National Library of Energy BETA

Sample records for radioactive source recovery

  1. Environmental Assessment Radioactive Source Recovery Program

    SciTech Connect (OSTI)

    1995-12-20

    In a response to potential risks to public health and safety, the U.S. Department of Energy (DOE) is evaluating the recovery of sealed neutron sources under the Radioactive Source Recovery Program (RSRP). This proposed program would enhance the DOE`s and the U.S. Nuclear Regulatory Commission`s (NRC`s) joint capabilities in the safe management of commercially held radioactive source materials. Currently there are no federal or commercial options for the recovery, storage, or disposal of sealed neutron sources. This Environmental Assessment (EA) analyzes the potential environmental impacts that would be expected to occur if the DOE were to implement a program for the receipt and recovery at the Los Alamos National Laboratory (LANL), Los Alamos, New Mexico, of unwanted and excess plutonium-beryllium ({sup 238}Pu-Be) and americium-beryllium ({sup 241}Am-Be) sealed neutron sources. About 1 kg (2.2 lb) plutonium and 3 kg (6.6 lb) americium would be recovered over a 15-year project. Personnel at LANL would receive neutron sources from companies, universities, source brokers, and government agencies across the country. These neutron sources would be temporarily stored in floor holes at the CMR Hot Cell Facility. Recovery reduces the neutron emissions from the source material and refers to a process by which: (1) the stainless steel cladding is removed from the neutron source material, (2) the mixture of the radioactive material (Pu-238 or Am-241) and beryllium that constitutes the neutron source material is chemically separated (recovered), and (3) the recovered Pu-238 or Am-241 is converted to an oxide form ({sup 238}PuO{sub 2} or {sup 241}AmO{sub 2}). The proposed action would include placing the {sup 238}PuO{sub 2} or {sup 241}AmO{sub 2} in interim storage in a special nuclear material vault at the LANL Plutonium Facility.

  2. Dynamic radioactive particle source

    DOE Patents [OSTI]

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

    2012-06-26

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

  3. Sealed Radioactive Source Accountability

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

    1991-12-24

    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.

  4. Sealed Radioactive Source Accountability

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

    1994-12-22

    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.

  5. Reporting of Radioactive Sealed Sources

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

    2008-02-27

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

  6. 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...

  7. Offsite source recovery project - ten years of sealed source recovery and disposal

    SciTech Connect (OSTI)

    Whitworth, Julia Rose [Los Alamos National Laboratory; Pearson, Mike [Los Alamos National Laboratory; Witkowski, Ioana [Los Alamos National Laboratory; Wald - Hopkins, Mark [Los Alamos National Laboratory; Cuthbertson, A [NNSA

    2010-01-01

    The Global Threat Reduction Initiative's (GTRI) Offsite Source Recovery Project (OSRP) has been recovering excess and unwanted radioactive sealed sources for ten years. In January 2009, GTRI announced that the project had recovered 20,000 sealed radioactive sources (this number has since increased to more than 23,000). This project grew out of early efforts at Los Alamos National Laboratory (LANL) to recover and disposition excess Plutonium-239 (Pu-239) sealed sources that were distributed in the 1960s and 1970s under the Atoms for Peace Program. Decades later, these sources began to exceed their special form certifications or fall out of regular use. As OSRP has collected and stored sealed sources, initially using 'No Path Forward' waste exemptions for storage within the Department of Energy (DOE) complex, it has consistently worked to create disposal pathways for the material it has recovered. The project was initially restricted to recovering sealed sources that would meet the definition of Greater-than-Class-C (GTCC) low-level radioactive waste, assisting DOE in meeting its obligations under the Low-level Radioactive Waste Policy Act Amendments (PL 99-240) to provide disposal for this type of waste. After being transferred from DOE-Environmental Management (EM) to the U.S. National Nuclear Security Administration (NNSA) to be part of GTRI, OSRP's mission was expanded to include not only material that would be classified as GTCC when it became waste, but also any other materials that might constitute a 'national security consideration.' It was recognized at the time that the GTCC category was a waste designation having to do with environmental consequence, rather than the threat posed by deliberate or accidental misuse. The project faces barriers to recovery in many areas, but disposal continues to be one of the more difficult to overcome. This paper discusses OSRP's disposal efforts over its 10-year history. For sources meeting the DOE definition of 'transuranic,' OSRP has achieved many milestones, including defense determinations for various isotopes, a WIPP RCRA permit modification to accommodate headspace gas sampling requirements, and approval of a peer-reviewed non-assay radiological characterization methodology. For non-transuranic sources, which OSRP began to recover in 2004, OSRP has achieved NEP A coverage for storage and implemented consolidated storage at both DOE and commercial locations, as well as completing several specific disposal operations. The closure of the Barnwell low-level waste disposal site in 2008 has left 36 states with absolutely no commercial disposal pathway for most sealed sources, increasing the demands on OSRP. This and other current challenges and future work will also be discussed.

  8. Particle beam generator using a radioactive source

    DOE Patents [OSTI]

    Underwood, David G. (Naperville, IL)

    1993-01-01

    The apparatus of the present invention selects from particles emitted by a radioactive source those particles having momentum within a desired range and focuses the selected particles in a beam having at least one narrow cross-dimension, and at the same time attenuates potentially disruptive gamma rays and low energy particles. Two major components of the present invention are an achromatic bending and focusing system, which includes sector magnets and quadrupole, and a quadrupole doublet final focus system. Permanent magnets utilized in the apparatus are constructed of a ceramic (ferrite) material which is inexpensive and easily machined.

  9. Sealed Radioactive Source Accountability and Control Guide

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

    1999-04-15

    For use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection. This Guide provides an acceptable methodology for establishing and operating a sealed radioactive source accountability and control program that will comply with U.S. Department of Energy (DOE) requirements specified in Title 10 of the Code of Federal Regulations (CFR), Part 835, Occupational Radiation Protection (DOE 1998a), hereinafter referred to as 10 CFR 835. In particular, this Guide provides guidance for achieving compliance with subpart M of 10 CFR 835. Canceled by DOE G 441.1-1B.

  10. Particle beam generator using a radioactive source

    DOE Patents [OSTI]

    Underwood, D.G.

    1993-03-30

    The apparatus of the present invention selects from particles emitted by a radioactive source those particles having momentum within a desired range and focuses the selected particles in a beam having at least one narrow cross-dimension, and at the same time attenuates potentially disruptive gamma rays and low energy particles. Two major components of the present invention are an achromatic bending and focusing system, which includes sector magnets and quadrupole, and a quadrupole doublet final focus system. Permanent magnets utilized in the apparatus are constructed of a ceramic (ferrite) material which is inexpensive and easily machined.

  11. 10 years and 20,000 sources: the offsite source recovery project

    SciTech Connect (OSTI)

    Whitworth, Julia R; Abeyta, Cristy L; Pearson, Michael W

    2009-01-01

    The Global Threat Reduction Initiative's (GTRI) Offsite Source Recovery Project (OSRP) has been recovering excess and unwanted sealed sources for ten years. In January 2009, GTRI announced that the project had recovered 20,000 sealed radioactive sources. This project grew out of early efforts at Los Alamos National Laboratory (LANL) to recover and disposition excess Plutonium-239 (Pu-239) sealed sources that were distributed in the 1960s and 1970s under the Atoms for Peace Program. Sealed source recovery was initially considered a waste management activity, as evidenced by its initial organization under the Department of Energy's (DOE's) Environmental Management (EM) program. After the terrorist attacks of 2001, however, the interagency community began to recognize the threat posed by excess and unwanted radiological material, particularly those that could not be disposed at the end of their useful life. After being transferred to the National Nuclear Security Administration (NNSA) to be part of GTRI, OSRP's mission was expanded to include not only material that would be classified as Greater-than-Class-C (GTCC) when it became waste, but also any other materials that might be a 'national security consideration.' This paper discusses OSRP's history, recovery operations, expansion to accept high-activity beta-gamma-emitting sealed sources and devices and foreign-possessed sources, and more recent efforts such as cooperative projects with the Council on Radiation Control Program Directors (CRCPD) and involvement in GTRI's Search and Secure project. Current challenges and future work will also be discussed.

  12. Management of Disused Radioactive Sealed Sources in Egypt - 13512

    SciTech Connect (OSTI)

    Mohamed, Y.T.; Hasan, M.A.; Lasheen, Y.F.

    2013-07-01

    The future safe development of nuclear energy and progressive increasing use of sealed sources in medicine, research, industry and other fields in Egypt depends on the safe and secure management of disused radioactive sealed sources. In the past years have determined the necessity to formulate and apply the integrated management program for radioactive sealed sources to assure harmless and ecological rational management of disused sealed sources in Egypt. The waste management system in Egypt comprises operational and regulatory capabilities. Both of these activities are performed under legislations. The Hot Laboratories and Waste Management Center HLWMC, is considered as a centralized radioactive waste management facility in Egypt by law 7/2010. (authors)

  13. Offsite Source Recovery Program (OSRP) Workshop Module: Tianjin, China, July 16-July 17, 2012

    SciTech Connect (OSTI)

    Houlton, Robert J. [Los Alamos National Laboratory

    2012-07-11

    Recovering and disposal of radioactive sources that are no longer in service in their intended capacity is an area of high concern Globally. A joint effort to recover and dispose of such sources was formed between the US Department of Energy and the Chinese Ministry of Environmental Protection (MEP), in preparation for the 2008 Beijing Olympics. LANL involvement in this agreement continues today under the DOE-Global Threat Reduction Initiative (GTRI) program. LANL will be presenting overview information on their Offsite Source Recovery (OSRP) and Source Disposal programs, in a workshop for the Ministry of Environmental Protection (MEP) at Tianjin, China, on July 16 and 17, 2012.

  14. Integrated Management Program for Radioactive Sealed Sources in EgyptIMPRSS

    SciTech Connect (OSTI)

    Hasan, A.; El-Adham, K.

    2004-10-03

    This presentation discusses the Integrated Management Program for Radioactive Realed Sources (IMPRSS) in Egypt.

  15. Method for fabricating thin californium-containing radioactive source wires

    DOE Patents [OSTI]

    Gross, Ian G; Pierce, Larry A

    2006-08-22

    A method for reducing the cross-sectional diameter of a radioactive californium-containing cermet wire while simultaneously improving the wire diameter to a more nearly circular cross section. A collet fixture is used to reduce the wire diameter by controlled pressurization pulses while simultaneously improving the wire cross-sectional diameter. The method is especially suitable for use in hot cells for the production of optimized cermet brachytherapy sources that contain large amounts of radioactive californium-252.

  16. Registration for the Hanford Site: Sources of radioactive emissions

    SciTech Connect (OSTI)

    Silvia, M.J.

    1993-04-01

    This Registration Application serves to renew the registration for all Hanford Site sources of radioactive air emissions routinely reported to the State of Washington Department of Health (DOH). The current registration expires on August 15, 1993. The Application is submitted pursuant to the Washington Administrative Code (WAC) Chapter 246--247, and is consistent with guidance provided by DOH for renewal. The Application subdivides the Hanford Site into six major production, processing or research areas. Those six areas are in the 100 Area, 200 East Area, 200 West Area, 300 Area, 400 Area, and 600 Area. Each major group of point sources within the six areas listed above is represented by a Source Registration for Radioactive Air Emissions form. Annual emissions. for the sources are listed in the ``Radionuclide Air Emissions Report for the Hanford Site,`` published annually. It is a requirement that the following Statement of Compliance be provided: ``The radioactive air emissions from the above sources do meet the emissions standards contained in Chapter 173-480-040 WAC, Ambient Air Quality Standards and Emissions Limits for Radionuclides. As the Statement of Compliance pertains to this submittal, the phrase ``above sources`` is to be understood as meaning the combined air emissions from all sources registered by this submittal.

  17. Recovery of {sup 241}Am/Be neutron sources, Wooster, Ohio

    SciTech Connect (OSTI)

    Tompkins, J.A.; Wannigman, D.; Hatler, V.

    1998-07-01

    In August 1997, the Nuclear Regulatory Commission (NRC) submitted to the US Department of Energy (DOE) a partial list of licensed radioactive sealed sources to be recovered under a pilot project initiating Radioactive Source Recovery Program (RSRP) operations. The first of the pilot project recoveries was scheduled for September 1997 at Eastern Well Surveys in Wooster, Ohio, a company with five unwanted sealed sources on the NRC list. The sources were neutron emitters, each containing {sup 241}Am/Be with activities ranging from 2.49 to 3.0 Ci. A prior radiological survey had established that one of these sources, a Gulf Nuclear Model 71-1 containing 3 Ci of {sup 241}Am, was contaminated with {sup 241}Am and might be leaking. The other four sources were obsolete and could no longer be used by Eastern Well Surveys for their intended application in well-logging applications due to NRC decertification of these sources. All of the sources exceeded the limits established for Class C waste under 10 CFR 61.55 and, as a result, are the ultimate responsibility of the DOE under the provisions of PL 99-240. This report describes the cooperative effort between the DOE and NRC to recover the sources and transport them to Los Alamos National Laboratory (LANL) for deactivation under the RSRP. This operation alleviated any potential risk to the public health and safety from the site which might result from the leaking neutron sources or the potential mismanagement of unwanted sources. The on-site recovery occurred on September 23, 1997, and was performed by personnel from LANL and its contractor and was observed by staff from the Region III office of the NRC. All aspects of the recovery were successfully accomplished, and the sources were received at LANL on September 29, 1997. Experience gained during this operation will be used to formulate operational poilicies and procedures which will contribute to the eventual routine recovery operations of a full-scale RSRP.

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

    E-Print Network [OSTI]

    , insufficient accountability, and improper disposal of radioactive materials. The US Environmental Protection end up in municipal waste disposal facilities. Scrap metal handlers and some landfill operators have1 The New Orphaned Radioactive Sources Program in the United States International Conference

  19. Cable attachment for a radioactive brachytherapy source capsule

    DOE Patents [OSTI]

    Gross, Ian G; Pierce, Larry A

    2006-07-18

    In cancer brachytherapy treatment, a small californium-252 neutron source capsule is attached to a guide cable using a modified crimping technique. The guide cable has a solid cylindrical end, and the attachment employs circumferential grooves micromachined in the solid cable end. The attachment was designed and tested, and hardware fabricated for use inside a radioactive hot cell. A welding step typically required in other cable attachments is avoided.

  20. 2011 Radioactive Materials Usage Survey for Unmonitored Point Sources

    SciTech Connect (OSTI)

    Sturgeon, Richard W.

    2012-06-27

    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.

  1. EA-1059: Radioactive Source Recovery Program, Los Alamos, New Mexico

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to establish a program to accept and recover surplus americium-241 mixed with beryllium metal (Be) and plutonium-238 mixed with Be sealed...

  2. MARSAME Appendix B B. SOURCES OF BACKGROUND RADIOACTIVITY

    E-Print Network [OSTI]

    : ∑ The Nuclear Regulatory Commission (NRC) provides information concerning background radioactivity in Background

  3. Follow-up on the Management of Plutonium-239 Sealed Sources Recovery...

    Office of Environmental Management (EM)

    on the Management of Plutonium-239 Sealed Sources Recovery Activities, OAS-M-06-09 Follow-up on the Management of Plutonium-239 Sealed Sources Recovery Activities, OAS-M-06-09 The...

  4. Automated management of radioactive sources in Saudi Arabia

    SciTech Connect (OSTI)

    Al-Kheliewi, Abdullah S.; Jamil, M. F.; Basar, M. R.; Tuwaili, W. R.

    2014-09-30

    For usage of radioactive substances, any facility has to register and take license from relevant authority of the country in which such facility is operating. In the Kingdom of Saudi Arabia (KSA), the authority for managing radioactive sources and providing licenses to organizations for its usage is the National Center of Radiation Protection (NCRP). This paper describes the system that automates registration and licensing process of the National Center of Radiation Protection. To provide 24◊7 accesses to all the customers of NCRP, system is developed as web-based application that provide facility to online register, request license, renew license, check request status, view historical data and reports etc. and other features are provided as Electronic Services that would be accessible to users via internet. The system also was designed to streamline and optimize internal operations of NCRP besides providing ease of access to its customers by implementing a defined workflow through which every registration and license request will be routed. In addition to manual payment option, the system would also be integrated with SADAD (online payment system) that will avoid lengthy and cumbersome procedures associated with manual payment mechanism. Using SADAD payment option license fee could be paid through internet/ATM machine or branch of any designated bank, Payment will be instantly notified to NCRP hence delay in funds transfer and verification of invoice could be avoided, SADAD integration is discussed later in the document.

  5. The Global Threat Reduction Initiative's Orphan Source Recovery Project in the Russian Federation

    SciTech Connect (OSTI)

    Russell, J. W. [NSTec; Ahumada, A. D. [NSTec; Blanchard, T. A. [NNSA

    2012-06-04

    After 9/11, officials at the United States Department of Energy (DOE), National Nuclear Security Administration (NNSA) grew more concerned about radiological materials that were vulnerable to theft and illicit use around the world. The concern was that terrorists could combine stolen radiological materials with explosives to build and detonate a radiological dispersal device (RDD), more commonly known as a ďdirty bomb.Ē In response to this and other terrorist threats, the DOE/NNSA formed what is now known as the Global Threat Reduction Initiative (GTRI) to consolidate and accelerate efforts to reduce and protect vulnerable nuclear and radiological materials located at civilian sites worldwide. Although a cooperative program was already underway in the Russian Federation to secure nuclear materials at a range of different facilities, thousands of sealed radioactive sources remained vulnerable at medical, research, and industrial sites. In response, GTRI began to focus efforts on addressing these materials. GTRIís Russia Orphan Source Recovery Project, managed at the Nevada National Security Siteís North Las Vegas facility, was initiated in 2002. Throughout the life of the project, Joint Stock Company ďIsotopeĒ has served as the primary Russian subcontractor, and the organization has proven to be a successful partner. Since the first orphan source recovery of an industrial cobalt-60 irradiator with 647 curies (Ci) at an abandoned facility in Moscow in 2003, the GTRI Orphan Source Recovery Project in the Russian Federation has accomplished substantial levels of threat reduction. To date, GTRI has recovered and securely disposed of more than 5,100 sources totaling more that 628,000 Ci. This project serves as an extraordinary example of how international cooperation can be implemented by partners with mutual interests to achieve significant goals.

  6. Electron energy recovery system for negative ion sources

    DOE Patents [OSTI]

    Dagenhart, William K. (Oak Ridge, TN); Stirling, William L. (Oak Ridge, TN)

    1982-01-01

    An electron energy recovery system for negative ion sources is provided. The system, employs crossed electric and magnetic fields to separate the electrons from ions as they are extracted from a negative ion source plasma generator and before the ions are accelerated to their full kinetic energy. With the electric and magnetic fields oriented 90.degree. to each other, the electrons are separated from the plasma and remain at approximately the electrical potential of the generator in which they were generated. The electrons migrate from the ion beam path in a precessing motion out of the ion accelerating field region into an electron recovery region provided by a specially designed electron collector electrode. The electron collector electrode is uniformly spaced from a surface of the ion generator which is transverse to the direction of migration of the electrons and the two surfaces are contoured in a matching relationship which departs from a planar configuration to provide an electric field component in the recovery region which is parallel to the magnetic field thereby forcing the electrons to be directed into and collected by the electron collector electrode. The collector electrode is maintained at a potential slightly positive with respect to the ion generator so that the electrons are collected at a small fraction of the full accelerating supply voltage energy.

  7. Demonstration and development of control mechanism for radioactive sources in Saudi Arabia

    SciTech Connect (OSTI)

    Al-Kheliewi, A. S. [National Center for Radiation Protection King Abdulaziz City for Science and Technology, P.O. Box 6086, Riyadh 11442 (Saudi Arabia)

    2012-06-06

    Saudi Arabia have no nuclear industry. Nevertheless, many radioactive sources, for different purposes, have been used in the country. There is upswing in the number of companies that recruit nuclear technology in their daily work. The National Center for Radiation Protection (NCRP) takes the full commitment and responsibility for monitoring and regulating the movement of radioactive sources in the country. NCRP issues the licenses for import, export, and use of radioactive sources. It, also, protects the country from any trespassing radiation through a sizable net of early warning and radiation monitoring stations along the borders of Saudi Arabia. This paper talks about the procedures of licensing, importing, exporting of radioactive sources. It, also, sheds light on types of implementing radioactive sources in different practices encompass medicine, industry, research. The NCRP has established an electronic web site to ease the communication with all users in the country. This site is yet in the experimental stage.

  8. Safety considerations in the disposal of disused sealed radioactive sources in borehole facilities

    E-Print Network [OSTI]

    International Atomic Energ Agency. Vienna

    2003-01-01

    Sealed radioactive sources are used in medicine, industry and research for a wide range of purposes. They can contain different radionuclides in greatly varying amounts. At the end of their useful lives, they are termed 'disused sources' but their activity levels can still be quite high. They are, for all practical purposes, another type of radioactive waste that needs to be disposed of safely. Disused sealed radioactive sources can represent a significant hazard to people if not managed properly. Many countries have no special facilities for the management or disposal of radioactive waste, as they have no nuclear power programmes requiring such facilities. Even in countries with developed nuclear programmes, disused sealed sources present problems as they often fall outside the common categories of radioactive waste for which disposal options have been identified. As a result, many disused sealed sources are kept in storage. Depending on the nature of the storage arrangements, this situation may represent a ...

  9. Safety and Security of Radioactive Sealed and Disused/Orphan Sources in Ukraine - German Contribution - 13359

    SciTech Connect (OSTI)

    Brasser, Thomas; Hertes, Uwe; Meyer, Thorsten; Uhlenbruck, Hermann; Shevtsov, Alexey

    2013-07-01

    Within the scope of 'Nuclear Security of Radioactive Sources', the German government implemented the modernization of Ukrainian State Production Company's transport and storage facility for radioactive sources (TSF) in Kiev. The overall management of optimizing the physical protection of the storage facility (including the construction of a hot cell for handling the radioactive sources) is currently carried out by the German Federal Foreign Office (AA). AA jointly have assigned Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Germany's leading expert institution in the area of nuclear safety and waste management, to implement the project and to ensure transparency by financial and technical monitoring. Sealed radioactive sources are widely used in industry, medicine and research. Their life cycle starts with the production and finally ends with the interim/long-term storage of the disused sources. In Ukraine, IZOTOP is responsible for all radioactive sources throughout their life cycle. IZOTOP's transport and storage facility (TSF) is the only Ukrainian storage facility for factory-fresh radioactive sources up to an activity of about 1 million Ci (3.7 1016 Bq). The TSF is specially designed for the storage and handling of radioactive sources. Storage began in 1968, and is licensed by the Ukrainian state authorities. Beside the outdated state of TSF's physical protection and the vulnerability of the facility linked with it, the lack of a hot cell for handling and repacking radioactive sources on the site itself represents an additional potential hazard. The project, financed by the German Federal Foreign Office, aims to significantly improve the security of radioactive sources during their storage and handling at the TSF site. Main tasks of the project are a) the modernization of the physical protection of the TSF itself in order to prevent any unauthorized access to radioactive sources as well as b) the construction of a hot cell to reduce the number of transports of radioactive sources within the city of Kiev. In future, the new established hot cell at IZOTOP's transport and storage facility will be useful for identification and characterization of orphan/disused radioactive sources. The projects implemented are performed in accordance with international recommendations (e. g. IAEA) and national normative documents and will make a crucial contribution towards an improved safety and security management of radioactive sources in Ukraine. (authors)

  10. Import and Export of Category 1 and 2 Radioactive Sources and Aggregated Quantities

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

    2008-11-10

    This Order has been developed to provide requirements and responsibilities pertaining to the International Atomic Energy Agency CODEOC/2004, Code of Conduct on the Safety and Security of Radioactive Sources. No cancellation. Admin Chg 1, 7-10-13.

  11. Import and Export of Category 1 and 2 Radioactive Sources Aggregated Quantities

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

    2008-11-10

    To formalize relevant guidance contained in the International Atomic Energy Agency (IAEA) CODEOC 2004, Code of Conduct on the Safety and Security of Radioactive Sources, January 2004 and IAEA CODEOC IMP-EXP 2005, Guidance on the Import and Export of Radioactive Sources, March 2005 and to assign responsibilities and prescribe procedures for DOE elements and contractors in support of the Import-Export Guidance. Admin Chg 1, 7-10-2013 supersedes DOE O 462.1. Certified 12-3-14.

  12. Disused Radioactive Sources Secured in Georgia | National Nuclear...

    National Nuclear Security Administration (NNSA)

    disused high activity sources from the Institute of Radiobiology to a more secure storage facility. As part of NNSA's broader cooperative effort to help prevent nuclear and...

  13. Development of Approach for Long-Term Management of Disused Sealed Radioactive Sources - 13630

    SciTech Connect (OSTI)

    Kinker, M.; Reber, E.; Mansoux, H.; Bruno, G. [International Atomic Energy Agency, PO Box 100, 1400 Vienna (Austria)] [International Atomic Energy Agency, PO Box 100, 1400 Vienna (Austria)

    2013-07-01

    Radioactive sources are used widely throughout the world in a variety of medical, industrial, research and military applications. When such radioactive sources are no longer used and are not intended to be used for the practice for which an authorization was granted, they are designated as 'disused sources'. Whether appropriate controls are in place during the useful life of a source or not, the end of this useful life is often a turning point after which it is more difficult to ensure the safety and security of the source over time. For various reasons, many disused sources cannot be returned to the manufacturer or the supplier for reuse or recycling. When these attempts fail, disused sources should be declared as radioactive waste and should be managed as such, in compliance with relevant international legal instruments and safety standards. However, disposal remains an unresolved issue in many counties, due to in part to limited public acceptance, insufficient funding, and a lack of practical examples of strategies for determining suitable disposal options. As a result, disused sources are often stored indefinitely at the facilities where they were once used. In order to prevent disused sources from becoming orphan sources, each country must develop and implement a comprehensive waste management strategy that includes disposal of disused sources. The International Atomic Energy Agency (IAEA) fosters international cooperation between countries and encourages the development of a harmonized 'cradle to grave' approach to managing sources consistent with international legal instruments, IAEA safety standards, and international good practices. This 'cradle to grave' approach requires the development of a national policy and implementing strategy, an adequate legal and regulatory framework, and adequate resources and infrastructure that cover the entire life cycle, from production and use of radioactive sources to disposal. (authors)

  14. The adequacy of current import and export controls on sealed radioactive sources.

    SciTech Connect (OSTI)

    Longley, Susan W.; Cochran, John Russell; Price, Laura L.; Lipinski, Kendra J.

    2003-10-01

    Millions of sealed radioactive sources (SRSs) are being used for a wide variety of beneficial purposes throughout the world. Security experts are now concerned that these beneficial SRSs could be used in a radiological dispersion device to terrorize and disrupt society. The greatest safety and security threat is from those highly radioactive Category 1 and 2 SRSs. Without adequate controls, it may be relatively easy to legally purchase a Category 1 or 2 SRS on the international market under false pretenses. Additionally, during transfer, SRSs are particularly susceptible to theft since the sources are in a shielded and mobile configuration, transportation routes are predictable, and shipments may not be adequately guarded. To determine if government controls on SRS are adequate, this study was commissioned to review the current SRS import and export controls of six countries. Canada, the Russian Federation, and South Africa were selected as the exporting countries, and Egypt, the Philippines, and the United States were selected as importing countries. A detailed review of the controls in each country is presented. The authors found that Canada and Russia are major exporters, and are exporting highly radioactive SRSs without first determining if the recipient is authorized by the receiving country to own and use the SRSs. Available evidence was used to estimate that on average there are tens to possibly hundreds of intercountry transfers of highly radioactive SRSs each day. Based on these and other findings, this reports recommends stronger controls on the export and import of highly radioactive SRSs.

  15. Method for the simultaneous recovery of radionuclides from liquid radioactive wastes using a solvent

    DOE Patents [OSTI]

    Romanovskiy, Valeriy Nicholiavich (St. Petersburg, RU); Smirnov, Igor V. (St. Petersburg, RU); Babain, Vasiliy A. (St. Petersburg, RU); Todd, Terry A. (Aberdeen, ID); Brewer, Ken N. (Arco, ID)

    2001-01-01

    The present invention relates to solvents, and methods, for selectively extracting and recovering radionuclides, especially cesium and strontium, rare earths and actinides from liquid radioactive wastes. More specifically, the invention relates to extracting agent solvent compositions comprising complex organoboron compounds, substituted polyethylene glycols, and neutral organophosphorus compounds in a diluent. The preferred solvent comprises a chlorinated cobalt dicarbollide, diphenyl-dibutylmethylenecarbamoylphosphine oxide, PEG-400, and a diluent of phenylpolyfluoroalkyl sulfone. The invention also provides a method of using the invention extracting agents to recover cesium, strontium, rare earths and actinides from liquid radioactive waste.

  16. Solvent for the simultaneous recovery of radionuclides from liquid radioactive wastes

    DOE Patents [OSTI]

    Romanovskiy, Valeriy Nicholiavich (St. Petersburg, RU); Smirnov, Igor V. (St. Petersburg, RU); Babain, Vasiliy A. (St. Petersburg, RU); Todd, Terry A. (Aberdeen, ID); Brewer, Ken N. (Arco, ID)

    2002-01-01

    The present invention relates to solvents, and methods, for selectively extracting and recovering radionuclides, especially cesium and strontium, rare earths and actinides from liquid radioactive wastes. More specifically, the invention relates to extracting agent solvent compositions comprising complex organoboron compounds, substituted polyethylene glycols, and neutral organophosphorus compounds in a diluent. The preferred solvent comprises a chlorinated cobalt dicarbollide, diphenyl-dibutylmethylenecarbamoylphosphine oxide, PEG-400, and a diluent of phenylpolyfluoroalkyl sulfone. The invention also provides a method of using the invention extracting agents to recover cesium, strontium, rare earths and actinides from liquid radioactive waste.

  17. German Support Program for Retrieval and Safe Storage of Disused Radioactive Sealed Sources in Ukraine - 13194

    SciTech Connect (OSTI)

    Pretzsch, Gunter; Salewski, Peter; Sogalla, Martin

    2013-07-01

    The German Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU) on behalf of the Government of the Federal Republic of Germany supports the State Nuclear Regulatory Inspectorate of Ukraine (SNRIU) in enhancement of nuclear safety and radiation protection and strengthening of the physical protection. One of the main objectives of the agreement concluded by these parties in 2008 was the retrieval and safe interim storage of disused orphan high radioactive sealed sources in Ukraine. At present, the Ukrainian National Registry does not account all high active radiation sources but only for about 70 - 80 %. GRS in charge of BMU to execute the program since 2008 concluded subcontracts with the waste management and interim storage facilities RADON at different regions in Ukraine as well with the waste management and interim storage facility IZOTOP at Kiev. Below selected examples of removal of high active Co-60 and Cs-137 sources from irradiation facilities at research institutes are described. By end of 2012 removal and safe interim storage of 12.000 disused radioactive sealed sources with a total activity of more than 5,7.10{sup 14} Bq was achieved within the frame of this program. The German support program will be continued up to the end of 2013 with the aim to remove and safely store almost all disused radioactive sealed sources in Ukraine. (authors)

  18. Methods for chemical recovery of non-carrier-added radioactive tin from irradiated intermetallic Ti-Sb targets

    DOE Patents [OSTI]

    Lapshina, Elena V. (Troitsk, RU); Zhuikov, Boris L. (Troitsk, RU); Srivastava, Suresh C. (Setauket, NY); Ermolaev, Stanislav V. (Obninsk, RU); Togaeva, Natalia R. (Obninsk, RU)

    2012-01-17

    The invention provides a method of chemical recovery of no-carrier-added radioactive tin (NCA radiotin) from intermetallide TiSb irradiated with accelerated charged particles. An irradiated sample of TiSb can be dissolved in acidic solutions. Antimony can be removed from the solution by extraction with dibutyl ether. Titanium in the form of peroxide can be separated from tin using chromatography on strong anion-exchange resin. In another embodiment NCA radiotin can be separated from iodide solution containing titanium by extraction with benzene, toluene or chloroform. NCA radiotin can be finally purified from the remaining antimony and other impurities using chromatography on silica gel. NCA tin-117m can be obtained from this process. NCA tin-117m can be used for labeling organic compounds and biological objects to be applied in medicine for imaging and therapy of various diseases.

