 26, 2010 Frank Marcinowski Acting Chief Technical Officer and Deputy Assistant Secretary for Technical and Regulatory Support Office of Environmental Management DOE's Radioactive Waste Management Priorities * Continue to manage waste inventories in a safe and compliant manner * Address high risk waste in a cost- ff ti effective manner * Maintain and optimize current disposal capability for future generations * Develop future disposal capacity in a complex environment * Promote the development of treatment and disposal alternatives in the 2 and disposal alternatives in the

84

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

85

RECLAMATION OF RADIOACTIVE MATERIAL PACKAGING COMPONENTS  

SciTech Connect (OSTI)

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

86

Transportation of Nuclear Materials | Department of Energy  

Energy Savers [EERE]

Transportation of Nuclear Materials Transportation of Nuclear Materials GC-52 provides legal advice to DOE on legal and regulatory requirements and standards for transportation of...

87

Experiment Hazard Class 8.1 - Radioactive Materials/Samples  

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

88

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.

89

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

90

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

SciTech Connect (OSTI)

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

91

Introduction to naturally occurring radioactive material  

SciTech Connect (OSTI)

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

Egidi, P.

1997-08-01T23:59:59.000Z

92

NEW APPROACH TO ADDRESSING GAS GENERATION IN RADIOACTIVE MATERIAL PACKAGING  

SciTech Connect (OSTI)

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

Watkins, R; Leduc, D; Askew, N

2009-06-25T23:59:59.000Z

93

Transportation Security | ornl.gov  

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

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

94

Materials and Transportation Services | The Ames Laboratory  

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

Materials and Transportation Services General Information: Materials and Transportation Services provides Ames Laboratory employees with a wide array of services and support...

95

Shipment of Small Quantities of Unspecified Radioactive Material in Chalfant Packagings  

SciTech Connect (OSTI)

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

96

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

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

97

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

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

98

Hazardous Material Packaging for Transport - Administrative Procedures  

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

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

1986-09-30T23:59:59.000Z

99

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

SciTech Connect (OSTI)

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

Smith, R.J.

1995-02-01T23:59:59.000Z

100

Safety and Security Technologies for Radioactive Material Shipments  

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

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

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


101

Naturally Occurring Radioactive Materials in Cargo at US Borders  

SciTech Connect (OSTI)

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

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

2006-01-01T23:59:59.000Z

102

High-Activity Radioactive Materials Removed From Mexico | National Nuclear  

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

103

NNSA: Securing Domestic Radioactive Material | National Nuclear Security  

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

104

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)

105

Sandia technology used to remove radioactive material at Fukushima |  

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

106

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

107

Materials Transportation Testing & Analysis at Sandia National Laboratories  

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

Unique Solutions] Unique Solutions] [Working With Us] [Contacting Us] [News Center] [Search] [Home] [navigation panel] Materials Transportation Testing & Analysis Our Mission Our Contacts Write to Us Package Development Risk Assessment RADTRAN GIS Mapping Structural Analysis Thermal Analysis Structural Testing Thermal Testing MIDAS Data Aquisition System Concepts Materials Characterization Regulatory Development Certification Support RMIR Data Base Scientific Visualization Mobile Instrumentation Data Acquisition System (MIDAS) Doug Ammerman, (505) 845-8158 The Mobile Instrumentation Data Acquisition System (MIDAS), developed by Sandia National Laboratories for the U.S. Department of Energy, provides on-site data acquisition of containers that transport radioactive materials during impact, puncture, fire, and immersion tests.

108

DOE - Safety of Radioactive Material Transportation  

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

109

DOE - Safety of Radioactive Material Transportation  

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

110

DOE - Safety of Radioactive Material Transportation  

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

111

DOE - Safety of Radioactive Material Transportation  

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

112

DOE - Safety of Radioactive Material Transportation  

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

113

DOE - Safety of Radioactive Material Transportation  

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

114

DOE - Safety of Radioactive Material Transportation  

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

115

Radioactive Materials Transportation and Incident Response  

Broader source: Energy.gov [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...

116

DOE - Safety of Radioactive Material Transportation  

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

117

DOE - Safety of Radioactive Material Transportation  

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

118

Office of Civilian Radioactive Waste Management Transportation Program: Tribal Initiatives  

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

COMMUNICATIONS BREAKOUT COMMUNICATIONS BREAKOUT SESSION Jay Jones Office of Civilian Radioactive Waste Management April 22, 2004 Albuquerque, New Mexico 2 Session Overview * Meeting objectives and expectations * Topic Group Background and History * Transportation information products - Information Product Survey results - Alliance for Transportation Research Institute Assessments * Discussion on future DOE communications * Information Display 3 Objectives and Expectations * OCRWM communications approach - Transportation Strategic Plan Collaborative effort with stakeholders Two-way interactions with program participants and public - provide information and receive feedback * Implement communications strategy - Identify stakeholders and issues - Engage nationally, regionally and with States - Participate through discussion and issue resolution

119

Departmental Materials Transportation and Packaging Management  

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

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

2010-11-18T23:59:59.000Z

120

Radioactive material in the West Lake Landfill: Summary report  

SciTech Connect (OSTI)

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

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


121

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...

122

Northeast High-Level Radioactive Waste Transportation Task Force Agenda  

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

Northeast High-Level Radioactive Waste Transportation Task Force Northeast High-Level Radioactive Waste Transportation Task Force Spring Meeting - May 15, 2012 Hilton Knoxville 501 West Church Avenue, Knoxville, TN 37902-2591 Agenda (Draft #1 - 4/18/12) ______________________________________________________________________________ Tuesday, May 15 - 9:00 AM - 3:30 PM / (need meeting room name) 8:00 a.m. Continental Breakfast - served in meeting room 9:00 a.m. Task Force Business Meeting - John Giarrusso, MEMA and Rich Pinney, NJDEP Co-chairs presiding  Welcome: Introductions; Agenda Review; Announcements  2012 funding  Co-Chair Election  Rules of Procedure  Membership: members & alternates appointment status  Legislative Liaisons  Staff Regional Meeting Attendance

123

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

SciTech Connect (OSTI)

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

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

1991-07-01T23:59:59.000Z

124

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

SciTech Connect (OSTI)

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

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

1991-07-01T23:59:59.000Z

125

Commercial low-level radioactive waste transportation liability and radiological risk  

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

126

BNL | CFN: Transport of Hazardous Materials  

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

Transportation of Hazardous Materials and Nanomaterials Transportation of Hazardous Materials and Nanomaterials The following contains guidance for transporting materials to and from BNL and for on-site transfers. All staff and users must adhere to Laboratory guidelines when making plans to move materials either by commercial carrier or in rented or personal vehicles. BNL hazardous material transport guidelines apply for products that meet the definition of hazardous materials according to 49 CFR 171.8 and any nanomaterial that has known hazardous properties (toxic, flammable, reactive). BNL guidelines are also provided for all other nanomaterials even if they have not been identified as hazardous materials. Some materials may be transported in personal vehicles as per "Materials of Trade" (MOT) guidance. The regulations for transporting MOT are much

127

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

128

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

SciTech Connect (OSTI)

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

NONE

1998-03-01T23:59:59.000Z

129

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

E-Print Network [OSTI]

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

Frolkovic, Peter

130

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

E-Print Network [OSTI]

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

Montes-Hernandez, German

131

Management of sewage sludge and ash containing radioactive materials.  

SciTech Connect (OSTI)

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

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

2007-01-01T23:59:59.000Z

132

Hanford Site Shares Lessons Learned in Retrieving Highly Radioactive Material  

Broader source: Energy.gov [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.

133

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

134

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

SciTech Connect (OSTI)

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

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

2008-07-01T23:59:59.000Z

135

Detection of radioactive materials at Astrakhan  

SciTech Connect (OSTI)

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

136

A manual for implementing residual radioactive material guidelines  

SciTech Connect (OSTI)

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

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

1989-06-01T23:59:59.000Z

137

Midwestern High-Level Radioactive Waste Transportation Project  

SciTech Connect (OSTI)

For more than half a century, the Council of State Governments has served as a common ground for the states of the nation. The Council is a nonprofit, state-supported and -directed service organization that provides research and resources, identifies trends, supplies answers and creates a network for legislative, executive and judicial branch representatives. This List of Available Resources was prepared with the support of the US Department of Energy, Cooperative Agreement No. DE-FC02-89CH10402. However, any opinions, findings, conclusions, or recommendations expressed herein are those of the author(s) and do not necessarily reflect the views of DOE. The purpose of the agreement, and reports issued pursuant to it, is to identify and analyze regional issues pertaining to the transportation of high-level radioactive waste and to inform Midwestern state officials with respect to technical issues and regulatory concerns related to waste transportation.

Dantoin, T.S.

1990-12-01T23:59:59.000Z

138

Departmental Materials Transportation and Packaging Management  

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

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

2004-12-22T23:59:59.000Z

139

Digital Radiography of a Drop Tested 9975 Radioactive Materials Packaging  

SciTech Connect (OSTI)

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

140

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

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


141

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

142

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

143

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

144

Materials Transportation Testing & Analysis at Sandia National Laboratories  

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

Testing Testing Carlos Lopez, (505) 845-9545 Packages transporting the larger "Type B" quantities of radioactive materials must be qualified and certified under Title 10, Code of Federal Regulations, Part 71, or under the equivalent international standard ST-1 issued by the International Atomic Energy Agency. The principal thermal qualification test is the 30 minute pool fire. As part of the National Transportation Program, the Transportation Risk & Packaging Program at Sandia can plan and conduct these tests for DOE and other package suppliers. Test Plans, QA plans and other necessary test documents can be prepared for customer and regulatory approval. Tests may be conducted with a variety of available facilities at Sandia, including large pools, an indoor fire facility, and a radiant heat test

145

Electronic transport in atomically thin layered materials  

E-Print Network [OSTI]

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

Baugher, Britton William Herbert

2014-01-01T23:59:59.000Z

146

Departmental Materials Transportation and Packaging Management  

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

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

1995-10-26T23:59:59.000Z

147

Departmental Materials Transportation and Packaging Management  

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

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

1995-09-27T23:59:59.000Z

148

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

149

Management of Naturally Occurring Radioactive Materials (NORM) in Canada  

SciTech Connect (OSTI)

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

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

2008-08-07T23:59:59.000Z

150

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

151

Best Practices for the Security of Radioactive Materials  

SciTech Connect (OSTI)

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

Coulter, D.T.; Musolino, S.

2009-05-01T23:59:59.000Z

152

TYPE B RADIOACTIVE MATERIAL PACKAGE FAILURE MODES AND CONTENTS COMPLIANCE  

SciTech Connect (OSTI)

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

153

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

SciTech Connect (OSTI)

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

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

1997-03-01T23:59:59.000Z

154

Thermal Energy Transport in Nanostructured Materials  

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

Thermal Energy Transport in Nanostructured Materials Thermal Energy Transport in Nanostructured Materials Speaker(s): Ravi Prasher Date: August 25, 2008 - 12:00pm Location: 90-3122 Seminar Host/Point of Contact: Ashok Gadgil World energy demand is expected to reach ~30 TW by 2050 from the current demand of ~13 TW. This requires substantial technological innovation. Thermal energy transport and conversion play a very significant role in more than 90% of energy technologies. All four modes of thermal energy transport, conduction, convection, radiation, and phase change (e.g. evaporation/boiling) are important in various energy technologies such as vapor compression power plants, refrigeration, internal combustion engines and building heating/cooling. Similarly thermal transport play a critical role in electronics cooling as the performance and reliability of

155

Plasma transport near material boundaries  

SciTech Connect (OSTI)

The fluid theory of two-dimensional (2-d) plasma transport in axisymmetric devices is reviewed. The forces which produce flow across the magnetic field in a collisional plasma are described. These flows may lead to up-down asymmetries in the poloidal rotation and radial fluxes. Emphasis is placed on understanding the conditions under which the known 2-d plasma fluid equations provide a valid description of these processes. Attempts to extend the fluid treatment to less collisional, turbulent plasmas are discussed. A reduction to the 1-d fluid equations used in many computer simulations is possible when sources or boundary conditions provide a large enough radial scale length. The complete 1-d fluid equations are given in the text, and 2-d fluid equations are given in the Appendix.

Singer, C.E.

1985-06-01T23:59:59.000Z

156

2011 Radioactive Materials Usage Survey for Unmonitored Point Sources  

SciTech Connect (OSTI)

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

Sturgeon, Richard W. [Los Alamos National Laboratory

2012-06-27T23:59:59.000Z

157

ELUCIDATING THE DIFFERENCES BETWEEN ONSITE AND OFFSITE SHIPMENT OF RADIOACTIVE MATERIALS  

SciTech Connect (OSTI)

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

Loftin, B.; Watkins, R.

2013-06-19T23:59:59.000Z

158

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

SciTech Connect (OSTI)

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

James E. Saiers

2012-09-20T23:59:59.000Z

159

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

SciTech Connect (OSTI)

Gas generation issues, particularly hydrogen, have been an area of concern for the transport and storage of radioactive materials and waste in the Department of Energy (DOE) complex. Potentially combustible gases can be generated through a variety of reactions, including chemical reactions and radiolytic decomposition of hydrogen-containing 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

160

Heat transport system, method and material  

DOE Patents [OSTI]

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

Musinski, D.L.

1987-04-28T23:59:59.000Z

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


161

Enhancements to System for Tracking Radioactive Waste Shipments...  

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

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

162

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

163

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.