  19. A compact ultra-clean system for deploying radioactive sources inside the KamLAND detector

    E-Print Network [OSTI]

    T. I. Banks; S. J. Freedman; J. Wallig; N. Ybarrolaza; A. Gando; Y. Gando; H. Ikeda; K. Inoue; Y. Kishimoto; M. Koga; T. Mitsui; K. Nakamura; I. Shimizu; J. Shirai; A. Suzuki; Y. Takemoto; K. Tamae; K. Ueshima; H. Watanabe; B. D. Xu; H. Yoshida; S. Yoshida; A. Kozlov; C. Grant; G. Keefer; A. Piepke; T. Bloxham; B. K. Fujikawa; K. Han; K. Ichimura; H. Murayama; T. O'Donnell; H. M. Steiner; L. A. Winslow; D. A. Dwyer; R. D. McKeown; C. Zhang; B. E. Berger; C. E. Lane; J. Maricic; T. Miletic; M. Batygov; J. G. Learned; S. Matsuno; M. Sakai; G. A. Horton-Smith; K. E. Downum; G. Gratta; Y. Efremenko; O. Perevozchikov; H. J. Karwowski; D. M. Markoff; W. Tornow; K. M. Heeger; J. A. Detwiler; S. Enomoto; M. P. Decowski

    2015-02-12

    We describe a compact, ultra-clean device used to deploy radioactive sources along the vertical axis of the KamLAND liquid-scintillator neutrino detector for purposes of calibration. The device worked by paying out and reeling in precise lengths of a hanging, small-gauge wire rope (cable); an assortment of interchangeable radioactive sources could be attached to a weight at the end of the cable. All components exposed to the radiopure liquid scintillator were made of chemically compatible UHV-cleaned materials, primarily stainless steel, in order to avoid contaminating or degrading the scintillator. To prevent radon intrusion, the apparatus was enclosed in a hermetically sealed housing inside a glove box, and both volumes were regularly flushed with purified nitrogen gas. An infrared camera attached to the side of the housing permitted real-time visual monitoring of the cable's motion, and the system was controlled via a graphical user interface.

  20. A Low-Tech, Low-Budget Storage Solution for High Level Radioactive Sources

    SciTech Connect (OSTI)

    Brett Carlsen; Ted Reed; Todd Johnson; John Weathersby; Joe Alexander; Dave Griffith; Douglas Hamelin

    2014-07-01

    The need for safe, secure, and economical storage of radioactive material becomes increasingly important as beneficial uses of radioactive material expand (increases inventory), as political instability rises (increases threat), and as final disposal and treatment facilities are delayed (increases inventory and storage duration). Several vendor-produced storage casks are available for this purpose but are often costly ó due to the required design, analyses, and licensing costs. Thus the relatively high costs of currently accepted storage solutions may inhibit substantial improvements in safety and security that might otherwise be achieved. This is particularly true in areas of the world where the economic and/or the regulatory infrastructure may not provide the means and/or the justification for such an expense. This paper considers a relatively low-cost, low-technology radioactive material storage solution. The basic concept consists of a simple shielded storage container that can be fabricated locally using a steel pipe and a corrugated steel culvert as forms enclosing a concrete annulus. Benefits of such a system include 1) a low-tech solution that utilizes materials and skills available virtually anywhere in the world, 2) a readily scalable design that easily adapts to specific needs such as the geometry and radioactivity of the source term material), 3) flexible placement allows for free-standing above-ground or in-ground (i.e., below grade or bermed) installation, 4) the ability for future relocation without direct handling of sources, and 5) a long operational lifetime . ĎLe mieux est líennemi du biení (translated: The best is the enemy of good) applies to the management of radioactive materials Ė particularly where the economic and/or regulatory justification for additional investment is lacking. Development of a low-cost alternative that considerably enhances safety and security may lead to a greater overall risk reduction than insisting on solutions that remain economically and/or politically Ďout of reachí.

  1. Radiological Threat Reduction (RTR) program : implementing physical security to protect large radioactive sources worldwide.

    SciTech Connect (OSTI)

    Lowe, Daniel L.

    2004-11-01

    The U.S. Department of Energy's Radiological Threat Reduction (RTR) Program strives to reduce the threat of a Radiological Dispersion Device (RDD) incident that could affect U.S. interests worldwide. Sandia National Laboratories supports the RTR program on many different levels. Sandia works directly with DOE to develop strategies, including the selection of countries to receive support and the identification of radioactive materials to be protected. Sandia also works with DOE in the development of guidelines and in training DOE project managers in physical protection principles. Other support to DOE includes performing rapid assessments and providing guidance for establishing foreign regulatory and knowledge infrastructure. Sandia works directly with foreign governments to establish cooperative agreements necessary to implement the RTR Program efforts to protect radioactive sources. Once necessary agreements are in place, Sandia works with in-country organizations to implement various security related initiatives, such as installing security systems and searching for (and securing) orphaned radioactive sources. The radioactive materials of interest to the RTR program include Cobalt 60, Cesium 137, Strontium 90, Iridium 192, Radium 226, Plutonium 238, Americium 241, Californium 252, and Others. Security systems are implemented using a standardized approach that provides consistency through out the RTR program efforts at Sandia. The approach incorporates a series of major tasks that overlap in order to provide continuity. The major task sequence is to: Establish in-country contacts - integrators, Obtain material characterizations, Perform site assessments and vulnerability assessments, Develop upgrade plans, Procure and install equipment, Conduct acceptance testing and performance testing, Develop procedures, and Conduct training. Other tasks are incorporated as appropriate and commonly include such as support of reconfiguring infrastructure, and developing security plans, etc. This standardized approach is applied to specific country and regional needs. Recent examples (FY 2003-2004) include foreign missions to Lithuania, Russian Federation Navy, Russia - PNPI, Greece (joint mission with IAEA), Tanzania, Iraq, Chile, Ecuador, and Egypt. Some of the ambitions and results of the RTR program may be characterized by the successes in Lithuania, Greece, and Russia.

  2. Present and Future Optics Challenges at CHESS and for Proposed Energy Recovery Linac Source of Synchrotron Radiation

    E-Print Network [OSTI]

    Shen, Qun

    Present and Future Optics Challenges at CHESS and for Proposed Energy Recovery Linac Source-ray optics, energy-recovery linac, high brilliance 1. INTRODUCTION As one of the pioneer synchrotron in the area of high heat load and high x-ray flux optics [1-5] since the high critical-energy wigglers

  3. Simulated Performance of Algorithms for the Localization of Radioactive Sources from a Position Sensitive Radiation Detecting System (COCAE)

    SciTech Connect (OSTI)

    Karafasoulis, K.; Zachariadou, K.; Seferlis, S.; Kaissas, I.; Potiriadis, C.; Lambropoulos, C.; Loukas, D.

    2011-12-13

    Simulation studies are presented regarding the performance of algorithms that localize point-like radioactive sources detected by a position sensitive portable radiation instrument (COCAE). The source direction is estimated by using the List Mode Maximum Likelihood Expectation Maximization (LM-ML-EM) imaging algorithm. Furthermore, the source-to-detector distance is evaluated by three different algorithms based on the photo-peak count information of each detecting layer, the quality of the reconstructed source image, and the triangulation method. These algorithms have been tested on a large number of simulated photons over a wide energy range (from 200 keV to 2 MeV) emitted by point-like radioactive sources located at different orientations and source-to-detector distances.

  4. WM '04 Conference, February 29 March 4, 2004, Tucson, AZ WM-4085 METAL MATRIX IMMOBILISATION OF SEALED RADIOACTIVE SOURCES FOR SAFE

    E-Print Network [OSTI]

    Sheffield, University of

    OF SEALED RADIOACTIVE SOURCES FOR SAFE STORAGE, TRANSPORTATION AND DISPOSAL M. I. Ojovan, W. E. Lee of radiation fields and concentrations of radionuclides from SRS may far exceed high-level radioactive waste OF SRS The classification of radioactive wastes in the Russian Federation is based on the nature

  5. Effect of geometrical configuration of radioactive sources on radiation intensity in beta-voltaic nuclear battery system: A preliminary result

    SciTech Connect (OSTI)

    Basar, Khairul, E-mail: khbasar@fi.itb.ac.id; Riupassa, Robi D., E-mail: khbasar@fi.itb.ac.id; Bachtiar, Reza, E-mail: khbasar@fi.itb.ac.id; Badrianto, Muldani D., E-mail: khbasar@fi.itb.ac.id [Nuclear Physics and Biophysics Research Division, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung (Indonesia)

    2014-01-01

    It is known that one main problem in the application of beta-voltaic nuclear battery system is its low efficiency. The efficiency of the beta-voltaic nuclear battery system mainly depends on three aspects: source of radioactive radiation, interface between materials in the system and process of converting electron-hole pair to electric current in the semiconductor material. In this work, we show the effect of geometrical configuration of radioactive sources on radiation intensity of beta-voltaic nuclear battery system.

  6. Source team evaluation for radioactive low-level waste disposal performance assessment

    SciTech Connect (OSTI)

    Cowgill, M.G.; Sullivan, T.M.

    1993-01-01

    Information compiled on the low-level radioactive waste disposed at the three currently operating commercial disposal sites during the period 1987--1989 have been reviewed and processed in order to determine the total activity distribution in terms of waste stream, waste classification and waste form. The review identified deficiencies in the information currently being recorded on shipping manifests and the development of a uniform manifest is recommended (the NRC is currently developing a rule to establish a uniform manifest). The data from waste disposed during 1989 at one of the sites (Richland, WA) were more detailed than the data available during other years and at other sites, and thus were amenable to a more in-depth treatment. This included determination of the distribution of activity for each radionuclide by waste form, and thus enabled these data to be evaluated in terms of the specific needs for improved modeling of releases from waste packages. From the results, preliminary lists have been prepared of the isotopes which might be the most significant from the aspect of the development of a source term model.

  7. Handling of Highly Radioactive Radiation Sources in a Hot Cell Using a Mechanically Driven Cell Crane - 13452

    SciTech Connect (OSTI)

    Klute, Stefan; Huber, Wolfgang-Bruno [Siempelkamp Nukleartechnik GmbH, Am Taubenfeld 25/1, 69123 Heidelberg (Germany)] [Siempelkamp Nukleartechnik GmbH, Am Taubenfeld 25/1, 69123 Heidelberg (Germany); Meyer, Franz [Nuclear Engineering Seibersdorf GmbH, 2444 Seibersdorf (Austria)] [Nuclear Engineering Seibersdorf GmbH, 2444 Seibersdorf (Austria)

    2013-07-01

    In 2010, Siempelkamp Nukleartechnik GmbH was awarded the contract for design and erection of a Hot Cell for handling and storage of highly radioactive radiation sources. This Hot Cell is part of a new hot cell laboratory, constructed for the NHZ (Neues Handhabungszentrum = New Handling Center) of the Nuclear Engineering Seibersdorf GmbH (NES). All incurring radioactive materials from Austria are collected in the NHZ, where they are safely conditioned and stored temporarily until their final storage. The main tasks of the NES include, apart from the collection, conditioning and storage of radioactive waste, also the reprocessing and the decontamination of facilities and laboratories originating from 45 years of research and development at the Seibersdorf site as well as the operation of the Hot Cell Laboratory [1]. The new Hot Cell Laboratory inside the NHZ consists of the following room areas: - One hot cell, placed in the center, for remote controlled, radiation protected handling of radioactive materials, including an integrated floor storage for the long-term temporary storage of highly radioactive radiation sources; - An anteroom for the loading and unloading of the hot cell; - One control room for the remote controlling of the hot cell equipment; - One floor storage, placed laterally to the hot cell, for burial, interim storage and removal of fissionable radioactive material in leak-proof packed units in 100 l drums. The specific design activity of the hot cell of 1.85 Pbq relating to 1-Me-Radiator including the integrated floor storage influences realization and design of the components used in the cell significantly. (authors)

  8. Characteristics and sources of intermediate size particles in recovery boilers : final project report.

    SciTech Connect (OSTI)

    Baxter, Larry L.; Shaddix, Christopher R.; Verrill, Christopher L.; Wessel, Richard A.

    2005-02-01

    As part of the U.S. Department of Energy (DOE) Office of Industrial Technologies (OIT) Industries of the Future (IOF) Forest Products research program, a collaborative investigation was conducted on the sources, characteristics, and deposition of particles intermediate in size between submicron fume and carryover in recovery boilers. Laboratory experiments on suspended-drop combustion of black liquor and on black liquor char bed combustion demonstrated that both processes generate intermediate size particles (ISP), amounting to 0.5-2% of the black liquor dry solids mass (BLS). Measurements in two U.S. recovery boilers show variable loadings of ISP in the upper furnace, typically between 0.6-3 g/Nm{sup 3}, or 0.3-1.5% of BLS. The measurements show that the ISP mass size distribution increases with size from 5-100 {micro}m, implying that a substantial amount of ISP inertially deposits on steam tubes. ISP particles are depleted in potassium, chlorine, and sulfur relative to the fuel composition. Comprehensive boiler modeling demonstrates that ISP concentrations are substantially overpredicted when using a previously developed algorithm for ISP generation. Equilibrium calculations suggest that alkali carbonate decomposition occurs at intermediate heights in the furnace and may lead to partial destruction of ISP particles formed lower in the furnace. ISP deposition is predicted to occur in the superheater sections, at temperatures greater than 750 C, when the particles are at least partially molten.

  9. Radioactive waste management in the USSR: A review of unclassified sources. Volume 2

    SciTech Connect (OSTI)

    Bradley, D.J.

    1991-03-01

    The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of contaminated areas. Meanwhile, many treatment, solidification, and disposal options for radioactive waste management are being investigated by the Soviets.

  10. Radioactive waste management in the USSR: A review of unclassified sources

    SciTech Connect (OSTI)

    Bradley, D.J.

    1991-03-01

    The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of contaminated areas. Meanwhile, many treatment, solidification, and disposal options for radioactive waste management are being investigated by the Soviets.

  11. RADIOACTIVE WASTE MANAGEMENT IN THE USSR: A REVIEW OF UNCLASSIFIED SOURCES, 1963-1990

    SciTech Connect (OSTI)

    Bradley, D. J.; Schneider, K. J.

    1990-03-01

    The Soviet Union operates a vast and growing radioactive waste management system. Detailed information on this system is rare and a general overall picture only emerges after a review of a great deal of literature. Poor waste management practices and slow implementation of environmental restoration activities have caused a great deal of national concern. The release of information on the cause and extent of an accident involving high-level waste at the Kyshtym production reactor site in 1957, as well as other contamination at the site, serve to highlight past Soviet waste management practices. As a result, the area of waste management is now receiving greater emphasis, and more public disclosures. Little is known about Soviet waste management practices related to uranium mining, conversion, and fuel fabrication processes. However, releases of radioactive material to the environment from uranium mining and milling operations, such as from mill tailings piles, are causing public concern. Official Soviet policy calls for a closed fuel cycle, with reprocessing of power reactor fuel that has been cooled for five years. For power reactors, only VVER-440 reactor fuel has been reprocessed in any significant amount, and a decision on the disposition of RBMK reactor fuel has been postponed indefinitely. Soviet reprocessing efforts are falling behind schedule; thus longer storage times for spent fuel will be required, primarily at multiple reactor stations. Information on reprocessing in the Soviet Union has been severely limited until 1989, when two reprocessing sites were acknowledged by the Soviets. A 400-metric ton (MT) per year reprocessing facility, located at Kyshtym, has been operational since 1949 for reprocessing production reactor fuel. This facility is reported to have been reprocessing VVER-440 and naval reactor fuel since 1978, with about 2000 MT of VVER-440 fuel being reprocessed by July 1989. A second facility, located near Krasnoyarsk and having a 1500 MT per year capacity as the first of several modules, was about 30% completed by July 1989. The completion of this plant was subsequently "indefinitely postponed." The initial reprocessing scheme at the Kyshtym site used sodium uranyl acetate precipitation from fuel dissolved in nitric acid solutions. The basic method~ ology now appears to be based on the conventional PUREX process. Dry reprocessing on a pilot or laboratory scale has been under way in Dimitrovgrad since 1984, and a larger unit is now being built, according to the French CEA. Perhaps significantly, much research is being done on partitioning high-level waste into element fractions. The Soviets appear to have the technology to remove radioactive noble gases released during reprocessing operations; however, there are no indications of its implementation. Millions of curies of liquid low- and intermediate-level wastes have been disposed of by well injection into underground areas where they were supposedly contained by watertight rock strata. Some gaseous wastes were also disposed of by well injection. This practice is not referred to in recent literature and thus may not be widely used today. Rather, it appears that these waste streams are now first treated to reduce volume, and then solidified using bitumen or concrete. These solidified liquid wastes from Soviet nuclear power reactor operations, along with solid wastes, are disposed of in shallow-land burial sites located at most large power reactor stations. In addition, 35 shallow-land burial sites have been alluded to by the Soviets for disposal of industrial, medical, and research low-level wastes as well as ionization sources. Research on tritium-bearing and other gaseous wastes is mentioned, as well as a waste minimization program aimed at reducing the volume of waste streams by 30%. The Soviets have announced that their high-level waste management plan is to 1) store liquid wastes for 3-5 years; 2) incorporate the waste into glass (at a final glass volume of 100-150 liters/MT of fuel reprocessed); 3) set it aside in air-cooled storage

  12. Recovery of energy from geothermal brine and other hot water sources

    DOE Patents [OSTI]

    Wahl, III, Edward F. (Claremont, CA); Boucher, Frederic B. (San Juan Capistrano, CA)

    1981-01-01

    Process and system for recovery of energy from geothermal brines and other hot water sources, by direct contact heat exchange between the brine or hot water, and an immiscible working fluid, e.g. a hydrocarbon such as isobutane, in a heat exchange column, the brine or hot water therein flowing countercurrent to the flow of the working fluid. The column can be operated at subcritical, critical or above the critical pressure of the working fluid. Preferably, the column is provided with a plurality of sieve plates, and the heat exchange process and column, e.g. with respect to the design of such plates, number of plates employed, spacing between plates, area thereof, column diameter, and the like, are designed to achieve maximum throughput of brine or hot water and reduction in temperature differential at the respective stages or plates between the brine or hot water and the working fluid, and so minimize lost work and maximize efficiency, and minimize scale deposition from hot water containing fluid including salts, such as brine. Maximum throughput approximates minimum cost of electricity which can be produced by conversion of the recovered thermal energy to electrical energy.

  13. LATIN AMERICAN AND CARIBBEAN WORKSHOP ON THE SUSTAINABILITY OF RADIOACTIVE SOURCE PHYSICAL PROTECTION UPGRADES HOSTED IN GUATEMALA

    SciTech Connect (OSTI)

    Greenberg, Raymond; Watson, Erica E.; Morris, Frederic A.; de Leal, Patty

    2009-10-07

    The Global Threat Reduction Initiative (GTRI) reduces and protects vulnerable nuclear and radiological material located at civilian sites worldwide. The GTRI program has worked successfully to remove and protect nuclear and radioactive materials, including orphaned and disused high-activity sources, and is now working to ensure sustainability. Internationally, over 40 countries are cooperating with GTRI to enhance the security of radiological materials. GTRI is now seeking to develop and enhance sustainability by coordinating its resources with those of the partner country, other donor countries, and international organizations such as the International Atomic Energy Agency (IAEA).

  14. Extraction processes and solvents for recovery of cesium, strontium, rare earth elements, technetium and actinides from liquid radioactive waste

    DOE Patents [OSTI]

    Zaitsev, Boris N. (St. Petersburg, RU); Esimantovskiy, Vyacheslav M. (St. Petersburg, RU); Lazarev, Leonard N. (St. Petersburg, RU); Dzekun, Evgeniy G. (Ozersk, RU); Romanovskiy, Valeriy N. (St. Petersburg, RU); Todd, Terry A. (Aberdeen, ID); Brewer, Ken N. (Arco, ID); Herbst, Ronald S. (Idaho Falls, ID); Law, Jack D. (Pocatello, ID)

    2001-01-01

    Cesium and strontium are extracted from aqueous acidic radioactive waste containing rare earth elements, technetium and actinides, by contacting the waste with a composition of a complex organoboron compound and polyethylene glycol in an organofluorine diluent mixture. In a preferred embodiment the complex organoboron compound is chlorinated cobalt dicarbollide, the polyethylene glycol has the formula RC.sub.6 H.sub.4 (OCH.sub.2 CH.sub.2).sub.n OH, and the organofluorine diluent is a mixture of bis-tetrafluoropropyl ether of diethylene glycol with at least one of bis-tetrafluoropropyl ether of ethylene glycol and bis-tetrafluoropropyl formal. The rare earths, technetium and the actinides (especially uranium, plutonium and americium), are extracted from the aqueous phase using a phosphine oxide in a hydrocarbon diluent, and reextracted from the resulting organic phase into an aqueous phase by using a suitable strip reagent.

  15. Design, construction, and use of a shipping case for radioactive sources used in the calibration of portal monitors in the radiation portal monitoring project

    SciTech Connect (OSTI)

    Lepel, Elwood A.; Hensley, Walter K.

    2009-12-01

    Pacific Northwest National Laboratory is working with US Customs and Border Protection to assist in the installation of radiation portal monitors. We need to provide radioactive sources Ė both gamma- and neutron-emitting Ė to ports of entry where the monitors are being installed. The monitors must be calibrated to verify proper operation and detection sensitivity. We designed a portable source-shipping case using numerical modeling to predict the neutron dose rate at the caseís surface. The shipping case including radioactive sources meets the DOT requirements for ďlimited quantity.Ē Over 300 shipments, domestic and international, were made in FY2008 using this type of shipping case.

  16. Recovery Act

    Broader source: Energy.gov [DOE]

    Recovery Act and Energy Department programs were designed to stimulate the economy while creating new power sources, conserving resources and aligning the nation to once again lead the global energy economy.

  17. Recovery Act Helps GE in-source Manufacturing | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||DepartmentReadoutReviewRecordRecovery Act Helps GE

  18. Energy recovery linacs as synchrotron radiation sources ,,invited... Sol M. Grunera)

    E-Print Network [OSTI]

    Shen, Qun

    , Cornell University, Ithaca, New York 14853 Don Bilderback Cornell High Energy Synchrotron Source York 14853 Ken Finkelstein Cornell High Energy Synchrotron Source, Cornell University, Ithaca, New York, Ithaca, New York 14853 Qun Shen Cornell High Energy Synchrotron Source and Department of Materials

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

    SciTech Connect (OSTI)

    Yamamoto, T.; Suzuki, M.; Ando, Y.

    2012-07-01

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

  20. CENTRAL STORAGE FACILITY PROJECT IN COLOMBIA TO PROVIDE THE SAFE STORAGE AND PROTECTION OF HIGH-ACTIVITY RADIOACTIVE SOURCES

    SciTech Connect (OSTI)

    Greenberg, Raymond; Wright, Kyle A.; McCaw, Erica E.; Vallejo, Jorge

    2009-10-07

    The Global Threat Reduction Initiative (GTRI) reduces and protects vulnerable nuclear and radiological material located at civilian sites worldwide. Internationally, over 40 countries are cooperating with GTRI to enhance the security of these materials. The GTRI program has worked successfully with foreign countries to remove and protect nuclear and radioactive materials, including orphaned and disused high-activity sources. GTRI began cooperation with the Republic of Colombia in April 2004. This cooperation has been a resounding success by securing forty high-risk sites, consolidating disused/orphan sources at an interim secure national storage facility, and developing a comprehensive approach to security, training, and sustainability. In 2005 the Colombian Ministry of Mines and Energy requested the Department of Energyís support in the construction of a new Central Storage Facility (CSF). In December 2005, the Ministry selected to construct this facility at the Institute of Geology and Mining (Ingeominas) site in Bogota. This site already served as Colombiaís national repository, where disused sources were housed in various buildings around the complex. The CSF project was placed under contract in May 2006, but environmental issues and public protests, which led to a class action lawsuit against the Colombian Government, forced the Ministry to quickly suspend activities, thereby placing the project in jeopardy. Despite these challenges, however, the Ministry of Mines and Energy worked closely with public and environmental authorities to resolve these issues, and continued to be a strong advocate of the GTRI program. In June 2008, the Ministry of Mines and Energy was granted the construction and environmental licenses. As a result, construction immediately resumed and the CSF was completed by December 2008. A commissioning ceremony was held for the new facility in January 2009, which was attended by representatives from the Department of Energy, U.S. Embassy, and the Ministry of Mines and Energy, including the Minister and Vice Minister.

  1. Energy recovery during expansion of compressed gas using power plant low-quality heat sources

    DOE Patents [OSTI]

    Ochs, Thomas L. (Albany, OR); O'Connor, William K. (Lebanon, OR)

    2006-03-07

    A method of recovering energy from a cool compressed gas, compressed liquid, vapor, or supercritical fluid is disclosed which includes incrementally expanding the compressed gas, compressed liquid, vapor, or supercritical fluid through a plurality of expansion engines and heating the gas, vapor, compressed liquid, or supercritical fluid entering at least one of the expansion engines with a low quality heat source. Expansion engines such as turbines and multiple expansions with heating are disclosed.

  2. Creation and recovery of a W(111) single atom gas field ion source

    SciTech Connect (OSTI)

    Pitters, Jason L. [National Institute for Nanotechnology, National Research Council of Canada, Edmonton, Alberta T6G 2M9 (Canada); Urban, Radovan [Department of Physics, University of Alberta, Edmonton, Alberta T6G 2G7 (Canada); Wolkow, Robert A. [National Institute for Nanotechnology, National Research Council of Canada, Edmonton, Alberta T6G 2M9 (Canada); Department of Physics, University of Alberta, Edmonton, Alberta T6G 2G7 (Canada)

    2012-04-21

    Tungsten single atom tips have been prepared from a single crystal W(111) oriented wire using the chemical assisted field evaporation and etching method. Etching to a single atom tip occurs through a symmetric structure and leads to a predictable last atom unlike etching with polycrystalline tips. The single atom tip formation procedure is shown in an atom by atom removal process. Rebuilds of single atom tips occur on the same crystalline axis as the original tip such that ion emission emanates along a fixed direction for all tip rebuilds. This preparation method could be utilized and developed to prepare single atom tips for ion source development.

  3. Waste heat recovery from the European Spallation Source cryogenic helium plants - implications for system design

    SciTech Connect (OSTI)

    Jurns, John M.; Bšck, Harald; Gierow, Martin

    2014-01-29

    The European Spallation Source (ESS) neutron spallation project currently being designed will be built outside of Lund, Sweden. The ESS design includes three helium cryoplants, providing cryogenic cooling for the proton accelerator superconducting cavities, the target neutron source, and for the ESS instrument suite. In total, the cryoplants consume approximately 7 MW of electrical power, and will produce approximately 36 kW of refrigeration at temperatures ranging from 2-16 K. Most of the power consumed by the cryoplants ends up as waste heat, which must be rejected. One hallmark of the ESS design is the goal to recycle waste heat from ESS to the city of Lund district heating system. The design of the cooling system must optimize the delivery of waste heat from ESS to the district heating system and also assure the efficient operation of ESS systems. This report outlines the cooling scheme for the ESS cryoplants, and examines the effect of the cooling system design on cryoplant design, availability and operation.

  4. Study finds radioactivity around Los Alamos largely due to natural...

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

    Radioactivity largely due to natural sources Study finds radioactivity around Los Alamos largely due to natural sources The study was subsequently peer reviewed externally by...

  5. Recovery Act: Finite Volume Based Computer Program for Ground Source Heat Pump Systems

    SciTech Connect (OSTI)

    James A Menart, Professor

    2013-02-22

    This report is a compilation of the work that has been done on the grant DE-EE0002805 entitled √?¬?√?¬Ę√?¬?√?¬?√?¬?√?¬?Finite Volume Based Computer Program for Ground Source Heat Pump Systems.√?¬?√?¬Ę√?¬?√?¬?√?¬?√?¬Ě The goal of this project was to develop a detailed computer simulation tool for GSHP (ground source heat pump) heating and cooling systems. Two such tools were developed as part of this DOE (Department of Energy) grant; the first is a two-dimensional computer program called GEO2D and the second is a three-dimensional computer program called GEO3D. Both of these simulation tools provide an extensive array of results to the user. A unique aspect of both these simulation tools is the complete temperature profile information calculated and presented. Complete temperature profiles throughout the ground, casing, tube wall, and fluid are provided as a function of time. The fluid temperatures from and to the heat pump, as a function of time, are also provided. In addition to temperature information, detailed heat rate information at several locations as a function of time is determined. Heat rates between the heat pump and the building indoor environment, between the working fluid and the heat pump, and between the working fluid and the ground are computed. The heat rates between the ground and the working fluid are calculated as a function time and position along the ground loop. The heating and cooling loads of the building being fitted with a GSHP are determined with the computer program developed by DOE called ENERGYPLUS. Lastly COP (coefficient of performance) results as a function of time are provided. Both the two-dimensional and three-dimensional computer programs developed as part of this work are based upon a detailed finite volume solution of the energy equation for the ground and ground loop. Real heat pump characteristics are entered into the program and used to model the heat pump performance. Thus these computer tools simulate the coupled performance of the ground loop and the heat pump. The price paid for the three-dimensional detail is the large computational times required with GEO3D. The computational times required for GEO2D are reasonable, a few minutes for a 20 year simulation. For a similar simulation, GEO3D takes days of computational time. Because of the small simulation times with GEO2D, a number of attractive features have been added to it. GEO2D has a user friendly interface where inputs and outputs are all handled with GUI (graphical user interface) screens. These GUI screens make the program exceptionally easy to use. To make the program even easier to use a number of standard input options for the most common GSHP situations are provided to the user. For the expert user, the option still exists to enter their own detailed information. To further help designers and GSHP customers make decisions about a GSHP heating and cooling system, cost estimates are made by the program. These cost estimates include a payback period graph to show the user where their GSHP system pays for itself. These GSHP simulation tools should be a benefit to the advancement of GSHP system

  6. Development and Evaluation of Rhenium-188-labeled Radioactive Stents for Restenosis Therapy and Development of Strategies for Radiolabeling Brachytherapy Sources with Palladium-103 CRADA FINAL REPORT

    SciTech Connect (OSTI)

    Knapp, F. F. [ORNL

    1998-06-01

    This project involved collaboration between InnerDyne, Inc., and radiopharmaceutical research programs at ORNL and Brookhaven National Laboratory (BNL) which explored new strategies for the development and animal testing of radioactive rhenium-188-labeled implantable stent sources for the treatment of coronary restenosis after angioplasty and the development of chemical species radiolabeled with the palladium-103 radioisotope for the treatment of cancer. Rhenium-l 88 was made available for these studies from radioactive decay of tungsten-188 produced in the ORNL High Flux Isotope Reactor (HFIR). Stent activation and coating technology was developed and provided by InnerDyne, Inc., and stent radiolabeling technology and animal studies were conducted by InnerDyne staff in conjunction with investigators at BNL. Collaborative studies in animals were supported at sites by InnerDyne, Inc. New chemical methods for attaching the palladium-103 radioisotope to bifunctional chelate technologies were developed by investigators at ORNL.

  7. WM'05 Conference, February 27 March 3, 2005, Tucson, AZ WM-5278 IDENTIFYING RADIOACTIVE SOURCES AT THE DEMOLITION SITE

    E-Print Network [OSTI]

    products. Industries that routinely use these devices include the automotive, paper manufacturing, sewage), in a cooperative partnership with the scrap metal industry, developed a CD ROM based training program to provide the demolition industry secure radioactive gauges and devices at their point of installation. Figure 1 Radiation

  8. Problems with packaged sources in foreign countries

    SciTech Connect (OSTI)

    Abeyta, Cristy L; Matzke, James L; Zarling, John; Tompkin, J. Andrew

    2010-01-01

    The Global Threat Reduction Initiative's (GTRI) Off-Site Source Recovery Project (OSRP), which is administered by the Los Alamos National Laboratory (LANL), removes excess, unwanted, abandoned, or orphan radioactive sealed sources that pose a potential threat to national security, public health, and safety. In total, GTRI/OSRP has been able to recover more than 25,000 excess and unwanted sealed sources from over 825 sites. In addition to transuranic sources, the GTRI/OSRP mission now includes recovery of beta/gamma emitting sources, which are of concern to both the U.S. government and the International Atomic Energy Agency (IAEA). This paper provides a synopsis of cooperative efforts in foreign countries to remove excess and unwanted sealed sources by discussing three topical areas: (1) The Regional Partnership with the International Atomic Energy Agency; (2) Challenges in repatriating sealed sources; and (3) Options for repatriating sealed sources.

  9. FOSTERING MULTI-LATERAL COOPERATION BETWEEN THE GOVERNMENTS OF MEXICO, COLOMBIA, AND THE UNITED STATES TO ENHANCE THE PROTECTION OF HIGH-ACTIVITY RADIOACTIVE SOURCES

    SciTech Connect (OSTI)

    Butler, Nicholas; Watson, Erica E.; Wright, Kyle A.

    2009-10-07

    The Global Threat Reduction Initiative (GTRI) reduces and protects vulnerable nuclear and radiological material located at civilian sites worldwide from sabotage, theft or diversion. The GTRI program has worked successfully with foreign countries to remove and protect nuclear and radioactive materials including high-activity sources used in medical, commercial, and research applications. There are many barriers to successful bilateral cooperation that must be overcome including language, preconceived perceptions, long distances, and different views on the threat and protection requirements. Successful cooperation is often based on relationships and building trusting relationships takes time. In the case of Mexico, GTRI first made contact in 2005. The project then lost momentum and stalled. At the same time, GTRIís cooperation with the Republic of Colombia was a resounding success resulting in the securing of forty sites; the consolidation of numerous disused/orphan sources at a secure national storage facility; and, the development of a comprehensive approach to security including, inter alia, training and sustainability. The government of Colombia also showcased this comprehensive approach to thirteen Central American and Caribbean countries at a GTRI regional security conference held in Panama in October 2004. Representatives from the Colombian government were aware of GTRIís interest in initiating cooperation with the Government of Mexico and to facilitate this cooperation, they offered to invite their Mexican counterparts to Colombia to observe its successful cooperation with GTRI. Shortly after that visit, the Government of Mexico agreed to move forward and requested that the cooperative efforts in Mexico be performed in a tripartite manner, leveraging the skills, experience, and resources of the Colombians. As a result, 22 of Mexicoís largest radioactive sites have had security upgrades in place within 18 months of cooperation.

  10. FOSTERING MULTI-LATERAL COOPERATION BETWEEN THE GOVERNMENTS OF DOMINICAN REPUBLIC, COLOMBIA, AND THE UNITED STATES TO ENHANCE THE PROTECTION OF HIGH-ACTIVITY RADIOACTIVE SOURCES

    SciTech Connect (OSTI)

    Butler, Nicholas; McCaw, Erica E.; Wright, Kyle A.; Medina, Maximo

    2009-10-06

    The Global Threat Reduction Initiative (GTRI) reduces and protects vulnerable nuclear and radiological material located at civilian sites worldwide from sabotage, theft or diversion. The GTRI has worked successfully with foreign countries to remove and protect nuclear and radioactive materials including high-activity sources used in medical, commercial, and research applications. There are many barriers to successful bilateral cooperation that must be overcome including language, preconceived perceptions, long distances, and different views on the threat and protection requirements. Successful cooperation is often based on relationships and building trusting relationships takes time. In the case of Dominican Republic, the GTRI first received contact in 2008 from the Government of Dominican Republic. They requested cooperation that was similar to the tri-partite cooperation between Colombia, Mexico and the United States. Throughout the region it was widely known that the GTRIís cooperation with the Government of Colombia was a resounding success resulting in the securing of forty sites; the consolidation of numerous disused/orphan sources at a secure national storage facility; and, the development of a comprehensive approach to security including, inter alia, training and sustainability. The Government of Colombia also showcased this comprehensive approach to thirteen Central American and Caribbean countries at a GTRI regional security conference held in Panama in October 2004. In 2007, Colombia was an integral component of GTRI multi-lateral cooperation initiation in Mexico. As a result, twenty two of Mexicoís largest radioactive sites have been upgraded in the past eighteen months. These two endeavors served as catalysts for cooperation opportunities in the Dominican Republic. Representatives from the Colombian government were aware of GTRIís interest in initiating cooperation with the Government of Dominican Republic and to facilitate this cooperation, they traveled to the Dominican Republic and provided briefings and presentations which demonstrated its successful cooperation with the GTRI. Shortly after that visit, the Government of Dominican Republic agreed to move forward and requested that the cooperative efforts in Dominican Republic be performed in a tripartite manner, leveraging the skills, experience, and resources of the Colombians, and the financial and technical support of the United States. As a result, two of Dominican Republicís largest radioactive sites had security upgrades in place within 90 days of the cooperation visit in December 2008.

  11. Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

    SciTech Connect (OSTI)

    Shott, Gregory

    2014-08-31

    The purpose of this special analysis (SA) is to determine if the Neutron Products Incorporated (NPI) Sealed Sources waste stream (DRTK000000056, Revision 0) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The NPI Sealed Sources waste stream consists of 850 60Co sealed sources (Duratek [DRTK] 2013). The NPI Sealed Sources waste stream requires a special analysis (SA) because the waste stream 60Co activity concentration exceeds the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

  12. Waste Steam Recovery

    E-Print Network [OSTI]

    Kleinfeld, J. M.

    1979-01-01

    An examination has been made of the recovery of waste steam by three techniques: direct heat exchange to process, mechanical compression, and thermocompression. Near atmospheric steam sources were considered, but the techniques developed are equally...

  13. Radiological Characterization Technical Report on Californium-252 Sealed Source Transuranic Debris Waste for the Off-Site Source Recovery Project at Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Feldman, Alexander

    2014-04-24

    This document describes the development and approach for the radiological characterization of Cf-252 sealed sources for shipment to the Waste Isolation Pilot Plant. The report combines information on the nuclear material content of each individual source (mass or activity and date of manufacture) with information and data on the radionuclide distributions within the originating nuclear material. This approach allows for complete and accurate characterization of the waste container without the need to take additional measurements. The radionuclide uncertainties, developed from acceptable knowledge (AK) information regarding the source material, are applied to the summed activities in the drum. The AK information used in the characterization of Cf-252 sealed sources has been qualified by the peer review process, which has been reviewed and accepted by the Environmental Protection Agency.

  14. Asymmetric Dual Axis Energy Recovery Linac for Ultra-High Flux sources of coherent X-ray/THz radiation: Investigations Towards its Ultimate Performance

    E-Print Network [OSTI]

    Ainsworth, R; Konoplev, I V; Seryi, A

    2015-01-01

    Truly compact and high current, efficient particle accelerators are required for sources of coherent high brightness and intensity THz and X-Ray radiation to be accepted by university or industrial R&D laboratories. The demand for compactness and efficiency can be satisfied by superconducting RF energy recovery linear accelerators (SRF ERL) allowing effectively minimising the footprint and maximising the efficiency of the system. However such set-ups are affected by regenerative beam-break up (BBU) instabilities which limit the beam current and may terminate the beam transport as well as energy recuperation. In this paper we suggest and discuss a SRF ERL with asymmetric configuration of accelerating and decelerating cavities resonantly coupled. In this model of SRF ERL we propose an electron bunch passing through accelerating and decelerating cavities each once and we show that in this case the regenerative BBU instability can be minimised allowing high currents to be achieved. We study the BBU start curr...

  15. Switchable radioactive neutron source device

    DOE Patents [OSTI]

    Stanford, G.S.; Rhodes, E.A.; Devolpi, A.; Boyar, R.E.

    1987-11-06

    This invention is a switchable neutron generating apparatus comprised of a pair of plates, the first plate having an alpha emitter section on it and the second plate having a target material portion on it which generates neutrons when its nuclei absorb an alpha particle. In operation, the alpha portion of the first plate is aligned with the neutron portion of the second plate to produce neutrons and brought out of alignment to cease production of neutrons. 3 figs.

  16. Control of Sealed Radioactive Sources

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i n c i p aDepartmentEnergy comparingDeep January 2012 PURPOSE This

  17. Novel 125 I production and recovery system†

    E-Print Network [OSTI]

    Kar, Adwitiya

    2009-05-15

    ????????????......... 32 5 Recovery of iodine versus initial mass (measured by spectrometry).............. 33 6 Recovery of iodine following distillation of extracted solution (measured by NAA)????????????????????????? ...... 34 7 Iodine recovery from... (6) In both cases the new isotope will carry the same mass number but a different atomic number than its parent. The iodine-125 formed will now undergo electron capture and decay to stable tellurium-125 completing the radioactive decay process...

  18. Recovery Act: Innovative CO2 Sequestration from Flue Gas Using Industrial Sources and Innovative Concept for Beneficial CO2 Use

    SciTech Connect (OSTI)

    Dando, Neal; Gershenzon, Mike; Ghosh, Rajat

    2012-07-31

    field testing of a biomimetic in-duct scrubbing system for the capture of gaseous CO2 coupled with sequestration of captured carbon by carbonation of alkaline industrial wastes. The Phase 2 project, reported on here, combined efforts in enzyme development, scrubber optimization, and sequestrant evaluations to perform an economic feasibility study of technology deployment. The optimization of carbonic anhydrase (CA) enzyme reactivity and stability are critical steps in deployment of this technology. A variety of CA enzyme variants were evaluated for reactivity and stability in both bench scale and in laboratory pilot scale testing to determine current limits in enzyme performance. Optimization of scrubber design allowed for improved process economics while maintaining desired capture efficiencies. A range of configurations, materials, and operating conditions were examined at the Alcoa Technical Center on a pilot scale scrubber. This work indicated that a cross current flow utilizing a specialized gas-liquid contactor offered the lowest system operating energy. Various industrial waste materials were evaluated as sources of alkalinity for the scrubber feed solution and as sources of calcium for precipitation of carbonate. Solids were mixed with a simulated sodium bicarbonate scrubber blowdown to comparatively examine reactivity. Supernatant solutions and post-test solids were analyzed to quantify and model the sequestration reactions. The best performing solids were found to sequester between 2.3 and 2.9 moles of CO2 per kg of dry solid in 1-4 hours of reaction time. These best performing solids were cement kiln dust, circulating dry scrubber ash, and spray dryer absorber ash. A techno-economic analysis was performed to evaluate the commercial viability of the proposed carbon capture and sequestration process in full-scale at an aluminum smelter and a refinery location. For both cases the in-duct scrubber technology was compared to traditional amine- based capture. Incorporation of the laboratory results showed that for the application at the aluminum smelter, the in-duct scrubber system is more economical than traditional methods. However, the reverse is true for the refinery case, where the bauxite residue is not effective enough as a sequestrant, combined with challenges related to contaminants in the bauxite residue accumulating in and fouling the scrubber absorbent. Sensitivity analyses showed that the critical variables by which process economics could be improved are enzyme concentration, efficiency, and half-life. At the end of the first part of the Phase 2 project, a gate review (DOE Decision Zero Gate Point) was conducted to decide on the next stages of the project. The original plan was to follow the pre-testing phase with a detailed design for the field testing. Unfavorable process economics, however, resulted in a decision to conclude the project before moving to field testing. It is noted that CO2 Solutions proposed an initial solution to reduce process costs through more advanced enzyme management, however, DOE program requirements restricting any technology development extending beyond 2014 as commercial deployment timeline did not allow this solution to be undertaken.

  19. Air Handler Condensate Recovery at the Environmental Protection Agency's Science and Ecosystem Support Division: Best Management Practice Case Study #14; Alternate Water Sources (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2010-02-01

    FEMP Water Efficiency Best Management Practice #14 Case Study: Overview of the air handler condensate recovery program at the Environmental Protection Agency's Science and Ecosystem Support Division.

  20. Hazardous and Radioactive Mixed Waste Program

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

    1989-02-22

    To establish Department of Energy (DOE) hazardous and radioactive mixed waste policies and requirements and to implement the requirements of the Resource Conservation and Recovery Act (RCRA) within the framework of the environmental programs established under DOE O 5400.1. This directive does not cancel any directives.

  1. Industrial Heat Recovery - 1982†

    E-Print Network [OSTI]

    Csathy, D.

    1982-01-01

    Industrial Research HTFS Re search Programme HTFS/1S/R19, "Dryout and Flow in Horizontal and Horizontal Hairpin Tubes". 6 l\\rnerican Boiler I1anufacturers Assoc iation, "Lexicon, Boiler & Auxiliary Eauinment", 7 G:t=iffith P., book of I:eat senow N... RECOVERY - 1982 by Denis Csathy, Deltak Corn,oration, !1inneapolis, 11N Two years ago I summarized 20 years of ex perience on Industrial Heat Recovery for the Energy-source Technology Conference and Exhibition held in New Orleans, Louisiana. l...

  2. Management of disused plutonium sealed sources

    SciTech Connect (OSTI)

    Whitworth, Julia Rose [Los Alamos National Laboratory; Pearson, Michael W [Los Alamos National Laboratory; Abeyta, Cristy [Los Alamos National Laboratory

    2010-01-01

    The Global Threat Reduction Initiative's (GTRI) Offsite Source Recovery Project (OSRP) has been recovering excess and unwanted radioactive sealed sources since 1999, including more than 2,400 Plutonium (Pu)-238 sealed sources and 653 Pu-239-bearing sources that represent more than 10% of the total sources recovered by GTRI/OSRP to date. These sources have been recovered from hundreds of sites within the United States (US) and around the world. OSRP grew out of early efforts at the Los Alamos National Laboratory (LANL) to recover and disposition excess Plutonium-239 (Pu-239) sealed sources that were distributed in the 1960s and 1970s under the Atoms for Peace Program, a loan-lease program that serviced 31 countries, as well as domestic users. In the conduct of these recovery operations, GTRI/OSRP has been required to solve problems related to knowledge-of-inventory, packaging and transportation of fissile and heat-source materials, transfer of ownership, storage of special nuclear material (SNM) both at US Department of Energy (DOE) facilities and commercially, and disposal. Unique issues associated with repatriation from foreign countries, including end user agreements required by some European countries and denials of shipment, will also be discussed.

  3. OSRP Source Repatriations-Case Studies: Brazil, Ecuador, Uruguay

    SciTech Connect (OSTI)

    Greenberg, Ray Jr. [U.S. Department of Energy, National Nuclear Security Administration, Office of Global Threat Reduction, Washington, DC (United States); Abeyta, Cristy; Matzke, Jim; Wald-Hopkins, Mark; Streeper, Charles [Offsite Source Recovery Project, Los Alamos National Laboratory, Los Alamos, New Mexico (United States)

    2012-07-01

    The Global Threat Reduction Initiative's (GTRI) Offsite Source Recovery Project (OSRP) began recovering excess and unwanted radioactive sealed sources (sources) in 1999. As of February 2012, the project had recovered over 30,000 sources totaling over 820,000 Ci. OSRP grew out of early efforts at Los Alamos National Laboratory (LANL) to recover disused excess Plutonium- 239 (Pu-239) sources that were distributed in the 1960's and 1970's under the Atoms for Peace Program. Source recovery was initially considered a waste management activity. However, after the 9/11 terrorist attacks, the interagency community began to recognize that excess and unwanted radioactive sealed sources pose a national security threat, particularly those that lack a disposition path. After OSRP's transfer to the U.S. National Nuclear Security Administration (NNSA) to be part of GTRI, its mission was expanded to include all disused sealed sources that might require national security consideration. Recognizing the transnational threat posed by porous borders and the ubiquitous nature of sources, GTRI/OSRP repatriates U.S. origin sources based on threat reduction prioritization criteria. For example, several recent challenging source repatriation missions have been conducted by GTRI/OSRP in South America. These include the repatriation of a significant amount of Cs-137 and other isotopes from Brazil; re-packaging of conditioned Ra-226 sources in Ecuador for future repatriation; and, multilateral cooperation in the consolidation and export of Canadian, US, and Indian Co-60/Cs-137 sources from Uruguay. In addition, cooperation with regulators and private source owners in other countries presents opportunities for GTRI/OSRP to exchange best practices for managing disused sources. These positive experiences often result in long-term cooperation and information sharing with key foreign counterparts. International source recovery operations are essential to the preservation of U.S. national security interests. They are also mutually beneficial for fostering positive relationships with other governments and private industry, and demonstrate that responsible end-of-life options are given to legacy U.S.-origin sources in other countries. GTRI/OSRP does not take back sources that have a viable path for commercial disposal. Most US origin sources were sold commercially and were not provided by the US government. Below is a synopsis of cooperative efforts with Brazil, Ecuador, and Uruguay. Bilateral and multilateral efforts have been successful in removing hundreds of U.S.origin sealed radioactive sources from Latin American countries to the U.S. As many disused sources remain in the region, and since repatriation is not always an option, GTRI will continue to work with those countries to ensure that these sources are stored securely for the long-term. Successful Latin America operations should serve as a model for other regional cooperation in the repatriation of sealed sources, encouraging other source exporting countries to implement similar programs. Securing and removing sources, both domestically and internationally, is crucial to strengthening the life-cycle management of radioactive sources worldwide. Such efforts not only prevent these materials from being used maliciously, but also address public health and safety concerns, and under-gird the IAEA Code of Conduct on the Safety and Security of Radioactive Sources. (authors)

  4. Radioactive Waste Management

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

    1984-02-06

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

  5. Radioactive Material Transportation Practices

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

    2002-09-23

    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.

  6. Power Recovery

    E-Print Network [OSTI]

    Murray, F.

    1986-01-01

    , will be the use of the ASTM Theoretical Steam Rate Tables. In addition, the author's experience regarding the minimum size for power recovery units that are economic in a Culf Coast plant will be presented. INTROD\\Jr.'rION When surveying an operation...)' The pressure ~ecompression term(~2) k~l, is used in the equat10n in a manner 1 which reduces the power recovery as calculated by the first term of the equation. From a practical view a decompression ra~~y ~0.3 is a good screening point. Note...

  7. REHABILITATION AND RECOVERY Rehabillitation and Recovery Following

    E-Print Network [OSTI]

    MacDonald, Lee

    REHABILITATION AND RECOVERY Rehabillitation and Recovery Following Wildfires: A Synthesis1 Lee H rehabilitation techniques applied in the Sierra Nevada, northern California, and southwestern Oregon objectives; and {5) recommend appropriate rehabilitation and recovery measures. Wildfires traditionally have

  8. 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...

  9. Recovering Radioactive Materials with OSRP team

    ScienceCinema (OSTI)

    None

    2010-01-08

    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

  10. Future Synchrotron Light Sources Based on Ultimate Storage Rings...

    Office of Scientific and Technical Information (OSTI)

    ACCELERATORS; APERTURES; BRIGHTNESS; DIFFRACTION; ELECTRON BEAMS; ELECTRONS; ENERGY RECOVERY; LIFETIME; LIGHT SOURCES; LINEAR ACCELERATORS; OPTIMIZATION; PHOTONS;...

  11. Radioactive Materials Product Stewardship

    E-Print Network [OSTI]

    Radioactive Materials Product Stewardship ABackground Report for the National Dialogue...................................................................................................26 Low Level Waste (LLW) Disposal Regulations on Radioactive Materials Product Stewardship Prepared by the: Product Stewardship Institute University

  12. Laboratory Heat Recovery System†

    E-Print Network [OSTI]

    Burrows, D. B.; Mendez, F. J.

    1981-01-01

    that they will be considerable. The system has been in successful operation since October 1979. 724 ESL-IE-81-04-123 Proceedings from the Third Industrial Energy Technology Conference Houston, TX, April 26-29, 1981 Conoco R&D West The award-winning laboratory heat-recovery... stream_source_info ESL-IE-81-04-123.pdf.txt stream_content_type text/plain stream_size 11112 Content-Encoding ISO-8859-1 stream_name ESL-IE-81-04-123.pdf.txt Content-Type text/plain; charset=ISO-8859-1 LABORATORY HEAT...

  13. Case Study in Corporate Memory Recovery: Hanford Tank Farms Miscellaneous Underground Waste Storage Tanks - 15344

    SciTech Connect (OSTI)

    Washenfelder, D. J.; Johnson, J. M.; Turknett, J. C.; Barnes, T. J.; Duncan, K. G.

    2015-01-07

    In addition to managing the 177 underground waste storage tanks containing 212,000 m3 (56 million gal) of radioactive waste at the U. S. Department of Energyís Hanford Site 200 Area Tank Farms, Washington River Protection Solutions LLC is responsible for managing numerous small catch tanks and special surveillance facilities. These are collectively known as ďMUSTsĒ - Miscellaneous Underground Storage Tanks. The MUSTs typically collected drainage and flushes during waste transfer system piping changes; special surveillance facilities supported Tank Farm processes including post-World War II uranium recovery and later fission product recovery from tank wastes. Most were removed from service following deactivation of the single-shell tank system in 1980 and stabilized by pumping the remaining liquids from them. The MUSTs were isolated by blanking connecting transfer lines and adding weatherproofing to prevent rainwater entry. Over the next 30 years MUST operating records were dispersed into large electronic databases or transferred to the National Archives Regional Center in Seattle, Washington. During 2014 an effort to reacquire the historical bases for the MUSTsí published waste volumes was undertaken. Corporate Memory Recovery from a variety of record sources allowed waste volumes to be initially determined for 21 MUSTs, and waste volumes to be adjusted for 37 others. Precursors and symptoms of Corporate Memory Loss were identified in the context of MUST records recovery.

  14. Lessons learned by southern states in transportation of radioactive materials

    SciTech Connect (OSTI)

    Not Available

    1992-03-01

    This report has been prepared under a cooperative agreement with DOE`s Office of Civilian Radioactive Waste Management (OCRWM) and is a summary of the lessons learned by southern states regarding the transportation of radioactive materials including High-Level Radioactive Wastes (HLRW) and Spent Nuclear Fuel (SNF). Sources used in this publication include interviews of state radiological health and public safety officials that are members of the Southern States Energy Board (SSEB) Advisory Committee on Radioactive Materials Transportation, as well as the Board`s Transuranic (TRU) Waste Transportation Working Group. Other sources include letters written by the above mentioned committees concerning various aspects of DOE shipment campaigns.

  15. Counterpulse railgun energy recovery circuit

    DOE Patents [OSTI]

    Honig, Emanuel M. (Los Alamos, NM)

    1986-01-01

    In an electromagnetic launcher such as a railgun for propelling a projectile at high velocity, a counterpulse energy recovery circuit is employed to transfer stored inductive energy from a source inductor to the railgun inductance to propel the projectile down the railgun. Switching circuitry and an energy transfer capacitor are used to switch the energy back to the source inductor in readiness for a repetitive projectile propelling cycle.

  16. Overpulse railgun energy recovery circuit

    DOE Patents [OSTI]

    Honig, Emanuel M. (Los Alamos, NM)

    1989-01-01

    In an electromagnetic launcher such as a railgun for propelling a projectile at high velocity, an overpulse energy recovery circuit is employed to transfer stored inductive energy from a source inductor to the railgun inductance to propel the projectile down the railgun. Switching circuitry and an energy transfer capacitor are used to switch the energy back to the source inductor in readiness for a repetitive projectile propelling cycle.

  17. Design Considerations for Industrial Heat Recovery Systems†

    E-Print Network [OSTI]

    Bywaters, R. P.

    1979-01-01

    recovery design considerations as well as a summary of typical "waste heat" sources and application sites. A procedure for conducting industrial waste heat surveys is presented. Thermodynamic and heat transfer factors are discussed. Problems associated...

  18. Supply Chain Logistics Post Recovery Landscape

    E-Print Network [OSTI]

    Minnesota, University of

    1 Supply Chain Logistics ≠ Post Recovery Landscape Freight and Logistics Symposium Center.... ∑ Logistics Perspective ∑ Transportation ∑ Trucking, Rail, Ocean, River, Fuel ∑ Global Sourcing & U.S. Logistics ∑ Land Bridges, Inland ports, Import Warehouses, Plant Locations ∑ Domestic Logistics ∑ Retail

  19. An Introduction to Waste Heat Recovery

    E-Print Network [OSTI]

    Darby, D. F.

    1985-01-01

    The recovery of waste heat energy is one element of a complete energy conservation plan. In addition to contributing to the goal of saving energy, utilization of waste heat is also an important source of cost savings. This presentation details...

  20. Recovering Radioactive Materials with ORSP Team

    ScienceCinema (OSTI)

    LANL

    2009-09-01

    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.

  1. Radioactivity and food

    SciTech Connect (OSTI)

    Olszyna-Marzys, A.E. (Laboratorio Unificado de Control de Alimentos y Medicamentos (LUCAM) (Guatemala))

    1990-03-01

    Two topics relating to radioactivity and food are discussed: food irradiation for preservation purposes, and food contamination from radioactive substances. Food irradiation involves the use of electromagnetic energy (x and gamma rays) emitted by radioactive substances or produced by machine in order to destroy the insects and microorganisms present and prevent germination. The sanitary and economic advantages of treating food in this way are discussed. Numerous studies have confirmed that under strictly controlled conditions no undesirable changes take place in food that has been irradiated nor is radioactivity induced. Reference is made to the accident at the Chernobyl nuclear power station, which aroused public concern about irradiated food. The events surrounding the accident are reviewed, and its consequences with regard to contamination of different foods with radioactive substances, particularly iodine-131 and cesium-137, are described. Also discussed are the steps that have been taken by different international organizations to set limits on acceptable radioactivity in food.15 references.

  2. Radiation Awareness TrainingRadiation Awareness Training Radioactive Material &Radioactive Material &

    E-Print Network [OSTI]

    Li, Mo

    & XX--RaysRays Office of Radiological Safety Environmental Health & Safety Georgia Institute, Chemistry, Physics, Applied Physiology ∑ Radioactive Material ≠ Sealed Sources, Unsealed Sources (liquid ∑ You can help us by informing potential users of the approval process and training! #12;Role of ORS

  3. Radioactive Waste Management Basis

    SciTech Connect (OSTI)

    Perkins, B K

    2009-06-03

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

  4. Thin californium-containing radioactive source wires

    DOE Patents [OSTI]

    Gross, Ian G (Clinton, TN); Pierce, Larry A (Kingston, TN)

    2012-01-03

    A cermet wire includes at least 1% californium-252 and is characterized by a diameter of no more than 0.0225 inch.

  5. Cosmic radioactivity and INTEGRAL results

    SciTech Connect (OSTI)

    Diehl, Roland [Max Planck Institut fŁr Extraterrestrische Physik, D-85748 Garching, Germany and Excellence Cluster Origin and Evolution of the Universe', D-85748 Garching (Germany)

    2014-05-02

    Gamma-ray lines from radioactive decay of unstable isotopes co-produced by nucleosynthesis in massive stars and supernova have been measured since more than thirty years. Over the past ten years, INTEGRAL complemented the first sky survey made by COMPTEL. The {sup 26}A1 isotope with 1 My decay time had been first direct proof of currently-ongoing nucleosynthesis in our Galaxy. This has now become a tool to study the ?My history of specific source regions, such as massive-star groups and associations in nearby regions which can be discriminated from the galactic-plane background, and the inner Galaxy, where Doppler shifted lines add to the astronomical information about bar and spiral structure. Recent findings suggest that superbubbles show a remarkable asymmetry, on average, in the spiral arms of our galaxy. {sup 60}Fe is co-produced by the sources of {sup 26}A1, and the isotopic ratio from their nucleosynthesis encodes stellar-structure information. Annihilation gamma-rays from positrons in interstellar space show a puzzling bright and extended source region central to our Galaxy, but also may be partly related to nucleosynthesis. {sup 56}Ni and {sup 44}Ti isotope gamma-rays have been used to constrain supernova explosion mechanisms. Here we report latest results using the accumulated multi-year database of INTEGRAL observations, and discuss their astrophysical interpretations, connecting to other traces of cosmic radioactivity and to other cosmic messengers.

  6. Radioactive waste disposal package

    DOE Patents [OSTI]

    Lampe, Robert F. (Bethel Park, PA)

    1986-01-01

    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.

  7. High-level radioactive wastes. Supplement 1

    SciTech Connect (OSTI)

    McLaren, L.H.

    1984-09-01

    This bibliography contains information on high-level radioactive wastes included in the Department of Energy's Energy Data Base from August 1982 through December 1983. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number. 1452 citations.

  8. Radioactive Waste Management Manual

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

    1999-07-09

    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.

  9. Heat recovery in building envelopes

    E-Print Network [OSTI]

    Walker, Iain S.; Sherman, Max H.

    2003-01-01

    2003). Infiltration heat recovery Ė ASHRAE Research ProjectModel for Infiltration Heat Recovery, Proc. 21 st AnnualN ATIONAL L ABORATORY Heat Recovery in Building Envelopes

  10. Heat Recovery in Building Envelopes

    E-Print Network [OSTI]

    Sherman, Max H.; Walker, Iain S.

    2001-01-01

    Model For Infiltration Heat Recovery. Proceedings 21st AivcLBNL 47329 HEAT RECOVERY IN BUILDING ENVELOPES Max H.contribution because of heat recovery within the building

  11. Heat recovery in building envelopes

    E-Print Network [OSTI]

    Walker, Iain S.; Sherman, Max H.

    2003-01-01

    2003). Infiltration heat recovery Ė ASHRAE Research ProjectModel for Infiltration Heat Recovery, Proc. 21 st AnnualWalker, I.S. (2001). "Heat Recovery in Building Envelopes".

  12. Overpulse railgun energy recovery circuit

    DOE Patents [OSTI]

    Honig, E.M.

    1984-09-28

    The invention presented relates to a high-power pulsing circuit and more particularly to a repetitive pulse inductive energy storage and transfer circuit for an electromagnetic launcher. In an electromagnetic launcher such as a railgun for propelling a projectile at high velocity, an overpulse energy recovery circuit is employed to transfer stored inductive energy from a source inductor to the railgun inductance to propel the projectile down the railgun. Switching circuitry and an energy transfer capacitor are used to switch the energy back to the source inductor in readiness for a repetitive projectile propelling cycle.

  13. Counterpulse railgun energy recovery circuit

    DOE Patents [OSTI]

    Honig, E.M.

    1984-09-28

    The invention presented relates to a high-power pulsing circuit and more particularly to a repetitive pulse inductive energy storage and transfer circuit for an electromagnetic launcher. In an electromagnetic launcher such as a railgun for propelling a projectile at high velocity, a counterpulse energy recovery circuit is employed to transfer stored inductive energy from a source inductor to the railgun inductance to propel the projectile down the railgun. Switching circuitry and an energy transfer capacitor are used to switch the energy back to the source inductor in readiness for a repetitive projectile propelling cycle.

  14. Recovery Act Milestones

    ScienceCinema (OSTI)

    Rogers, Matt

    2013-05-29

    Every 100 days, the Department of Energy is held accountable for a progress report on the American Recovery and Reinvestment Act. Update at 200 days, hosted by Matt Rogers, Senior Advisor to Secretary Steven Chu for Recovery Act Implementation.

  15. Locating Heat Recovery Opportunities†

    E-Print Network [OSTI]

    Waterland, A. F.

    1981-01-01

    Basic concepts of heat recovery are defined as they apply to the industrial community. Methods for locating, ranking, and developing heat recovery opportunities are presented and explained. The needs for useful heat 'sinks' are emphasized as equal...

  16. Understanding radioactive waste

    SciTech Connect (OSTI)

    Murray, R.L.

    1981-12-01

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

  17. Radioactive Waste Management Manual

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

    1999-07-09

    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.

  18. Radioactive Materials Emergencies Course Presentation

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Hanford Fire Department has developed this training to assist emergency responders in understanding the hazards in responding to events involving radioactive materials, to know the fundamentals of radioactive contamination, to understand the biological affects of exposure to radioactive materials, and to know how to appropriately respond to hazardous material events involving radioactive materials.

  19. Battleground Energy Recovery Project

    SciTech Connect (OSTI)

    Daniel Bullock

    2011-12-31

    In October 2009, the project partners began a 36-month effort to develop an innovative, commercial-scale demonstration project incorporating state-of-the-art waste heat recovery technology at Clean Harbors, Inc., a large hazardous waste incinerator site located in Deer Park, Texas. With financial support provided by the U.S. Department of Energy, the Battleground Energy Recovery Project was launched to advance waste heat recovery solutions into the hazardous waste incineration market, an area that has seen little adoption of heat recovery in the United States. The goal of the project was to accelerate the use of energy-efficient, waste heat recovery technology as an alternative means to produce steam for industrial processes. The project had three main engineering and business objectives: Prove Feasibility of Waste Heat Recovery Technology at a Hazardous Waste Incinerator Complex; Provide Low-cost Steam to a Major Polypropylene Plant Using Waste Heat; and Ô?∑ Create a Showcase Waste Heat Recovery Demonstration Project.

  20. Radioactivity in food crops

    SciTech Connect (OSTI)

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

    1983-05-01

    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.

  1. Regulatory Control of Sealed Sources in Germany including Regulations Regarding Spent and Disused Sources - 13176

    SciTech Connect (OSTI)

    Dollan, Ralph; Haeusler, Uwe; Czarwinski, Renate

    2013-07-01

    Effective regulatory control is essential to ensure the safe and secure use of radioactive material and the appropriate management of radioactive waste. To ensure a sustainable control of high radioactive sources, the European Commission published the Council Directive 2003/122/EURATOM on the control of high-activity sealed radioactive sources and orphan sources, which had to be transferred into national legislation by all member states of the European Union. Major requirement of the Directive is a system to ensure traceability of high-activity sealed sources from 'cradle to grave' as well as the provision to take back disused sources by the supplier or manufacturer. With the Act on high-activity sealed radioactive sources Germany implemented the requirements of the Directive 2003/122/EURATOM and established a national registry of high-activity sealed sources in 2006. Currently, about 27.000 high-activity sealed sources are recorded in this national registry. (authors)

  2. Container for radioactive materials

    DOE Patents [OSTI]

    Fields, S.R.

    1984-05-30

    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.

  3. Radioactive Waste Management Manual

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

    1999-07-09

    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, supersedes DOE M 435.1-1 Chg 1.

  4. Waste Heat Recovery

    Office of Environmental Management (EM)

    DRAFT - PRE-DECISIONAL - DRAFT 1 Waste Heat Recovery 1 Technology Assessment 2 Contents 3 1. Introduction to the TechnologySystem ......

  5. Radioactive Waste Management

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

    1999-07-09

    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. Supersedes DOE O 5820.2A. Chg 1 dated 8-28-01. Certified 1-9-07.

  6. New Proton Radioactivity Measurements

    E-Print Network [OSTI]

    Edinburgh, University of

    New Proton Radioactivity Measurements Richard J. Irvine Thesis submitted for the degree of Doctor to search for examples of proton emission from ground and low­lying states in odd­Z nuclei at the proton into a double­sided silicon strip detector system, where their subsequent particle decays (proton or alpha) were

  7. Radioactivity and foods

    SciTech Connect (OSTI)

    Olszyna-Marzys, A.E. (Unified Lab. of Food and Drug Control, Guatemala City (Guatemala))

    1991-01-01

    The purpose of this article is to describe and contrast two relationships between radiation and food--on the one hand, beneficial preservation of food by controlled exposure to ionizing radiation; and, on the other, contamination of food by accidental incorporation of radioactive nuclides within the food itself. In food irradiation, electrons or electromagnetic radiation is used to destroy microorganisms and insects or prevent seed germination. The economic advantages and health benefits of sterilizing food in this manner are clear, and numerous studies have confirmed that under strictly controlled conditions no undersirable changes or induced radioactivity is produced in the irradiated food. An altogether different situation is presented by exposure of food animals and farming areas to radioactive materials, as occurred after the major Soviet nuclear reactor accident at Chenobyl. This article furnishes the basic information needed to understand the nature of food contamination associated with that event and describes the work of international organizations seeking to establish appropriate safe limits for levels of radioactivity in foods.