164

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

165

Weather and the Transport of Hazardous Materials | Department...  

Office of Environmental Management (EM)

and the Transport of Hazardous Materials More Documents & Publications The Role of GIS in Decision Support Systems Section 180(c) Ad Hoc Working Group Transportation Plan Ad...

166

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

SciTech Connect (OSTI)

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

167

Weather and the Transport of Hazardous Materials  

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

FHWA FHWA R d W h M P FHWA R d W h M P FHWA Road Weather Management Program FHWA Road Weather Management Program " "Weather and the transport of Hazardous Materials" Ray Murphy Office of Technical Services Ray Murphy, Office of Technical Services U.S. DOT - Federal Highway Administration Breako t Session Using Technolog to Dispatch U.S. DOE National Transportation Stakeholder Forum Breakout Session: Using Technology to Dispatch and Monitor Shipments During Adverse Conditions Presentation Contents Presentation Contents * * Context Context Cl Cl I iti ti I iti ti * * Clarus Clarus Initiative Initiative * * Connected Vehicles & Weather Connected Vehicles & Weather Connected Vehicles & Weather Connected Vehicles & Weather U.S. DOE National Transportation Stakeholder Forum

168

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

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

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

169

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

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

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

170

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

SciTech Connect (OSTI)

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

171

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

172

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

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

to classified information. Section 5.0 explains unclassified, potentially non-sensitive, types of information, organized by subject area, which are pertinent to the Transportation...

173

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

SciTech Connect (OSTI)

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

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

1993-09-01T23:59:59.000Z

174

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

SciTech Connect (OSTI)

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

Blanton, P.; Eberl, K.

2008-09-14T23:59:59.000Z

175

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

176

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

SciTech Connect (OSTI)

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

Not Listed

2011-09-01T23:59:59.000Z

177

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

SciTech Connect (OSTI)

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

Lisa Harvego; Brion Bennett

2011-09-01T23:59:59.000Z

178

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 (OSTI)

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

179

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

180

Lightweight materials for transportation: Program plan  

SciTech Connect (OSTI)

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

Not Available

1993-07-01T23:59:59.000Z

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


181

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

182

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

SciTech Connect (OSTI)

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

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

1989-01-01T23:59:59.000Z

183

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

SciTech Connect (OSTI)

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

Smith, A

2008-12-31T23:59:59.000Z

184

Materials Transportation Testing & Analysis at Sandia National Laboratories  

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

Testing Testing Doug Ammerman, (505) 845-8158 Type B packages that transport radioactive materials must survive a sequence of full-scale (actual physical size) impact, puncture, fire, and immersion tests designed to replicate transportation accident conditions. The Hypothetical Accident Conditions (six tests as defined in 10 CFR Part 71.73) tests 1 through 4 (Drop, Crush, Puncture and Fire) are sequential, test 5 (Immersion) is performed on either a previously tested or untested package. Free Drop Test Crush Test Puncture Test Thermal Test Immersion Test [drop] Click to view picture [crush] Click to view picture [puncture] Click to view picture [thermal] Click to view picture [immersion] Click to view picture Dropping a package from 30 feet onto an unyielding target. (the unyielding target forces all of the deformation to be in the package, none in the target). The speed on impact is 44 feet per second or 30 miles per hour. Dropping a 1100 pound steel plate from 30 feet onto a package. This test is only required for packages weighing less than 1100 pounds. The speed on impact is 44 feet per second or 30 miles per hour. Dropping a package from 40 inches onto a welded, 6 inch diameter, steel spike. The speed on impact is 14.6 feet per second or 10 miles per hour. Placing a package 40 inches above a pool of burning fuel for 30 minutes at 800 degrees Celsius (1475 degrees Fahrenheit). Placing a package under 50 feet of water for 8 hours. Fissile material packages are also immersed under 3 feet of water for 8 hours sequentially after tests 1 through 4

185

Information-Sharing Protocol for the Transportation of Radioactive Waste to Yucca Mountain  

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

Preliminary Draft for Review Only Preliminary Draft for Review Only Information-Sharing for Transportation of Radioactive Waste to Yucca Mountain Office of Logistics Management Office of Civilian Radioactive Waste Management U. S. Department of Energy Preliminary Draft July 2007 1 Preliminary Draft for Review Only TABLE OF CONTENTS 1.0 INTRODUCTION...........................................................................3 1.1 Background ....................................................................................................... 3 1.2 Document Origin and Structure...................................................................... 4 1.3 Information Sharing with Department of Homeland Security..................... 4 2.0 DISCUSSION OF TERMS ..................................................................................

186

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

187

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

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

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

188

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

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

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

189

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

SciTech Connect (OSTI)

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

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

2008-07-01T23:59:59.000Z

190

Water Management in A PEMFC: Water Transport Mechanism and Material  

E-Print Network [OSTI]

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

Kandlikar, Satish

191

Fluorescent Functionalized Mesoporous Silica for Radioactive Material Extraction  

SciTech Connect (OSTI)

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

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

2012-08-01T23:59:59.000Z

192

Gamma motes for detection of radioactive materials in shipping containers  

SciTech Connect (OSTI)

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

193

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

SciTech Connect (OSTI)

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

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

1997-10-01T23:59:59.000Z

194

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

SciTech Connect (OSTI)

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

195

APPLICATION FO FLOW FORMING FOR USE IN RADIOACTIVE MATERIAL PACKAGING DESIGNS  

SciTech Connect (OSTI)

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

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

2012-07-11T23:59:59.000Z

196

ECUT energy data reference series: lightweight materials for ground transportation  

SciTech Connect (OSTI)

This report summarizes information that describes the use of lightweight materials in automobiles. The information on this mode of transportation represents the largest potential energy savings for substitution of lightweight materials in the transportation sector. Included are data on energy conversion efficiency of the engine and its relationship to vehicle weight, the capital stock, the amount of energy used, and the service activity level as measured in ton-miles.

Abarcar, R.B.; Hane, G.J.; Johnson, D.R.

1984-07-01T23:59:59.000Z

197

Vulnerability Analysis Considerations for the Transportation of Special Nuclear Material  

SciTech Connect (OSTI)

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

Nicholson, Lary G.; Purvis, James W.

1999-07-21T23:59:59.000Z

198

Neutron transport in Eulerian coordinates with bulk material motion  

SciTech Connect (OSTI)

A consistent, numerically stable algorithm for the solution of the neutron transport equation in the presence of a moving material background is presented for one-dimensional spherical geometry. Manufactured solutions are used to demonstrate the correctness and stability of our numerical algorithm. The importance of including moving material corrections is shown for the r-process in proto-neutron stars. (authors)

Baker, R. S.; Dahl, J. A.; Fichtl, E. D. [Los Alamos National Laboratory, Computational Physics Group (United States); Morel, J. E. [Department of Nuclear Engineering, Texas A and M University (United States)

2013-07-01T23:59:59.000Z

199

The importance of transport parameter cross correlations in natural systems radioactive transport models  

SciTech Connect (OSTI)

Transport parameter cross correlations are rarely considered in models used to predict radionuclide transport in natural systems. In this paper, it is shown that parameter cross correlations could have a significant impact on radionuclide transport predictions in saturated media. In fractured rock, the positive correlation between fracture apertures and groundwater residence times is shown to result in significantly less retardation due to matrix diffusion than is predicted without the correlation. The suppression of matrix diffusion is further amplified by a tendency toward larger apertures, smaller matrix diffusion coefficients, and less sorption capacity in rocks of lower matrix porosity. In a hypothetical example, strong cross correlations between these parameters result in a decrease in predicted radionuclide travel times of an order of magnitude or more relative to travel times calculated with uncorrelated parameters. In porous media, expected correlations between permeability, porosity, and sorption capacity also result in shorter predicted travel times than when the parameters are assumed to be uncorrelated. Individual parameter standard deviations can also have a significant influence on predicted radionuclide travel times, particularly when cross correlations are considered.

Reimus, Paul W [Los Alamos National Laboratory

2011-01-03T23:59:59.000Z

200

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

SciTech Connect (OSTI)

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

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

1995-12-01T23:59:59.000Z

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


201

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

SciTech Connect (OSTI)

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

Tyacke, M.; Schmitt, R.

1993-07-01T23:59:59.000Z

202

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

203

Transporting & Shipping Hazardous Materials at LBNL: Chemicals  

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

Chemicals Chemicals Hand-Carry Self-Transport by Vehicle Ship by Common Carrier Conduct Field Work Hand-Carry Employees may hand-carry small quantities of hazardous materials between adjacent buildings and in connecting spaces (i.e., hallways, stairs, etc.) within buildings, provided it can be done safely and without spilling the materials. Staff must use hand carts, drip trays, or another type of secondary container to contain any spills should they occur during self-transport. Hazardous materials hand-carried between non-adjacent buildings should be packaged to a higher level of integrity. As a best practice, package these substances following the General Requirements listed under the Self-Transport by Vehicle. As with any work involving chemicals, staff must also have completed

204

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

205

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

206

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

SciTech Connect (OSTI)

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

207

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

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

208

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

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

209

Analysis of emitter material transport in thermionic converter  

SciTech Connect (OSTI)

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

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

1996-03-01T23:59:59.000Z

210

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

SciTech Connect (OSTI)

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

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

1997-11-01T23:59:59.000Z

211

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

SciTech Connect (OSTI)

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

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

1992-05-01T23:59:59.000Z

212

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

SciTech Connect (OSTI)

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

213

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

SciTech Connect (OSTI)

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

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

2010-06-03T23:59:59.000Z

214

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

SciTech Connect (OSTI)

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

215

Secure Transportation_final_print-ready  

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

A A History of Secure Transportation * The transportation of the CEUSP material in casks will be made by Hittman Transport, a commercial carrier * Hittman Transport is a specialty company whose primary mission is transporting hazardous materials * Transport method meets all of the requirements of the Department of Energy, Nuclear Regulatory Commission, and Department of Transportation for shipment of hazardous radioactive material * Hittman Transport maintains drivers with DOE security clearances and all shipments will be escorted by armed Federal officers Hittman Transport drivers' average number of years experience 26 Completed Hittman Transport shipments without significant accident or loss of material 196K Hittman Transport began supporting the nuclear industry

216

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

217

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

SciTech Connect (OSTI)

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

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

2001-08-17T23:59:59.000Z

218

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

219

Transportation risk assessment of radioactive wastes generated by the N-Reactor stabilization program at the Hanford Site, Washington  

SciTech Connect (OSTI)

The potential radiological and nonradiological risks associated with specific radioactive waste shipping campaigns at the Hanford Site are estimated. The shipping campaigns analyzed are associated with the transportation of wastes from the N-Reactor site at the 200-W Area, both within the Hanford Reservation, for disposal. The analysis is based on waste that would be generated from the N-Reactor stabilization program.

Wheeler, T.

1994-12-01T23:59:59.000Z

220

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

SciTech Connect (OSTI)

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

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

1989-01-01T23:59:59.000Z

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


221

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

SciTech Connect (OSTI)

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

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

1991-12-31T23:59:59.000Z

222

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

SciTech Connect (OSTI)

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

223

Enhancements to System for Tracking Radioactive Waste Shipments Benefit  

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

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

224

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

SciTech Connect (OSTI)

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

225

Electron Transport Materials: Synthesis, Properties and Device Performance  

SciTech Connect (OSTI)

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

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

2012-06-01T23:59:59.000Z

226

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...

227

Materials performance in a high-level radioactive waste vitrification system  

SciTech Connect (OSTI)

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

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

1996-06-17T23:59:59.000Z

228

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 (OSTI)

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

229

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

SciTech Connect (OSTI)

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

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

1993-02-01T23:59:59.000Z

230

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

SciTech Connect (OSTI)

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

Smith, K.P.

1992-12-01T23:59:59.000Z

231

Transportation  

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

Transportation Transportation Transportation of Depleted Uranium Materials in Support of the Depleted Uranium Hexafluoride Conversion Program Issues associated with transport of depleted UF6 cylinders and conversion products. Conversion Plan Transportation Requirements The DOE has prepared two Environmental Impact Statements (EISs) for the proposal to build and operate depleted uranium hexafluoride (UF6) conversion facilities at its Portsmouth and Paducah gaseous diffusion plant sites, pursuant to the National Environmental Policy Act (NEPA). The proposed action calls for transporting the cylinder at ETTP to Portsmouth for conversion. The transportation of depleted UF6 cylinders and of the depleted uranium conversion products following conversion was addressed in the EISs.

232

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

SciTech Connect (OSTI)

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

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

1997-05-01T23:59:59.000Z

233

Quantitative Relationships between Microstructure and Effective Transport Properties based on Virtual Materials Testing  

E-Print Network [OSTI]

studies in e.g. batteries, fuel cells and for transport processes in porous materials. Keywords science (e.g. charge transport in electrodes of fuel cells and batteries5;6 ), or for chemical and bio

Schmidt, Volker

234

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

SciTech Connect (OSTI)

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

Blanton, P.S.

1997-11-11T23:59:59.000Z

235

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

236

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

E-Print Network [OSTI]

. V MATERIAL TRANSPORT CONTROLLER: FUNCTIONS 2b SPECIFICATIONS . . 5. 1 Startup Routine 5 2 External Commands. 5. 3 Internal Commands. . 5. 4 Message Sequence. . Page 10 13 15 21 21 23 23 25 27 28 34 34 35 39 40 CHAPTER 5. 5... decomposition for the AGV controller. RapidCIM shop floor controller structure Material transport controller structure. Material transport controller architecture. Control configurations. Physical layout of a conveyor network Conventional representation...

Edlabadkar, Abhay

2012-06-07T23:59:59.000Z

237

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

SciTech Connect (OSTI)

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

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

1995-08-01T23:59:59.000Z

238

Radioactive Waste Management (Minnesota)  

Broader source: Energy.gov [DOE]

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

239

Upgrading the Radioactive Waste Management Infrastructure in Azerbaijan  

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

240

Radioactive ion beam transportation for the fundamental symmetry study with laser-trapped atomsa)  

Science Journals Connector (OSTI)

The search for the violation of the fundamental symmetry in a radioactive atom is the promising candidate for precision tests of the standard model and its possible extensions. The subtle signal arising from the symmetry violation is enhanced in heavy atoms such as a francium (Fr). To realize high precision measurements a large amount of radioactive isotopes is required. The Fr is produced via a nuclear fusion reaction using a melted gold target with a 18O primary beam at Cyclotron and Radioisotope Center Tohoku University. The maximum extraction efficiency of the Fr ion was achieved at approximately 35%. The beam line consists of an electrostatic deflector three electrostatic quadrupole triplets to the measurement area at 10 m away from the reaction point and several beam diagnosis systems. We optimized parameters of the beam line.

H. Kawamura; K. Hatanaka; K. Imai

2014-01-01T23:59:59.000Z

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


241

Packaging and Transportation Safety  

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

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

2010-05-14T23:59:59.000Z

242

Optimizing Tank Car Safety Design to Reduce Hazardous Materials Transportation Risk  

E-Print Network [OSTI]

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

Barkan, Christopher P.L.

243

Packaging and Transfer or Transportation of Materials of National Security Interest  

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

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

2000-09-29T23:59:59.000Z

244

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

245

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

246

Transporting & Shipping Hazardous Materials at LBNL: Compressed Gases  

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

Compressed Gases Compressed Gases Self-Transport by Hand & Foot Self-Transport by Vehicle Ship by Common Carrier Conduct Field Work Return Cylinders Self-Transport by Hand & Foot Staff may personally move (self-transport) compressed gas cylinders by hand & foot between buildings and in connecting spaces (i.e., hallways, elevators, etc.) within buildings provided it can be done safely. The following safety precautions apply: Use standard cylinder dollies to transport compressed gas cylinders. While dollies are preferred, cylinders weighing 11 Kg (25 lbs) or less may be hand-carried. Never move a cylinder with a regulator connected to it. Cylinder valve-protection caps and valve-opening caps must be in place when moving cylinders. Lecture bottles and other cylinders that are

247

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

SciTech Connect (OSTI)

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

248

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

E-Print Network [OSTI]

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

Hu, Qinhong "Max"

249

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

250

Exciton transport and coherence in molecular and nanostructured materials  

E-Print Network [OSTI]

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

Akselrod, Gleb M. (Gleb Markovitch)

2013-01-01T23:59:59.000Z

251

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

SciTech Connect (OSTI)

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

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

1995-02-01T23:59:59.000Z

252

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

E-Print Network [OSTI]

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

Zhang, Yingchun

2009-06-02T23:59:59.000Z

253

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

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

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

1996-11-15T23:59:59.000Z

254

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

Broader source: Energy.gov [DOE]

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

255

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

256

Spring 2012 National Transportation Stakeholder Forum Meetings, Tennessee |  

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

Services » Waste Management » Packaging and Transportation » Services » Waste Management » Packaging and Transportation » National Transportation Stakeholders Forum » Spring 2012 National Transportation Stakeholder Forum Meetings, Tennessee Spring 2012 National Transportation Stakeholder Forum Meetings, Tennessee NTSF Registration Website Save The Date! NTSF Spring 2012 Agenda NTSF Agenda Midwestern Radioactive Materials Transportation Committee Agenda Northeast High-Level Radioactive Waste Transportation Task Force Agenda Transuranic Waste Transportation Working Group Agenda Western Governor's Association Agenda NTSF Presentations Session Newcomers' Orientation Plenary Sessions Keynote Address Oak Ridge Operations Office of Environmental Management Overview Global Threat Reduction Initiative Task Force for Strategic Developments to Blue Ribbon Commission

257

Disposed Material Mobility and Transport in the Vicinity of the  

E-Print Network [OSTI]

after the day of deployment. A 1-D sediment resuspension and transport model was verified using to be in suspension for the majority of the time and in particular following a resuspension event. The low settling velocities allow them to be in resuspension for long times (over 24 hours). Finally, we recommend monitoring

Voulgaris, George

258

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

SciTech Connect (OSTI)

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

Halsey, W

2009-01-15T23:59:59.000Z

259

Update to the Fissile Materials Disposition program SST/SGT transportation estimation  

SciTech Connect (OSTI)

This report is an update to ``Fissile Materials Disposition Program SST/SGT Transportation Estimation,'' SAND98-8244, June 1998. The Department of Energy Office of Fissile Materials Disposition requested this update as a basis for providing the public with an updated estimation of the number of transportation loads, load miles, and costs associated with the preferred alternative in the Surplus Plutonium Disposition Final Environmental Impact Statement (EIS).

John Didlake

1999-11-15T23:59:59.000Z

260

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

SciTech Connect (OSTI)

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

Blanton, P; Kurt Eberl, K

2007-10-23T23:59:59.000Z

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


261

North American Standard Level VI Inspection Program Update: Ensuring Safe Transportation of Radioactive Material  

Broader source: Energy.gov [DOE]

Presentation made by Carlisle Smith for the NTSF annual meeting held from May 14-16, 2013 in Buffalo, NY

262

Materials Transportation Testing & Analysis at Sandia National Laboratories  

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

Transportation Risk & Packaging Contacts Transportation Risk & Packaging Contacts Ken Sorenson Program Manager (505) 844-0074 kbsoren@sandia.gov David Miller Operations Manager (505) 284-2574 drmille@sandia.gov Administrative Assistant Pat Tode (505) 845-8339, 845-7800 pprippl@sandia.gov Financial Analyst Laurel Taylor (505) 845-8598 ljtaylo@sandia.gov Risk Assessment Ruth Weiner (505) 284-8406 rfweine@sandia.gov Jeremy Sprung (505) 844-0314 jlsprun@sandia.gov Doug Osborn (505) 284-6416 dosborn@sandia.gov RADTRAN Ruth Weiner (505) 284-8406 rfweine@sandia.gov GIS Mapping Doug Osborn (505) 284-6416 dosborn@sandia.gov Structural Analysis Doug Ammerman (505) 845-8158 djammer@sandia.gov Bob Kalan (505) 844-0244 rjkalan@sandia.gov Jeff Smith (505) 845-0299 jasmith@sandia.gov Thermal Analysis Carlos Lopez

263

Materials Transportation Testing & Analysis at Sandia National Laboratories  

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

Analysis Analysis Doug Ammerman, (505) 845-8158 Structural analysis utilizes computer design and analysis tools to provide package designers and certifiers with the most accurate method of determining package response to transportation environments. 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. It can be used for package certification by generating a computer model of a test object (package) and subjecting it to an accident environment to understand its response. A computer model must be constructed with the same weights, dimensions, hardnesses, specific heat, conduction, etc. as an

264

Monte Carlo Study of the Spin Transport in Magnetic Materials , K. Akablia,b  

E-Print Network [OSTI]

Monte Carlo Study of the Spin Transport in Magnetic Materials Y. Magnina , K. Akablia,b , H. T of Natural Science and Technology, Okayama University 3-1-1 Tsushima-naka, Kita-ku, Okayama 700-8530, Japan.. Abstract The resistivity in magnetic materials has been theoretically shown to depend on the spin

265

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

DOE Patents [OSTI]

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

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

2014-01-28T23:59:59.000Z

266

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

SciTech Connect (OSTI)

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

267

Spring 2010 National Transportation Stakeholder Forum Meetings, Illinois |  

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

0 National 0 National Transportation Stakeholder Forum Meetings, Illinois Spring 2010 National Transportation Stakeholder Forum Meetings, Illinois NTSF Spring 2010 Agenda Final Agenda NTSF Presentations Applying Risk Communication to the Transportation of Radioactive Materials Department of Energy Office of Science Transportation Overview Department of Transportation Pipeline and Hazardous Materials Safety Administration Activities EM Waste and Materials Disposition & Transportation National Transportation Stakeholders Forum Nuclear Regulatory Commission's Integrated Strategy for Spent Fuel Management Status and Future of TRANSCOM Transportation Emergency Preparedness Program - Making A Difference Waste Isolation Pilot Plant Status and Plans - 2010 Meeting Summary Meeting Summary Notes

268

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

SciTech Connect (OSTI)

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

269

Packaging and Transportation | Department of Energy  

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

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

270

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

SciTech Connect (OSTI)

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

271

Spring 2013 National Transportation Stakeholders Forum Meeting, New York |  

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

National Transportation Stakeholders Forum » Spring 2013 National National Transportation Stakeholders Forum » Spring 2013 National Transportation Stakeholders Forum Meeting, New York Spring 2013 National Transportation Stakeholders Forum Meeting, New York Spring 2013 National Transportation Stakeholders Forum Meeting, New York Save the Date NTSF Registration Announcement NTSF 2013 Agenda EM's Huizenga Gives Keynote Address at National Transportation Stakeholders Forum Spring 2013 NTSF Presentations May 14, 2013 Presentations Communication Is Key to Packaging and Transportation Safety and Compliance North American Standard Level VI Inspection Program Update: Ensuring Safe Transportation of Radioactive Material Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing U.S. Nuclear Waste Technical Review Board: Roles and Priorities

272

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

SciTech Connect (OSTI)

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

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

1995-06-01T23:59:59.000Z

273

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

SciTech Connect (OSTI)

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

Hakonson, T.E.

1986-02-01T23:59:59.000Z

274

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

SciTech Connect (OSTI)

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

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

1999-07-01T23:59:59.000Z

275

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

SciTech Connect (OSTI)

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

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

1995-09-22T23:59:59.000Z

276

Emerging Technologies Applicable to the Safe and Secure Transportation of Hazardous Materials  

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

National Transportation Stakeholders Forum National Transportation Stakeholders Forum May 16, 2012 HMCRP Project HM-04: Emerging Technologies Applicable to Hazardous Materials Transportation Safety and Security 2 The HM-04 Team * Battelle - Prime - Bill Tate, Project Director/PI & Co-Author * Dr. Mark Abkowitz, Vanderbilt University - Co-Author * American Transportation Research Institute (ATRI) - Dan Murray, Lead * Visionary Solutions, LLC - Dan Hoglund, Lead * Olin Chemical Chlor-Alkali Division - Don Loftis 3 Project Objectives * Develop a list of near-term (less than 5 years) and longer-term (5-15 years) technologies that are candidates for enhancing safety and security of Hazmat transportation; * Identify emerging technologies that hold the greatest promise (in terms of effectiveness) of being introduced

277

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

SciTech Connect (OSTI)

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

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

1996-12-01T23:59:59.000Z

278

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

279

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

SciTech Connect (OSTI)

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

280

An indole derivative as a high triplet energy hole transport material for blue phosphorescent organic light-emitting diodes  

Science Journals Connector (OSTI)

Abstract A thermally stable high triplet energy material derived from an indoloacridine core and indole hole transport units, 8,8-bis(4-(1H-indol-1-yl)phenyl)-8H-indolo[3,2,1-de]acridine (BIPIA), was synthesized as the hole transport material for deep blue phosphorescent organic light-emitting diodes. The BIPIA hole transport material showed a high triplet energy of 2.95eV and high glass transition temperature of 142C. A high quantum efficiency of 19.3% was obtained in the deep blue device using BIPIA as the high triplet energy hole transport material.

Min Su Park; Jun Yeob Lee

2013-01-01T23:59:59.000Z

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


281

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

SciTech Connect (OSTI)

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

McGuire, S.A.

1985-06-01T23:59:59.000Z

282

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

SciTech Connect (OSTI)

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

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

2013-11-01T23:59:59.000Z

283

Review of the Lawrence Livermore Nationa Laboratory Identiified Defective Department of Transportation Hazardous Material Packages  

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

5 5 Site Visit Report - Review of the Lawrence Livermore National Laboratory Identified Defective Department of Transportation Hazardous Material Packages This site visit report documents the results of Office of Health, Safety and Security's review of the Lawrence Livermore National Laboratory (LLNL) identification, immediate actions, communications, documentation, evaluation, reporting and follow-up to the discovery of defective Department of Transportation (DOT) UN1A2 55- and 30-gallon open head single bolt closure steel drums intended for storage and transportation of hazardous waste and materials. This review, conducted on January 26-29, 2010, was sponsored by the DOE Livermore Site Office (LSO) to support interface with the lab and this report is intended to support follow-up

284

Emergency response planning for railroad transportation related spills of oil or other hazardous materials  

E-Print Network [OSTI]

In December 1984 an unintentional release of poison gas from a chemical plant in Bhopal, India killed over 2,500 people. Thousands of others were injured. Although this material was not in transportation at the time, this accident raised public...