  8. Radioactive Waste Management

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

    1999-07-09

    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

  9. The development of radioactive sample surrogates for training and exercises

    SciTech Connect (OSTI)

    Martha Finck; Bevin Brush; Dick Jansen; David Chamberlain; Don Dry; George Brooks; Margaret Goldberg

    2012-03-01

    The development of radioactive sample surrogates for training and exercises Source term information is required for to reconstruct a device used in a dispersed radiological dispersal device. Simulating a radioactive environment to train and exercise sampling and sample characterization methods with suitable sample materials is a continued challenge. The Idaho National Laboratory has developed and permitted a Radioactive Response Training Range (RRTR), an 800 acre test range that is approved for open air dispersal of activated KBr, for training first responders in the entry and exit from radioactively contaminated areas, and testing protocols for environmental sampling and field characterization. Members from the Department of Defense, Law Enforcement, and the Department of Energy participated in the first contamination exercise that was conducted at the RRTR in the July 2011. The range was contaminated using a short lived radioactive Br-82 isotope (activated KBr). Soil samples contaminated with KBr (dispersed as a solution) and glass particles containing activated potassium bromide that emulated dispersed radioactive materials (such as ceramic-based sealed source materials) were collected to assess environmental sampling and characterization techniques. This presentation summarizes the performance of a radioactive materials surrogate for use as a training aide for nuclear forensics.

  10. Model-Driven Business Process Recovery , Terence C. Lau2

    E-Print Network [OSTI]

    Zou, Ying

    Model-Driven Business Process Recovery Ying Zou1 , Terence C. Lau2 , Kostas Kontogiannis3 , Tack. In this paper, we propose a model-driven business process recovery framework that captures the essential-to-date linkage between business tasks and their implementation in source code, we propose a model-driven business

  11. Hazardous and radioactive substances in

    E-Print Network [OSTI]

    Hazardous and radioactive substances in danisH Marine Waters Ingela DahllŲf & Jesper H. Andersen University #12;#12;Hazardous and radioactive substances in danisH Marine Waters #12;#12;Hazardous Hazardous and radioactive substances in danisH Marine Waters status and teMporal trends #12;Hazardous

  12. Managing Manure with Biogas Recovery Systems

    E-Print Network [OSTI]

    Mukhtar, Saqib

    such as natural gas, propane, and fuel oil. Biogas can also be flared to control odor if energy recovery source of energy with much lower environmental impacts than conventional fossil fuel. The methane States Environmental Protection Agency The AgSTAR Program #12;Office of Air and Radiation (6202J) EPA-430

  13. Recovery of ammonia from industrial wastewater

    SciTech Connect (OSTI)

    Marr, R. ); Koncar, M. )

    1993-07-01

    The ecological problems of ammonia and ammonium salts in wastewater, and the sources of effluents containing these two products, are discussed. Feasible separation processes and methods of recovery are reviewed, and the advantages and disadvantages of the individual processes are compared.

  14. WIPP Recovery Information | Department of Energy

    Office of Environmental Management (EM)

    WIPP Recovery Information WIPP Recovery Information Topic: J. R. Stroble CBFO, Provided Information on Locations to Access WIPP Recovery Information. WIPP Recovery - March 26, 2014...

  15. FUELS; 54 ENVIRONMENTAL SCIENCES; RADIOACTIVE EFFLUENTS; EMISSION...

    Office of Scientific and Technical Information (OSTI)

    SRP radioactive waste releases. Startup through 1959 Ashley, C. 05 NUCLEAR FUELS; 54 ENVIRONMENTAL SCIENCES; RADIOACTIVE EFFLUENTS; EMISSION; ENVIRONMENTAL MATERIALS;...

  16. Mass and Heat Recovery

    E-Print Network [OSTI]

    Hindawai, S. M.

    2010-01-01

    In the last few years heat recovery was under spot and in air conditioning fields usually we use heat recovery by different types of heat exchangers. The heat exchanging between the exhaust air from the building with the fresh air to the building...

  17. Recovery Boiler Corrosion Chemistry

    E-Print Network [OSTI]

    Das, Suman

    11/13/2014 1 Recovery Boiler Corrosion Chemistry Sandy Sharp and Honghi Tran Symposium on Corrosion of a recovery boiler each cause their own forms of corrosion and cracking Understanding the origin of the corrosive conditions enables us to operate a boiler so as to minimize corrosion and cracking select

  18. Recovery Act-Funded Geothermal Heat Pump projects

    Office of Energy Efficiency and Renewable Energy (EERE)

    The U.S. Department of Energy (DOE) was allocated funding from the American Recovery and Reinvestment Act to conduct research into ground source heat pump technologies and applications. Projects...

  19. Methane Digesters and Biogas Recovery - Masking the Environmental Consequences of Industrial Concentrated Livestock Production

    E-Print Network [OSTI]

    Di Camillo, Nicole G.

    2011-01-01

    renewa- ble energy production from biogas burned in internalbiogas recovery systems are pro- moted as an auspicious source of renewable energy production

  20. Radioactive ion detector

    DOE Patents [OSTI]

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

    1997-01-01

    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.

  1. Radioactive ion detector

    DOE Patents [OSTI]

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

    1997-08-12

    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.

  2. Radioactive waste storage issues

    SciTech Connect (OSTI)

    Kunz, D.E.

    1994-08-15

    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.

  3. Standard guide for sampling radioactive tank waste

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2011-01-01

    1.1 This guide addresses techniques used to obtain grab samples from tanks containing high-level radioactive waste created during the reprocessing of spent nuclear fuels. Guidance on selecting appropriate sampling devices for waste covered by the Resource Conservation and Recovery Act (RCRA) is also provided by the United States Environmental Protection Agency (EPA) (1). Vapor sampling of the head-space is not included in this guide because it does not significantly affect slurry retrieval, pipeline transport, plugging, or mixing. 1.2 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  4. Recovery Act State Memos Virginia

    Energy Savers [EERE]

    * VIRGINIA RECOVERY ACT SNAPSHOT Virginia has substantial natural resources, including coal and natural gas. The American Recovery & Reinvestment Act (ARRA) is making a...

  5. ARM - Recovery Act

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory of raregovAboutRecovery Act Recovery Act Logo Subscribe FAQs Recovery Act

  6. Exhaust Energy Recovery

    Broader source: Energy.gov [DOE]

    Exhaust energy recovery proposed to achieve 10% fuel efficiency improvement and reduce or eliminate the need for increased heat rejectioncapacity for future heavy duty engines in Class 8 Tractors

  7. Imbibition assisted oil recovery

    E-Print Network [OSTI]

    Pashayev, Orkhan H.

    2004-11-15

    analyzed in detail to investigate oil recovery during spontaneous imbibition with different types of boundary conditions. The results of these studies have been upscaled to the field dimensions. The validity of the new definition of characteristic length...

  8. RADIOACTIVE MATERIALS SENSORS

    SciTech Connect (OSTI)

    Mayo, Robert M.; Stephens, Daniel L.

    2009-09-15

    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.

  9. Radioactive waste material disposal

    DOE Patents [OSTI]

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

    1995-10-24

    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.

  10. Radioactive waste material disposal

    DOE Patents [OSTI]

    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)

    1995-01-01

    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.

  11. Radioactive waste processing apparatus

    DOE Patents [OSTI]

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

    1987-01-01

    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.

  12. Magnesium fluoride recovery method

    DOE Patents [OSTI]

    Gay, Richard L. (Canoga Park, CA); McKenzie, Donald E. (Woodland Hills, CA)

    1989-01-01

    A method of obtaining magnesium fluoride substantially free from radioactive uranium from a slag containing the same and having a radioactivity level of at least about 7000 pCi/gm. The slag is ground to a particle size of about 200 microns or less. The ground slag is contacted with an acid under certain prescribed conditions to produce a liquid product and a particulate solid product. The particulate solid product is separated from the liquid and treated at least two more times with acid to produce a solid residue consisting essentially of magnesium fluoride substantially free of uranium and having a residual radioactivity level of less than about 1000 pCi/gm. In accordance with a particularly preferred embodiment of the invention a catalyst and an oxidizing agent are used during the acid treatment and preferably the acid is sulfuric acid having a strength of about 1.0 Normal.

  13. Radioactive waste management in the former USSR

    SciTech Connect (OSTI)

    Bradley, D.J.

    1992-06-01

    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.

  14. Radioactive Material Transportation Practices Manual

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

    2008-06-04

    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. Supersedes DOE M 460.2-1.

  15. Enhanced coalbed methane recovery

    SciTech Connect (OSTI)

    Mazzotti, M.; Pini, R.; Storti, G. [ETH, Zurich (Switzerland). Inst. of Process Engineering

    2009-01-15

    The recovery of coalbed methane can be enhanced by injecting CO{sub 2} in the coal seam at supercritical conditions. Through an in situ adsorption/desorption process the displaced methane is produced and the adsorbed CO{sub 2} is permanently stored. This is called enhanced coalbed methane recovery (ECBM) and it is a technique under investigation as a possible approach to the geological storage of CO{sub 2} in a carbon dioxide capture and storage system. This work reviews the state of the art on fundamental and practical aspects of the technology and summarizes the results of ECBM field tests. These prove the feasibility of ECBM recovery and highlight substantial opportunities for interdisciplinary research at the interface between earth sciences and chemical engineering.

  16. Solvent recovery targeting

    SciTech Connect (OSTI)

    Ahmad, B.S.; Barton, P.I.

    1999-02-01

    One of the environmental challenges faced by the pharmaceutical and specialty chemical industries is the widespread use of organic solvents. With a solvent-based chemistry, the solvent necessarily has to be separated from the product. Chemical species in waste-solvent streams typically form multicomponent azeotropic mixtures, and this often complicates separation and, hence, recovery of solvents. A design approach is presented whereby process modifications proposed by the engineer to reduce the formation of waste-solvent streams can be evaluated systematically. This approach, called solvent recovery targeting, exploits a recently developed algorithm for elucidating the separation alternatives achievable when applying batch distillation to homogeneous multicomponent mixtures. The approach places the composition of the waste-solvent mixture correctly in the relevant residue curve map and computes the maximum amount of pure material that can be recovered via batch distillation. Solvent recovery targeting is applied to two case studies derived from real industrial processes.

  17. Radioactive waste processing apparatus

    DOE Patents [OSTI]

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

    1985-08-30

    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.

  18. Development of iron phosphate ceramic waste form to immobilize radioactive waste solution

    SciTech Connect (OSTI)

    Choi, Jongkwon; Um, Wooyong; Choung, Sungwook

    2014-05-09

    The objective of this research was to develop an iron phosphate ceramic (IPC) waste form using converter slag obtained as a by-product of the steel industry as a source of iron instead of conventional iron oxide. Both synthetic off-gas scrubber solution containing technetium-99 (or Re as a surrogate) and LiCl-KCl eutectic salt, a final waste solution from pyrochemical processing of spent nuclear fuel, were used as radioactive waste streams. The IPC waste form was characterized for compressive strength, reduction capacity, chemical durability, and contaminant leachability. Compressive strengths of the IPC waste form prepared with different types of waste solutions were 16 MPa and 19 MPa for LiCl-KCl eutectic salt and the off-gas scrubber simulant, respectively, which meet the minimum compressive strength of 3.45 MPa (500 psi) for waste forms to be accepted into the radioactive waste repository. The reduction capacity of converter slag, a main dry ingredient used to prepare the IPC waste form, was 4,136 meq/kg by the Ce(IV) method, which is much higher than those of the conventional Fe oxides used for the IPC waste form and the blast furnace slag materials. Average leachability indexes of Tc, Li, and K for the IPC waste form were higher than 6.0, and the IPC waste form demonstrated stable durability even after 63-day leaching. In addition, the Toxicity Characteristic Leach Procedure measurements of converter slag and the IPC waste form with LiCl-KCl eutectic salt met the universal treatment standard of the leachability limit for metals regulated by the Resource Conservation and Recovery Act. This study confirms the possibility of development of the IPC waste form using converter slag, showing its immobilization capability for radionuclides in both LiCl-KCl eutectic salt and off-gas scrubber solutions with significant cost savings.

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

    Office of Environmental Management (EM)

    - Radioactive Handling Materials Facility (RMHF) Leachfield ETEC - Radioactive Handling Materials Facility (RMHF) Leachfield January 1, 2014 - 12:00pm Addthis US Department of...

  20. Recovery Act Workforce Development | Department of Energy

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

    Announces Nearly 100 Million for Smart Grid Workforce Training and Development. Congressional Testimony Recovery Act Recovery Act Interoperability Recovery Act SGIG...

  1. Distributed Generation with Heat Recovery and Storage

    E-Print Network [OSTI]

    Siddiqui, Afzal; Marnay, Chris; Firestone, Ryan M.; Zhou, Nan

    2005-01-01

    Generation with Heat Recovery and Storage á Afzal Sgeneration unit with heat recovery for space and watergeneration unit with heat recovery for space and water

  2. Distributed Generation with Heat Recovery and Storage

    E-Print Network [OSTI]

    Siddiqui, Afzal S.; Marnay, Chris; Firestone, Ryan M.; Zhou, Nan

    2008-01-01

    Distributed Generation with Heat Recovery and Storage AfzalGeneration with Heat Recovery and Storage Manuscript Numberhere in order to focus on heat recovery and storage) utility

  3. A mathematical model for infiltration heat recovery

    E-Print Network [OSTI]

    Buchanan, C.R.; Sherman, M.H.

    2000-01-01

    Simulation of Infiltration Heat RecoveryĒ, 19 th AIVC Annualfor infiltration heat recovery could easily be incorporatedSimplified Infiltration Heat Recovery Model ÖÖÖÖÖÖÖÖ17

  4. Releases of radioactivity at the Savannah River Plant, 1954--1985

    SciTech Connect (OSTI)

    Zeigler, C.C.; Lawrimore, I.B.

    1988-07-01

    Radioactive releases from Savannah River Plant (SRP) facilities to air, water and earthen seepage basins have been monitored and tabulated throughout the history of the site. The purpose of this report is to provide a source of data on routine releases of radioactivity to air, water and seepage basins that can be used for analyses of trends, environmental impact, etc. As used in this report, routine radioactive releases means radioactive materials that are released through established effluents from process facilities. This report is not intended to provide interpretation of the release values, their transport and impact or information on spills, leaks, buried waste or special use facilities. These subjects are covered in other SRP publications. This report provides a summary of radioactive releases that reflects the release values contained in records and documents from startup through 1985. Releases are tabulated in the following categories: Annual radioactive releases by emission source and radionuclide for 1954 through 1985; Annual radioactive releases by receptor medium and radionuclide for 1954 through 1985; Monthly releases by emission source and radionuclide for 1981 through 1985. The presentation of all SRP routine radioactive releases data in these categories provides a reference for historic data on SRP releases. 34 refs.

  5. Challenges in Industrial Heat Recovery

    E-Print Network [OSTI]

    Dafft, T.

    2007-01-01

    This presentation will address several completed and working projects involving waste heat recovery in a chemical plant. Specific examples will be shown and some of the challenges to successful implementation and operation of heat recovery projects...

  6. New York Recovery Act Snapshot

    Broader source: Energy.gov [DOE]

    The American Recovery & Reinvestment Act (ARRA) is making a meaningful down payment on the nation's energy and environmental future. The Recovery Act investments in New York are supporting a...

  7. [Waste water heat recovery system

    SciTech Connect (OSTI)

    Not Available

    1993-04-28

    The production capabilities for and field testing of the heat recovery system are described briefly. Drawings are included.

  8. Radioactive decay data tables

    SciTech Connect (OSTI)

    Kocher, D.C.

    1981-01-01

    The estimation of radiation dose to man from either external or internal exposure to radionuclides requires a knowledge of the energies and intensities of the atomic and nuclear radiations emitted during the radioactive decay process. The availability of evaluated decay data for the large number of radionuclides of interest is thus of fundamental importance for radiation dosimetry. This handbook contains a compilation of decay data for approximately 500 radionuclides. These data constitute an evaluated data file constructed for use in the radiological assessment activities of the Technology Assessments Section of the Health and Safety Research Division at Oak Ridge National Laboratory. The radionuclides selected for this handbook include those occurring naturally in the environment, those of potential importance in routine or accidental releases from the nuclear fuel cycle, those of current interest in nuclear medicine and fusion reactor technology, and some of those of interest to Committee 2 of the International Commission on Radiological Protection for the estimation of annual limits on intake via inhalation and ingestion for occupationally exposed individuals.

  9. The Radioactivity Characteristics of the NPP Charcoal Sample Contaminated by Carbon-14 - 13531

    SciTech Connect (OSTI)

    Kim, Hee Reyoung

    2013-07-01

    The radioactivity of {sup 14}C-contaminated charcoal sample was analyzed by using a high temperature oxidation and liquid scintillation counting method. The radioactivity of the sample was monotonically increased according to the increase of the combustion time at each temperature where the experimental uncertainty was calculated in the 95 % confidence level. It showed that the {sup 14}C radioactivity was not completely extracted from the sample by simply increasing the combustion time unless the combustion temperature was high enough. The higher the combustion temperature was, the higher the recovery during the first 30 minutes was. The first 30 minute recoveries were 100 % at a temperature equal to or greater than 450 deg. C. The ratios of the recovery during the first 30 minutes to the total recovery during whole duration were more than 90 % at each experiment temperature. It was understood that the temperature was a critical factor for the complete removal of the {sup 14}C from the waste sample. (authors)

  10. Radioactive waste material melter apparatus

    DOE Patents [OSTI]

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

    1990-04-24

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

  11. Radioactive waste material melter apparatus

    DOE Patents [OSTI]

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

    1990-01-01

    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.

  12. Incorporating Energy Efficiency into Disaster Recovery Efforts...

    Energy Savers [EERE]

    Incorporating Energy Efficiency into Disaster Recovery Efforts Incorporating Energy Efficiency into Disaster Recovery Efforts Better Buildings Residential Network Program...

  13. Waste Heat Recovery Opportunities for Thermoelectric Generators...

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

    Waste Heat Recovery Opportunities for Thermoelectric Generators Waste Heat Recovery Opportunities for Thermoelectric Generators Thermoelectrics have unique advantages for...

  14. Emergency Responder Radioactive Material Quick Reference Sheet

    Broader source: Energy.gov [DOE]

    Transportation Emergency Preparedness Program (TEPP) Emergency Responder Radioactive Material Quick Reference Sheet

  15. Storage depot for radioactive material

    DOE Patents [OSTI]

    Szulinski, Milton J. (Richland, WA)

    1983-01-01

    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.

  16. Memorandum, Reporting of Radiological Sealed Sources Transactions

    Broader source: Energy.gov [DOE]

    The requirements for reporting transactions involving radiological sealed sources are identified in Department of Energy (DOE) Notice (N) 234.1, Reporting of Radioactive Sealed Sources. The data reported in accordance with DOE N 234.1 are maintained in the DOE Radiological Source Registry and Tracking (RSRT) database by the Office of Information Management, within the Office of Environment, Health, Safety and Security.

  17. Elemental sulfur recovery process

    DOE Patents [OSTI]

    Flytzani-Stephanopoulos, M.; Zhicheng Hu.

    1993-09-07

    An improved catalytic reduction process for the direct recovery of elemental sulfur from various SO[sub 2]-containing industrial gas streams. The catalytic process provides combined high activity and selectivity for the reduction of SO[sub 2] to elemental sulfur product with carbon monoxide or other reducing gases. The reaction of sulfur dioxide and reducing gas takes place over certain catalyst formulations based on cerium oxide. The process is a single-stage, catalytic sulfur recovery process in conjunction with regenerators, such as those used in dry, regenerative flue gas desulfurization or other processes, involving direct reduction of the SO[sub 2] in the regenerator off gas stream to elemental sulfur in the presence of a catalyst. 4 figures.

  18. Elemental sulfur recovery process

    DOE Patents [OSTI]

    Flytzani-Stephanopoulos, Maria (Winchester, MA); Hu, Zhicheng (Somerville, MA)

    1993-01-01

    An improved catalytic reduction process for the direct recovery of elemental sulfur from various SO.sub.2 -containing industrial gas streams. The catalytic process provides combined high activity and selectivity for the reduction of SO.sub.2 to elemental sulfur product with carbon monoxide or other reducing gases. The reaction of sulfur dioxide and reducing gas takes place over certain catalyst formulations based on cerium oxide. The process is a single-stage, catalytic sulfur recovery process in conjunction with regenerators, such as those used in dry, regenerative flue gas desulfurization or other processes, involving direct reduction of the SO.sub.2 in the regenerator off gas stream to elemental sulfur in the presence of a catalyst.

  19. Spent Sealed Sources Management in Switzerland - 12011

    SciTech Connect (OSTI)

    Beer, H.F.

    2012-07-01

    Information is provided about the international recommendations for the safe management of disused and spent sealed radioactive sources wherein the return to the supplier or manufacturer is encouraged for large radioactive sources. The legal situation in Switzerland is described mentioning the demand of minimization of radioactive waste as well as the situation with respect to the interim storage facility at the Paul Scherrer Institute (PSI). Based on this information and on the market situation with a shortage of some medical radionuclides the management of spent sealed sources is provided. The sources are sorted according to their activity in relation to the nuclide-specific A2-value and either recycled as in the case of high active sources or conditioned as in the case for sources with lower activity. The results are presented as comparison between recycled and conditioned activity for three selected nuclides, i.e. Cs-137, Co-60 and Am-241. (author)

  20. Method for making radioactive metal articles having small dimensions

    DOE Patents [OSTI]

    Ohriner, Evan K. (Knoxville, TN)

    2000-01-01

    A method for making a radioactive article such as wire, includes the steps of providing a metal article having a first shape, such a cylinder, that is either radioactive itself or can be converted to a second, radioactive isotope by irradiation; melting the metal article one or more times; optionally adding an alloying metal to the molten metal in order to enhance ductility or other properties; placing the metal article having the first shape (e.g., cylindrical) into a cavity in the interior of an extrusion body (e.g., a cylinder having a cylindrical cavity therein); extruding the extrusion body and the article having the first shape located in the cavity therein, resulting in an elongated extrusion body and an article having a second shape; removing the elongated extrusion body, for example by chemical means, leaving the elongated inner article substantially intact; optionally repeating the extrusion procedure one or more times; and then drawing the elongated article to still further elongate it, into wire, foil, or another desired shape. If the starting metal is enriched in a radioactive isotope or a precursor thereof, the end product can provide a more intense radiation source than conventionally manufactured radioactive wire, foil, or the like.

  1. Status report on energy recovery from municipal solid waste: technologies, lessons and issues. Information bulletin of the energy task force of the urban consortium

    SciTech Connect (OSTI)

    1980-01-01

    A review is presented of the lessons learned and issues raised regarding the recovery of energy from solid wastes. The review focuses on technologies and issues significant to currently operating energy recovery systems in the US - waterwall incineration, modular incineration, refuse derived fuels systems, landfill gas recovery systems. Chapters are: Energy Recovery and Solid Waste Disposal; Energy Recovery Systems; Lessons in Energy Recovery; Issues in Energy Recovery. Some basic conclusions are presented concerning the state of the art of energy from waste. Plants in shakedown or under construction, along with technologies in the development stages, are briefly described. Sources of additional information and a bibliography are included. (MCW)

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

    SciTech Connect (OSTI)

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

    2007-07-01

    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)

  3. Recovery of organic acids

    DOE Patents [OSTI]

    Verser, Dan W. (Golden, CO); Eggeman, Timothy J. (Lakewood, CO)

    2009-10-13

    A method is disclosed for the recovery of an organic acid from a dilute salt solution in which the cation of the salt forms an insoluble carbonate salt. A tertiary amine and CO.sub.2 are introduced to the solution to form the insoluble carbonate salt and a complex between the acid and an amine. A water immiscible solvent, such as an alcohol, is added to extract the acid/amine complex from the dilute salt solution to a reaction phase. The reaction phase is continuously dried and a product between the acid and the solvent, such as an ester, is formed.

  4. Recovery of organic acids

    DOE Patents [OSTI]

    Verser, Dan W. (Menlo Park, CA); Eggeman, Timothy J. (Lakewood, CO)

    2011-11-01

    A method is disclosed for the recovery of an organic acid from a dilute salt solution in which the cation of the salt forms an insoluble carbonate salt. A tertiary amine and CO.sub.2 are introduced to the solution to form the insoluble carbonate salt and a complex between the acid and an amine. A water immiscible solvent, such as an alcohol, is added to extract the acid/amine complex from the dilute salt solution to a reaction phase. The reaction phase is continuously dried and a product between the acid and the solvent, such as an ester, is formed.

  5. ARM - Recovery Act Instruments

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Comments?govInstrumentsnoaacrnBarrow, Alaska OutreachCalendarPress Releases Related2ActRecovery Act Instruments

  6. Geological Problems in Radioactive Waste Isolation: Second Worldwide Review

    E-Print Network [OSTI]

    2010-01-01

    radioactive waste disposal programme; Nagra Technical Reportfor radioactive waste disposal; and ē a summary report onof Radioactive Waste Disposal Facilities, O E C D , Report,

  7. Evaluation of radioactive scrap metal recycling

    SciTech Connect (OSTI)

    Nieves, L.A.; Chen, S.Y.; Kohout, E.J.; Nabelssi, B.; Tilbrook, R.W.; Wilson, S.E.

    1995-12-01

    This report evaluates the human health risks and environmental and socio-political impacts of options for recycling radioactive scrap metal (RSM) or disposing of and replacing it. Argonne National Laboratory (ANL) is assisting the US Department of Energy (DOE), Office of Environmental Restoration and Waste Management, Oak Ridge Programs Division, in assessing the implications of RSM management alternatives. This study is intended to support the DOE contribution to a study of metal recycling being conducted by the Task Group on Recycling and Reuse of the Organization for Economic Cooperation and Development. The focus is on evaluating the justification for the practice of recycling RSM, and the case of iron and steel scrap is used as an example in assessing the impacts. To conduct the evaluation, a considerable set of data was compiled and developed. Much of this information is included in this document to provide a source book of information.

  8. Register file soft error recovery

    DOE Patents [OSTI]

    Fleischer, Bruce M.; Fox, Thomas W.; Wait, Charles D.; Muff, Adam J.; Watson, III, Alfred T.

    2013-10-15

    Register file soft error recovery including a system that includes a first register file and a second register file that mirrors the first register file. The system also includes an arithmetic pipeline for receiving data read from the first register file, and error detection circuitry to detect whether the data read from the first register file includes corrupted data. The system further includes error recovery circuitry to insert an error recovery instruction into the arithmetic pipeline in response to detecting the corrupted data. The inserted error recovery instruction replaces the corrupted data in the first register file with a copy of the data from the second register file.

  9. Biomass Production and Nitrogen Recovery

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

    Project Peer Review WBS 4.2.2.10: Biomass Production and Nitrogen Recovery Date: March 23, 2015 Technology Area Review: Sustainability Principal Investigator: M. Cristina Negri...

  10. Sulfur recovery process

    SciTech Connect (OSTI)

    Hise, R.E.; Cook, W.J.

    1991-06-04

    This paper describes a method for recovering sulfur from a process feed stream mixture of gases comprising sulfur-containing compounds including hydrogen sulfide using the Claus reaction to convert sulfur-containing compounds to elemental sulfur and crystallization to separate sulfur-containing compounds from a tail gas of the Claus reaction for further processing as a recycle stream. It comprises: providing a Claus feed stream containing a stoichiometric excess of hydrogen sulfide, the Claus feed stream including the process feed stream and the recycles stream; introducing the Claus feed stream and an oxidizing agent into a sulfur recovery unit for converting sulfur-containing compounds in the Claus feed stream to elemental sulfur; withdrawing the tail gas from the sulfur recovery unit; separating water from the tail gas to producing a dehydrated tail gas; separating sulfur-containing compounds including carbonyl sulfide from the dehydrated tail gas as an excluded material by crystallization and withdrawing an excluded material-enriched output from the crystallization to produce the recycle stream; and combining the recycle stream with the process feed stream to produce the Claus feed stream.

  11. Low Temperature Heat Recovery for Boiler Systems†

    E-Print Network [OSTI]

    Shook, J. R.; Luttenberger, D. B.

    1986-01-01

    stream_source_info ESL-IE-86-06-70.pdf.txt stream_content_type text/plain stream_size 27871 Content-Encoding ISO-8859-1 stream_name ESL-IE-86-06-70.pdf.txt Content-Type text/plain; charset=ISO-8859-1 LOW TEMPERATURE HEAT... RECOVERY FOR BOILER SYSTEMS James R. Shook & David B. Luttenberger FLUE GAS RESOURCES, INC. Toledo, Ohio ABSTRACT Low temperature corrosion proof heat exchangers desbgned to reduce boiler flue gas temperatures to 170 F or lower are now being...

  12. SRP RADIOACTIVE WASTE RELEASES S

    Office of Scientific and Technical Information (OSTI)

    . . . . . -- SRP RADIOACTIVE WASTE RELEASES S t a r t u p t h r o u g h 1 9 5 9 September 1 9 6 0 - R E C O R D - W O R K S T E C H N I C A L D E P A R T M E N T 1 J. E. C o l e ,...

  13. The Radioactive Beam Program at Argonne

    E-Print Network [OSTI]

    B. B. Back

    2006-06-06

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

  14. Recovery Act Energy Jobs Bring New Era of Opportunity

    Broader source: Energy.gov [DOE]

    Hundreds of thousands of people found work in the past few years thanks to Recovery Act and Energy Department programs designed to stimulate the economy while creating new power sources, conserving resources and aligning the nation to once again lead the global energy economy.

  15. Disruption of cell walls for enhanced lipid recovery

    DOE Patents [OSTI]

    Knoshaug, Eric P; Donohoe, Bryon S; Gerken, Henri; Laurens, Lieve; Van Wychen, Stefanie Rose

    2015-03-24

    Presented herein are methods of using cell wall degrading enzymes for recovery of internal lipid bodies from biomass sources such as algae. Also provided are algal cells that express at least one exogenous gene encoding a cell wall degrading enzyme and methods for recovering lipids from the cells.

  16. Radioactive Waste Management Complex Wide Review

    Office of Environmental Management (EM)

    This page intentionally blank i Complex-Wide Review of DOE's Radioactive Waste Management Summary Report TABLE OF CONTENTS Acronyms ......

  17. Biomass Program Recovery Act Factsheet

    SciTech Connect (OSTI)

    2010-03-01

    The Biomass Program has awarded about $718 million in American Recovery and Reinvestment Act (Recovery Act) funds. The projects the Program is supporting are intended to: Accelerate advanced biofuels research, development, and demonstration; Speed the deployment and commercialization of advanced biofuels and bioproducts; Further the U.S. bioindustry through market transformation and creating or saving a range of jobs.

  18. Metal recovery from porous materials

    DOE Patents [OSTI]

    Sturcken, E.F.

    1991-01-01

    The present invention relates to recovery of metals. More specifically, the present invention relates to the recovery of plutonium and other metals from porous materials using microwaves. The United States Government has rights in this invention pursuant to Contract No. DE-AC09-89SR18035 between the US Department of Energy and Westinghouse Savannah River Company.

  19. s How many meltings of radioactive sources have occured?

    E-Print Network [OSTI]

    , EPA developed a CD ROM- based training program that uses interactive modules to illustrate response skills Response to Radiation Alarms at Metal Processing Facilities EPA's Interactive Training

  20. Armenia Secures Dangerous Radioactive Sources in Cooperation with NNSA |

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouthReporteeo | National Nucleara min [Type theCertification |

  1. Enhanced oil recovery system

    DOE Patents [OSTI]

    Goldsberry, Fred L. (Spring, TX)

    1989-01-01

    All energy resources available from a geopressured geothermal reservoir are used for the production of pipeline quality gas using a high pressure separator/heat exchanger and a membrane separator, and recovering waste gas from both the membrane separator and a low pressure separator in tandem with the high pressure separator for use in enhanced oil recovery, or in powering a gas engine and turbine set. Liquid hydrocarbons are skimmed off the top of geothermal brine in the low pressure separator. High pressure brine from the geothermal well is used to drive a turbine/generator set before recovering waste gas in the first separator. Another turbine/generator set is provided in a supercritical binary power plant that uses propane as a working fluid in a closed cycle, and uses exhaust heat from the combustion engine and geothermal energy of the brine in the separator/heat exchanger to heat the propane.