Reeder, Geoffrey Benton

2012-06-07T23:59:59.000Z

285

Hazardous Materials Incident Response Procedure | Department of Energy  

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

Hazardous Materials Incident Response Procedure Hazardous Materials Incident Response Procedure Hazardous Materials Incident Response Procedure The purpose of this procedure is to provide guidance for developing an emergency response plan, as outlined in OSHA's 29 CFR 1910.120(q), for facility response. This model has been adopted and applied to work for response to transportation accidents involving radioactive material or other hazardous materials incidents Hazardous Materials Incident Response Procedure.docx More Documents & Publications Handling and Packaging a Potentially Radiologically Contaminated Patient Decontamination Dressdown at a Transportation Accident Involving Radioactive Material Medical Examiner/Coroner on the Handling of a Body/Human Remains that are Potentially Radiologically Contaminated

286

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

287

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

288

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

SciTech Connect (OSTI)

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

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

2013-08-18T23:59:59.000Z

289

A gas-jet transport and catcher technique for on-line production of radioactive ion beams using an electron cyclotron resonance ion-source  

SciTech Connect (OSTI)

Radioactive ion beams (RIB) have been produced on-line, using a gas-jet recoil transport coupled Electron Cyclotron Resonance (ECR) ion-source at the VECC-RIB facility. Radioactive atoms/molecules carried through the gas-jet were stopped in a catcher placed inside the ECR plasma chamber. A skimmer has been used to remove bulk of the carrier gas at the ECR entrance. The diffusion of atoms/molecules through the catcher has been verified off-line using stable isotopes and on-line through transmission of radioactive reaction products. Beams of {sup 14}O (71 s), {sup 42}K (12.4 h), {sup 43}K (22.2 h), and {sup 41}Ar (1.8 h) have been produced by bombarding nitrogen and argon gas targets with proton and alpha particle beams from the K130 cyclotron at VECC. Typical measured intensity of RIB at the separator focal plane is found to be a few times 10{sup 3} particles per second (pps). About 3.2 Multiplication-Sign 10{sup 3} pps of 1.4 MeV {sup 14}O RIB has been measured after acceleration through a radiofrequency quadrupole linac. The details of the gas-jet coupled ECR ion-source and RIB production experiments are presented along with the plans for the future.

Naik, V.; Chakrabarti, A.; Bhattacharjee, M.; Karmakar, P.; Bandyopadhyay, A.; Dechoudhury, S.; Mondal, M.; Pandey, H. K.; Lavanyakumar, D.; Mandi, T. K.; Dutta, D. P.; Kundu Roy, T.; Bhowmick, D.; Sanyal, D.; Srivastava, S. C. L.; Ray, A.; Ali, Md. S. [Variable Energy Cyclotron Centre (VECC), Sector-1, Block-AF, Bidhan Nagar, Kolkata 700064 (India); Bhattacharjee, S. [UGC-DAE CSR, Kolkata Centre, III/LB-8, Bidhan Nagar, Kolkata 700098 (India)

2013-03-15T23:59:59.000Z

290

Radionuclide-Chelating Agent Complexes in Low-Level Radioactive Decontamination Waste; Stability, Adsorption and Transport Potential  

SciTech Connect (OSTI)

Speciation calculations were done to determine whether organic complexants facilitate transport of radionuclides leached from waste buried in soils. EDTA readily mobilizes divalent transition metals and moderately impacts trivalent actinides. Picolinate readily mobilizes only Ni2+ and Co2+. These speciation predictions ignore the influence of soil adsorption and biodegradation that break apart the complexes. In adsorption studies, picolinate concentrations have to be >10-4 M to lower the adsorption of Ni and Co. For Sm(III), Th(IV), Np(V), U(VI), and Pu, the picolinate concentration must be >10-3 M before adsorption decreases. EDTA forms strong complexes with divalent transition metals and can stop adsorption of Ni and Co when EDTA solution concentrations are 10-5 M. EDTA complexes with Np(V), U(VI), and Pu are much weaker; EDTA concentrations would have to be >10-3 M to adversely effects non-transition metal/radionuclide adsorption. Most picolinate and ETDA-metal complexes appear to readily dissociate during interactions with soils. The enhanced migration of radionuclide-organic complexes may be limited to a few unique conditions. We recommend that mixtures of metal/radionuclides and EDTA should not be solidified or co-disposed with high pH materials such as cement. For weaker binding organic complexants, such as picolinate, citrate and oxalate, co-disposal of decontamination wastes and concrete should be acceptable.

Serne, R. Jeffrey; Cantrell, Cantrell J.; Lindenmeier, Clark W.; Owen, Antionette T.; Kutnyakov, Igor V.; Orr, Robert D.; Felmy, Andrew R.

2002-02-01T23:59:59.000Z

291

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

SciTech Connect (OSTI)

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

292

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

SciTech Connect (OSTI)

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

Bander, T.J.

1982-11-01T23:59:59.000Z

293

Public involvement in radioactive waste management decisions  

SciTech Connect (OSTI)

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

NONE

1994-04-01T23:59:59.000Z

294

Transport modeling in performance assessments for the Yucca Mountain disposal system for spent nuclear fuel and high-level radioactive waste  

Science Journals Connector (OSTI)

Abstract This paper summarizes modeling of radionuclide transport in the unsaturated and saturated zone conducted between 1984 and 2008 to evaluate feasibility, viability, and assess compliance of a repository for spent nuclear fuel and high-level radioactive waste at Yucca Mountain, Nevada. One dimensional (1-D) transport for a single porosity media without lateral dispersion was solved in both the saturated zone (SZ) and unsaturated zone (UZ) for the first assessment in 1984 but progressed to a dual-porosity formulation for the UZ in the second assessment in 1991. By the time of the viability assessment, a dual-permeability transport formulation was used in the UZ. With the planned switch to a dose performance measure, individual dose from a drinking water pathway was evaluated for the third assessment in 1993 and from numerous pathways for the viability assessment in 1998 and thereafter. Stream tubes for transport in the SZ were initially developed manually but progressed to particle tracking in 1991. For the viability assessment, particle tracking was used to solve the transport equations in the 3-D UZ and SZ flow fields. To facilitate calculations, the convolution method was also used in the SZ for the viability assessment. For the site recommendation in 2001 and licensing compliance analysis in 2008, the 3-D transport results of the SZ were combined with 1-D transport results, which evaluated decay of radionuclides, in order to evaluate compliance with groundwater protection requirements. Uncertainty in flow within the unsaturated and saturated zone was generally important to explaining the spread in the individual dose performance measure.

Rob P. Rechard; Bill W. Arnold; Bruce A. Robinson; James E. Houseworth

2014-01-01T23:59:59.000Z

295

Finding of No Significant Impact for the Offsite Transportation of Certain Low-Level and Mixed Radioactive Waste from Savannah River Site for Treatment and Disposal at Commercial and Government Facilities, DOE/EA-1308 (02/15/01)  

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

Finding of No Significant Impact Finding of No Significant Impact for the Offsite Transportation of Certain Low-level and Mixed Radioactive Waste from the Savannah River Site for Treatment and Disposal at Commercial and Government Facilities Agency: U. S. Department of Energy Action: Finding of No Significant Impact Summary: The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-1308) to analyze the potential environmental impacts associated with the proposed offsite transportation of certain low-level radioactive waste (LLW) and mixed (i.e., hazardous and radioactive) low-level radioactive waste (MLLW) from the Savannah River Site (SRS), located near Aiken, South Carolina. Based on the analyses in the EA, DOE has determined that the action is not a major Federal action significantly affecting

296

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

SciTech Connect (OSTI)

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

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

2012-08-01T23:59:59.000Z

297

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

298

HM-ACCESS Project (Framework for the Use of Electronic Shipping Papers for the Transport of Hazardous Materials)  

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

Pipeline and Hazardous Materials Pipeline and Hazardous Materials Safety Administration Pipeline and Hazardous Materials Safety Administration HM-ACCESS Initiative James Simmons Acting Chief, Research and Development Office of Hazardous Materials Safety Engineering and Research Division May 2012 U.S. Department of Transportation Pipeline and Hazardous Materials Safety Administration 2 H-azardous M-aterials A-utomated C-argo C-ommunication for E-fficient and S-afe S-hipments U.S. Department of Transportation Pipeline and Hazardous Materials Safety Administration Background Purpose: To identify and eliminate barriers to the use of paperless hazard communication technologies to improve the delivery of critical hazardous materials (HM) safety information throughout the transportation chain.

299

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

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

in PEM Fuel Cells: in PEM Fuel Cells: Advanced Modeling, Material Selection, Testing, and Design Optimization J. Vernon Cole and Ashok Gidwani CFDRC Prepared for: DOE Hydrogen Fuel Cell Kickoff Meeting February 13, 2007 This presentation does not contain any proprietary or confidential information. Background Water Management Issues Arise From: ƒ Generation of water by cathodic reaction ƒ Membrane humidification requirements ƒ Capillary pressure driven transport through porous MEA and GDL materials ƒ Scaling bipolar plate channel dimensions J.H. Nam and M. Kaviany, Int. J. Heat Mass Transfer, 46, pp. 4595-4611 (2003) Relevant Barriers and Targets ƒ Improved Gas Diffusion Layer, Flow Fields, Membrane Electrode Assemblies Needed to Improve Water Management: * Flooding blocks reactant transport

300

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

SciTech Connect (OSTI)

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

Pescatore, C.; Sullivan, T.

1984-01-01T23:59:59.000Z

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301

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

302

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

SciTech Connect (OSTI)

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

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

2013-07-08T23:59:59.000Z

303

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

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

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

2010-12-20T23:59:59.000Z

304

The Regional Role in Addressing DOE Transportation Concerns  

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

CSG's Midwestern Radioactive CSG's Midwestern Radioactive Materials Transportation Project Presented to the U.S. Department of Energy's Transportation External Coordination Working Group April 21, 2004 Lisa R. Sattler The Council of State Governments Midwestern Office Regional groups as "anchors" "State regional groups will anchor our collaborative process with the states." Strategic Plan for the Safe Transportation of Spent Nuclear Fuel and High-Level Radioactive Waste to Yucca Mountain: A Guide to Stakeholder Interactions (2003) Background on CSG The Council of State Governments (CSG) is a nonprofit, nonpartisan association of state governments Mission: build leadership skills, advocate multi- state problem solving and partnerships; interpret changing national and international conditions;

305

Three-dimensional simulation of groundwater flow and transport of chemical and low-level radioactive constituents within two production areas of the Savannah River Plant  

SciTech Connect (OSTI)

Modeling of transport in the environmental media was performed. Predicting the future performance of any waste site or facility and postulated actions in terms of migration of potential hazardous materials requires mathematical models capable of simulating flow and transport in the groundwater. Three-dimensional groundwater flow and transport models were developed to simulate the groundwater movement and contaminant transport in the Raw Materials Fabrication Area and the Separations Area. The overall objective of the analysis was to develop groundwater flow models that quantifies the rate and direction of the groundwater movement from the waste sites to points of discharge. The USGS Modular 3D model uses the strongly implicit procedure to solve sets of simultaneous finite-difference equations that represent the groundwater flow process. The transport functions, which are the concentration or mass flux at time t due to continuous injection starting at time t', were obtained by solving the three-dimensional advection-dispersion equations using the Sandia Waste Isolation Flow and Transport (SWIFT) model. 5 refs., 7 figs., 2 tabs.

Stephenson, D.E.; Looney, B.B.; Andrews, C.B.; Buss, D.R.

1987-01-01T23:59:59.000Z

306

Radioactive Nickel-63 - ORNL Neutron Sciences  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (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,"

307

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

SciTech Connect (OSTI)

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

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

2010-10-01T23:59:59.000Z

308

Computational modelling of transport phenomena in high energy materials processing application: large eddy simulation and parallelisation  

Science Journals Connector (OSTI)

A comprehensive three-dimensional numerical model is presented in order to address the coupled turbulent momentum, heat and species transport during molten metal-pool convection in association with continuous evolution of solid-liquid interface typically encountered in high energy materials processing applications. The turbulent aspect is handled by a large eddy simulation (LES) model and the phase changing phenomena is taken care of by a modified enthalpy-porosity technique. The proposed finite volume based LES model is subsequently parallelised for effective computational economy. To demonstrate the effectiveness of the present model, a systematic analysis is subsequently carried out to simulate a typical high power laser surface alloying process, where the effects of turbulent transport can actually be realised.

Dipankar Chatterjee

2011-01-01T23:59:59.000Z

309

Building waste management core indicators through Spatial Material Flow Analysis: Net recovery and transport intensity indexes  

SciTech Connect (OSTI)

Highlights: Black-Right-Pointing-Pointer Sustainability and proximity principles have a key role in waste management. Black-Right-Pointing-Pointer Core indicators are needed in order to quantify and evaluate them. Black-Right-Pointing-Pointer A systematic, step-by-step approach is developed in this study for their development. Black-Right-Pointing-Pointer Transport may play a significant role in terms of environmental and economic costs. Black-Right-Pointing-Pointer Policy action is required in order to advance in the consecution of these principles. - Abstract: In this paper, the material and spatial characterization of the flows within a municipal solid waste (MSW) management system are combined through a Network-Based Spatial Material Flow Analysis. Using this information, two core indicators are developed for the bio-waste fraction, the Net Recovery Index (NRI) and the Transport Intensity Index (TII), which are aimed at assessing progress towards policy-related sustainable MSW management strategies and objectives. The NRI approaches the capacity of a MSW management system for converting waste into resources through a systematic metabolic approach, whereas the TII addresses efficiency in terms of the transport requirements to manage a specific waste flow throughout the entire MSW management life cycle. Therefore, both indicators could be useful in assessing key MSW management policy strategies, such as the consecution of higher recycling levels (sustainability principle) or the minimization of transport by locating treatment facilities closer to generation sources (proximity principle). To apply this methodological approach, the bio-waste management system of the region of Catalonia (Spain) has been chosen as a case study. Results show the adequacy of both indicators for identifying those points within the system with higher capacity to compromise its environmental, economic and social performance and therefore establishing clear targets for policy prioritization. Moreover, this methodological approach permits scenario building, which could be useful in assessing the outcomes of hypothetical scenarios, thus proving its adequacy for strategic planning.

Font Vivanco, David, E-mail: font@cml.leidenuniv.nl [Institut de Ciencia i Tecnologia Ambientals (ICTA), Departament d'Enginyeria Quimica, Universitat Autonoma de Barcelona (UAB), 08193 Bellaterra, Barcelona (Spain); Institute of Environmental Sciences (CML), Leiden University, P.O. Box 9518, 2300 RA Leiden (Netherlands); Puig Ventosa, Ignasi [ENT Environment and Management, Carrer Sant Joan 39, First Floor, 08800 Vilanova i la Geltru, Barcelona (Spain); Gabarrell Durany, Xavier [Institut de Ciencia i Tecnologia Ambientals (ICTA), Departament d'Enginyeria Quimica, Universitat Autonoma de Barcelona (UAB), 08193 Bellaterra, Barcelona (Spain)

2012-12-15T23:59:59.000Z

310

DOE Order Self Study Modules - DOE O 460.1C Packaging and Transportation Safety and DOE O 460.2A Departmental Materials Transportation and Packaging Management  

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

60.1C 60.1C PACKAGING AND TRANSPORTATION SAFETY DOE O 460.2A DEPARTMENTAL MATERIALS TRANSPORTATION AND PACKAGING MANAGEMENT DOE O 460.1C and 460.2A Familiar Level June 2011 1 DOE O 460.1C PACKAGING AND TRANSPORTATION SAFETY DOE O 460.2A DEPARTMENTAL MATERIALS TRANSPORTATION AND PACKAGING MANAGEMENT FAMILIAR LEVEL _________________________________________________________________________ OBJECTIVES Given the familiar level of this module and the resources, you will be able to perform the following: 1. What are the objectives of U.S. Department of Energy (DOE) O 460.1C? 2. What is the DOE/National Nuclear Security Administration (NNSA) exemption process in DOE O 460.1C? 3. What are the onsite safety requirements specified by DOE O 460.1C? 4. What are the objectives of DOE O 460.2A?

311

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

312

Shielding requirements for the transport of nuclear warhead components under decommissioning  

SciTech Connect (OSTI)

The requirements to carry out accurate shielding calculations involved with the safe off-site transportation of packages containing nuclear warhead components, special assemblies and radioactive materials are discussed. The need for (a) detailed information on the geometry and material composition of the packaging and radioactive load, (b) accurate representation of the differential energy spectra (dN/dE) for the neutron and gamma spectra emitted by the radioactive materials enclosed in the packaging, (c) well-tested neutron and photon cross section libraries, (d) and accurate three-dimensional Monte Carlo transport codes are illustrated. A brief discussion of the need for reliable dose measurements is presented.

Hansen, L.F.

1994-09-01T23:59:59.000Z

313

Transportation Security Rulemaking Activities at the U.S. Nuclear Regulatory Commission  

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

AT THE AT THE U.S. NUCLEAR REGULATORY COMMISSION R. Clyde Ragland, P.E. Office of Nuclear Security and Incident Response 2011 DOE National Transportation Stakeholders Forum May 11, 2011 2 NRC Focus Prior to September 11, 2001 * Historically, NRC Transportation Security Regulations Focused on Highest Risk Radioactive Material, consisted of Special Nuclear Material (SNM) and Spent Nuclear Fuel (SNF) NRC Actions Since September 11, 2001 * Domestically, reviewed materials transported by NRC licensees and re- evaluated security requirements considering: - applicable threats to shipments - material considerations - magnitude of adverse consequences * Internationally, participated in the development of the IAEA Code of Conduct on the Safety and Security of Radioactive

314

Transportation Security  

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

For Review Only 1 Transportation Security Draft Annotated Bibliography Review July 2007 Preliminary Draft - For Review Only 2 Work Plan Task * TEC STG Work Plan, dated 8/2/06, Product #16, stated: "Develop an annotated bibliography of publicly-available documents related to security of radioactive material transportation." * Earlier this year, a preliminary draft annotated bibliography on this topic was developed by T-REX , UNM, to initially address this STG Work Plan Task. Preliminary Draft - For Review Only 3 Considerations in Determining Release of Information * Some "Publicly-available" documents could potentially contain inappropriate information according to standards set by DOE information security policy and DOE Guides. - Such documents would not be freely

315

Transuranic Waste Transportation Working Group Agenda  

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

States Energy Board States Energy Board Joint Meeting of the Radioactive Materials Transportation Committee and the Transuranic Waste Transportation Working Group The Hilton Knoxville Knoxville, Tennessee May 15, 2012 Tuesday, May 15, 2012 8:30 a.m. Breakfast 9:30 a.m. Welcome / Opening Remarks / Introductions - Christopher Wells, Southern States Energy Board - Sandra Threatt, Chair, SSEB Radioactive Materials Transportation Working Group - Elgan Usrey, Chair, SSEB Transuranic Waste Transportation Working Group 9:45 a.m. WIPP Transportation Program and National TRU Activities - Bill Mackie, Carlsbad Field Office 10:30 a.m. Break 10:45 a.m. Commercial Vehicle Safety Alliance Level VI Program Update - Larry Stern, Commercial Vehicle Safety Alliance

316

Transportation  

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

Health Risks » Transportation Health Risks » Transportation DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Transportation A discussion of health risks associated with transport of depleted UF6. Transport Regulations and Requirements In the future, it is likely that depleted uranium hexafluoride cylinders will be transported to a conversion facility. For example, it is currently anticipated that the cylinders at the ETTP Site in Oak Ridge, TN, will be transported to the Portsmouth Site, OH, for conversion. Uranium hexafluoride has been shipped safely in the United States for over 40 years by both truck and rail. Shipments of depleted UF6 would be made in accordance with all applicable transportation regulations. Shipment of depleted UF6 is regulated by the

317

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

SciTech Connect (OSTI)

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

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

1981-04-01T23:59:59.000Z

318

EMSL Research and Capability Development Proposals Nonlinear Radiation Response and Transport Properties in Scintillating Materials  

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

Figure 1. Time-of-Flight (TOF) versus light Figure 1. Time-of-Flight (TOF) versus light output (L) of CsI:Tl to He + ions. The inset is an example where L=263 is determined for particles with certainty energy (TOF=840). The energy resolution can be determined by ∆L/L = 45/263. The light-energy dependence and energy resolution can be observed as the difference in curvature and dispersive of the data. EMSL Research and Capability Development Proposals Nonlinear Radiation Response and Transport Properties in Scintillating Materials Project start date: Spring 2007 EMSL Lead Investigator: Yanwen Zhang Deposition and Microfabrication, EMSL, PNNL Co-investigators: Vaithiyalingam Shutthanandan Deposition and Microfabrication, EMSL, PNNL Scintillation response has wide applications in the field of astronomy, medical physics, high-energy

319

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

320

Real-Time Gamma Imaging of Technetium Transport through Natural and Engineered Porous Materials for Radioactive Waste Disposal  

Science Journals Connector (OSTI)

A significant obstacle to implementation of GDF is public and political concern around risks and consequences of failure against design criteria over the 105 to 106 year required lifespan of the facility,(4) highlighted by several failures to site GDF repositories, e.g., in the UK(5, 6) and at Yucca Mountain in the USA. ... N.C.H. is grateful to the Royal Academy of Engineering and the Nuclear Decommissioning Authority for funding. ...

Claire L. Corkhill; Jonathan W. Bridge; Xiaohui C. Chen; Phil Hillel; Steve F. Thornton; Maria E. Romero-Gonzalez; Steven A. Banwart; Neil C. Hyatt

2013-10-22T23:59:59.000Z

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


321

Development of long-term performance models for radioactive waste forms  

SciTech Connect (OSTI)

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

Bacon, Diana H.; Pierce, Eric M.

2011-03-22T23:59:59.000Z

322

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

SciTech Connect (OSTI)

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

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

2010-10-26T23:59:59.000Z

323

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

SciTech Connect (OSTI)

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

None

2013-08-29T23:59:59.000Z

324

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

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

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

None

2013-08-29T23:59:59.000Z

325

Open literature review of threats including sabotage and theft of fissile material transport in Japan.  

SciTech Connect (OSTI)

This report is a review of open literature concerning threats including sabotage and theft related to fissile material transport in Japan. It is intended to aid Japanese officials in the development of a design basis threat. This threat includes the external threats of the terrorist, criminal, and extremist, and the insider threats of the disgruntled employee, the employee forced into cooperation via coercion, the psychotic employee, and the criminal employee. Examination of the external terrorist threat considers Japanese demographics, known terrorist groups in Japan, and the international relations of Japan. Demographically, Japan has a relatively homogenous population, both ethnically and religiously. Japan is a relatively peaceful nation, but its history illustrates that it is not immune to terrorism. It has a history of domestic terrorism and the open literature points to the Red Army, Aum Shinrikyo, Chukaku-Ha, and Seikijuku. Japan supports the United States in its war on terrorism and in Iraq, which may make Japan a target for both international and domestic terrorists. Crime appears to remain low in Japan; however sources note that the foreign crime rate is increasing as the number of foreign nationals in the country increases. Antinuclear groups' recent foci have been nuclear reprocessing technology, transportation of MOX fuel, and possible related nuclear proliferation issues. The insider threat is first defined by the threat of the disgruntled employee. This threat can be determined by studying the history of Japan's employment system, where Keiretsu have provided company stability and lifetime employment. Recent economic difficulties and an increase of corporate crime, due to sole reliability on the honor code, have begun to erode employee loyalty.

Cochran, John Russell; Furaus, James Phillip; Marincel, Michelle K.

2005-06-01T23:59:59.000Z

326

Transportation Services  

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

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

327

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.

328

Transportation  

Science Journals Connector (OSTI)

The romantic rides in Sandburgs eagle-car changed society. On the one hand, motor vehicle transportation is an integral thread of societys fabric. On the other hand, excess mobility fractures old neighborh...

David Hafemeister

2014-01-01T23:59:59.000Z

329

WIPP Transportation (FINAL)  

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

(DOE) has established an elaborate system for safely transporting transuranic, or TRU, radioactive waste to the Waste Isolation Pilot Plant (WIPP) for permanent disposal, or...

330

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

SciTech Connect (OSTI)

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

Alfred Wickline

2007-06-01T23:59:59.000Z

331

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

SciTech Connect (OSTI)

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

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

1993-08-01T23:59:59.000Z

332

Use of Composite Pipe Materials in the Transportation of Natural Gas (INEEL/EXT-02-00992)  

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

992 992 Use of Composite Pipe Materials in the Transportation of Natural Gas Patrick Laney July 2002 Idaho National Engineering and Environmental Laboratory Bechtel BWXT Idaho, LLC INEEL/EXT-02-00992 Use of Composite Pipe Materials in the Transportation of Natural Gas Sponsored by Natural Gas Pipeline Infrastructure Reliability Program National Energy Technology Laboratory INEEL Field Work Proposal # 4340-70 Prepared by: Patrick Laney Idaho National Engineering and Environmental Laboratory Idaho Falls, Idaho With Contributions From: Ian Kopp Kenway Corporation Augusta, Maine July 2002 Idaho National Engineering and Environmental Laboratory Fossil Energy Technologies Department Idaho Falls, Idaho 83415 Prepared for the U.S. Department of Energy Office of Energy Efficiency and Renewable Energy

333

Decontamination Dressdown at a Transportation Accident Involving  

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

Decontamination Dressdown at a Transportation Accident Involving Decontamination Dressdown at a Transportation Accident Involving Radioactive Material Decontamination Dressdown at 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 how the decontamination dressdown process is implemented. During this discussion, the instructor can present various scenarios, each of which would discuss decontamination at the accident scene. The purpose of this discussion would be to cover how responders

334

Uranium Compounds and Other Natural Radioactivities  

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

335

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

E-Print Network [OSTI]

thermoelectric materials are the intermetallic clathrates. Clathrates are cage-structured materials with guest atoms enclosed. Previous studies have shown lower thermal conductivities compared with many other bulk compounds, and it is believed that guest atom...

Zheng, Xiang

2012-10-19T23:59:59.000Z

336

Transportation External Coordination Working Group:  

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

Study of Study of DOE FY03 SNF Shipments Judith Holm National Transportation Program Albuquerque, New Mexico April 21, 2004 Background Benchmarking * The goal of benchmarking is to identify, understand, and adapt outstanding practices from organizations anywhere in the world to help your organization improve its performance * Benchmarking looks outward to find best practice and high performance and then measures actual business operations against those goals Background Best Practices * Best practices are proven solutions that represent superior performance when adapted and implemented in one's own organization. This includes processes and procedures that others are using to transport radioactive materials Background Lessons Learned * Lessons learned are "good work practices" or

337

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

E-Print Network [OSTI]

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

338

Improved power efficiency in blue phosphorescent organic light-emitting diodes using diphenylmethyl linkage based high triplet energy hole transport materials  

Science Journals Connector (OSTI)

Improved power efficiency in blue phosphorescent organic light-emitting diodes (PHOLEDs) was demonstrated by using new high triplet energy hole-transport materials based on the diphenylmethyl linkage. Two high triplet energy hole-transport materials with diphenylamine or ditolyamine moieties linked through a diphenylmethyl linkage, 4,4?-(diphenylmethylene)bis(N,N-diphenylaniline) (TCBPA) and 4,4?-(diphenylmethylene)bis(N,N-di-p-tolylaniline), were synthesized and evaluated as hole-transport materials for blue PHOLEDs. The power efficiency of TCBPA was superior to that of standard 1,1-bis[4-[N,N?-di(p-tolyl)amino]phenyl]cyclohexane.