  2. Energy recovery system

    DOE Patents [OSTI]

    Moore, Albert S. (Morgantown, WV); Verhoff, Francis H. (Morgantown, WV)

    1980-01-01

    The present invention is directed to an improved wet air oxidation system and method for reducing the chemical oxygen demand (COD) of waste water used from scrubbers of coal gasification plants, with this COD reduction being sufficient to effectively eliminate waste water as an environmental pollutant. The improvement of the present invention is provided by heating the air used in the oxidation process to a temperature substantially equal to the temperature in the oxidation reactor before compressing or pressurizing the air. The compression of the already hot air further heats the air which is then passed in heat exchange with gaseous products of the oxidation reaction for "superheating" the gaseous products prior to the use thereof in turbines as the driving fluid. The superheating of the gaseous products significantly minimizes condensation of gaseous products in the turbine so as to provide a substantially greater recovery of mechanical energy from the process than heretofore achieved.

  3. Speech recovery device

    DOE Patents [OSTI]

    Frankle, Christen M.

    2004-04-20

    There is provided an apparatus and method for assisting speech recovery in people with inability to speak due to aphasia, apraxia or another condition with similar effect. A hollow, rigid, thin-walled tube with semi-circular or semi-elliptical cut out shapes at each open end is positioned such that one end mates with the throat/voice box area of the neck of the assistor and the other end mates with the throat/voice box area of the assisted. The speaking person (assistor) makes sounds that produce standing wave vibrations at the same frequency in the vocal cords of the assisted person. Driving the assisted person's vocal cords with the assisted person being able to hear the correct tone enables the assisted person to speak by simply amplifying the vibration of membranes in their throat.

  4. Radioactive isotopes in Danish drinking water

    E-Print Network [OSTI]

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

  5. CFD Simulation of Infiltration Heat Recovery

    E-Print Network [OSTI]

    Buchanan, C.R.

    2011-01-01

    So the infiltration heat recovery in most new houses wouldCFDSimulationof Infiltration Heat Recovery C.R.BuchananandSimulation of Infiltration Heat Recovery C.R. Buchanan and

  6. The radioactive Substances (Testing Instruments) Exemption Order 1962†

    E-Print Network [OSTI]

    Keith, Joseph

    1962-01-01

    STATUTORY INSTRUMENTS 1962 No. 2643 ATOMIC ENERGY AND RADIOACTIVE SUBSTANCES The Radioactive Substances (Testing Instruments) Exemption Order 1962

  7. The radioactive Substances (Irradiated Material) Exemption Order 1962†

    E-Print Network [OSTI]

    Joseph, Keith

    1962-01-01

    STATUTORY INSTRUMENTS 1962 No. 2647 ATOMIC ENERGY AND RADIOACTIVE SUBSTANCES The Radioactive Substances (Irradiated Material) Exemption Order 1962

  8. The radioactive Substances (Civil Defence) Exemption Order 1962†

    E-Print Network [OSTI]

    Keith, Joseph

    1962-01-01

    STATUTORY INSTRUMENTS 1962 No. 2641 ATOMIC ENERGY AND RADIOACTIVE SUBSTANCES The Radioactive Substances (Civil Defence) Exemption Order 1962

  9. The radioactive Substances (Uranium and Thorium) Exemption Order 1962†

    E-Print Network [OSTI]

    Joseph, Keith

    1962-01-01

    STATUTORY INSTRUMENTS 1962 No.2710 ATOMIC ENERGY AND RADIOACTIVE SUBSTANCES The Radioactive Substances (Uranium and Thorium) Exemption Order 1962

  10. Method for magnesium sulfate recovery

    DOE Patents [OSTI]

    Gay, R.L.; Grantham, L.F.

    1987-08-25

    A method is described for obtaining magnesium sulfate substantially free from radioactive uranium from a slag containing the same and having a radioactivity level of at least about 7,000 pCi/gm. The slag is ground to a particle size of about 200 microns or less. The ground slag is then contacted with a concentrated sulfuric acid under certain prescribed conditions to produce a liquid product and a solid product. The particulate solid product and a minor amount of the liquid is then treated to produce a solid residue consisting essentially of magnesium sulfate substantially free of uranium and having a residual radioactivity level of less than 1,000 pCi/gm. In accordance with the preferred embodiment of the invention, a catalyst and an oxidizing agent are used during the initial acid treatment and a final solid residue has a radioactivity level of less than about 50 pCi/gm.

  11. Method for magnesium sulfate recovery

    DOE Patents [OSTI]

    Gay, Richard L. (Canoga Park, CA); Grantham, LeRoy F. (Calabasas, CA)

    1987-01-01

    A method of obtaining magnesium sulfate substantially free from radioactive uranium from a slag containing the same and having a radioactivity level of at least about 7000 pCi/gm. The slag is ground to a particle size of about 200 microns or less. The ground slag is then contacted with a concentrated sulfuric acid under certain prescribed conditions to produce a liquid product and a solid product. The particulate solid product and a minor amount of the liquid is then treated to produce a solid residue consisting essentially of magnesium sulfate substantially free of uranium and having a residual radioactivity level of less than 1000 pCi/gm. In accordance with the preferred embodiment of the invention, a catalyst and an oxidizing agent are used during the initial acid treatment and a final solid residue has a radioactivity level of less than about 50 pCi/gm.

  12. Solid low-level radioactive waste radiation stability studies†

    E-Print Network [OSTI]

    Williams, Arnold Andre?

    1989-01-01

    MANAGEMENT . . . Historical background Characteristics of radioactive wastes Classification of radioactive wastes Disposal methodology and criteria Handling and storage of radioactive wastes SOLID RADIOACTIVE WASTES Historical background... Characteristics of the solidified wastes Storage and handling of solid radioactive wastes Shipment of solid radioactive wastes Solidification of waste solutions MATERIALS AND METHODS Ion-exchange methods. High integrity containers (HIC). . tv tx 15 15...

  13. Radioactive waste treatment technologies and environment

    SciTech Connect (OSTI)

    HORVATH, Jan; KRASNY, Dusan [JAVYS, PLc. - Nuclear and Decommisioning Company, PLc. (Slovakia)

    2007-07-01

    The radioactive waste treatment and conditioning are the most important steps in radioactive waste management. At the Slovak Electric, plc, a range of technologies are used for the processing of radioactive waste into a form suitable for disposal in near surface repository. These technologies operated by JAVYS, PLc. Nuclear and Decommissioning Company, PLc. Jaslovske Bohunice are described. Main accent is given to the Bohunice Radwaste Treatment and Conditioning Centre, Bituminization plant, Vitrification plant, and Near surface repository of radioactive waste in Mochovce and their operation. Conclusions to safe and effective management of radioactive waste in the Slovak Republic are presented. (authors)

  14. Recovery of cesium

    DOE Patents [OSTI]

    Izatt, Reed M. (Provo, UT); Christensen, James J. (Provo, UT); Hawkins, Richard T. (Orem, UT)

    1984-01-01

    A process of recovering cesium ions from mixtures of ions containing them and other ions, e.g., a solution of nuclear waste materials, which comprises establishing a separate source phase containing such a mixture of ions, establishing a separate recipient phase, establishing a liquid membrane phase in interfacial contact with said source and recipient phases, said membrane phase containing a ligand, preferably a selected calixarene as depicted in the drawing, maintaining said interfacial contact for a period of time long enough to transport by said ligand a substantial portion of the cesium ion from the source phase to the recipient phase, and recovering the cesium ion from the recipient phase. The separation of the source and recipient phases may be by the membrane phase only, e.g., where these aqueous phases are emulsified as dispersed phases in a continuous membrane phase, or may include a physical barrier as well, e.g., an open-top outer container with an inner open-ended container of smaller cross-section mounted in the outer container with its open bottom end spaced from and above the closed bottom of the outer container so that the membrane phase may fill the outer container to a level above the bottom of the inner container and have floating on its upper surface a source phase and a recipient phase separated by the wall of the inner container as a physical barrier. A preferred solvent for the ligand is a mixture of methylene chloride and carbon tetrachloride.

  15. Weatherization Formula Grants - American Recovery and Reinvestment...

    Energy Savers [EERE]

    Weatherization Formula Grants - American Recovery and Reinvestment Act (ARRA) Weatherization Formula Grants - American Recovery and Reinvestment Act (ARRA) U.S. Department of...

  16. Optimize carbon dioxide sequestration, enhance oil recovery

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

    Optimize carbon dioxide sequestration, enhance oil recovery Optimize carbon dioxide sequestration, enhance oil recovery The simulation provides an important approach to estimate...

  17. Cummins Waste Heat Recovery | Department of Energy

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

    Waste Heat Recovery Cummins Waste Heat Recovery Poster presentation at the 2007 Diesel Engine-Efficiency & Emissions Research Conference (DEER 2007). 13-16 August, 2007, Detroit,...

  18. Thermoelectric Technology for Automotive Waste Heat Recovery...

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

    Technology for Automotive Waste Heat Recovery Thermoelectric Technology for Automotive Waste Heat Recovery Presentation given at the 2007 Diesel Engine-Efficiency & Emissions...

  19. Energy Positive Water Resource Recovery Workshop Presentations...

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

    Presentations Energy Positive Water Resource Recovery Workshop Presentations Presentations: Keynote 1: Energy-Positive Water Resource Recovery Facilities Ed McCormick, President,...

  20. Enhancing Heat Recovery for Thermoelectric Devices | Department...

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

    Heat Recovery for Thermoelectric Devices Enhancing Heat Recovery for Thermoelectric Devices Presentation given at the 16th Directions in Engine-Efficiency and Emissions Research...

  1. PHASE I ENERGY RECOVERY LINAC AT CORNELL UNIVERSITY* I. Bazarov, S. Belomestnykh, D. Bilderback, S. Gray, S. Gruner, Y. Li, M. Liepe, H. Padamsee, V.

    E-Print Network [OSTI]

    Gruner, Sol M.

    components, heat losses in the cryogenic system, and energy recovery efficiency. Study of halo formationPHASE I ENERGY RECOVERY LINAC AT CORNELL UNIVERSITY* I. Bazarov, S. Belomestnykh, D. Bilderback, S on the energy recovery linac (ERL) concept [1, 2]. Such a source will exceed the brightness of third generation

  2. Radioactive Waste Management BasisApril 2006

    SciTech Connect (OSTI)

    Perkins, B K

    2011-08-31

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  3. Fluidized-Bed Waste-Heat Recovery System Advances†

    E-Print Network [OSTI]

    Patch, K. D.; Cole, W. E.

    1986-01-01

    stream_source_info ESL-IE-86-06-09.pdf.txt stream_content_type text/plain stream_size 23561 Content-Encoding ISO-8859-1 stream_name ESL-IE-86-06-09.pdf.txt Content-Type text/plain; charset=ISO-8859-1 FLUIDIZED-BED WASTE-HEAT... RECOVERY SYSTEM ADVANCES Keith D. Patch William E. Cole Thermo Electron Corporation Waltham, Massachusetts ABSTRACT The Fluidized-Bed Waste-Heat Recovery (FBWHR) System is a combustion air preheater designed for existing unrecuperated...

  4. Calculation of dose to soft tisse from implanted beta sources

    E-Print Network [OSTI]

    Dauffy, Lucile

    1998-01-01

    , spherical radioactive particles are injected into these arteries. This study deals with the development of BRAIN-DOSES, a computer code based on VARSKIN MOD2 and SADDE MOD2, which evaluates gamma and beta dose distributions for radioactive sources with five...

  5. Wastewater heat recovery apparatus

    DOE Patents [OSTI]

    Kronberg, J.W.

    1992-09-01

    A heat recovery system is described with a heat exchanger and a mixing valve. A drain trap includes a heat exchanger with an inner coiled tube, baffle plate, wastewater inlet, wastewater outlet, cold water inlet, and preheated water outlet. Wastewater enters the drain trap through the wastewater inlet, is slowed and spread by the baffle plate, and passes downward to the wastewater outlet. Cold water enters the inner tube through the cold water inlet and flows generally upward, taking on heat from the wastewater. This preheated water is fed to the mixing valve, which includes a flexible yoke to which are attached an adjustable steel rod, two stationary zinc rods, and a pivoting arm. The free end of the arm forms a pad which rests against a valve seat. The rods and pivoting arm expand or contract as the temperature of the incoming preheated water changes. The zinc rods expand more than the steel rod, flexing the yoke and rotating the pivoting arm. The pad moves towards the valve seat as the temperature of the preheated water rises, and away as the temperature falls, admitting a variable amount of hot water to maintain a nearly constant average process water temperature. 6 figs.

  6. Wastewater heat recovery apparatus

    DOE Patents [OSTI]

    Kronberg, James W. (108 Independent Blvd., Aiken, SC 29801)

    1992-01-01

    A heat recovery system with a heat exchanger and a mixing valve. A drain trap includes a heat exchanger with an inner coiled tube, baffle plate, wastewater inlet, wastewater outlet, cold water inlet, and preheated water outlet. Wastewater enters the drain trap through the wastewater inlet, is slowed and spread by the baffle plate, and passes downward to the wastewater outlet. Cold water enters the inner tube through the cold water inlet and flows generally upward, taking on heat from the wastewater. This preheated water is fed to the mixing valve, which includes a flexible yoke to which are attached an adjustable steel rod, two stationary zinc rods, and a pivoting arm. The free end of the arm forms a pad which rests against a valve seat. The rods and pivoting arm expand or contract as the temperature of the incoming preheated water changes. The zinc rods expand more than the steel rod, flexing the yoke and rotating the pivoting arm. The pad moves towards the valve seat as the temperature of the preheated water rises, and away as the temperature falls, admitting a variable amount of hot water to maintain a nearly constant average process water temperature.

  7. Radioactive waste management treatments: A selection for the Italian scenario

    SciTech Connect (OSTI)

    Locatelli, G. [Univ. of Lincoln, Lincoln School of Engineering, Brayford Pool - Lincoln LN6 7TS (United Kingdom); Mancini, M. [Politecnico di Milano, Dept. of Management, Economics and Industrial Engineering, Via Lambruschini 4/B, Milano (Italy); Sardini, M. [Politecnico di Milano, Dept. of Energy, Via Lambruschini 4, Milano (Italy)

    2012-07-01

    The increased attention for radioactive waste management is one of the most peculiar aspects of the nuclear sector considering both reactors and not power sources. The aim of this paper is to present the state-of-art of treatments for radioactive waste management all over the world in order to derive guidelines for the radioactive waste management in the Italian scenario. Starting with an overview on the international situation, it analyses the different sources, amounts, treatments, social and economic impacts looking at countries with different industrial backgrounds, energetic policies, geography and population. It lists all these treatments and selects the most reasonable according to technical, economic and social criteria. In particular, a double scenario is discussed (to be considered in case of few quantities of nuclear waste): the use of regional, centralized, off site processing facilities, which accept waste from many nuclear plants, and the use of mobile systems, which can be transported among multiple nuclear sites for processing campaigns. At the end the treatments suitable for the Italian scenario are presented providing simplified work-flows and guidelines. (authors)

  8. Wyoming Recovery Act State Memo

    Broader source: Energy.gov [DOE]

    Wyoming has substantial natural resources including coal, natural gas, oil, and wind power. The American Recovery & Reinvestment Act (ARRA) is making a meaningful down payment on the nationís...

  9. Waste Heat Recovery from Refrigeration†

    E-Print Network [OSTI]

    Jackson, H. Z.

    1982-01-01

    heat recovery from refrigeration machines is a concept which has great potential for implementation in many businesses. If a parallel requirement for refrigeration and hot water exists, the installation of a system to provide hot water as a by...

  10. Olefin recovery via chemical absorption

    SciTech Connect (OSTI)

    Barchas, R.

    1998-06-01

    The recovery of fight olefins in petrochemical plants has generally been accomplished through cryogenic distillation, a process which is very capital and energy intensive. In an effort to simplify the recovery process and reduce its cost, BP Chemicals has developed a chemical absorption technology based on an aqueous silver nitrate solution. Stone & Webster is now marketing, licensing, and engineering the technology. The process is commercially ready for recovering olefins from olefin derivative plant vent gases, such as vents from polyethylene, polypropylene, ethylene oxide, and synthetic ethanol units. The process can also be used to debottleneck C{sub 2} or C{sub 3} splinters, or to improve olefin product purity. This paper presents the olefin recovery imp technology, discusses its applications, and presents economics for the recovery of ethylene and propylene.

  11. Wisconsin Recovery Act State Memo

    Office of Energy Efficiency and Renewable Energy (EERE)

    Wisconsin has substantial natural resources, including biomass and hydroelectric power. The American Recovery & Reinvestment Act (ARRA)is making a meaningful down payment on the nationís energy...

  12. Heat Recovery Steam Generator Simulation†

    E-Print Network [OSTI]

    Ganapathy, V.

    1993-01-01

    The paper discusses the applications of Heat Recovery Steam Generator Simulation. Consultants, plant engineers and plant developers can evaluate the steam side performance of HRSGs and arrive at the optimum system which matches the needs...

  13. Recovery Act | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuels Data CenterFinancialInvesting inServicesRecovery Act ¬Ľ Recovery Act

  14. Method for the removal and recovery of mercury

    DOE Patents [OSTI]

    Easterly, C.E.; Vass, A.A.; Tyndall, R.L.

    1997-01-28

    The present invention is an enhanced method for the removal and recovery of mercury from mercury-contaminated matrices. The method involves contacting a mercury-contaminated matrix with an aqueous dispersant solution derived from specific intra-amoebic isolates to release the mercury from the mercury-contaminated matrix and emulsify the mercury; then, contacting the matrix with an amalgamating metal from a metal source to amalgamate the mercury to the amalgamating metal; removing the metallic source from the mercury-contaminated matrix; and heating the metallic source to vaporize the mercury in a closed system to capture the mercury vapors.

  15. Iraq liquid radioactive waste tanks maintenance and monitoring program plan.

    SciTech Connect (OSTI)

    Dennis, Matthew L.; Cochran, John Russell; Sol Shamsaldin, Emad

    2011-10-01

    The purpose of this report is to develop a project management plan for maintaining and monitoring liquid radioactive waste tanks at Iraq's Al-Tuwaitha Nuclear Research Center. Based on information from several sources, the Al-Tuwaitha site has approximately 30 waste tanks that contain varying amounts of liquid or sludge radioactive waste. All of the tanks have been non-operational for over 20 years and most have limited characterization. The program plan embodied in this document provides guidance on conducting radiological surveys, posting radiation control areas and controlling access, performing tank hazard assessments to remove debris and gain access, and conducting routine tank inspections. This program plan provides general advice on how to sample and characterize tank contents, and how to prioritize tanks for soil sampling and borehole monitoring.

  16. Requirements for shipment of DOE radioactive mixed waste

    SciTech Connect (OSTI)

    Gablin, K.; No, Hyo; Herman, J.

    1993-08-01

    There are several sources of radioactive mixed waste (RMW) at Argonne National Laboratory which, in the past, were collected at waste tanks and/or sludge tanks. They were eventually pumped out by special pumps and processed in an evaporator located in the waste operations area in Building No. 306. Some of this radioactive mixed waste represents pure elementary mercury. These cleaning tanks must be manually cleaned up because the RMW material was too dense to pump with the equipment in use. The four tanks being discussed in this report are located in Building No. 306. They are the Acid Waste Tank, IMOX/FLOC Tanks, Evaporation Feed Tanks, and Waste Storage Tanks. All of these tanks are characterized and handled separately. This paper discusses the process and the requirements for characterization and the associated paperwork for Argonne Waste to be shipped to Westinghouse Hanford Company for storage.

  17. Industrial Technology of Decontamination of Liquid Radioactive Waste in SUE MosSIA 'Radon' - 12371

    SciTech Connect (OSTI)

    Adamovich, Dmitry V.; Neveykin, Petr P.; Karlin, Yuri V.; Savkin, Alexander E. [SUE MosSIA 'Radon', 7th Rostovsky lane 2/14, Moscow 119121 (Russian Federation)

    2012-07-01

    SUE MosSIA 'RADON' - this enterprise was created more than 50 years ago, which deals with the recycling of radioactive waste and conditioning of spent sources of radiation in stationary and mobile systems in the own factory and operating organizations. Here is represented the experience SUE MosSIA 'Radon' in the field of the management with liquid radioactive waste. It's shown, that the activity of SUE MosSIA 'RADON' is developing in three directions - improvement of technical facilities for treatment of radioactive waters into SUE MosSIA 'RADON' development of mobile equipment for the decontamination of radioactive waters in other organizations, development of new technologies for decontamination of liquid radioactive wastes as part of various domestic Russian and international projects including those related to the operation of nuclear power and nuclear submarines. SUE MosSIA 'RADON' has processed more than 270 thousand m{sup 3} of radioactive water, at that more than 7000 m{sup 3} in other organizations for more than 50 years. It is shown that a number of directions, particularly, the development of mobile modular units for decontamination of liquid radioactive waste, SUE MosSIA 'RADON' is a leader in the world. (authors)

  18. Factories: The Ionising Radiations (Sealed Sources) (Leakage Test) Order, 1961†

    E-Print Network [OSTI]

    Hare, John

    1961-01-01

    This Order prescribes the test for leakage of radioactive substance to be made of sealed sources and (the particulars to be contained in registers of every such test, required under Regulation 15 of the Ionising ...

  19. New Jersey State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-04-01

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

  20. North Carolina State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-08-01

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

  1. Massachusetts State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-03-12

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

  2. Ohio State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-04-01

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

  3. Wyoming State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-10-01

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

  4. South Carolina State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-08-01

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

  5. Pennsylvania State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-04-01

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

  6. Washington State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1980-12-01

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

  7. Advanced heat pump for the recovery of volatile organic compounds

    SciTech Connect (OSTI)

    Not Available

    1992-03-01

    Emissions of Volatile Organic Compounds (VOC) from stationary industrial and commercial sources represent a substantial portion of the total US VOC emissions. The Toxic-Release Inventory'' of The US Environmental Protection Agency estimates this to be at about 3 billion pounds per year (1987 estimates). The majority of these VOC emissions are from coating processes, cleaning processes, polymer production, fuel production and distribution, foam blowing,refrigerant production, and wood products production. The US Department of Energy's (DOE) interest in the recovery of VOC stems from the energy embodied in the recovered solvents and the energy required to dispose of them in an environmentally acceptable manner. This Phase I report documents 3M's work in close working relationship with its subcontractor Nuclear Consulting Services (Nucon) for the preliminary conceptual design of an advanced Brayton cycle heat pump for the recovery of VOC. Nucon designed Brayton cycle heat pump for the recovery of methyl ethyl ketone and toluene from coating operations at 3M Weatherford, OK, was used as a base line for the work under cooperative agreement between 3M and ODE. See appendix A and reference (4) by Kovach of Nucon. This cooperative agreement report evaluates and compares an advanced Brayton cycle heat pump for solvent recovery with other competing technologies for solvent recovery and reuse. This advanced Brayton cycle heat pump is simple (very few components), highly reliable (off the shelf components), energy efficient and economically priced.

  8. System for recovery of daughter isotopes from a source material

    DOE Patents [OSTI]

    Tranter, Troy J. (Idaho Falls, ID) [Idaho Falls, ID; Todd, Terry A. (Aberdeen, ID) [Aberdeen, ID; Lewis, Leroy C. (Idaho Falls, ID) [Idaho Falls, ID; Henscheid, Joseph P. (Idaho Falls, ID) [Idaho Falls, ID

    2009-08-04

    A method of separating isotopes from a mixture containing at least two isotopes in a solution is disclosed. A first isotope is precipitated and is collected from the solution. A daughter isotope is generated and collected from the first isotope. The invention includes a method of producing an actinium-225/bismuth-213 product from a material containing thorium-229 and thorium-232. A solution is formed containing nitric acid and the material containing thorium-229 and thorium-232, and iodate is added to form a thorium iodate precipitate. A supernatant is separated from the thorium iodate precipitate and a second volume of nitric acid is added to the thorium iodate precipitate. The thorium iodate precipitate is stored and a decay product comprising actinium-225 and bismuth-213 is generated in the second volume of nitric acid, which is then separated from the thorium iodate precipitate, filtered, and treated using at least one chromatographic procedure. A system for producing an actinium-225/bismuth-213 product is also disclosed.

  9. Process for recovery of daughter isotopes from a source material

    DOE Patents [OSTI]

    Tranter, Troy J.; Todd, Terry A.; Lewis, Leroy C.; Henscheid, Joseph P.

    2005-10-04

    The invention includes a method of separating isotopes from a mixture containing at least two isotopes in a solution. A first isotope is precipitated and is collected from the solution. A daughter isotope is generated and collected from the first isotope. The invention includes a method of producing an actinium-225/bismuth-213 product from a material containing thorium-229 and thorium-232. A solution is formed containing nitric acid and the material and iodate is added to form a thorium iodate precipitate. A supernatant is separated from the thorium iodate precipitate and a second volume of nitric acid is added to the precipitate. The precipitate is stored and a decay product comprising actinium-225 and bismuth-213 is generated in the second volume of nitric acid which is then separated from the thorium iodate precipitate, filtered, and treated using at least one chromatographic procedure. The invention also includes a system for producing an actinium-225/bismuth-213 product.

  10. Low-temperature waste-heat recovery in the food and paper industries

    SciTech Connect (OSTI)

    Foell, W.K.; Lund, D.; Mitchell, J.W.; Ray, D.; Stevenson, R.; TenWolde, A.

    1980-11-01

    The potential of low-temperature waste-heat recovery technology is examined. An examination of barriers to impede waste-heat recovery is made and research programs are identified. Extensive information and data are presented in the following chapters: Waste Heat Recovery in the Wisconsin Food Industry; Waste Heat Recovery in the Wisconsin Pulp and Paper Industry; Industries' Economic Analysis of Energy Conservation Projects; Industrial Waste Heat Recovery (selection of heat-recovery heat exchangers for industrial applications, simplified procedure for selection of heat recovery heat exchangers for industrial applications, selection of heat pumps for industrial applications); Institutional Aspects of Industrial Energy Conservation (economic motivation for energy conservation and the industrial response, intrafirm idea channels and their sources, evaluation and approval of plant improvement projects, reported barriers to adopting waste heat recovery projects and recommendations for government involvement, and the final chapter is a summary with major conclusions given. Additional information is given in two appendices on the potential waste heat recovery in a cheese plant (calculation) and conditions for optimum exchanger size and break-even fuel cost. (MCW)

  11. 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.

  12. Radioactive Material or Multiple Hazardous Materials Decontamination

    Broader source: Energy.gov [DOE]

    The purpose of this procedure is to provide guidance for performing decontamination of†individuals who have entered a ďhot zoneĒ during transportation incidents involving †radioactive.

  13. Radioactivity in Precipitation: Methods and Observations from...

    Office of Environmental Management (EM)

    Radioactivity in Precipitation: Methods & Observations from Savannah River Site Dennis Jackson P.E. & Timothy Jannik - Savannah River National Laboratory Teresa Eddy - Savannah...

  14. Restoration of water environment contaminated by radioactive cesium released from Fukushima Daiichi NPP

    SciTech Connect (OSTI)

    Takeshita, K.; Takahashi, H.; Jinbo, Y.; Ishido, A.

    2013-07-01

    In the Fukushima Daiichi NPP Accident, large amounts of volatile radioactive nuclides, such as {sup 131}I, {sup 134}Cs and {sup 137}Cs, were released to the atmosphere and huge areas surrounding the nuclear site were contaminated by the radioactive fallout. In this study, a combined process with a hydrothermal process and a coagulation settling process was proposed for the separation of radioactive Cs from contaminated soil and sewage sludge. The coagulation settling operation uses Prussian Blue (Ferric ferrocyanide) and an inorganic coagulant. The recovery of Cs from sewage sludge sampled at Fukushima city (100.000 Bq/kg) and soil at a nearby village (55.000 Bq/kg), was tested. About 96% of Cs in the sewage sludge was removed successfully by combining simple hydrothermal decomposition and coagulation settling. However, Cs in the soil was not removed sufficiently by the combined process (Cs removal is only 56%). The hydrothermal decomposition with blasting was carried out. The Cs removal from the soil was increased to 85%. When these operations were repeated twice, the Cs recovery was over 90%. The combined process with hydrothermal blasting and coagulation settling is applicable to the removal of Cs from highly contaminated soil.

  15. Technical Aspects Regarding the Management of Radioactive Waste from Decommissioning of Nuclear Facilities

    SciTech Connect (OSTI)

    Dragolici, F.; Turcanu, C. N.; Rotarescu, G.; Paunica, I.

    2003-02-25

    The proper application of the nuclear techniques and technologies in Romania started in 1957, once with the commissioning of the Research Reactor VVR-S from IFIN-HH-Magurele. During the last 45 years, appear thousands of nuclear application units with extremely diverse profiles (research, biology, medicine, education, agriculture, transport, all types of industry) which used different nuclear facilities containing radioactive sources and generating a great variety of radioactive waste during the decommissioning after the operation lifetime is accomplished. A new aspect appears by the planning of VVR-S Research Reactor decommissioning which will be a new source of radioactive waste generated by decontamination, disassembling and demolition activities. By construction and exploitation of the Radioactive Waste Treatment Plant (STDR)--Magurele and the National Repository for Low and Intermediate Radioactive Waste (DNDR)--Baita, Bihor county, in Romania was solved the management of radioactive wastes arising from operation and decommissioning of small nuclear facilities, being assured the protection of the people and environment. The present paper makes a review of the present technical status of the Romanian waste management facilities, especially raising on treatment capabilities of ''problem'' wastes such as Ra-266, Pu-238, Am-241 Co-60, Co-57, Sr-90, Cs-137 sealed sources from industrial, research and medical applications. Also, contain a preliminary estimation of quantities and types of wastes, which would result during the decommissioning project of the VVR-S Research Reactor from IFIN-HH giving attention to some special category of wastes like aluminum, graphite and equipment, components and structures that became radioactive through neutron activation. After analyzing the technical and scientific potential of STDR and DNDR to handle big amounts of wastes resulting from the decommissioning of VVR-S Research Reactor and small nuclear facilities, the necessity of up-gradation of these nuclear objectives before starting the decommissioning plan is revealed. A short presentation of the up-grading needs is also presented.

  16. Hazardous and Radioactive Mixed Waste

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

    1982-12-31

    To establish hazardous waste management procedures for facilities operated under authority of the Atomic Energy Act of 1954, as amended (AEA). The procedures will follow. to the extent practicable, regulations issued by the Environmental Protection Agency (EPA) pursuant to the Resource Conservation and Recovery Act of 1976 (RCRA). Although Department of Energy (DOE) operations conducted under authority other than the AEA are subject to EPA or State regulations conforming with RCRA, facilities administered under the authority of the AEA are not bound by such requirements.

  17. Thermal expansion recovery microscopy: Practical design considerations

    SciTech Connect (OSTI)

    Mingolo, N. MartŪnez, O. E.

    2014-01-15

    A detailed study of relevant parameters for the design and operation of a photothermal microscope technique recently introduced is presented. The technique, named thermal expansion recovery microscopy (ThERM) relies in the measurement of the defocusing introduced by a surface that expands and recovers upon the heating from a modulated source. A new two lens design is presented that can be easily adapted to commercial infinite conjugate microscopes and the sensitivity to misalignment is analyzed. The way to determine the beam size by means of a focus scan and the use of that same scan to verify if a thermoreflectance signal is overlapping with the desired ThERM mechanism are discussed. Finally, a method to cancel the thermoreflectance signal by an adequate choice of a nanometric coating is presented.

  18. Polarized CMB recovery with sparse component separation

    E-Print Network [OSTI]

    Bobin, Jerome; Starck, Jean-Luc

    2015-01-01

    The polarization modes of the cosmological microwave background are an invaluable source of information for cosmology, and a unique window to probe the energy scale of inflation. Extracting such information from microwave surveys requires disentangling between foreground emissions and the cosmological signal, which boils down to solving a component separation problem. Component separation techniques have been widely studied for the recovery of CMB temperature anisotropies but quite rarely for the polarization modes. In this case, most component separation techniques make use of second-order statistics to discriminate between the various components. More recent methods, which rather emphasize on the sparsity of the components in the wavelet domain, have been shown to provide low-foreground, full-sky estimate of the CMB temperature anisotropies. Building on sparsity, the present paper introduces a new component separation technique dubbed PolGMCA (Polarized Generalized Morphological Component Analysis), which r...

  19. Radioactive waste management in the former USSR. Volume 3

    SciTech Connect (OSTI)

    Bradley, D.J.

    1992-06-01

    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.

  20. The Bayo Canyon/radioactive lanthanum (RaLa) program

    SciTech Connect (OSTI)

    Dummer, J.E.; Taschner, J.C.; Courtright, C.C.

    1996-04-01

    LANL conducted 254 radioactive lanthanum (RaLa) implosion experiments Sept. 1944-March 1962, in order to test implosion designs for nuclear weapons. High explosives surrounding common metals (surrogates for Pu) and a radioactive source containing up to several thousand curies of La, were involved in each experiment. The resulting cloud was deposited as fallout, often to distances of several miles. This report was prepared to summarize existing records as an aid in evaluating the off-site impact, if any, of this 18-year program. The report provides a historical setting for the program, which was conducted in Technical Area 10, Bayo Canyon about 3 miles east of Los Alamos. A description of the site is followed by a discussion of collateral experiments conducted in 1950 by US Air Force for developing an airborne detector for tracking atmospheric nuclear weapons tests. All known off-site data from the RaLa program are tabulated and discussed. Besides the radiolanthanum, other potential trace radioactive material that may have been present in the fallout is discussed and amounts estimated. Off-site safety considerations are discussed; a preliminary off-site dose assessment is made. Bibliographical data on 33 persons important to the program are presented as footnotes.