Chil Won Lee; Jun Yeob Lee

2013-01-01T23:59:59.000Z

339

The Resource Handbook on DOE Transportation Risk Assessment  

SciTech Connect (OSTI)

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

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

2003-02-27T23:59:59.000Z

340

Thermographic analysis of polyurethane foams integrated with phase change materials designed for dynamic thermal insulation in refrigerated transport  

Science Journals Connector (OSTI)

Abstract The dispersion process of a micro-encapsulated phase change material (n-tetradecane) into a polyurethane foam was studied in order to develop a micro-composite insulating material with both low thermal conductivity and latent heat storage properties. The maximum weight content of micro-capsules added to the cellular matrix was 13.5%. Dynamic thermal properties of hybrid foams were investigated by means of a thermographic analysis. This was found to be a very effective diagnostic technique in detecting the change in heat transfer rate across the micro-composite foam in an indirect way, i.e. by measuring how the surface temperature changes over time under heat irradiation. Such a material would be of interest in the field of transport of perishable goods, particularly those requiring a controlled regime of carriage/storage temperatures.

Andrea Tinti; Antonella Tarzia; Alessandra Passaro; Riccardo Angiuli

2014-01-01T23:59:59.000Z

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


341

DOE/EA-1308; Environmental Assessment for the Offsite Transportation of Certain Low-Level and Mixed Radioactive Waste from the Savannah River Site for Treatment and Disposal at Commercial and Government Facilities (February 2001)  

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

08 08 ENVIRONMENTAL ASSESSMENT FOR THE OFFSITE TRANSPORTATION OF CERTAIN LOW-LEVEL AND MIXED RADIOACTIVE WASTE FROM THE SAVANNAH RIVER SITE FOR TREATMENT AND DISPOSAL AT COMMERCIAL AND GOVERNMENT FACILITIES FEBRUARY 2001 U. S. DEPARTMENT OF ENERGY SAVANNAH RIVER OPERATIONS OFFICE SAVANNAH RIVER SITE i ii This page is intentionally left blank iii TABLE OF CONTENTS Page 1.0 INTRODUCTION 1 1.1 Background 1 1.2 Purpose and Need for Action 6 2.0 PROPOSED ACTION AND ALTERNATIVES 6 2.1 Proposed Action 6 2.2 Alternatives to the Proposed Action 11 2.2.1 No Action, Continue to Store These Waste Forms at SRS 11 2.2.2 Construct and Operate Onsite Treatment and Disposal Facilities 11 3.0 ENVIRONMENTAL CONSEQUENCES OF THE PROPOSED ACTION AND ALTERNATIVES 12 3.1 Onsite Loading Operations 12 3.2 Transportation Impacts

342

Radioactive waste management in the former USSR  

SciTech Connect (OSTI)

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

Bradley, D.J.

1992-06-01T23:59:59.000Z

343

Transportation  

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

Due to limited parking, all visitors are strongly encouraged to: Due to limited parking, all visitors are strongly encouraged to: 1) car-pool, 2) take the Lab's special conference shuttle service, or 3) take the regular off-site shuttle. If you choose to use the regular off-site shuttle bus, you will need an authorized bus pass, which can be obtained by contacting Eric Essman in advance. Transportation & Visitor Information Location and Directions to the Lab: Lawrence Berkeley National Laboratory is located in Berkeley, on the hillside directly above the campus of University of California at Berkeley. The address is One Cyclotron Road, Berkeley, California 94720. For comprehensive directions to the lab, please refer to: http://www.lbl.gov/Workplace/Transportation.html Maps and Parking Information: On Thursday and Friday, a limited number (15) of barricaded reserved parking spaces will be available for NON-LBNL Staff SNAP Collaboration Meeting participants in parking lot K1, in front of building 54 (cafeteria). On Saturday, plenty of parking spaces will be available everywhere, as it is a non-work day.

344

Gas Generation Test Support for Transportation and Storage of Plutonium Residue Materials - Part 1: Rocky Flats Sand, Slag, and Crucible Residues  

SciTech Connect (OSTI)

The purpose of this report is to present experimental results that can be used to establish one segment of the safety basis for transportation and storage of plutonium residue materials.

Livingston, R.R.

1999-08-24T23:59:59.000Z

345

Disilane- and siloxane-bridged biphenyl and bithiophene derivatives as electron-transporting materials in \\{OLEDs\\}  

Science Journals Connector (OSTI)

Optical, electrochemical, and electron-transporting properties of disilane- and siloxane-bridged biphenyl and bithiophene derivatives were investigated, in comparison with those of the monosilane-bridged analogues (siloles). The UV spectra and cyclic voltammograms indicated that elongation of the silicon bridge suppresses the ?-conjugation, in accordance with the results of DFT calculations. The DFT calculations indicated also that the disilane-bridged biphenyl and siloxane-bridged bithiophene should have the low-lying \\{HOMOs\\} and LUMOs. The electron-transporting properties were evaluated by the performance of triple-layered \\{OLEDs\\} having vapor-deposited films of the Si-bridged compound, Alq3, and TPD, as the electron-transport, emitter, and hole-transport, respectively. Of these, the device with a disilane-bridged biphenyl exhibited the high performance with the maximum current density of 590mA/cm2 at the applied electric field of 12נ107V/m (applied bias voltage=13V) and the maximum luminance of 22000cd/m2 at 13נ107V/m.

Hiroyuki Kai; Joji Ohshita; Sayaka Ohara; Naohiro Nakayama; Atsutaka Kunai; In-Sook Lee; Young-Woo Kwak

2008-01-01T23:59:59.000Z

346

Packaging and Transfer or Transportation of Materials of National Security Interest  

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

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

2004-04-26T23:59:59.000Z

347

Auxiliary analyses in support of performance assessment of a hypothetical low-level waste facility: Two-phase flow and contaminant transport in unsaturated soils with application to low-level radioactive waste disposal. Volume 2  

SciTech Connect (OSTI)

A numerical model of multiphase air-water flow and contaminant transport in the unsaturated zone is presented. The multiphase flow equations are solved using the two-pressure, mixed form of the equations with a modified Picard linearization of the equations and a finite element spatial approximation. A volatile contaminant is assumed to be transported in either phase, or in both phases simultaneously. The contaminant partitions between phases with an equilibrium distribution given by Henry`s Law or via kinetic mass transfer. The transport equations are solved using a Galerkin finite element method with reduced integration to lump the resultant matrices. The numerical model is applied to published experimental studies to examine the behavior of the air phase and associated contaminant movement under water infiltration. The model is also used to evaluate a hypothetical design for a low-level radioactive waste disposal facility. The model has been developed in both one and two dimensions; documentation and computer codes are available for the one-dimensional flow and transport model.

Binning, P. [Newcastle Univ., NSW (Australia); Celia, M.A.; Johnson, J.C. [Princeton Univ., NJ (United States). Dept. of Civil Engineering and Operations Research

1995-05-01T23:59:59.000Z

348

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

349

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

350

Nuclear Resonance Fluorescence for Materials Assay  

SciTech Connect (OSTI)

This paper discusses the use of nuclear resonance fluorescence (NRF) techniques for the isotopic and quantitative assaying of radioactive material. Potential applications include age-dating of an unknown radioactive source, pre- and post-detonation nuclear forensics, and safeguards for nuclear fuel cycles Examples of age-dating a strong radioactive source and assaying a spent fuel pin are discussed. The modeling work has ben performed with the Monte Carlo radiation transport computer code MCNPX, and the capability to simulate NRF has bee added to the code. Discussed are the limitations in MCNPX?s photon transport physics for accurately describing photon scattering processes that are important contributions to the background and impact the applicability of the NRF assay technique.

Quiter, Brian J.; Ludewigt, Bernhard; Mozin, Vladimir; Prussin, Stanley

2009-06-29T23:59:59.000Z

351

Nuclear Resonance Fluorescence for Materials Assay  

SciTech Connect (OSTI)

This paper discusses the use of nuclear resonance fluorescence (NRF) techniques for the isotopic and quantitative assaying of radioactive material. Potential applications include age-dating of an unknown radioactive source, pre- and post-detonation nuclear forensics, and safeguards for nuclear fuel cycles Examples of age-dating a strong radioactive source and assaying a spent fuel pin are discussed. The modeling work has ben performed with the Monte Carlo radiation transport computer code MCNPX, and the capability to simulate NRF has bee added to the code. Discussed are the limitations in MCNPX's photon transport physics for accurately describing photon scattering processes that are important contributions to the background and impact the applicability of the NRF assay technique.

Quiter, Brian; Ludewigt, Bernhard; Mozin, Vladimir; Prussin, Stanley

2009-06-05T23:59:59.000Z

352

Normal Condition on Transport Thermal Analysis and Testing of a Type B Drum Package  

SciTech Connect (OSTI)

Increasing the content limits of radioactive material packagings can save money and increase transportation safety by decreasing the total number of shipments required to transport large quantities of material. The contents of drum packages can be limited by unacceptable containment vessel pressures and temperatures due to the thermal properties of the insulation. The purpose of this work is to understand and predict the effects of insulation properties on containment system performance.

Jerrell, J.W.; van Alstine, M.N.; Gromada, R.J.

1995-03-21T23:59:59.000Z

353

Radioactivity and Radiation  

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

354

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

SciTech Connect (OSTI)

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

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

2008-07-09T23:59:59.000Z

355

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

E-Print Network [OSTI]

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

Goddard III, William A.

356

Materials  

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

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

357

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

358

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

SciTech Connect (OSTI)

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

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

2012-10-02T23:59:59.000Z

359

Clean Slate transportation and human health risk assessment  

SciTech Connect (OSTI)

Public concern regarding activities involving radioactive material generally focuses on the human health risk associated with exposure to ionizing radiation. This report describes the results of a risk analysis conducted to evaluate risk for excavation, handling, and transport of soil contaminated with transuranics at the Clean Slate sites. Transportation risks were estimated for public transport routes from the Tonopah Test Range (TTR) to the Envirocore disposal facility or to the Area 3 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) for both radiological risk and risk due to traffic accidents. Human health risks were evaluated for occupational and radiation-related health effects to workers. This report was generated to respond to this public concern, to provide an evaluation of the risk, and to assess feasibility of transport of the contaminated soil for disposal.

NONE

1997-02-01T23:59:59.000Z

360

Applications of radioactive tracer technology in the real-time measurement of wear and corrosion  

Science Journals Connector (OSTI)

Radioactive tracer technology has been used for many years as a tool to make highly sensitive real-time measurements of wear and corrosion. With this technique, the material of interest is tagged with radioactive isotopes through either direct activation of a relatively small number of atoms in the component itself, or implantation of radioactive isotopes. As the component wears or corrodes under test, radioactive atoms are transported from the surface in the form of wear particles or corrosion products. Wear or corrosion is measured in real-time through either interrogation of the buildup of radioactivity in the transport fluid, or by the reduction in activity of the labeled wear component. The process involves selection of an appropriate labeling technique, labeling of a component or components of interest, calibration, testing and data reduction and analysis. Although the majority of the work performed has been in the automotive engine and lubricant industry, Southwest Research Institute has recently extended the application into other fields, such as hydraulic pump wear, prosthetic hip joint wear, wear in marine engines and crude oil corrosivity. This paper discusses the various techniques employed to label components of interest, the advantages of the techniques, and gives several examples of current applications of this technology.

D.C. Eberle; C.M. Wall; M.B. Treuhaft

2005-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "radioactive materials transportation" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
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361

National Transportation Stakeholders Forum (NTSF) Charter | Department of  

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

Services » Waste Management » Packaging and Transportation » Services » Waste Management » Packaging and Transportation » National Transportation Stakeholders Forum » National Transportation Stakeholders Forum (NTSF) Charter National Transportation Stakeholders Forum (NTSF) Charter The U.S. Department of Energy (DOE) National Transportation Stakeholders Forum (NTSF) is the mechanism through which DOE engages at a national level with states, tribes, federal agencies and other interested stakeholders about the Department's shipments of radioactive waste and materials, as well as occasional high- visibility shipments that are nonradioactive. The purpose of the NTSF is to bring transparency, openness, and accountability to DOE's offsite transportation activities through collaboration with state and tribal governments. DOE will work through existing agreements and

362

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

Broader source: Energy.gov [DOE]

On Friday, May 14, 2004, at approximately 11:30 a.m., a dump truck transporting mixing tank T-12 (Tank T-12) from the New Hydrofracture Facility (NHF) Decontamination and Decommissioning (D&D) Project arrived at the Environmental Management Waste Management Facility (EMWMF). Upon arrival, an incoming radiological survey was performed.