  1. Recovery | National Nuclear Security Administration

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) by Carbon-RichProtonAbout Us Hanford SiteRecovery Act ¬ĽRecovery Act

  2. Bioindicators for Monitoring Radioactive Pollution of the

    E-Print Network [OSTI]

    * IK s Dfc2looX|o RisÝ-R-443 Bioindicators for Monitoring Radioactive Pollution of the Marine-R-443 BIOINDICATORS FOR MONITORING RADIOACTIVE POLLUTION OF THE MARINE ENVIRONMENT Experiments Dahlgaard Abstract. Mussels (Mytilus edulis) are globally used as bio- indicators for pollution of coastal

  3. Road to Recovery: Bringing Recovery to Small Town America

    ScienceCinema (OSTI)

    Nettamo, Paivi

    2012-06-14

    The Recovery Act hits the road to reach out to surrounding towns of the Savannah River Site that are struggling with soaring unemployment rates. This project helps recruit thousands of people to new jobs in environmental cleanup at the Savannah River Site.

  4. Apparatus and method for radioactive waste screening

    DOE Patents [OSTI]

    Akers, Douglas W.; Roybal, Lyle G.; Salomon, Hopi; Williams, Charles Leroy

    2012-09-04

    An apparatus and method relating to screening radioactive waste are disclosed for ensuring that at least one calculated parameter for the measurement data of a sample falls within a range between an upper limit and a lower limit prior to the sample being packaged for disposal. The apparatus includes a radiation detector configured for detecting radioactivity and radionuclide content of the of the sample of radioactive waste and generating measurement data in response thereto, and a collimator including at least one aperture to direct a field of view of the radiation detector. The method includes measuring a radioactive content of a sample, and calculating one or more parameters from the radioactive content of the sample.

  5. Diverter assembly for radioactive material

    DOE Patents [OSTI]

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

    1988-04-11

    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.

  6. Recovery Act Federal Register Notices | Department of Energy

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

    a grant from the Department of Energy's Smart Grid Investment Grant (SGIG) Program. More Congressional Testimony Recovery Act Recovery Act Interoperability Recovery Act SGIG...

  7. Microsoft Word - Attachment 3 Recovery Act notification | Department...

    Energy Savers [EERE]

    Microsoft Word - Attachment 3 Recovery Act notification Microsoft Word - Attachment 3 Recovery Act notification More Documents & Publications Microsoft Word - Attachment 3 Recovery...

  8. Connecticut Recovery Act State Memo | Department of Energy

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

    Connecticut Recovery Act State Memo Connecticut Recovery Act State Memo The American Recovery & Reinvestment Act (ARRA) is making a meaningful downpayment on the nation's energy...

  9. Modeling, Estimation, and Control of Waste Heat Recovery Systems

    E-Print Network [OSTI]

    Luong, David

    2013-01-01

    System for Waste Heat Recovery. Ē Journal of Heat Transfer,Rankine cycle for waste heat recovery. Ē Energy, 29:1207ĖStrategy of Waste Heat Recovery Organic Rankine Cycles. Ē

  10. Radioactive Contamination Control Work Practices

    SciTech Connect (OSTI)

    WAGGONER, L.O.

    2002-10-01

    At Hanford, loose radioactive material can be found in plant systems, rooms, ventilation ducts, fuel pools, and outside radiological work facilities. Work practices used to accomplish radiological work in nuclear facilities often concern keeping radioactive contamination from spreading. This is not an easy task as the contamination activity levels can be very high and the material can be very unstable. Most of the time, the contamination is not visible, so we have to rely on surveys taken by Radiological Controls personnel to tell workers where the contamination is located and the activity levels present. The work practices used by workers are critical in controlling contamination spread, but it is impossible to document all of the work practices a worker should use. Many times, something will happen during the job that could result in a contamination spread. We rely on the workers knowledge and experience to realize when a potential spread of contamination is occurring, and take the actions necessary to prevent it from happening. It is important that a worker understand the concepts of contamination control in order to make the right decisions when work is accomplished. In facilities that work with ''fissile'' materials there is increased concern that nothing be done that increases the chance that a ''criticality accident'' might occur during work. Criticality safety personnel need to be consulted and approve contamination control practices that could increase the potential for a criticality accident. This Workshop includes a discussion of fundamental contamination control practices and new techniques used for radiological work. This is intended to be very informative and include hands-on exercises to provide the attendees with an appreciation of the methods being used to confine contamination spread.

  11. Integrated data base report--1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    SciTech Connect (OSTI)

    1997-12-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are reported as of the end of fiscal year (FY) 1996, which is September 30, 1996. Commercial SNF and commercial uranium mill tailings inventories are reported on an end-of-calendar year (CY) basis. All SNF and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are SNF, high-level waste, transuranic waste, low-level waste, uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through FY 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

  12. Implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

    SciTech Connect (OSTI)

    Stewart, L.; Tonkay, D.

    2004-10-03

    This paper discusses the implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The Joint Convention: establishes a commitment with respect to safe management of spent nuclear fuel and radioactive waste; requires the Parties to ''take appropriate steps'' to ensure the safety of their spent fuel and waste management activities, but does not delineate standards the Parties must meet; and seeks to attain, through its Contracting Parties, a higher level of safety with respect to management of their spent nuclear fuel, disused sealed sources, and radioactive waste.

  13. Biosurfactant and enhanced oil recovery

    DOE Patents [OSTI]

    McInerney, Michael J. (Norman, OK); Jenneman, Gary E. (Norman, OK); Knapp, Roy M. (Norman, OK); Menzie, Donald E. (Norman, OK)

    1985-06-11

    A pure culture of Bacillus licheniformis strain JF-2 (ATCC No. 39307) and a process for using said culture and the surfactant lichenysin produced thereby for the enhancement of oil recovery from subterranean formations. Lichenysin is an effective surfactant over a wide range of temperatures, pH's, salt and calcium concentrations.

  14. ENERGY RECOVERY COUNCIL WEEKLY UPDATE

    E-Print Network [OSTI]

    Columbia University

    Vincent Langone, vice president of Wheelabrator for the New York and Connecticut region. "Over the course of the first mobile app dedicated to Waste to Energy facilities. The new application "Waste2EnENERGY RECOVERY COUNCIL WEEKLY UPDATE June 21, 2013 WTE DEVELOPMENTS The U.S. Energy Department

  15. Promising Technology: Energy Recovery Ventilation

    Broader source: Energy.gov [DOE]

    Energy recovery ventilation (ERV) systems exchange heat between outgoing exhaust air and the incoming outdoor air. Using exhaust air to pre-condition supply air can reduce the capacity of the heating and cooling system and save heating and cooling energy consumption.

  16. Portsmouth Site Delivers First Radioactive Waste Shipment to...

    Office of Environmental Management (EM)

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

  17. The radioactive Substances (Testing Instruments) Exemption (Scotland)Order 1962†

    E-Print Network [OSTI]

    Noble, Michael

    1962-01-01

    STATUTORY INSTRUMENTS 1962 No. 2764 (S. 124) ATOMIC ENERGY AND RADIOACTIVE SUBSTANCES The Radioactive Substances (Testing instruments) Exemption (Scotland) Order 1962

  18. RESRAD Computer Code- Evaluation of Radioactively Contaminated Sites

    Office of Energy Efficiency and Renewable Energy (EERE)

    The evaluation of sites with radioactive contamination was a problem until the RESidual RADioactivity (RESRAD) Computer Code was first released in 1989.

  19. THRESHOLD RADIOACTIVITY FOR BULK FOOD SAMPLES BY GAMMA SPECTROSCOPY...

    Office of Scientific and Technical Information (OSTI)

    THRESHOLD RADIOACTIVITY FOR BULK FOOD SAMPLES BY GAMMA SPECTROSCOPY Citation Details In-Document Search Title: THRESHOLD RADIOACTIVITY FOR BULK FOOD SAMPLES BY GAMMA SPECTROSCOPY...

  20. Letter to Congress RE: Office of Civilian Radioactive Waste Management...

    Office of Environmental Management (EM)

    to Congress RE: Office of Civilian Radioactive Waste Management's Annual Financial Report Letter to Congress RE: Office of Civilian Radioactive Waste Management's Annual Financial...

  1. Geological Problems in Radioactive Waste Isolation: Second Worldwide Review

    E-Print Network [OSTI]

    2010-01-01

    Civilian Radioactive Waste Management Program Plan. DOE/RW-Civilian Radioactive Waste Management Program Plan. DraftBasis for Nuclear Waste Management X V I , Mat. Res. Soc.

  2. Geological challenges in radioactive waste isolation: Third worldwide review

    E-Print Network [OSTI]

    Witherspoon editor, P.A.; Bodvarsson editor, G.S.

    2001-01-01

    level radioactive waste disposal, 1993Ė1996, Annual Reportradioactive waste disposal programme, Nagra Technical ReportDisposal concepts for radioactive wastes, Final Report,

  3. Management Not Available 12 MANAGEMENT OF RADIOACTIVE AND NON...

    Office of Scientific and Technical Information (OSTI)

    87 Oak Ridge model conference: Proceedings: Volume I, Part 3, Waste Management Not Available 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 11...

  4. Automated intrusion recovery for web applications

    E-Print Network [OSTI]

    Chandra, Ramesh, Ph. D. Massachusetts Institute of Technology

    2013-01-01

    In this dissertation, we develop recovery techniques for web applications and demonstrate that automated recovery from intrusions and user mistakes is practical as well as effective. Web applications play a critical role ...

  5. Web Services for Recovery.gov

    E-Print Network [OSTI]

    Wilde, Erik; Kansa, Eric C; Yee, Raymond

    2009-01-01

    of Information Report 2009-035 Web Services for Recovery.govInformation Report 2009-035 Web Services for Recovery.gov [and Sam Ruby. RESTful Web Services. OíReilly & Associates,

  6. Multiwavelength all-optical clock recovery

    E-Print Network [OSTI]

    Johnson, C.; Demarest, Kenneth; Allen, Christopher Thomas; Hui, Rongqing; Peddanarappagari, K. V.; Zhu, B.

    1999-07-01

    Multiwavelength clock recovery is especially desirable in systems that use wavelength-division-multipleged technology. A multiwavelength clock-recovery device can greatly simplify costs by eliminating the need to have a separate regenerator for each...

  7. Heat Recovery Boilers for Process Applications†

    E-Print Network [OSTI]

    Ganapathy, V.; Rentz, J.; Flanagan, D.

    1985-01-01

    Heat recovery boilers are widely used in process plants for recovering energy from various waste gas streams, either from the consideration of process or of economy. Sulfuric, as well as nitric, acid plant heat recovery boilers are examples...

  8. District of Columbia Recovery Act State Memo

    Broader source: Energy.gov [DOE]

    The American Recovery & Reinvestment Act (ARRA) is making a meaningful down payment on the nationís energy and environmental future. The Recovery Act investments in the District of Columbia...

  9. Appendix 69 Bull Trout Draft Recovery Plan. Chapter 3: Clark Fork Recovery Unit

    E-Print Network [OSTI]

    Appendix 69 Bull Trout Draft Recovery Plan. Chapter 3: Clark Fork Recovery Unit #12;Chapter 3 State(s): Montana, Idaho, and Washington Recovery Unit Name: Clark Fork River (Including Lake Pend Oreille, Priest and Wildlife Service. 2002. Chapter 3, Clark Fork River Recovery Unit, Montana, Idaho, and Washington. 285 p. U

  10. Drain-Water Heat Recovery | Department of Energy

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

    Drain-Water Heat Recovery Drain-Water Heat Recovery June 15, 2012 - 6:20pm Addthis Diagram of a drain water heat recovery system. Diagram of a drain water heat recovery system. How...

  11. Radioactive anomaly discrimination from spectral ratios

    DOE Patents [OSTI]

    Maniscalco, James; Sjoden, Glenn; Chapman, Mac Clements

    2013-08-20

    A method for discriminating a radioactive anomaly from naturally occurring radioactive materials includes detecting a first number of gamma photons having energies in a first range of energy values within a predetermined period of time and detecting a second number of gamma photons having energies in a second range of energy values within the predetermined period of time. The method further includes determining, in a controller, a ratio of the first number of gamma photons having energies in the first range and the second number of gamma photons having energies in the second range, and determining that a radioactive anomaly is present when the ratio exceeds a threshold value.

  12. Airborne radioactive effluent study at the Savannah River Plant

    SciTech Connect (OSTI)

    Blanchard, R.L.; Broadway, J.A.; Sensintaffar, E.L.; Kirk, W.P.; Kahn, B.; Garrett, A.J.

    1984-07-01

    Under the Clean Air Act, Sections 112 and 122 as amended in 1977, the Office of Radiation Programs (OPR) of the United States Environmental Protection Agency is currently developing standards for radionuclides emitted to the air by several source categories. In order to confirm source-term measurements and pathway calculations for radiation exposures to humans offsite, the ORP performs field studies at selected facilities that emit radionuclides. This report describes the field study conducted at the Savannah River Plant (SRP), a laboratory operated by E.I. du Pont de Nemours and Company for the US Department of Energy. This purpose of the study at ARP was to verify reported airborne releases and resulting radiation doses from the facility. Measurements of radionuclide releases for brief periods were compared with measurements performed by SRP staff on split samples and with annual average releases reported by SRP for the same facilities. The dispersion model used by SRP staff to calculate radiation doses offsite was tested by brief environmental radioactivity measurements performed simultaneously with the release measurements, and by examining radioactivity levels in environmental samples. This report describes in detail all measurements made and data collected during the field study and presents the results obtained. 34 references, 18 figures, 49 tables.

  13. Effect of radioactivity decrease. Is there a link with solar flares?

    E-Print Network [OSTI]

    A. G. Parkhomov

    2010-05-15

    Results obtained with multichannel installation created for long-term studies of various processes, are collated with the data published by J.H. Jenkins and E.Fischbach, who found a decrease of 54Mn radioactivity near the time of series of solar flares between 5 and 17 December 2006. Analysis of the data from our installation in December 2006 has not revealed any deviations from the usual behaviour of the count rates for 90Sr-90Y, 60Co and 239Pu sources. The same can be said of the data collected during the period of highly powerful solar flares between 19 October and 4 November 2003. Apparent drops in the count rate were detected between 10 and 12 May 2002 while registering the activity of 60Co and on 19 and 20 June 2004 for 90Sr-90Y source. Around the time of these events, no observations of large solar flares were reported. Thus, proposed link between the drop in the rates of radioactive decay and appearance of solar flares could not be confirmed. From obtained outcomes follows, that the radioactivity drop effect, if it really exists, is rather rare, and that the reason calling this effect unequally influences various radioactive sources.

  14. Management of Disused Sealed Sources in Hungary - 13077

    SciTech Connect (OSTI)

    Kapitany, Sandor

    2013-07-01

    Since 1976 the spent and disused radioactive sources arisen in Hungary are stored in a central storage facility called Radioactive Waste Treatment and Disposal Facility operated by Public Limited Company for Radioactive Waste Management. The Facility is responsible for the record keeping, the waste acceptance procedure, the shipment and the storage or disposal (whether a certain source meets the waste acceptance criteria for disposal or not) of sources. Based on the more than 35 year old operation of the facility many experiences have been gathered regarding the technology for long-term storage of sources, the attitude of the users of sources, the evolution of the legislation and the national record keeping system. Recently a new legislation for the security of radioactive materials (including sources) was introduced, first in Central-Europe. It requires special security arrangements from the facility for transport and for storage. Due to the ongoing retrieval of radioactive waste formerly disposed of, partly containing sealed sources, there is a new challenge in the physical inventory control of historical waste. The paper would show the effect of the changes in the legislation system of record keeping or security on the users' attitude for discard of sources and on the management of the sources in the facility. The facility has a unique storage technology (shallow boreholes) in the narrow region. The sealed sources are placed into vertical pipes sunk into the surface. In the beginning, each of the sources were dropped into the pipe directly, recently they are placed in a metal tube first ensuring the retrieval. The lessons learned will be presented. There were several issues to introduce the new security arrangements (partly financially supported by US DOE) for storage and for transportation of sealed sources. These issues are addressed. In the past part of the sealed sources were disposed together with solid radioactive waste packaged in plastic bags. A waste retrieval campaign was fulfilled in 2008 to retrieve the sealed sources. The paper demonstrates the conditions of sealed sources after twenty-year disposal period. As a summary, the paper will share the main experiences of a 35-year old facility, managing radioactive sealed sources in Central Europe. (authors)

  15. Engine breather oil recovery system

    SciTech Connect (OSTI)

    Speer, S.R.; Norton, J.G.; Wilson, J.D.

    1990-08-14

    This patent describes an engine breather oil recovery system, for use with reciprocating engines having an oil breather and an oil reservoir recovery system. It comprises:an engine breather outlet from the engine; a vapor and oil separator device in fluid flow connection with the engine breather outlet; a motive flow suction means in fluid flow connection between the separator device and the engine, so as to provide a substantially continuous pressure drop between the separator device and the engine oil reservoir; an engine fluid system in parallel with the separator device; and an engine driven pump in fluid flow connection with such other engine fluid system, wherein the motive force for the motive flow suction means is provided by the fluid from the engine pump.

  16. Principles for Sampling Airborne Radioactivity from Stacks

    SciTech Connect (OSTI)

    Glissmeyer, John A.

    2010-10-18

    This book chapter describes the special processes involved in sampling the airborne effluents from nuclear faciities. The title of the book is Radioactive Air Sampling Methods. The abstract for this chapter was cleared as PNNL-SA-45941.

  17. CRAD, NNSA- Radioactive Waste Management Program (RW)

    Broader source: Energy.gov [DOE]

    CRAD for Radioactive Waste Management Program (RW). Criteria Review and Approach Documents (CRADs) that can be used to conduct a well-organized and thorough assessment of elements of safety and health programs.

  18. Recovery Act State Memos Tennessee

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Financing Tool FitsProject Developsfor UCNIEnvironmental Impact StatementRecovery Act Smart

  19. Recovery Act State Memos California

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankADVANCED MANUFACTURINGEnergy BillsNo. 195 - Oct. 7,DOERTI | Department8Recovery ActCalifornia For

  20. Vitrification of hazardous and radioactive wastes

    SciTech Connect (OSTI)

    Bickford, D.F.; Schumacher, R.

    1995-12-31

    Vitrification offers many attractive waste stabilization options. Versatility of waste compositions, as well as the inherent durability of a glass waste form, have made vitrification the treatment of choice for high-level radioactive wastes. Adapting the technology to other hazardous and radioactive waste streams will provide an environmentally acceptable solution to many of the waste challenges that face the public today. This document reviews various types and technologies involved in vitrification.

  1. Transport of Radioactive Material by Alpha Recoil

    SciTech Connect (OSTI)

    Icenhour, A.S.

    2005-05-19

    The movement of high-specific-activity radioactive particles (i.e., alpha recoil) has been observed and studied since the early 1900s. These studies have been motivated by concerns about containment of radioactivity and the protection of human health. Additionally, studies have investigated the potential advantage of alpha recoil to effect separations of various isotopes. This report provides a review of the observations and results of a number of the studies.

  2. Radioactive Waste Conditioning, Immobilisation, And Encapsulation Processes And Technologies: Overview And Advances (Chapter 7)

    SciTech Connect (OSTI)

    Jantzen, Carol M.; Lee, William E.; Ojovan, Michael I.

    2012-10-19

    The main immobilization technologies that are available commercially and have been demonstrated to be viable are cementation, bituminization, and vitrification. Vitrification is currently the most widely used technology for the treatment of high level radioactive wastes (HLW) throughout the world. Most of the nations that have generated HLW are immobilizing in either alkali borosilicate glass or alkali aluminophosphate glass. The exact compositions of nuclear waste glasses are tailored for easy preparation and melting, avoidance of glass-in-glass phase separation, avoidance of uncontrolled crystallization, and acceptable chemical durability, e.g., leach resistance. Glass has also been used to stabilize a variety of low level wastes (LLW) and mixed (radioactive and hazardous) low level wastes (MLLW) from other sources such as fuel rod cladding/decladding processes, chemical separations, radioactive sources, radioactive mill tailings, contaminated soils, medical research applications, and other commercial processes. The sources of radioactive waste generation are captured in other chapters in this book regarding the individual practices in various countries (legacy wastes, currently generated wastes, and future waste generation). Future waste generation is primarily driven by interest in sources of clean energy and this has led to an increased interest in advanced nuclear power production. The development of advanced wasteforms is a necessary component of the new nuclear power plant (NPP) flowsheets. Therefore, advanced nuclear wasteforms are being designed for robust disposal strategies. A brief summary is given of existing and advanced wasteforms: glass, glass-ceramics, glass composite materials (GCMís), and crystalline ceramic (mineral) wasteforms that chemically incorporate radionuclides and hazardous species atomically in their structure. Cementitious, geopolymer, bitumen, and other encapsulant wasteforms and composites that atomically bond and encapsulate wastes are also discussed. The various processing technologies are cross-referenced to the various types of wasteforms since often a particular type of wasteform can be made by a variety of different processing technologies.

  3. Nevada Test Site 2007 Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2008-01-01

    This report is a compilation of the groundwater sampling results from three monitoring wells located near the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), Nye County, Nevada, for calendar year 2007. The NTS is an approximately 3,561 square kilometer (1,375 square mile) restricted-access federal installation located approximately 105 kilometers (65 miles) northwest of Las Vegas, Nevada (Figure 1). Pilot wells UE5PW-1, UE5PW-2, and UE5PW-3 are used to monitor the groundwater at the Area 5 RWMS (Figure 2). In addition to groundwater monitoring results, this report includes information regarding site hydrogeology, well construction, sample collection, and meteorological data measured at the Area 5 RWMS. The disposal of low-level radioactive waste and mixed low-level radioactive waste at the Area 5 RWMS is regulated by U.S. Department of Energy (DOE) Order 435.1, 'Radioactive Waste Management'. The disposal of mixed low-level radioactive waste is also regulated by the state of Nevada under the Resource Conservation and Recovery Act (RCRA) regulation Title 40 Code of Federal Regulations (CFR) Part 265, 'Interim Status Standards for Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities' (CFR, 1999). The format of this report was requested by the Nevada Division of Environmental Protection (NDEP) in a letter dated August 12, 1997. The appearance and arrangement of this document have been modified slightly since that date to provide additional information and to facilitate the readability of the document. The objective of this report is to satisfy any Area 5 RWMS reporting agreements between DOE and NDEP.

  4. Small plasma focus as neutron pulsed source for nuclides identification

    SciTech Connect (OSTI)

    Milanese, M.; Moroso, R.; Barbaglia, M.; Universidad del Centro de la Provincia de Buenos Aires , Pinto 399, Tandil 7000, Buenos Aires ; Niedbalski, J.; Mayer, R.; Castillo, F.

    2013-10-15

    In this paper, we present preliminary results on the feasibility of employing a low energy (2 kJ, 31 kV) plasma focus device as a portable source of pulsed neutron beams (2.45 MeV) generated by nuclear fusion reactions D-D, for the ďin situĒ analysis of substances by nuclear activation. This source has the relevant advantage of being pulsed at requirement, transportable, not permanently radioactive, without radioactive waste, cheap, among others. We prove the feasibility of using this source showing several spectra of the characteristic emission line for manganese, gold, lead, and silver.

  5. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    SciTech Connect (OSTI)

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi; Cochran, John R.

    2013-07-01

    Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning Directorate (IDD) is responsible for decommissioning activities. The IDD and the RWTMD work together on decommissioning projects. The IDD has developed plans and has completed decommissioning of the GeoPilot Facility in Baghdad and the Active Metallurgical Testing Laboratory (LAMA) in Al-Tuwaitha. Given this experience, the IDD has initiated work on more dangerous facilities. Plans are being developed to characterize, decontaminate and decommission the Tamuz II Research Reactor. The Tammuz Reactor was destroyed by an Israeli air-strike in 1981 and the Tammuz II Reactor was destroyed during the First Gulf War in 1991. In addition to being responsible for managing the decommissioning wastes, the RWTMD is responsible for more than 950 disused sealed radioactive sources, contaminated debris from the first Gulf War and (approximately 900 tons) of naturally-occurring radioactive materials wastes from oil production in Iraq. The RWTMD has trained staff, rehabilitated the Building 39 Radioactive Waste Storage building, rehabilitated portions of the French-built Radioactive Waste Treatment Station, organized and secured thousands of drums of radioactive waste organized and secured the stores of disused sealed radioactive sources. Currently, the IDD and the RWTMD are finalizing plans for the decommissioning of the Tammuz II Research Reactor. (authors)

  6. Texas State Briefing Book for low-level radioactive waste management

    SciTech Connect (OSTI)

    Not Available

    1981-08-01

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

  7. RADIOACTIVE WASTE DISPOSAL PROCEDURES 1. Radioactive waste is accepted for disposal by Radiation Safety on Monday, Wednesday and

    E-Print Network [OSTI]

    Hammack, Richard

    attire including lab coats when transporting radioactive waste. LABS OUTSIDE SANGER HALL 1RADIOACTIVE WASTE DISPOSAL PROCEDURES 1. Radioactive waste is accepted for disposal by Radiation are required and may be scheduled by calling 8289131. 2. Segregate and package radioactive waste according

  8. Management of Low-Level Radioactive Waste from Research, Hospitals and Nuclear Medical Centers in Egypt - 13469

    SciTech Connect (OSTI)

    Hasan, M.A.; Selim, Y.T.; Lasheen, Y.F.

    2013-07-01

    The application of radioisotopes and radiation sources in medical diagnosis and therapy is an important issue. Physicians can use radioisotopes to diagnose and treat diseases. Methods of treatment, conditioning and management of low level radioactive wastes from the use of radiation sources and radioisotopes in hospitals and nuclear medicine application, are described. Solid Radioactive waste with low-level activity after accumulation, minimization, segregation and measurement, are burned or compressed in a compactor according to the international standards. Conditioned drums are transported to the interim storage site at the Egyptian Atomic Energy Authority (EAEA) represented in Hot Labs and Waste Management Center (HLWMC) for storage and monitoring. (authors)

  9. Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

    SciTech Connect (OSTI)

    1995-09-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

  10. CHAPTER 5-RADIOACTIVE WASTE MANAGEMENT

    SciTech Connect (OSTI)

    Marra, J.

    2010-05-05

    The ore pitchblende was discovered in the 1750's near Joachimstal in what is now the Czech Republic. Used as a colorant in glazes, uranium was identified in 1789 as the active ingredient by chemist Martin Klaproth. In 1896, French physicist Henri Becquerel studied uranium minerals as part of his investigations into the phenomenon of fluorescence. He discovered a strange energy emanating from the material which he dubbed 'rayons uranique.' Unable to explain the origins of this energy, he set the problem aside. About two years later, a young Polish graduate student was looking for a project for her dissertation. Marie Sklodowska Curie, working with her husband Pierre, picked up on Becquerel's work and, in the course of seeking out more information on uranium, discovered two new elements (polonium and radium) which exhibited the same phenomenon, but were even more powerful. The Curies recognized the energy, which they now called 'radioactivity,' as something very new, requiring a new interpretation, new science. This discovery led to what some view as the 'golden age of nuclear science' (1895-1945) when countries throughout Europe devoted large resources to understand the properties and potential of this material. By World War II, the potential to harness this energy for a destructive device had been recognized and by 1939, Otto Hahn and Fritz Strassman showed that fission not only released a lot of energy but that it also released additional neutrons which could cause fission in other uranium nuclei leading to a self-sustaining chain reaction and an enormous release of energy. This suggestion was soon confirmed experimentally by other scientists and the race to develop an atomic bomb was on. The rest of the development history which lead to the bombing of Hiroshima and Nagasaki in 1945 is well chronicled. After World War II, development of more powerful weapons systems by the United States and the Soviet Union continued to advance nuclear science. It was this defense application that formed the basis for the commercial nuclear power industry.

  11. American Recovery and Reinvestment Act

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 OutreachProductswsicloudwsiclouddenDVA N C E D B L O O D S TAPropaneand Los Alamos NationalAmerican Recovery

  12. Heat recovery | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QAsource History View NewTexas: Energy Resources Jump to: navigation, search Equivalent|CornHeat recovery Jump to:

  13. Recovery Act State Memos Nevada

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankADVANCED MANUFACTURINGEnergy BillsNo. 195 - Oct. 7,DOERTI | Department8Recovery ActCalifornia ForNevada

  14. Recovery Act | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative FuelsofProgram: Report Appendices |ProjectKnow YourDepartment ofAugustPastRecovery Act

  15. Recovery from chemical, biological, and radiological incidents :

    SciTech Connect (OSTI)

    Franco, David Oliver; Yang, Lynn I.; Hammer, Ann E.

    2012-06-01

    To restore regional lifeline services and economic activity as quickly as possible after a chemical, biological or radiological incident, emergency planners and managers will need to prioritize critical infrastructure across many sectors for restoration. In parallel, state and local governments will need to identify and implement measures to promote reoccupation and economy recovery in the region. This document provides guidance on predisaster planning for two of the National Disaster Recovery Framework Recovery Support Functions: Infrastructure Systems and Economic Recovery. It identifies key considerations for infrastructure restoration, outlines a process for prioritizing critical infrastructure for restoration, and identifies critical considerations for promoting regional economic recovery following a widearea disaster. Its goal is to equip members of the emergency preparedness community to systematically prioritize critical infrastructure for restoration, and to develop effective economic recovery plans in preparation for a widearea CBR disaster.

  16. Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513

    SciTech Connect (OSTI)

    Mohamed, Yasser T. [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)] [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)

    2013-07-01

    The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Center has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)

  17. Criteria and Processes for the Certification of Non-Radioactive Hazardous and Non-Hazardous Wastes

    SciTech Connect (OSTI)

    Dominick, J

    2008-12-18

    This document details Lawrence Livermore National Laboratory's (LLNL) criteria and processes for determining if potentially volumetrically contaminated or potentially surface contaminated wastes are to be managed as material containing residual radioactivity or as non-radioactive. This document updates and replaces UCRL-AR-109662, Criteria and Procedures for the Certification of Nonradioactive Hazardous Waste (Reference 1), also known as 'The Moratorium', and follows the guidance found in the U.S. Department of Energy (DOE) document, Performance Objective for Certification of Non-Radioactive Hazardous Waste (Reference 2). The 1992 Moratorium document (UCRL-AR-109662) is three volumes and 703 pages. The first volume provides an overview of the certification process and lists the key radioanalytical methods and their associated Limits of Sensitivities. Volumes Two and Three contain supporting documents and include over 30 operating procedures, QA plans, training documents and organizational charts that describe the hazardous and radioactive waste management system in place in 1992. This current document is intended to update the previous Moratorium documents and to serve as the top-tier LLNL institutional Moratorium document. The 1992 Moratorium document was restricted to certification of Resource Conservation and Recovery Act (RCRA), State and Toxic Substances Control Act (TSCA) hazardous waste from Radioactive Material Management Areas (RMMA). This still remains the primary focus of the Moratorium; however, this document increases the scope to allow use of this methodology to certify other LLNL wastes and materials destined for off-site disposal, transfer, and re-use including non-hazardous wastes and wastes generated outside of RMMAs with the potential for DOE added radioactivity. The LLNL organization that authorizes off-site transfer/disposal of a material or waste stream is responsible for implementing the requirements of this document. The LLNL Radioactive and Hazardous Waste Management (RHWM) organization is responsible for the review and maintenance of this document. It should be noted that the DOE metal recycling moratorium is still in effect and is implemented as outlined in reference 17 when metals are being dispositioned for disposal/re-use/recycling off-site. This document follows the same methodology as described in the previously approved 1992 Moratorium document. Generator knowledge and certification are the primary means of characterization. Sampling and analysis are used when there is insufficient knowledge of a waste to determine if it contains added radioactivity. Table 1 (page 12) presents a list of LLNL's analytical methods for evaluating volumetrically contaminated waste and updates the reasonably achievable analytical-method-specific Minimum Detectable Concentrations (MDCs) for various matrices. Results from sampling and analysis are compared against the maximum MDCs for the given analytical method and the sample specific MDC to determine if the sample contains DOE added volumetric radioactivity. The evaluation of an item that has a physical form, and history of use, such that accessible surfaces may be potentially contaminated, is based on DOE Order 5400.5 (Reference 3), and its associated implementation guidance document DOE G 441.1-XX, Control and Release of Property with Residual Radioactive Material (Reference 4). The guidance document was made available for use via DOE Memorandum (Reference 5). Waste and materials containing residual radioactivity transferred off-site must meet the receiving facilities Waste Acceptance Criteria (if applicable) and be in compliance with other applicable federal or state requirements.

  18. Recovery Act Progress Update: Reactor Closure Feature

    SciTech Connect (OSTI)

    Cody, Tom

    2010-01-01

    A Recovery Act Progress Update. Decommissioning of two nuclear reactor sites at the Department of Energy's facilities has been approved and is underway.

  19. Faces of the Recovery Act: 1366 Technologies

    Broader source: Energy.gov [DOE]

    LEXINGTON, MA - At 1366 Technologies, Ely Sachs and Frank van Mierlo are using ARPA-E Recovery Act funding to dramatically reduce the costs of solar panel production.