363

Radioactive waste storage issues  

SciTech Connect (OSTI)

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

364

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

365

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

SciTech Connect (OSTI)

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

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

2010-01-21T23:59:59.000Z

366

Materials  

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

367

Radioactive Waste Management  

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

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

1984-02-06T23:59:59.000Z

368

Low-Level Radioactive Waste Disposal Act (Pennsylvania) | Department of  

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

Low-Level Radioactive Waste Disposal Act (Pennsylvania) Low-Level Radioactive Waste Disposal Act (Pennsylvania) Low-Level Radioactive Waste Disposal Act (Pennsylvania) < Back Eligibility Utility Commercial Investor-Owned Utility State/Provincial Govt Municipal/Public Utility Local Government Rural Electric Cooperative Transportation Program Info State Pennsylvania Program Type Environmental Regulations Provider Pennsylvania Department of Environmental Protection This act provides a comprehensive strategy for the siting of commercial low-level waste compactors and other waste management facilities, and to ensure the proper transportation, disposal and storage of low-level radioactive waste. Commercial incineration of radioactive wastes is prohibited. Licenses are required for low-level radioactive waste disposal facilities not licensed to accept low-level radioactive waste. Disposal at

369

Bacteria eats radioactive waste  

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

370

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

E-Print Network [OSTI]

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

Sordelet, Tyler Christopher

2012-01-01T23:59:59.000Z

371

DOE-Idaho's Packaging and Transportation Perspective  

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

Idaho's Packaging and Idaho's Packaging and T t ti P ti Transportation Perspective Richard Provencher Manager DOE Idaho Operations Office DOE Idaho Operations Office Presented to the DOE National Transportation Stakeholders Forum Stakeholders Forum May 12, 2011 DOE's Idaho site ships and receives a wide variety of radioactive materials 2 Engineering Test Reactor vessel excavated, transported across the site and disposed 3 Navy SNF moved from wet to dry storage storage 4 5 Left: Contact-handled TRU shipments Right: A remote-handled TRU shipment Right: A remote handled TRU shipment 6 NAC spent nuclear fuel container on its trailer, prior to installation of its impact limiters 7 Examples of dry (CPP-603) and wet (CPP-666) storage in Idaho (CPP 666) storage in Idaho 8 INL's Materials and Fuels Complex Hot Fuel Examination

372

National Transportation Stakeholders Forum (NTSF) | Department of Energy  

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

National Transportation Stakeholders Forum (NTSF) National Transportation Stakeholders Forum (NTSF) National Transportation Stakeholders Forum (NTSF) The U.S. Department of Energy (DOE) National Transportation Stakeholders Forum (NTSF) is the mechanism through which DOE communicates 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 nonradioactive. The purpose of the NTSF is to bring transparency, openness, and accountability to DOE's offsite transportation activities through collaboration with state and tribal governments. The NTSF meetings and webinars will be particularly relevant for personnel with responsibilities in packaging and transportation, emergency management, security, inspection and enforcement, and radiation protection. Send your

373

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

374

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

375

FINAL Transportation External Coordination Working Group (TEC)  

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

Transportation External Coordination Working Group (TEC) January 28-30, 2002 New Orleans, Louisiana Meeting Summary The Transportation External Coordination Working Group (TEC) held its 20 th semi-annual meeting January 28-30, 2002, in New Orleans, Louisiana. This was the tenth anniversary of TEC, and 102 attendees from national, State, Tribal, and local government organizations; industry and professional groups and other interested parties in the U.S. Department of Energy (DOE) programs, met to address a variety of issues related to DOE's radioactive materials transportation activities. The TEC process includes the involvement of these key stakeholders in developing solutions to DOE transportation issues through their actual participation in the work product. These members provide continuing and improved

376

Transportation External Coordination Working Group (TEC)  

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

Portland, Oregon - February 6-7, 2001 Portland, Oregon - February 6-7, 2001 Transportation External Coordination Working Group (TEC) February 6-7, 2001 Portland, Oregon Meeting Summary The Transportation External Coordination Working Group (TEC) held its 18 th semi-annual meeting February 6-7, 2001, in Portland, Oregon. Attending were 125 representatives from national, State, Tribal and local government organizations, industry and professional groups and other interested parties/DOE programs who meet to address a variety of issues related to DOE's radioactive materials transportation activities and provide continuing and improved coordination between DOE, other levels of government, and outside organizations with DOE transportation-related responsibilities. PLENARY I - TRANSCOM 2000 PRESENTATION (February 6)

377

Fiscal year 1985 Department of Energy authorization (transportation programs). Hearings before the Subcommittee on Transportation, Aviation and Materials of the Committee on Science and Technology, House of Representatives, Ninety-Eighth Congress, Second Session, February 21,22, 1984  

SciTech Connect (OSTI)

Representatives of DOE agencies, automotive and alternative fuel research groups, and the electrical vehicle industry testified during a two-day hearing on 1984 appropriations for research and development on transportation. Of major concern was an administration proposal to reduce spending for these programs by 23%, consolidating some and terminating others. Positive signs in the budget proposal for 1985 include an emphasis on high-temperature materials development. DOE spokesmen explained the rationale behind the budget figures and allocations, emphasizing the need to improve efficiency and reduce costs. Others spoke to the energy supply and security implications of pursuing alternative fuel and transportation modes. Two letters submitted for the record follow the testimony.

Not Available

1984-01-01T23:59:59.000Z

378

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

Broader source: Energy.gov [DOE]

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

379

Resource handbook on transportation risk assessment.  

SciTech Connect (OSTI)

This resource handbook contains useful information to streamline radioactive material transportation risk assessments for National Environmental Policy Act (NEPA) documents prepared for U.S. Department of Energy (DOE) programs. Streamlining refers to instituting steps that can increase the efficiency of future assessments, reduce costs, and promote increased quality and consistency across the DOE complex. This handbook takes advantage of the wealth of information developed through decades of DOE's NEPA experience. It contains a review of historical assessments; a description of comprehensive and generally acceptable transportation risk assessment methodology (i.e., models); and a compilation of supporting data, parameters, and generally accepted assumptions. This handbook also includes a discussion paper that addresses cumulative impacts (Appendix A). The discussion paper illustrates the evolving and sometimes unresolved issues encountered in transportation risk assessment. Other topics, such as sabotage, environmental justice, and human factors, may be addressed in the future. This resource document was developed as the first primary reference book providing useful information for conducting transportation risk assessments for radioactive material in the NEPA context.

Chen, S. Y.; Biwer, B. M.; Monette, F. A.; Environmental Assessment; SNL; BAPL; USOE; Battelle Memorial Inst.

2003-01-01T23:59:59.000Z

380

Radioactive waste management in the former USSR. Volume 3  

SciTech Connect (OSTI)

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

Bradley, D.J.

1992-06-01T23:59:59.000Z

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


381

Transportation System Requirements Document  

SciTech Connect (OSTI)

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

Not Available

1993-09-01T23:59:59.000Z

382

Radioactive Waste Incineration: Status Report  

SciTech Connect (OSTI)

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

383

The effect of cargo on the crush loading of RAM transportation packages in ship collisions  

SciTech Connect (OSTI)

Recent intercontinental radioactive material shipping campaigns have focused public and regulatory attention on the safety of transport of this material by ocean-going vessels. One major concern is the response of the vessel and onboard radioactive material (RAM) packages during a severe ship-to-ship collision. These collisions occur at velocities less than the velocity obtained in the Type B package regulatory impact event and the bow of the striking ship is less rigid than the unyielding target used in those tests (Ammerman and Daidola, 1996). This implies that ship impact is not a credible scenario for damaging the radioactive material packages during ship collisions. It is possible, however, for these collisions to generate significant amounts of crush force by the bow of the impacting ship overrunning the package. It is the aim of this paper to determine an upper bound on the magnitude of this crush force taking into account the strength of the radioactive material carrying vessel and any other cargo that may be stowed in the same hold as the radioactive material.

Radloff, H.D.; Ammerman, D.J.

1998-03-01T23:59:59.000Z

384

APS Radioactive Sample Safety Review Committee  

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

385

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

386

Breaking symmetries in ordered materials : spin polarized light transport in magnetized noncentrosymmetric 1D photonic crystals, and photonic gaps and fabrication of quasiperiodic structured materials from interference lithography  

E-Print Network [OSTI]

Effects of breaking various symmetries on optical properties in ordered materials have been studied. Photonic crystals lacking space-inversion and time-reversal symmetries were shown to display nonreciprocal dispersion ...

Bita, Ion

2006-01-01T23:59:59.000Z

387

Waste gas combustion in a Hanford radioactive waste tank  

SciTech Connect (OSTI)

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

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

1994-07-01T23:59:59.000Z

388

Argonne Transportation - TransForum Volume 1  

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

TransForum: Volume 1 TransForum: Volume 1 ISSN 2156-3594 (Print) ISSN 2156-373X (Online) Vol. 1, No. 4, Winter 1998-99 (966k pdf ) Energy Secretary Dedicates Argonne's Transportation Center: New Technology Promises Cleaner Diesels Measuring How Fuel Cell Stack Up Vol. 1, No. 3, Summer 1998 (684k pdf ) Using Corn to Fuel Your Car: A Good Environmental Choice? If You Can't Stand the Heat ... Call Argonne Modeling Cars Isn't Just Child's Play Lilliputian Sensors Could Help Solve a Gigantic Pollution Problem Making a Material Difference in Advanced Batteries Vol. 1, No. 2, Spring 1998 (577k pdf ) Gearing Up for HEV Powertrain Design Taking a Closer Look into How Batteries and Fuel Cells Work ITS Makes Life in the Fast Lane Easier "Wrapping It Up to Go": Transporting Hazardous and Radioactive Materials Safely

389

Low-level radioactive waste technology: a selected, annotated bibliography. [416 references  

SciTech Connect (OSTI)

This annotated bibliography of 416 references represents the third in a series to be published by the Hazardous Materials Information Center containing scientific, technical, economic, and regulatory information relevant to low-level radioactive waste technology. The bibliography focuses on disposal site, environmental transport, and waste treatment studies as well as general reviews on the subject. The publication covers both domestic and foreign literature for the period 1951 to 1981. Major chapters selected are Chemical and Physical Aspects; Container Design and Performance; Disposal Site; Environmental Transport; General Studies and Reviews; Geology, Hydrology, and Site Resources; Regulatory and Economic Aspects; Social Aspects; Transportation Technology; Waste Production; and Waste Treatment. Entries in each of the chapters are further classified as a field study, laboratory study, theoretical study, or general overview involving one or more of these research areas.

Fore, C.S.; Carrier, R.F.; Brewster, R.H.; Hyder, L.K.; Barnes, K.A.

1981-10-01T23:59:59.000Z

390

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

SciTech Connect (OSTI)

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

Marsha Keister; Kathryn McBride

2006-08-01T23:59:59.000Z

391

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:...

392

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

SciTech Connect (OSTI)

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

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

1998-09-01T23:59:59.000Z

393

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

SciTech Connect (OSTI)

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

394

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

SciTech Connect (OSTI)

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

Blanton, P.; Eberl, K.

2013-10-10T23:59:59.000Z

395

CSER 00-008 use of PFP Glovebox HC-18BS for Storage and Transport of Fissionable Material  

SciTech Connect (OSTI)

This CSER addresses the feasibility of increasing the allowed number of open containers and permitting the transfer and storage of fissionable material in Glovebox HC-18BS without regard to form or density (metal, oxide having an H/X {le} 20, material having unrestricted moderation and plutonium hydroxide having a plutonium density of 0.2 g/cm{sup 3}).

ERICKSON, D.G.

2000-06-01T23:59:59.000Z

396

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

397

ONSITE TRANSPORTATION AUTHORIZATION CHALLENGES AT THE SAVANNAH RIVER SITE  

SciTech Connect (OSTI)

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

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

2012-05-30T23:59:59.000Z

398

Office of Packaging and Transportation Fiscal Year 2012 Annual Report |  

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

Packaging and Transportation Fiscal Year 2012 Annual Packaging and Transportation Fiscal Year 2012 Annual Report Office of Packaging and Transportation Fiscal Year 2012 Annual Report The Office of Environmental Management (EM) was established to mitigate the risks and hazards posed by the legacy of nuclear weapons production and research. The most ambitious and far ranging of these missions is dealing with the environmental legacy of the Cold War. Many problems posed by its operations are unique, and include the transportation of unprecedented amounts of contaminated waste, water, and soil, and a vast number of contaminated structures during remediation of the contaminated sites. Since Fiscal Year (FY) 2004, EM has completed over 150,000 shipments of radioactive material and waste. The mission of the Department of Energy (DOE) Office of Packaging and

399

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

400

Examination of radioactive decay methodology in the HASCAL code  

SciTech Connect (OSTI)

The HASCAL 2.0 code provides dose estimates for nuclear, chemical, and biological facility accident and terrorist weapon strike scenarios. In the analysis of accidents involving radioactive material, an approximate method is used to account for decay during transport. Rather than perform the nuclide decay during the atmospheric transport calculation, the decay is performed a priori and a table look up method is used during the transport of a depositing tracer particle and non depositing (gaseous) tracer particle. In order to investigate the accuracy of this decay methodology two decay models were created using the ORIGEN2 computer program. The first is a HASCAL like model that treats decay and growth of all nuclide explicitly over the time interval specified for atmospheric transport, but does not change the relative mix of depositing and non-depositing nuclides due to deposition to the ground, nor does it treat resuspension. The second model explicitly includes resuspension as well as separate decay of the nuclides in the atmosphere and on the ground at each deposition time step. For simplicity, both of these models uses a one-dimensional layer model for the atmospheric transport. An additional investigation was performed to determine the accuracy of the HASCAL like model in separately following Cs-137 and I-131. The results from this study show that the HASCAL decay model compares closely with the more rigorous model with the computed doses are generally within one percent (maximum error of 7 percent) over 48 hours following the release. The models showed no difference for Cs-137 and a maximum error of 2.5 percent for I-131 over the 96 hours following release.