  20. Bioelectrochemical Integration of Waste Heat Recovery, Waste...

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

    - Allentown, PA A microbial reverse electrodialysis technology will be combined with waste heat recovery to convert effluents into electricity and chemical products, including...

  1. American Recovery and Reinvestment Act Accelerated Milestones

    Office of Environmental Management (EM)

    RECOVERY PROJECT OR ACTIVITY ACCELERATED MILESTONE TITLE MILESTONE DUE DATE EXPECTED ACCELERATED COMPLETION DATE WITH ARRA FUNDING STATUS INL - Cleanup of Surplus Nuclear...

  2. Faces of the Recovery Act: Sun Catalytix

    Broader source: Energy.gov [DOE]

    At the Massachusetts Institute of Technology, Dan Nocera talks about Sun Catalytix, the next generation of solar energy, and ARPA-E funding through the Recovery Act.

  3. Industrial Plate Exchangers Heat Recovery and Fouling†

    E-Print Network [OSTI]

    Cross, P. H.

    1981-01-01

    Plate and Frame Heat Exchangers have special characteristics for both fouling and heat recovery. These are discussed in general then related to two industrial examples....

  4. Recovery News Flashes | Department of Energy

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

    June 7, 2011 Recovery Act Supports Construction of Site's Largest Groundwater Treatment Facility Construction of the largest groundwater treatment facility at the Hanford Site...

  5. Recovery Act Progress Update: Reactor Closure Feature

    ScienceCinema (OSTI)

    Cody, Tom

    2012-06-14

    A Recovery Act Progress Update. Decommissioning of two nuclear reactor sites at the Department of Energy's facilities has been approved and is underway.

  6. Ion source

    DOE Patents [OSTI]

    Leung, Ka-Ngo (Hercules, CA); Ehlers, Kenneth W. (Alamo, CA)

    1984-01-01

    A magnetic filter for an ion source reduces the production of undesired ion species and improves the ion beam quality. High-energy ionizing electrons are confined by the magnetic filter to an ion source region, where the high-energy electrons ionize gas molecules. One embodiment of the magnetic filter uses permanent magnets oriented to establish a magnetic field transverse to the direction of travel of ions from the ion source region to the ion extraction region. In another embodiment, low energy 16 eV electrons are injected into the ion source to dissociate gas molecules and undesired ion species into desired ion species.

  7. Brushing up on oil recovery

    SciTech Connect (OSTI)

    Mackey, J.

    1995-12-01

    To be prepared for a range of oil spills, emergency response organizations must have an arsenal of powerful and adaptable equipment. Around the coastal United States, a network of oil spill cooperatives and emergency response organizations stand ready with the technology and the know-how to respond to the first sign of an oil spill. When the telephone rings, they may be required to mop up 200 gallons of oil that leaked off the deck of a ship or to contain and skim 2,000 gallons of oil from a broken hose at a loading terminal. In a few cases each year, they may find themselves responding to a major pollution incident, one that involves hundreds of people and tons of equipment. To clean an oil spill at a New Jersey marine terminal, the local cooperative used the Lundin Oil Recovery Inc. (LORI) skimming system to separate the oil and water and the lift the oil out of the river. The LORI skimming technology is based on sound principles of fluid management - using the natural movement of water instead of trying to fight against it. A natural feeding mechanism delivers oily water through the separation process, and a simple mechanical separation and recovery device - a brush conveyor - removes the pollutants from the water.

  8. Effects of fracturing fluid recovery upon well performance and ultimate recovery of hydraulically fractured gas wells†

    E-Print Network [OSTI]

    Berthelot, Jan Marie

    1990-01-01

    EFFECTS OF FRACTURING FLUID RECOVERY UPON WELL PERFORMANCE AND ULTIMATE RECOVERY OF HYDRAULICALLY FRACTURED GAS WELLS A Thesis IAN MARIE BERTHELOT Submitted to the Office of Graduate Studies of Texas AdtM University in partial fulfillment... of the requirements for the degree of MASTER OF SCIENCE May 1990 Major Subject: Petroleum Engineering EFFECTS OF FRACTURING FLUID RECOVERY UPON WELL PERFORMANCE AND ULTIMATE RECOVERY OF HYDRAULICALLY FRACTURED GAS WELLS by JAN MARIE BERTIIELOT Appmved...

  9. Radioactive tank waste remediation focus area

    SciTech Connect (OSTI)

    1996-08-01

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

  10. Wide range radioactive gas concentration detector

    DOE Patents [OSTI]

    Anderson, David F. (Los Alamos, NM)

    1984-01-01

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

  11. ECR Ion Source Developments at the Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Alton, G.D.; Liu, Y.; Meyer, F.W.

    1998-10-05

    New techniques for enhancing the performances of electron cyclotron resonance (ECR) ion sources are being investigated at the Oak Ridge National Laboratory. We have utilized the multiple discrete frequency technique to improve the charge state distributions extracted from conventional magnetic field geometry ECR source by injecting three frequencies into the source. A new flat central magnetic field concept, has been incorporated in the designs of a compact all-permanent-magnet source for high charge-state ion beam generation and a compact electromagnetic source for singly ionized radioactive ion beam generation for use in the Holifield Radioactive Ion Beam Facility (HRIBF) research program. A review of the three frequency injection experiments and descriptions of the design aspects of the "volume-type" ECR ion sources will be given in this report.

  12. Advanced Burners and Combustion Controls for Industrial Heat Recovery Systems†

    E-Print Network [OSTI]

    Ferri, J. L.

    1988-01-01

    stream_source_info ESL-IE-88-09-52.pdf.txt stream_content_type text/plain stream_size 10271 Content-Encoding ISO-8859-1 stream_name ESL-IE-88-09-52.pdf.txt Content-Type text/plain; charset=ISO-8859-1 ADVANCED BURNERS... AND COMBUSTION CONTROLS FOR INDUSTRIAL HEAT RECOVERY SYSTEMS J.L.FERRI GTE PRODUCTS CORPORATION TOWANDA, PA ABSTRACT When recuperators are installed on indus trial furnaces, burners and ratio control systems must continue to operate reliably under a...

  13. Heat Recovery From Arc Furnaces Using Water Cooled Panels†

    E-Print Network [OSTI]

    Darby, D. F.

    1987-01-01

    located on the intake air side of the gas burners. From the heat/vent units, the glycol is re turned via the glycol return piping (GWHR) to the secondary side of the water to glycol heat exchanger HE-I, and then back to the surge tank. The system... stream_source_info ESL-IE-87-09-17.pdf.txt stream_content_type text/plain stream_size 21344 Content-Encoding ISO-8859-1 stream_name ESL-IE-87-09-17.pdf.txt Content-Type text/plain; charset=ISO-8859-1 HEAT RECOVERY FROM...

  14. Radioisotopes for heat-source applications

    SciTech Connect (OSTI)

    Hoisington, J.E.

    1982-10-06

    Potential DOD requirements for noninterruptable power sources could total 1 MW thermal by FY 1990. Of the three isotopes considered, (/sup 90/Sr, /sup 147/Pm, /sup 238/Pu) /sup 90/Sr is the only one available in sufficient amounts to meet this requirement. To meet the DOD FY 1990 requirements, it would be necessary to undertake /sup 90/Sr recovery operations from spent fuel reprocessing at SRP, Hanford, and the Barnwell Nuclear Fuels Plant (BNFP). /sup 90/Sr recovery from the existing alkaline high level waste (HLW) at Hanford and SRP is not attractive because the isotopic purity of the /sup 90/Sr is below that required for DOD applications. Without reprocessing LWR spent fuel, SRP and Hanford could not supply the demand of 1 MW thermal until FY 1996. Between FY 1983 and FY 1996, SRP and Hanford could supply approximately 0.70 MW of /sup 90/Sr and 0.15 MW of /sup 147/Pm. SRP could supply an additional 0.15 MW from the production and recovery of /sup 238/Pu. Strontium-90 is the most economical of the three heat source radionuclides considered. The /sup 90/Sr unit recovery cost from SRP fresh acid waste would be $180/watt. The BNFP /sup 90/Sr recovery cost would be $130/watt to $235/watt depending on the age and burnup of the LWR spent fuel. Hanford /sup 90/Sr recovery costs form Purex fresh acid waste are unavailable, but they are expected to be comparable to the SRP costs. /sup 147/Pm and /sup 238/Pu are considerably more expensive heat source materials. /sup 147/Pm recovery costs at SRP are estimated to be $450/watt. As with /sup 90/Sr, the Hanford /sup 147/Pm recovery costs are expected to be comparabl to the SRP costs. Production of high assay (93.5%) /sup 238/Pu at SRP from excess /sup 231/Np would cost about $1160/watt, while recovery of low assay (27%) /sup 238/Pu from the waste stream is estimated at $1850/watt.

  15. RESRAD-BUILD: A computer model for analyzing the radiological doses resulting from the remediation and occupancy of buildings contaminated with radioactive material

    SciTech Connect (OSTI)

    Yu, C.; LePoire, D.J.; Jones, L.G. [and others

    1994-11-01

    The RESRAD-BUILD computer code is a pathway analysis model designed to evaluate the potential radiological dose incurred by an individual who works or lives in a building contaminated with radioactive material. The transport of radioactive material inside the building from one compartment to another is calculated with an indoor air quality model. The air quality model considers the transport of radioactive dust particulates and radon progeny due to air exchange, deposition and resuspension, and radioactive decay and ingrowth. A single run of the RESRAD-BUILD code can model a building with up to: three compartments, 10 distinct source geometries, and 10 receptor locations. A shielding material can be specified between each source-receptor pair for external gamma dose calculations. Six exposure pathways are considered in the RESRAD-BUILD code: (1) external exposure directly from the source; (2) external exposure to materials deposited on the floor; (3) external exposure due to air submersion; (4) inhalation of airborne radioactive particulates; (5) inhalation of aerosol indoor radon progeny; and (6) inadvertent ingestion of radioactive material, either directly from the sources or from materials deposited on the surfaces of the building compartments. 4 refs., 23 figs., 4 tabs.

  16. Pump station for radioactive waste water

    DOE Patents [OSTI]

    Whitton, John P.; Klos, Dean M.; Carrara, Danny T.; Minno, John J.

    2003-11-18

    A pump station for transferring radioactive particle containing waste water, includes: (a.) an enclosed sump having a vertically elongated right frusto conical wall surface and a bottom surface and (b.) a submersible volute centrifugal pump having a horizontally rotating impeller and a volute exterior surface. The sump interior surface, the bottom surface and the volute exterior surface are made of stainless steel having a 30 Ra or finer surface finish. A 15 Ra finish has been found to be most cost effective. The pump station is used for transferring waste water, without accumulation of radioactive fines.

  17. Radioactivity and health: A history

    SciTech Connect (OSTI)

    Stannard, J.N.; Baalman, R.W. Jr.

    1988-10-01

    This book is designed to be primarily a history of research facts, measurements, and ideas and the people who developed them. ''Research'' is defined very broadly to include from bench-top laboratory experiments to worldwide environmental investigations. The book is not a monograph or a critical review. The findings and conclusions are presented largely as the investigators saw and reported them. Frequently, the discussion utilizes the terminology and units of the time, unless they are truly antiquated or potentially unclear. It is only when the work being reported is markedly iconoclastic or obviously wrong that I chose to make special note of it or to correct it. Nevertheless, except for direct quotations, the language is mine, and I take full responsibility for it. The working materials for this volume included published papers in scientific journals, books, published conferences and symposia, personal interviews with over 100 individuals, some of them more than once (see Appendix A), and particularly for the 1940--1950 decade and for the large government-supported laboratories to the present day, ''in-house'' reports. These reports frequently represent the only comprehensive archive of what was done and why. Unfortunately, this source is drying up because of storage problems and must be retrieved by ever more complex and inconvenient means. For this reason, special efforts have been taken to review and document these sources, though even now some sections of the field are partially inaccessible. Nevertheless, the volume of all materials available for this review was surprisingly large and the quality much better than might have been expected for so complex and disparate a fields approached under conditions of considerable urgency.

  18. RESEARCH OIL RECOVERY MECHANISMS IN HEAVY OIL RESERVOIRS

    SciTech Connect (OSTI)

    Anthony R. Kovscek; William E. Brigham

    1999-06-01

    The United States continues to rely heavily on petroleum fossil fuels as a primary energy source, while domestic reserves dwindle. However, so-called heavy oil (10 to 20{sup o}API) remains an underutilized resource of tremendous potential. Heavy oils are much more viscous than conventional oils. As a result, they are difficult to produce with conventional recovery methods such as pressure depletion and water injection. Thermal recovery is especially important for this class of reservoirs because adding heat, usually via steam injection, generally reduces oil viscosity dramatically. This improves displacement efficiency. The research described here was directed toward improved understanding of thermal and heavy-oil production mechanisms and is categorized into: (1) flow and rock properties; (2) in-situ combustion; (3) additives to improve mobility control; (4) reservoir definition; and (5) support services. The scope of activities extended over a three-year period. Significant work was accomplished in the area of flow properties of steam, water, and oil in consolidated and unconsolidated porous media, transport in fractured porous media, foam generation and flow in homogeneous and heterogeneous porous media, the effects of displacement pattern geometry and mobility ratio on oil recovery, and analytical representation of water influx. Significant results are described.

  19. Assessment of central receiver solar thermal enhanced oil recovery systems

    SciTech Connect (OSTI)

    Gorman, D.N.

    1987-07-01

    In November 1982, ARCO Solar, Incorporated, with the cooperation of ARCO Oil and Gas Company, completed installation and began operation of a central receiver solar thermal pilot plant to produce steam for enhanced oil recovery. The highly automated plant can produce approximately one megawtt of thermal power in the form of 80% quality steam, which is delivered to a distribution header for injection into heavy oil formations. An engineering evaluation of data from the ARCO plant has been performed, with the conclusion that central receiver solar systems can be very effective sources of power to generate steam for the enhanced recovery of heavy oil. The highly automated pilot plant exhibited outstanding reliability of the solar power conversion components while operating routinely with a single attendant, demonstrating the capability for very low operating and maintenance costs for these systems relative to the use of conventional oil-burning steam generators. This document reports the operating and performance characteristics of the ARCO solar thermal enhanced oil recovery (STEOR) system over a full year of operation. System sizing and performance projection for a much larger commercial plant is also presented.

  20. Enhancing Low-Grade Thermal Energy Recovery in a Thermally Regenerative Ammonia Battery Using

    E-Print Network [OSTI]

    Enhancing Low-Grade Thermal Energy Recovery in a Thermally Regenerative Ammonia Battery Using of renewable energy that is carbon neutral and sustainable.[1] Low-grade thermal energy from either industrial processes or natural solar or geothermal pro- cesses becomes attractive as a possible energy source because

  1. Nonlinear inverse problem for a model of ion-exchange filter: numerical recovery of parameters

    E-Print Network [OSTI]

    methods of ion exchange is based on passing of source water or partially treated water through a filter-exchange filters results in highly mineralized, acidic and alkaline waste water [9]. With the continuous1 Nonlinear inverse problem for a model of ion-exchange filter: numerical recovery of parameters

  2. Recovery Act Special Provisions Leased Subcontract UT-B Contracts Div Page 1 of 3

    E-Print Network [OSTI]

    of evidence of a false claim to the Inspector General. (1) Definitions For purposes of this clause, "Covered funding as necessary to complete projects, but tracking and reporting must be separate to meet the reporting requirements of the Recovery Act and related Guidance. For projects funded by sources other than

  3. Optimize carbon dioxide sequestration, enhance oil recovery

    E-Print Network [OSTI]

    - 1 - Optimize carbon dioxide sequestration, enhance oil recovery January 8, 2014 Los Alamos simulation to optimize carbon dioxide (CO2) sequestration and enhance oil recovery (CO2-EOR) based on known production. Due to carbon capture and storage technology advances, prolonged high oil prices

  4. Faces of the Recovery Act: Sun Catalytix

    ScienceCinema (OSTI)

    Nocera, Dave

    2013-05-29

    BOSTON- At the Massachusetts Institute of Technology, Dan Nocera talks about Sun Catalytix, the next generation of solar energy, and ARPA-E funding through the Recovery Act. To learn about more ARPA-E projects through the Recovery Act: http://arpa-e.energy.gov/FundedProjects.aspx

  5. New waste-heat-recovery units introduced

    SciTech Connect (OSTI)

    Not Available

    1982-09-13

    Three new entries in the waste-heat-recovery system market are introduced by JMC Energy Inc., National Energy Savers Products, and North American Manufacturing Co. There is a brief description of each unit's design, application, and cost. A directory lists 138 major manufacturers of waste-heat-recovery systems. (DCK)

  6. Learning Dynamic Arm Motions for Postural Recovery

    E-Print Network [OSTI]

    Massachusetts at Amherst, University of

    Learning Dynamic Arm Motions for Postural Recovery Scott Kuindersma, Roderic Grupen, Andrew Barto}@cs.umass.edu Abstract--The biomechanics community has recently made progress toward understanding the role of rapid arm of arm recovery motions in humans and experimentally demonstrate advantages of this behavior

  7. Know Your Rights Under the Recovery Act!

    E-Print Network [OSTI]

    Rock, Chris

    by the employee to the Recovery Accountability and Transparency Board, an Inspector General, the Comptroller General, a member of Congress, a state or federal regulatory or law enforcement agency, a person rights and details on how to report at www.recovery.gov. 1 Section 1553 of Division A, Title XV

  8. Method for enhanced oil recovery

    DOE Patents [OSTI]

    Comberiati, Joseph R. (Morgantown, WV); Locke, Charles D. (Morgantown, WV); Kamath, Krishna I. (Chicago, IL)

    1980-01-01

    The present invention is directed to an improved method for enhanced recovery of oil from relatively "cold" reservoirs by carbon dioxide flooding. In oil reservoirs at a temperature less than the critical temperature of 87.7.degree. F. and at a pore pressure greater than the saturation pressure of carbon dioxide at the temperature of the reservoir, the carbon dioxide remains in the liquid state which does not satisfactorily mix with the oil. However, applicants have found that carbon dioxide can be vaporized in situ in the reservoir by selectively reducing the pore pressure in the reservoir to a value less than the particular saturated vapor pressure so as to greatly enhance the mixing of the carbon dioxide with the oil.

  9. Shell boosts recovery at Kernridge

    SciTech Connect (OSTI)

    Moore, S.

    1984-01-01

    Since acquiring the Kernridge property in December 1979, Shell Oil Co. has drilled more than 1,800 wells and steadily increased production from 42,000 to 89,000 b/d of oil. Currently, the Kernridge Production Division of Shell California Production Inc. (SCPI), a newly formed subsidiary of Shell Oil Co., is operator for the property. The property covers approximately 35,000 mostly contiguous net acres, with production concentrated mainly on about 5,500 net acres. SCPI's four major fields in the area are the North and South Belridge, Lost Hills, and Antelope Hills. Most of the production comes from the North and South Belridge fields, which were previously held by the Belridge Oil Co. Productive horizons in the fields are the Tulare, Diatomite, Brown Shale, Antelope Shale, 64 Zone, and Agua sand. The Tulare and Diatomite are the two major reservoirs SCPI is developing. The Tulare, encountered between 400 and 1,300 ft, is made up of fine- to coarse-grained, unconsolidated sands with interbedded shales and silt stones and contains 13 /sup 0/ API oil. Using steam drive as the main recovery method, SCPI estimates an ultimate recovery from the Tulare formation of about 60% of the original 1 billion barrels in place. The Diatomite horizon, found between 800 and 3,500 ft and containing light, 28 /sup 0/ API oil, has high porosity (more than 60%), low permeability (less than 1 md), and natural fractures. Because of the Diatomite's low permeability, fracture stimulation is being used to increase well productivity. SCPI anticipates that approximately 5% of the almost 2 billion barrels of oil originally in place will be recovered by primary production.

  10. Entry Survey for Laboratories Using Radioactive Materials

    E-Print Network [OSTI]

    Jia, Songtao

    Entry Survey for Laboratories Using Radioactive Materials Procedure: 7.50 Created: 11 materials or radiation-generating devices is restricted to those facilities, spaces and/or rooms that have materials (RAM) in this location. The entry survey will be performed by Radiation Safety Program personnel

  11. Canister arrangement for storing radioactive waste

    DOE Patents [OSTI]

    Lorenzo, D.K.; Van Cleve, J.E. Jr.

    1980-04-23

    The subject invention relates to a canister arrangement for jointly storing high level radioactive chemical waste and metallic waste resulting from the reprocessing of nuclear reactor fuel elements. A cylindrical steel canister is provided with an elongated centrally disposed billet of the metallic waste and the chemical waste in vitreous form is disposed in the annulus surrounding the billet.

  12. RADIOACTIVE METALLOFULLERENES: HOT ATOM CHEMISTRY ASPECTS.

    E-Print Network [OSTI]

    Titov, Anatoly

    , enrichment, neutron activation, Szilard-Chalmers, retention, recoil implosion, radiation stability The n geometry of target/projectile system can not explain low implosion yields observed so far. Possible role studies and monitoring of 1 #12;chemical properties of metallofullerenes, in technology of radioactive

  13. Method for decontamination of radioactive metal surfaces

    DOE Patents [OSTI]

    Bray, L.A.

    1996-08-13

    Disclosed is a method for removing radioactive contaminants from metal surfaces by applying steam containing an inorganic acid and cerium IV. Cerium IV is applied to contaminated metal surfaces by introducing cerium IV in solution into a steam spray directed at contaminated metal surfaces. Cerium IV solution is converted to an essentially atomized or vapor phase by the steam.

  14. Nondestructive assay of boxed radioactive waste

    SciTech Connect (OSTI)

    Gilles, W.P.; Roberts, R.J.; Jasen, W.G.

    1992-12-01

    This paper describes the problems related to the nondestructive assay (NDA) of boxed radioactive waste at the Hanford Site and how Westinghouse Hanford company (WHC) is solving the problems. The waste form and radionuclide content are described. The characteristics of the combined neutron and gamma-based measurement system are described.

  15. Annual Radioactive Waste Tank Inspection Program - 1998

    SciTech Connect (OSTI)

    McNatt, F.G.

    1999-10-27

    Aqueous radioactive wastes from Savannah River Site separations processes are contained in large underground carbon steel tanks. Inspections made during 1998 to evaluate these vessels and auxiliary appurtenances, along with evaluations based on data accrued by inspections performed since the tanks were constructed, are the subject of this report.

  16. Canister arrangement for storing radioactive waste

    DOE Patents [OSTI]

    Lorenzo, Donald K. (Knoxville, TN); Van Cleve, Jr., John E. (Kingston, TN)

    1982-01-01

    The subject invention relates to a canister arrangement for jointly storing high level radioactive chemical waste and metallic waste resulting from the reprocessing of nuclear reactor fuel elements. A cylindrical steel canister is provided with an elongated centrally disposed billet of the metallic waste and the chemical waste in vitreous form is disposed in the annulus surrounding the billet.

  17. Background radioactivity of construction materials, raw substance and ready-made CaMoO4 crystals

    E-Print Network [OSTI]

    Busanov, O A; Gavriljuk, Yu M; Gezhaev, A M; Kazalov, V V; Kornoukhov, V N; Kuzminov, V V; Moseev, P S; Panasenko, S I; Ratkevich, S S; Yakimenko, S P

    2013-01-01

    The results of measurements of natural radioactive isotopes content in different source materials of natural and enriched composition used for CaMoO4 scintillation crystal growing are presented. The crystals are to be used in the experiment to search for double neutrinoless betas-decay of Mo-100.

  18. Geological challenges in radioactive waste isolation: Third worldwide review

    E-Print Network [OSTI]

    Witherspoon editor, P.A.; Bodvarsson editor, G.S.

    2001-01-01

    Radioactive Waste Long-Term Storage Piero Risoluti ENEA,The National Agency for New Technologies, Energy and Environment,environment, and the tech- nology for shutting down radioactive waste storage

  19. Geological challenges in radioactive waste isolation: Third worldwide review

    E-Print Network [OSTI]

    Witherspoon editor, P.A.; Bodvarsson editor, G.S.

    2001-01-01

    International Atomic Energy Agency (IAEA), Underground Disposal of Radioactive Waste,International Atomic Energy Agency (IAEA) regulations. The site- selection procedure began with exploring the possibility of radioactive waste

  20. CRAD, Low-Level Radioactive Waste Management - April 30, 2015...

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

    Low-Level Radioactive Waste Management - April 30, 2015 (EA CRAD 31-11, Rev. 0) CRAD, Low-Level Radioactive Waste Management - April 30, 2015 (EA CRAD 31-11, Rev. 0) April 2015...

  1. Demonstration of Heat Recovery in the Meat Industry†

    E-Print Network [OSTI]

    Molczan, T. J.; Scriven, A. P.; Magro, J.

    1984-01-01

    Canada Packers Inc. has successfully demonstrated condensing flue gas heat recovery and rendering vapour heat recovery under the Federal/Provincial Conservation and Renewable Energy Demonstration Agreement. The condensing flue gas heat recovery...

  2. Geological Problems in Radioactive Waste Isolation: Second Worldwide Review

    E-Print Network [OSTI]

    2010-01-01

    knowledge of radioactive waste management rather than dissent from any disposal solution and, surprisingly, general agreement with nuclear

  3. Geological Problems in Radioactive Waste Isolation: Second Worldwide Review

    E-Print Network [OSTI]

    2010-01-01

    International Atomic Energy Agency). The Mission Report Radioactive Wasteradioactive waste and "to partic- *Currently with International Atomic Energy Agency

  4. Recovery Act Progress Update: HWCTR Tapping

    ScienceCinema (OSTI)

    Tire, Brian

    2012-06-14

    Closure activity at the half-century old heavy water components reactor. Decommissioning is kicked off with the grouting of the basin to further protect the environment from radioactive waste.

  5. Recovery Act Progress at Idaho National Lab

    Office of Energy Efficiency and Renewable Energy (EERE)

    North Wind Services will be constructing several new structures at the INL Radioactive Waste Management Complex -- facilities that will provide important protection from the elements and minimize the spread of contamination during buried waste excavation, retrieval and packaging operations.

  6. DEVELOPMENT PROGRAM FOR PU-238 AQUEOUS RECOVERY PROCESS

    SciTech Connect (OSTI)

    M. PANSOY-HJELVIK; M. REIMUS; ET AL

    2000-10-01

    Aqueous processing is necessary for the removal of impurities from {sup 238}Pu dioxide ({sup 238}PuO{sub 2}) fuel due to unacceptable levels of {sup 234}U and other non-actinide impurities in the scrap fuel. Impurities at levels above General Purpose Heat Source (GPHS) fuel specifications may impair the performance.of the heat sources. Efforts at Los Alamos have focused on developing the bench scale methodology for the aqueous process steps which includes comminution, dissolution, ion exchange, precipitation, and calcination. Recently, work has been performed to qualify the bench scale methodology, to show that the developed process produces pure {sup 238}PuO{sub 2} meeting GPHS fuel specifications. In addition, this work has enabled us to determine how waste volumes may be minimized during full-scale processing. Results of process qualification for the bench scale aqueous recovery operation and waste minimization efforts are presented.

  7. Working with Radioactive Materials in Clinical Areas -Documentation

    E-Print Network [OSTI]

    Jia, Songtao

    Working with Radioactive Materials in Clinical Areas - Documentation Procedure: 7.54 Created: 2008 Version: 1.1 Revised: 11/5/2013 10/22/2014 Working with Radioactive Materials in Clinical Areas of the City of New York, Article 175, Radiation Control1 and New York City Department of Health Radioactive

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

    SciTech Connect (OSTI)

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

    1997-05-01

    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.

  9. American Recovery and Reinvestment Act of 2009: Biomass Program Investments

    SciTech Connect (OSTI)

    2012-06-01

    This fact sheet discusses the Biomass Program's investments using Recovery Act funding, as well as make note of how Recovery Act projects are currently doing.

  10. Post-Shred Materials Recovery Technology Development and Demonstration...

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

    Shred Materials Recovery Technology Development and Demonstration Post-Shred Materials Recovery Technology Development and Demonstration 2009 DOE Hydrogen Program and Vehicle...

  11. Thermoelectrical Energy Recovery From the Exhaust of a Light...

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

    Thermoelectrical Energy Recovery From the Exhaust of a Light Truck Thermoelectrical Energy Recovery From the Exhaust of a Light Truck 2003 DEER Conference Presentation: Clarkson...

  12. Recovery Act Selections for Smart Grid Invesment Grant Awards...

    Energy Savers [EERE]

    Recovery Act Selections for Smart Grid Invesment Grant Awards- By Category Updated July 2010 Recovery Act Selections for Smart Grid Invesment Grant Awards- By Category Updated July...

  13. Recovery Act Selections for Smart Grid Investment Grant Awards...

    Energy Savers [EERE]

    Recovery Act Selections for Smart Grid Investment Grant Awards- By Category Updated July 2010 Recovery Act Selections for Smart Grid Investment Grant Awards- By Category Updated...

  14. Successful Sequestration and Enhanced Oil Recovery Project Could...

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

    Successful Sequestration and Enhanced Oil Recovery Project Could Mean More Oil and Less CO2 Emissions Successful Sequestration and Enhanced Oil Recovery Project Could Mean More Oil...

  15. High Efficiency Microturbine with Integral Heat Recovery - Fact...

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

    Efficiency Microturbine with Integral Heat Recovery - Fact Sheet, 2014 High Efficiency Microturbine with Integral Heat Recovery - Fact Sheet, 2014 Capstone Turbine Corporation, in...

  16. Waste Isolation Pilot Plant Update and Status of Recovery | Department...

    Office of Environmental Management (EM)

    Status of Recovery Topic: Dana Bryson CBFO, Provided Information on the Status of the WIPP Site Recovery. Information Provided Included the two WIPP Events that Resulted in the...

  17. Air Handler Condensate Recovery at the Environmental Protection...

    Office of Environmental Management (EM)

    Handler Condensate Recovery at the Environmental Protection Agency's Science and Ecosystem Support Division Air Handler Condensate Recovery at the Environmental Protection Agency's...

  18. Buckley, J.S. 02 PETROLEUM; PETROLEUM; ENHANCED RECOVERY; ASPHALTENES...

    Office of Scientific and Technical Information (OSTI)

    Reservoir Wettability and its Effect on Oil Recovery. Buckley, J.S. 02 PETROLEUM; PETROLEUM; ENHANCED RECOVERY; ASPHALTENES; MINERALS; SURFACES; MICA; WETTABILITY We report on the...

  19. Protecting Recovery Act Cleanup Site During Massive Wildfire

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

    Recovery NEWS FLASH RECOVERY.GOV U.S. Depar tment of Energy | Office of Environmental Management ENVIRONMENTAL MANAGEMENT OFFICE OF ENVIRONMENTAL MANAGEMENT OFFICE OF ENVIRONMENTAL...

  20. Steelmaker Matches Recovery Act Funds to Save Energy & Reduce...

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

    Reduce Steel Production Costs ArcelorMittal Indiana Harbor Energy Recovery & Reuse 504 Boiler constructed and installed with DOE Recovery Act Funding The Advanced Manufacturing...

  1. Steelmaker Matches Recovery Act Funds to Save Energy & Reduce...

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

    factsheet describing how ArcelorMittal Indiana Harbor Energy Recovery & Reuse 504 Boiler was constructed and installed with DOE Recovery Act Funding. Blast Furnace Gas...

  2. President Obama Announces Over $467 Million in Recovery Act Funding...

    Energy Savers [EERE]

    President Obama Announces Over 467 Million in Recovery Act Funding for Geothermal and Solar Energy Projects President Obama Announces Over 467 Million in Recovery Act Funding for...

  3. President Obama Announces Over $467 Million in Recovery Act Funding...

    Energy Savers [EERE]

    Over 467 Million in Recovery Act Funding for Geothermal and Solar Energy Projects President Obama Announces Over 467 Million in Recovery Act Funding for Geothermal and Solar...

  4. Diesel Engine Waste Heat Recovery Utilizing Electric Turbocompound...

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

    Inc. 2002deerhopmann.pdf More Documents & Publications Diesel Engine Waste Heat Recovery Utilizing Electric Turbocompound Technology Diesel Engine Waste Heat Recovery...

  5. Diesel Engine Waste Heat Recovery Utilizing Electric Turbocompound...

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

    of Energy 2004deerhopmann.pdf More Documents & Publications Diesel Engine Waste Heat Recovery Utilizing Electric Trubocompound Technology Diesel Engine Waste Heat Recovery...

  6. Composites for Multi-energy conversion & waste heat recovery...

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

    Composites for Multi-energy conversion & waste heat recovery Composites for Multi-energy conversion & waste heat recovery Discusses development of a composite that transfers energy...

  7. DOE Offers $15 Million Geothermal Heat Recovery Opportunity ...

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

    15 Million Geothermal Heat Recovery Opportunity DOE Offers 15 Million Geothermal Heat Recovery Opportunity August 25, 2010 - 11:11am Addthis Photo of geothermal power plant....

  8. Exhaust Heat Recovery for Rural Alaskan Diesel Generators | Department...

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

    Recovery for Rural Alaskan Diesel Generators Exhaust Heat Recovery for Rural Alaskan Diesel Generators Poster presentation at the 2007 Diesel Engine-Efficiency & Emissions Research...