Steffler, R.S. [Texas A and M Univ., College Station, TX (United States). Dept. of Nuclear Engineering; Ryman, J.C.; Gehin, J.C.; Worley, B.A. [Oak Ridge National Lab., TN (United States)

1998-01-01T23:59:59.000Z

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


401

Emergency Responder Radioactive Material Quick Reference Sheet  

Broader source: Energy.gov [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...

402

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...

403

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

404

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...

405

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

406

Microbial transformation of low-level radioactive waste  

SciTech Connect (OSTI)

Microorganisms play a significant role in the transformation of the radioactive waste and waste forms disposed of at shallow-land burial sites. Microbial degradation products of organic wastes may influence the transport of buried radionuclides by leaching, solubilization, and formation of organoradionuclide complexes. The ability of indigenous microflora of the radioactive waste to degrade the organic compounds under aerobic and anaerobic conditions was examined. Leachate samples were extracted with methylene chloried and analyzed for organic compounds by gas chromatography and mass spectrometry. In general, several of the organic compounds in the leachates were degraded under aerobic conditions. Under anaerobic conditions, the degradation of the organics was very slow, and changes in concentrations of several acidic compounds were observed. Several low-molecular-weight organic acids are formed by breakdown of complex organic materials and are further metabolized by microorganisms; hence these compounds are in a dynamic state, being both synthesized and destroyed. Tributyl phosphate, a compound used in the extraction of metal ions from solutions of reactor products, was not degraded under anaerobic conditions.

Francis, A.J.

1980-06-01T23:59:59.000Z

407

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

408

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

409

Transportation of radionuclides in urban environs: draft environmental assessment  

SciTech Connect (OSTI)

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

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

1980-07-01T23:59:59.000Z

410

Automated Transportation Management System (ATMS)  

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

Re evised June 2010 Re evised June 2010 Autom The Depa Transport an integra system al outbound air. Its ea 1989 DOE significant operationa commerce electronic rates, pre transporta users eva shipments opportunit logistics im ATMS is i radioactiv shipments System ATMS is a activities p packaging including materials. common s lading, fre * W * C S * A * H * E * * O 0 mated T artment of Ene tation Manage ated web-base lowing users freight shipm arly developm E Inspector G t opportunitie al efficiency t e. Today's sy cally prepare s pare shipping ation bills befo aluate carrier s, and use co ties for system mprovements ts capability t ve and other h s in a comple Modules a modular sys performed by g and transpo radioactive a . Its modules shipment info eight bills, rate System Web Applic Carrier Eval Selection Automated

411

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

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

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

412

National Transportation Stakeholders Forum  

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

Transportation Stakeholders Forum Transportation Stakeholders Forum May 14-16, 2013 Tuesday, May 14 7:00 am - 5:00 pm Registration Niagara Foyer 7:00 am - 7:45 am Breakfast and Networking Grand A 8:00 am - 10:00 am National Updates for Transportation Stakeholder Groups and Guests - Panel Grand BC Moderator: John Giarrusso Jr., MA Emergency Management Agency / Northeast High-Level Radioactive Waste Transportation Task Force Co-Chair US Department of Energy, Office of Environmental Management - Steve O'Connor, Director, Office of Packaging & Transportation US Nuclear Regulatory Commission - Earl P. Easton, Senior Level Advisor (retired) and David W. Pstrak, Transportation and Storage Specialist, Division of Spent Fuel Storage and Transportation

413

Packaging and Transportation Safety  

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

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

1996-10-02T23:59:59.000Z

414

Packaging and Transportation Safety  

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

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

1995-09-27T23:59:59.000Z

415

Radioactive Waste Management Manual  

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

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

1999-07-09T23:59:59.000Z

416

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

417

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...

418

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

419

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

420

Transportation | ornl.gov  

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

Transportation Transportation Power Electronics and Electric Machinery Fuels, Engines, Emissions Transportation Analysis Vehicle Systems Energy Storage Propulsion Materials Lightweight Materials Bioenergy Fuel Cell Technologies Clean Energy Home | Science & Discovery | Clean Energy | Research Areas | Transportation SHARE Transportation Research ORNL researcher Jim Szybist uses a variable valve-train engine to evaluate different types of fuels, including ethanol blends, and their effects on the combustion process in an internal combustion engine. Oak Ridge National Laboratory brings together science and technology experts from across scientific disciplines to partner with government and industry in addressing transportation challenges. Research objectives are

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


421

Radioactive Waste Management Manual  

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

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

1999-07-09T23:59:59.000Z

422

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

423

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

424

Materials - Home  

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

* Coatings & Lubricants * Coatings & Lubricants * Nanofluids * Deformation Joining * Recycling * Catalysts * Assessment * Illinois Center for Advanced Tribology Modeling, Simulation & Software Plug-In Hybrid Electric Vehicles PSAT Smart Grid Student Competitions Technology Analysis Transportation Research and Analysis Computing Center Working With Argonne Contact TTRDC Materials ring on liner reciprocating tester Tribology Lab: Ring-on-liner reciprocating tester. Argonne National Laboratory plays an important role in the Department of Energy's (DOE's) efforts to develop advanced materials for transportation. The materials are developed with DOE support from the EERE Office of Vehicle Technology and Office of Hydrogen, Fuel Cells, and Infrastructure Technologies in collaboration with worldwide industrial partners. Examples

425

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

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

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

426

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

427

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

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

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

428

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

Broader source: Energy.gov [DOE]

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

429

Transportation Baseline Schedule  

SciTech Connect (OSTI)

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

Fawcett, Ricky Lee; John, Mark Earl

2000-01-01T23:59:59.000Z

430

Radioactivity in food crops  

SciTech Connect (OSTI)

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

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

1983-05-01T23:59:59.000Z

431

An overview of the Radioisotope Thermoelectric Generator Transportation System Program  

SciTech Connect (OSTI)

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

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

1996-03-01T23:59:59.000Z

432

Quality assurance in the transport of UF{sub 6}  

SciTech Connect (OSTI)

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

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

1991-12-31T23:59:59.000Z

433

Radioactive Waste Management Manual  

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

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

1999-07-09T23:59:59.000Z

434

Security for Radioactive Sources: Fact Sheet | National Nuclear Security  

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

435

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

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

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

436

Yucca MountainTransportation: Private Sector Perspective  

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

Transportation: Transportation: Private Sector "Lessons Learned" US Transport Council David Blee Executive Director dblee@ustransportcouncil.org DOE Transportation External Coordination (TEC) Working Group April 4, 2005 Phoenix, Arizona US Transport Council -- DOE TEC 4/4/05 2 US Transport Council Formed in 2002 during the Yucca Mountain Ratification debate to provide factual information on nuclear materials transportation, experience, safety & emergency planning Comprised of 24 member companies from the transport sector including suppliers and customers Principal focus is transport education, policy and business commerce related to nuclear materials transport US Transport Council -- DOE TEC 4/4/05 3 USTC Members AREVA BNFL, Inc Burns & Roe Cameco

437

Management of Transuranic Contaminated Material  

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

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

1982-09-30T23:59:59.000Z

438

Sealed Radioactive Source Accountability  

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

This Notice extends DOE N 5400.9, Sealed Radioactive Source Accountability, of 12-24-91, until 12-24-95, unless sooner superseded or rescinded. The contents of DOE N 5400.9 will be updated and incorporated in the revised DOE O 5480.11, Radiation Protection for Occupational Workers.

1994-12-22T23:59:59.000Z

439

Sealed Radioactive Source Accountability  

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

To establish Department of Energy (DOE) interim policy and to provide guidance for sealed radioactive source accountability. The directive does not cancel any directives. Extended by DOE N 5400.10 to 12-24-93 & Extended by DOE N 5400.12 to 12-24-94.

1991-12-24T23:59:59.000Z

440

Vacuuming radioactive sludge  

SciTech Connect (OSTI)

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

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


441

Radioactive Waste Management  

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

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

1999-07-09T23:59:59.000Z

442

MATERIALS PERFORMANCE TARGETED THRUST FY 2004 PROJECTS  

SciTech Connect (OSTI)

The Yucca Mountain site was recommended by the President to be a geological repository for commercial spent nuclear fuel and high-level radioactive waste. The multi-barrier approach was adopted for assessing and predicting system behavior, including both natural barriers and engineered barriers. A major component of the long-term strategy for safe disposal of nuclear waste is first to completely isolate the radionuclides in waste packages for long times and then to greatly retard the egress and transport of radionuclides from penetrated packages. The goal of the Materials Performance Targeted Thrust program is to further enhance the understanding of the role of engineered barriers in waste isolation. In addition, the Thrust will explore technical enhancements and seek to offer improvements in materials costs and reliability.

DOE

2005-09-13T23:59:59.000Z

443

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

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

444

Fuel Cycle Technologies Near Term Planning for Storage and Transportation of Used Nuclear Fuel  

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

of Section 180(c) of the Nuclear of Section 180(c) of the Nuclear Waste Policy Act, as amended National Transportation Stakeholder's Forum Buffalo, NY May 15, 2013 Section 180(c) Mandate "The Secretary shall provide technical assistance and funds to States for training for public safety officials of appropriate units of local government and Indian tribes through whose jurisdiction the Secretary plans to transport spent nuclear fuel or high-level radioactive waste [to an NWPA-authorized facility]. * The training shall cover procedures for safe routine transportation of these materials and procedures for dealing with emergency response situations. * Covers all modes of transport 2 Section 180(c) - Background  DOE nearly implemented Section 180(c) in the mid-

445

Materials | Argonne National Laboratory  

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

today New high-tech materials are the key to breakthroughs in biology, the environment, nuclear energy, transportation and national security. Argonne continues to make...

446

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal  

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

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

447

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal  

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

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

448

Migration of Radioactive Wastes: Radionuclide Mobilization by Complexing Agents  

Science Journals Connector (OSTI)

...the Hanford, West Valley, and Maxey Flats facilities, respectively (29-31...Chalk River, West Valley, and Maxey Flats (31, 32). The use of EDTA and...transport at many radio-active waste disposal sites in this coun-try, and migration...

JEFFREY L. MEANS; DAVID A. CRERAR; JAMES O. DUGUID

1978-06-30T23:59:59.000Z

449

Assessment of radioactive wastes from a DCLL fusion reactor: Disposal in El Cabril facility  

Science Journals Connector (OSTI)

Abstract Under the Spanish Breeding Blanket Technology Programme TECNO_FUS a conceptual design of a DCLL (Dual-Coolant LithiumLead) blanket-based reactor is being revised. The dually cooled breeding zone is composed of He/LiPb and SiC as material of the liquid metal flow channel inserts. Structural materials are ferritic-martensitic steel (Eurofer) for the blanket and austenitic steel (SS316LN) for the vacuum vessel (VV) and the cryostat. In this work, radioactive wastes are assessed in order to determine if they can be disposed as low and intermediate level radioactive waste (LILW) in the Spanish near surface disposal facility of El Cabril. Also, unconditional clearance and recycling waste management options are studied. The neutron transport calculations have been performed with MCNPX code, while the ACAB code is used for calculations of the inventory of activation products and for activation analysis, in terms of waste management ratings for the options considered. Results show that the total amount of the cryostat can be disposed in El Cabril joined to the outer layer of both VV and channel inserts, whereas only concrete-made biological shield can be managed through clearance and none of the steels can be recycled. Those results are compared with those corresponding to French regulation, showing similar conclusions.

Raquel Garca; Juan Pablo Cataln; Javier Sanz

2014-01-01T23:59:59.000Z

450

Evaluation of Type B shipping packages used to transport potentially flammable gas mixtures  

SciTech Connect (OSTI)

Using Type B shipping packages to transport radioactive materials within a potentially flammable gas mixture is a bold proposal. The Nuclear Regulatory Commission (NRC) has essentially prohibited such shipments. Furthermore, the NRC requires extensive modeling and/or testing of selective contents (e.g., Transuranic Waste) which are prone to generate hydrogen gas to demonstrate that, in general, a flammable mixture inside the containment vessel will not occur during shipment. Contrary to the NRC position, this paper proposes a rigorous containment vessel evaluation methodology to justify shipment of Type B quantities of radioactive materials in the presence of potentially flammable gas mixtures. The Department of Energy (DOE) is currently reviewing the methodology as applied to the 9975 package for shipment of plutonium oxide which may generate significant quantities of hydrogen gas.

Hensel, S.J.

2000-04-26T23:59:59.000Z

451

Finding Aids: Radioactive Fallout  

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

452

Final Programmatic Environmental Assessment and Finding of No Significant Impact for the U.S. Department of Energy, Oak Ridge Operations Implementation of a Comprehensive Management Program for the Storage, Transportation, and Disposition of Potentially Reusable Uranium Materials  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) proposes to implement a comprehensive management program to safely, efficiently, and effectively manage its potentially reusable low enriched uranium (LEU), normal uranium (NU), and depleted uranium (DU). Uranium materials, which are presently located at multiple sites, are to be consolidated by transporting the materials to one or several storage locations, to facilitate ultimate disposition. Management would include the storage, transport, and ultimate disposition of these materials. This action is needed because of DOE's current missions and functions; increasing budget pressures; the continuing need for good stewardship of resources, including materials in inventory; and continuing DOE attention to considerations of environment, safety, and health. Also, increased pressure on the federal budget requires that DOE take a closer look at materials management in