  9. High Efficiency Microturbine with Integral Heat Recovery - Presentatio...

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

    High Efficiency Microturbine with Integral Heat Recovery - Presentation by Capstone Turbine Corporation, June 2011 High Efficiency Microturbine with Integral Heat Recovery -...

  10. Performance of an Organic Rankine Cycle Waste Heat Recovery System...

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

    Performance of an Organic Rankine Cycle Waste Heat Recovery System for Light Duty Diesel Engines Performance of an Organic Rankine Cycle Waste Heat Recovery System for Light Duty...

  11. High Efficiency Microturbine with Integral Heat Recovery - Fact...

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

    High Efficiency Microturbine with Integral Heat Recovery - Fact Sheet, 2014 High Efficiency Microturbine with Integral Heat Recovery - Fact Sheet, 2014 Capstone Turbine...

  12. Study Shows Significant Economic Impact from Recovery Act | Department...

    Office of Environmental Management (EM)

    Study Shows Significant Economic Impact from Recovery Act Study Shows Significant Economic Impact from Recovery Act A study recently released shows the 1.6 billion the Savannah...

  13. Opportunities and Challenges of Thermoelectrlic Waste Heat Recovery...

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

    and Challenges of Thermoelectrlic Waste Heat Recovery in the Automotive Industry Opportunities and Challenges of Thermoelectrlic Waste Heat Recovery in the Automotive Industry 2005...

  14. Recovery of sugars from ionic liquid biomass liquor by solvent...

    Office of Scientific and Technical Information (OSTI)

    Patent: Recovery of sugars from ionic liquid biomass liquor by solvent extraction Citation Details In-Document Search Title: Recovery of sugars from ionic liquid biomass liquor by...

  15. Overview of Fordźs Thermoelectric Programs: Waste Heat Recovery...

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

    Fords Thermoelectric Programs: Waste Heat Recovery and Climate Control Overview of Fords Thermoelectric Programs: Waste Heat Recovery and Climate Control Overview of progress...

  16. Thermoelectric Waste Heat Recovery Program for Passenger Vehicles...

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

    Waste Heat Recovery Program for Passenger Vehicles Thermoelectric Waste Heat Recovery Program for Passenger Vehicles 2012 DOE Hydrogen and Fuel Cells Program and Vehicle...

  17. An Overview of Thermoelectric Waste Heat Recovery Activities...

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

    An Overview of Thermoelectric Waste Heat Recovery Activities in Europe An Overview of Thermoelectric Waste Heat Recovery Activities in Europe An overview presentation of R&D...

  18. Recovery Act: Clean Coal Power Initiative | Department of Energy

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

    A report detailling the Clean Coal Power initiative funded under the American Recovery and Renewal Act of 2009. Recovery Act: Clean Coal Power Initiative More Documents &...

  19. Californium Recovery from Palladium Wire

    SciTech Connect (OSTI)

    Burns, Jon D.

    2014-08-01

    The recovery of 252Cf from palladium-252Cf cermet wires was investigated to determine the feasibility of implementing it into the cermet wire production operation at Oak Ridge National Laboratoryís Radiochemical Engineering Development Center. The dissolution of Pd wire in 8 M HNO3 and trace amounts of HCl was studied at both ambient and elevated temperatures. These studies showed that it took days to dissolve the wire at ambient temperature and only 2 hours at 60įC. Adjusting the ratio of the volume of solvent to the mass of the wire segment showed little change in the kinetics of dissolution, which ranged from 0.176 mL/mg down to 0.019 mL/mg. A successful chromatographic separation of 153Gd, a surrogate for 252Cf, from Pd was demonstrated using AG 50x8 cation exchange resin with a bed volume of 0.5 mL and an internal diameter of 0.8 cm.

  20. Proton radioactivity with a Yukawa effective interaction

    E-Print Network [OSTI]

    T. R. Routray; S. K. Tripathy; B. B. Dash; B. Behera; D. N. Basu

    2011-04-26

    The half lives of proton radioactivity of proton emitters are investigated theoretically. Proton-nucleus interaction potentials are obtained by folding the densities of the daughter nuclei with a finite range effective nucleon-nucleon interaction having Yukawa form. The Wood-Saxon density distributions for the nuclei used in calculating the nuclear as well as the Coulomb interaction potentials are predictions of the interaction. The quantum mechanical tunneling probability is calculated within the WKB framework. These calculations provide reasonable estimates for the observed proton radioactivity lifetimes. The effects of neutron-proton effective mass splitting in neutron rich asymmetric matter as well as the nuclear matter incompressibility on the decay probability are investigated.

  1. Radioactive beam production at the Bevalac

    SciTech Connect (OSTI)

    Alonso, J.R.; Feinberg, B.; Kalnins, J.G.; Krebs, G.F.; McMahan, M.A.; Tanihata, I.

    1989-10-01

    At the Bevalac radioactive beams are routinely produced by the fragmentation process. The effectiveness of this process with respect to the secondary beam's emittance, intensity and energy spread depends critically on the nuclear reaction kinematics and the magnitude of the incident beam energy. When this beam energy significantly exceeds the energies of the nuclear reaction process, many of the qualities of the incident beam can be passed on to the secondary beam. Factors affecting secondary beam quality are discussed along with techniques for isolating and purifying a specific reaction product. The on-going radioactive beam program at the Bevalac is used as an example with applications, present performance and plans for the future. 6 refs., 6 figs., 1 tab.

  2. Solar Powered Radioactive Air Monitoring Stations

    SciTech Connect (OSTI)

    Barnett, J. M.; Bisping, Lynn E.; Gervais, Todd L.

    2013-10-30

    Environmental monitoring of ambient air for radioactive material is required as stipulated in the PNNL Site radioactive air license. Sampling ambient air at identified preferred locations could not be initially accomplished because utilities were not readily available. Therefore, solar powered environmental monitoring systems were considered as a possible option. PNNL purchased two 24-V DC solar powered environmental monitoring systems which consisted of solar panels, battery banks, and sampling units. During an approximate four month performance evaluation period, the solar stations operated satisfactorily at an on-site test location. They were subsequently relocated to their preferred locations in June 2012 where they continue to function adequately under the conditions found in Richland, Washington.

  3. Soluble pig for radioactive waste transfer lines

    SciTech Connect (OSTI)

    Ohl, P.C., Westinghouse Hanford

    1996-12-02

    Flushing transfer pipe after radioactive waste transfers generates thousands of gallons of additional radioactive waste each year at the Hanford site. The use of pneumatic pigging with waste soluble pigs as a means to clear transfer piping may be an effective alternative to raw water flushes. A feasibility study was performed by a group of senior mechanical engineering students for their senior design project as part of their curriculum at Washington State University. The students divided the feasibility study into three sub-projects involving: (1) materials research, (2) delivery system design, and (3) mockup fabrication and testing. The students screened through twenty-three candidate materials and selected a thermoplastic polymer combined 50:50 wt% with sucrose to meet the established material performance criteria. The students also prepared a conceptual design of a remote pneumatic delivery system and constructed a mockup section of transfer pipe for testing the prototype pigs.

  4. Fields of View for Environmental Radioactivity

    E-Print Network [OSTI]

    Malins, Alex; Machida, Masahiko; Takemiya, Hiroshi; Saito, Kimiaki

    2015-01-01

    The gamma component of air radiation dose rates is a function of the amount and spread of radioactive nuclides in the environment. These radionuclides can be natural or anthropogenic in origin. The field of view describes the area of radionuclides on, or below, the ground that is responsible for determining the air dose rate, and hence correspondingly the external radiation exposure. This work describes Monte Carlo radiation transport calculations for the field of view under a variety of situations. Presented first are results for natural 40K and thorium and uranium series radionuclides distributed homogeneously within the ground. Results are then described for atmospheric radioactive caesium fallout, such as from the Fukushima Daiichi Nuclear Power Plant accident. Various stages of fallout evolution are considered through the depth distribution of 134Cs and 137Cs in soil. The fields of view for the natural radionuclides and radiocaesium are different. This can affect the responses of radiation monitors to th...

  5. Electrically Driven Technologies for Radioactive Aerosol Abatement

    SciTech Connect (OSTI)

    David W. DePaoli; Ofodike A. Ezekoye; Costas Tsouris; Valmor F. de Almeida

    2003-01-28

    The purpose of this research project was to develop an improved understanding of how electriexecy driven processes, including electrocoalescence, acoustic agglomeration, and electric filtration, may be employed to efficiently treat problems caused by the formation of aerosols during DOE waste treatment operations. The production of aerosols during treatment and retrieval operations in radioactive waste tanks and during thermal treatment operations such as calcination presents a significant problem of cost, worker exposure, potential for release, and increased waste volume.

  6. Promoting neurological recovery of function via metaplasticity

    E-Print Network [OSTI]

    Cho, Kathleen K.

    The modification of synapses by neural activity has been proposed to be the substrate for experience-dependent brain development, learning, and recovery of visual function after brain injury. The effectiveness or Ďstrengthí ...

  7. Z-Bed Recovery Water Disposal

    Office of Environmental Management (EM)

    Z-Bed Recovery Water Disposal Tritium Programs Engineering Louis Boone Josh Segura Savannah River Nuclear Solutions, LLC M-TRT-H-00087 Rev 0 Date: 4102014 Tritium Facilities...

  8. An autoassociative model of recovery in memory†

    E-Print Network [OSTI]

    Cohen, Andrew L

    1996-01-01

    A model of memory is presented. The model is a neural system which utilizes an autoassociator trained via the Buhmann learning rule. Context plays a central role in the storage and recovery of stored items. Context is ...

  9. RECOVERY ACT: TAPOCO PROJECT: CHEOAH UPGRADE

    SciTech Connect (OSTI)

    Tran, Paul

    2013-02-28

    Under Funding Opportunity Announcement Number: DE-FOA-0000120, Recovery Act: Hydroelectric Facility Modernization, Alcoa Power Generating Inc. (APGI), a fully owned subsidiary of Alcoa Inc., implemented major upgrades at its Cheoah hydroelectric facility near Robbinsville, North Carolina.

  10. Autonomous thruster failure recovery for underactuated spacecraft

    E-Print Network [OSTI]

    Pong, Christopher Masaru

    2010-01-01

    Thruster failures historically account for a large percentage of failures that have occurred on orbit. Therefore, autonomous thruster failure detection, isolation, and recovery (FDIR) is an essential component to any robust ...

  11. Fluid Catalytic Cracking Power Recovery Computer Simulation†

    E-Print Network [OSTI]

    Samurin, N. A.

    1979-01-01

    operating conditions. The digital computer model simulates the performance of the axial compressor, power recovery expander, regenerator section, and system pressure drops. The program can simulate the process system design conditions for compatibility...

  12. Advanced Membrane Separation Technologies for Energy Recovery

    SciTech Connect (OSTI)

    2009-05-01

    This factsheet describes a research project whose goal is to develop novel materials for use in membrane separation technologies for the recovery of waste energy and water from industrial process streams.

  13. The Economic Recovery Tax Act of 1981.†

    E-Print Network [OSTI]

    Pena, Jose G.; Lovell, Ashley C.; Kensing, Robert H.

    1983-01-01

    . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Considerations for Estate Planning under ERTA ............................................... 8 2 The Economic Recovery Tax Act of 1981 Jose G. Pena, Ashley C. Lovell and Robert H. Kensing* Major changes in the gift and estate tax laws were...

  14. Heat Recovery Design Considerations for Cogeneration Systems†

    E-Print Network [OSTI]

    Pasquinelli, D. M.; Burns, E. D.

    1985-01-01

    The design and integration of the heat recovery section, which includes the steam generation, auxiliary firing, and steam turbine modules, is critical to the overall performance and economics of cogeneration, systems. In gas turbine topping...

  15. Experiences of recovery in mental illness†

    E-Print Network [OSTI]

    Bibby, Paul

    2009-01-01

    Introduction In recent years the concept of Ďrecoveryí has become increasingly prevalent in both government and health service policy, and in the terminology used by mental health service users. The current study examines ...

  16. Advanced Computer Control Concepts Facilitate Energy Recovery

    E-Print Network [OSTI]

    Cutler, C. R.

    1981-01-01

    A process computer is a powerful tool for maximizing the use of energy and raw materials. Advanced computer control techniques are evolving which facilitate the recovery of energy by predictive control techniques. One such technique is Dynamic...

  17. Walk, Haydel Approach to Process Heat Recovery

    E-Print Network [OSTI]

    Waldsmith, R. W.; Hendrickson, M. J.

    1983-01-01

    Walk, Haydel has developed a two phase approach to optimize the recovery of process heat in energy intensive operations. While the approach can be used on 'grassroots' designs, it has been used primarily for revamps. The capital investment...

  18. Energy Recovery Ventilator Membrane Efficiency Testing†

    E-Print Network [OSTI]

    Rees, Jennifer Anne

    2013-05-07

    A test setup was designed and built to test energy recovery ventilator membranes. The purpose of this test setup was to measure the heat transfer and water vapor transfer rates through energy recover ventilator membranes and find their effectiveness...

  19. Quantifying Vegetation Recovery on Santa Rosa Island†

    E-Print Network [OSTI]

    Rentschlar, Elizabeth

    2014-12-09

    following Hurricanes Opal and Ivan. Multispectral airborne imagery is used to analyze vegetation patterns and recovery. If no vegetation is present, sediment will not be deposited consistently. The clumps of plants collect sand in their wind shadows...

  20. Robust phase sensitive inversion recovery imaging†

    E-Print Network [OSTI]

    Garach, Ravindra Mahendrakumar

    2005-11-01

    Imaging. (August 2005) Garach, Ravindra Mahendrakumar, B.E., Gujarat University Chair of Advisory Committee: Dr. Jim Ji Inversion Recovery (IR) is a powerful tool for contrast manipulation in Mag- netic Resonance Imaging (MRI). IR can provide strong...

  1. Catastrophic Incident Recovery: Long-Term Recovery from an Anthrax Event Symposium

    SciTech Connect (OSTI)

    Lesperance, Ann M.

    2008-06-30

    On March 19, 2008, policy makers, emergency managers, and medical and Public Health officials convened in Seattle, Washington, for a workshop on Catastrophic Incident Recovery: Long-Term Recovery from an Anthrax Event. The day-long symposium was aimed at generating a dialogue about restoration and recovery through a discussion of the associated challenges that impact entire communities, including people, infrastructure, and critical systems.

  2. Geological problems in radioactive waste isolation

    SciTech Connect (OSTI)

    Witherspoon, P.A.

    1991-01-01

    The problem of isolating radioactive wastes from the biosphere presents specialists in the fields of earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high level waste (HLW) which must be isolated in the underground and away from the biosphere for thousands of years. Essentially every country that is generating electricity in nuclear power plants is faced with the problem of isolating the radioactive wastes that are produced. The general consensus is that this can be accomplished by selecting an appropriate geologic setting and carefully designing the rock repository. Much new technology is being developed to solve the problems that have been raised and there is a continuing need to publish the results of new developments for the benefit of all concerned. The 28th International Geologic Congress that was held July 9--19, 1989 in Washington, DC provided an opportunity for earth scientists to gather for detailed discussions on these problems. Workshop W3B on the subject, Geological Problems in Radioactive Waste Isolation -- A World Wide Review'' was organized by Paul A Witherspoon and Ghislain de Marsily and convened July 15--16, 1989 Reports from 19 countries have been gathered for this publication. Individual papers have been cataloged separately.

  3. Biochemically enhanced oil recovery and oil treatment

    DOE Patents [OSTI]

    Premuzic, Eugene T. (East Moriches, NY); Lin, Mow (Rocky Point, NY)

    1994-01-01

    This invention relates to the preparation of new, modified organisms, through challenge growth processes, that are viable in the extreme temperature, pressure and pH conditions and salt concentrations of an oil reservoir and that are suitable for use in microbial enhanced oil recovery. The modified microorganisms of the present invention are used to enhance oil recovery and remove sulfur compounds and metals from the crude oil.

  4. Biochemically enhanced oil recovery and oil treatment

    DOE Patents [OSTI]

    Premuzic, E.T.; Lin, M.

    1994-03-29

    This invention relates to the preparation of new, modified organisms, through challenge growth processes, that are viable in the extreme temperature, pressure and pH conditions and salt concentrations of an oil reservoir and that are suitable for use in microbial enhanced oil recovery. The modified microorganisms of the present invention are used to enhance oil recovery and remove sulfur compounds and metals from the crude oil. 62 figures.

  5. Recovery of tritium from tritiated molecules

    DOE Patents [OSTI]

    Swansiger, W.A.

    1984-10-17

    This invention relates to the recovery of tritium from various tritiated molecules by reaction with uranium. More particularly, the invention relates to the recovery of tritium from tritiated molecules by reaction with uranium wherein the reaction is conducted in a reactor which permits the reaction to occur as a moving front reaction from the point where the tritium enters the reactor charged with uranium down the reactor until the uranium is exhausted.

  6. Faces of the Recovery Act: 1366 Technologies

    SciTech Connect (OSTI)

    Sachs, Ely; Mierlo, Frank van; Obama, Barack

    2010-01-01

    LEXINGTON, MA - At 1366 Technologies, Ely Sachs and Frank van Mierlo are using ARPA-E Recovery Act funding to dramatically reduce the costs of solar panel production. To read more about the project: http://arpa-e.energy.gov/FundedProjects.aspx#1366 To see more projects funded by the Recovery Act through ARPA-E: http://arpa-e.energy.gov/FundedProjects.aspx

  7. Faces of the Recovery Act: 1366 Technologies

    ScienceCinema (OSTI)

    Sachs, Ely; Mierlo, Frank van; Obama, Barack

    2013-05-29

    LEXINGTON, MA - At 1366 Technologies, Ely Sachs and Frank van Mierlo are using ARPA-E Recovery Act funding to dramatically reduce the costs of solar panel production. To read more about the project: http://arpa-e.energy.gov/FundedProjects.aspx#1366 To see more projects funded by the Recovery Act through ARPA-E: http://arpa-e.energy.gov/FundedProjects.aspx

  8. Flare Gas Recovery in Shell Canada Refineries†

    E-Print Network [OSTI]

    Allen, G. D.; Wey, R. E.; Chan, H. H.

    1983-01-01

    six years total operating experience with modern flare gas recovery units. The compression facilities in each utilize a two-stage reciprocating machine, one liquid seal drum per flare stack, and an automated load control strategy. The purpose... these issues. SYSTEM CONFIGURATION A schematic of a typical refinery flare gas recovery facility is shown in Figure I. The facilities include the following pieces of equipment: - compressor suction drum - compressor set - inter-stage knock-out drum...

  9. Advanced Fluidized Bed Waste Heat Recovery Systems†

    E-Print Network [OSTI]

    Peterson, G. R.

    1988-01-01

    BED WASTE HEAT RECOVERY SYSTEMS G. R. PETERSON Project Manager U.S. Department of Energy, Idaho Operations Office Idaho Falls, Idaho ABSTRACT The U.S. Department of Energy, Office of Industri al Programs, has sponsored the development of a... Fluidized Bed Waste Heat Recovery System (FBWHRS) and a higher temperature variant, the Ceramic Tubular Distributor Plate (CTOP) Fluidized Bed Heat Exchanger (FBHX) system. Both systems recover energy from high-temperature flue gases and produce steam...

  10. Recovery Act Recipient Data | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterested PartiesBuildingBudget ||DepartmentReadoutReviewRecordRecoveryRecovery Act

  11. Recovery Act Reports | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuels Data CenterFinancialInvesting inServicesRecovery Act ¬Ľ Recovery Act Reports

  12. Assessment of Radioactive Liquid Effluents Release at IPEN-CNEN/SP

    SciTech Connect (OSTI)

    Bessa Nisti, Marcelo; Godoy dos Santos, Adir Janete

    2008-08-07

    A continuous effluent monitoring program has been established at IPEN's plant in order to allow an environmental impact assessment due to radioactive liquid effluent discharge to sanitary system. Representative samples of radioactive liquid effluents are analyzed by using high resolution gamma spectroscopy and instrumental neutron activation analysis, facing to Brazilian radioprotection regulatory rules. The results are consolidating yearly in the Institute source-term. In this paper, results of the source-term are presented, concerning to years 2004, 2005 and 2006. The total activity discharged was 8.5xl0{sup 8} Bq, 5.7x10{sup 8} Bq and 2.7xl0{sup 8} Bq, respectively. As the release is strongly dependent on the total amount of the effluent and on the dilution factor, special attention is needed in order to obtain the correct value of that last one. The estimated inside plant dilution factor, considering the recent facilities and the reshaping of the sewerage system was 80, 180 and 130, for period of 2004, 2005 and 2006 discharged liquid radioactive effluent.

  13. Develop Thermoelectric Technology for Automotive Waste Heat Recovery

    Broader source: Energy.gov [DOE]

    Develop thermoelectric technology for waste heat recovery with a 10% fuel economy improvement without increasing emissions.

  14. The Spanish General Radioactive Waste Management Plan

    SciTech Connect (OSTI)

    Espejo, J.M.; Abreu, A. [National Company for Radioactive Waste Limited Company (ENRESA), Madrid (Spain)

    2008-07-01

    This paper mainly describes the strategies, the necessary actions and the technical solutions to be developed by ENRESA in the short, medium and long term, aimed at ensuring the adequate management of radioactive waste, the dismantling and decommissioning of nuclear and radioactive facilities and other activities, including economic and financial measures required to carry them out. Starting with the Spanish administrative organization in this field, which identifies the different agents involved and their roles, and after referring to the waste generation, the activities to be performed in the areas of LILW, SF and HLW management, decommissioning of installations and others are summarized. Finally, the future management costs are estimated and the financing system currently in force is explained. The so-called Sixth General Radioactive Waste Plan (6. GRWP), approved by the Spanish Government, is the 'master document' of reference where all the above mentioned issues are contemplated. In summary: The 6. GRWP includes the strategies and actions to be performed by Enresa in the coming years. The document, revised by the Government and subject to a process of public information, underlines the fact that Spain possesses an excellent infrastructure for the safe and efficient management of radioactive waste, from the administrative, technical and economic-financial points of view. From the administrative point of view there is an organisation, supported by ample legislative developments, that contemplates and governs the main responsibilities of the parties involved in the process (Government, CSN, ENRESA and waste producers). As regards the technical aspect, the experience accumulated to date by Enresa is particularly significant, as are the technologies now available in the field of management and for dismantling processes. As regards the economic-financial basis, a system is in place that guarantees the financing of radioactive waste management costs. This system is based on the generation of funds up front, during the operating lifetime of the facilities, through the application of fees established by Statutory provisions. Finally, a mandatory mechanism of annual revision for both technical issues and economic and financial aspects, allows to have updated all the courses of action. (authors)

  15. Nuisance Source Population Modeling for Radiation Detection System Analysis

    SciTech Connect (OSTI)

    Sokkappa, P; Lange, D; Nelson, K; Wheeler, R

    2009-10-05

    A major challenge facing the prospective deployment of radiation detection systems for homeland security applications is the discrimination of radiological or nuclear 'threat sources' from radioactive, but benign, 'nuisance sources'. Common examples of such nuisance sources include naturally occurring radioactive material (NORM), medical patients who have received radioactive drugs for either diagnostics or treatment, and industrial sources. A sensitive detector that cannot distinguish between 'threat' and 'benign' classes will generate false positives which, if sufficiently frequent, will preclude it from being operationally deployed. In this report, we describe a first-principles physics-based modeling approach that is used to approximate the physical properties and corresponding gamma ray spectral signatures of real nuisance sources. Specific models are proposed for the three nuisance source classes - NORM, medical and industrial. The models can be validated against measured data - that is, energy spectra generated with the model can be compared to actual nuisance source data. We show by example how this is done for NORM and medical sources, using data sets obtained from spectroscopic detector deployments for cargo container screening and urban area traffic screening, respectively. In addition to capturing the range of radioactive signatures of individual nuisance sources, a nuisance source population model must generate sources with a frequency of occurrence consistent with that found in actual movement of goods and people. Measured radiation detection data can indicate these frequencies, but, at present, such data are available only for a very limited set of locations and time periods. In this report, we make more general estimates of frequencies for NORM and medical sources using a range of data sources such as shipping manifests and medical treatment statistics. We also identify potential data sources for industrial source frequencies, but leave the task of estimating these frequencies for future work. Modeling of nuisance source populations is only useful if it helps in understanding detector system performance in real operational environments. Examples of previous studies in which nuisance source models played a key role are briefly discussed. These include screening of in-bound urban traffic and monitoring of shipping containers in transit to U.S. ports.

  16. Waste Heat Recovery System: Lightweight Thermal Energy Recovery (LIGHTER) System

    SciTech Connect (OSTI)

    2010-01-01

    Broad Funding Opportunity Announcement Project: GM is using shape memory alloys that require as little as a 10įC temperature difference to convert low-grade waste heat into mechanical energy. When a stretched wire made of shape memory alloy is heated, it shrinks back to its pre-stretched length. When the wire cools back down, it becomes more pliable and can revert to its original stretched shape. This expansion and contraction can be used directly as mechanical energy output or used to drive an electric generator. Shape memory alloy heat engines have been around for decades, but the few devices that engineers have built were too complex, required fluid baths, and had insufficient cycle life for practical use. GM is working to create a prototype that is practical for commercial applications and capable of operating with either air- or fluid-based heat sources. GMís shape memory alloy based heat engine is also designed for use in a variety of non-vehicle applications. For example, it can be used to harvest non-vehicle heat sources, such as domestic and industrial waste heat and natural geothermal heat, and in HVAC systems and generators.

  17. Two stage, low temperature, catalyzed fluidized bed incineration with in situ neutralization for radioactive mixed wastes

    SciTech Connect (OSTI)

    Wade, J.F.; Williams, P.M.

    1995-05-17

    A two stage, low temperature, catalyzed fluidized bed incineration process is proving successful at incinerating hazardous wastes containing nuclear material. The process operates at 550{degrees}C and 650{degrees}C in its two stages. Acid gas neutralization takes place in situ using sodium carbonate as a sorbent in the first stage bed. The feed material to the incinerator is hazardous waste-as defined by the Resource Conservation and Recovery Act-mixed with radioactive materials. The radioactive materials are plutonium, uranium, and americium that are byproducts of nuclear weapons production. Despite its low temperature operation, this system successfully destroyed poly-chlorinated biphenyls at a 99.99992% destruction and removal efficiency. Radionuclides and volatile heavy metals leave the fluidized beds and enter the air pollution control system in minimal amounts. Recently collected modeling and experimental data show the process minimizes dioxin and furan production. The report also discusses air pollution, ash solidification, and other data collected from pilot- and demonstration-scale testing. The testing took place at Rocky Flats Environmental Technology Site, a US Department of Energy facility, in the 1970s, 1980s, and 1990s.

  18. Audit Report on "The Department of Energy's American Recovery and Reinvestment Act -- Florida State Energy Program"

    SciTech Connect (OSTI)

    2010-06-01

    The Department of Energy's Office of Energy Efficiency and Renewable Energy (EERE) provides grants to states, territories, and the District of Columbia to support their energy priorities through the State Energy Program (SEP). The SEP provides Federal financial assistance to carry out energy efficiency and renewable energy projects that meet each state's unique energy needs while also addressing national goals such as energy security. Federal funding is based on a grant formula that takes into account population and energy consumption. The SEP emphasizes the state's role as the decision maker and administrator for the program. The American Recovery and Reinvestment Act of 2009 (Recovery Act) expanded the SEP, authorizing $3.1 billion in grants. Based on existing grant formulas and after reviewing state-level plans, EERE made awards to states. The State of Florida's Energy Office (Florida) was allocated $126 million - a 90-fold increase over Florida's average annual SEP grant of $1.4 million. Per the Recovery Act, this funding must be obligated by September 30, 2010, and spent by April 30, 2012. As of March 10, 2010, Florida had expended $13.2 million of the SEP Recovery Act funds. Florida planned to use its grant funds to undertake activities that would preserve and create jobs; save energy; increase renewable energy sources; and, reduce greenhouse gas emissions. To accomplish Recovery Act objectives, states could either fund new or expand existing projects. As a condition of the awards, EERE required states to develop and implement sound internal controls over the use of Recovery Act funds. Based on the significant increase in funding from the Recovery Act, we initiated this review to determine whether Florida had internal controls in place to provide assurance that the goals of the SEP and Recovery Act will be met and accomplished efficiently and effectively. We identified weaknesses in the implementation of SEP Recovery Act projects that have adversely impacted Florida's ability to meet the goals of the SEP and the Recovery Act. Specifically: (1) Florida used about $8.3 million to pay for activities that did not meet the intent of the Recovery Act to create new or save existing jobs. With the approval of the Department, Florida used these funds to pay for rebates related to solar energy projects that had been completed prior to passage of the Recovery Act; (2) State officials did not meet Florida's program goals to obligate all Recovery Act funds by January 1, 2010, thus delaying projects and preventing them from achieving the desired stimulative economic impact. Obligations were delayed because Florida officials selected a number of projects that either required a lengthy review and approval process or were specifically prohibited. In June 2009, the Department notified Florida that a number of projects would not be approved; however, as of April 1, 2010, the State had not acted to name replacement projects or move funds to other projects; (3) Florida officials had not ensured that 7 of the 18 award requirements for Recovery Act funding promulgated by the Department had been passed down to sub-recipients of the award, as required; and, (4) Certain internal control weaknesses that could jeopardize the program and increase the risk of fraud, waste and abuse were identified in the Solar Energy System Incentives Program during our September 2009 visit to Florida. These included a lack of separation of duties related to the processing of rebates and deficiencies in the written procedures for grant managers to review and approve rebates. From a forward looking perspective, absent aggressive corrective action, these weaknesses threaten Florida's efforts to meet future Recovery Act goals. In response to our review, Florida took corrective action to incorporate the additional award requirements in sub-recipient documents. It also instituted additional controls to correct the internal control weaknesses we identified. More, however, needs to be done with respect to Department oversight. This report details the circumstances sur

  19. Resource Recovery Opportunities at Americaís Water Resource Recovery Facilities

    Broader source: Energy.gov [DOE]

    Breakout Session 3AóConversion Technologies III: Energy from Our WasteóWill we Be Rich in Fuel or Knee Deep in Trash by 2025? Resource Recovery Opportunities at Americaís Water Resource Recovery Facilities Todd Williams, Deputy Leader for Wastewater Infrastructure Practice, CH2M HILL

  20. New surfactant classes for enhanced oil recovery and their tertiary oil recovery potential

    E-Print Network [OSTI]

    Goddard III, William A.

    esters sorbitan ester ultra-low interfacial tension enhanced oil recovery surfactant flood chemical flood sandstones. In addition to the corefloods, one sandpack surfactant flood was performed. The porous media were by polymer drive slug injection, and incremental oil recovery was measured against time. The tested

  1. Considerations Related To Human Intrusion In The Context Of Disposal Of Radioactive Waste-The IAEA HIDRA Project

    SciTech Connect (OSTI)

    Seitz, Roger; Kumano, Yumiko; Bailey, Lucy; Markley, Chris; Andersson, Eva; Beuth, Thomas

    2014-01-09

    The principal approaches for management of radioactive waste are commonly termed Ďdelay and decayí, Ďconcentrate and containí and Ďdilute and disperseí. Containing the waste and isolating it from the human environment, by burying it, is considered to increase safety and is generally accepted as the preferred approach for managing radioactive waste. However, this approach results in concentrated sources of radioactive waste contained in one location, which can pose hazards should the facility be disrupted by human action in the future. The International Commission on Radiological Protection (ICRP), International Atomic Energy Agency (IAEA), and Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA) agree that some form of inadvertent human intrusion (HI) needs to be considered to address the potential consequences in the case of loss of institutional control and loss of memory of the disposal facility. Requirements are reflected in national regulations governing radioactive waste disposal. However, in practice, these requirements are often different from country to country, which is then reflected in the actual implementation of HI as part of a safety case. The IAEA project on HI in the context of Disposal of RadioActive waste (HIDRA) has been started to identify potential areas for improved consistency in consideration of HI. The expected outcome is to provide recommendations on how to address human actions in the safety case in the future, and how the safety case may be used to demonstrate robustness and optimize siting, design and waste acceptance criteria within the context of a safety case.

  2. Integrated Data Base for 1992: US spent fuel and radioactive waste inventories, projections, and characteristics. Revision 8

    SciTech Connect (OSTI)

    Payton, M. L.; Williams, J. T.; Tolbert-Smith, M.; Klein, J. A.

    1992-10-01

    The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1991. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal.

  3. Integrated Data Base report--1993: U.S. spent nuclear fuel and radioactive waste inventories, projections, and characteristics. Revision 10

    SciTech Connect (OSTI)

    Not Available

    1994-12-01

    The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and DOE spent nuclear fuel; also, commercial and US government-owned radioactive wastes through December 31, 1993. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 256 refs., 38 figs., 141 tabs.

  4. Integrated data base for 1993: US spent fuel and radioactive waste inventories, projections, and characteristics. Revision 9

    SciTech Connect (OSTI)

    Klein, J.A.; Storch, S.N.; Ashline, R.C.

    1994-03-01

    The Integrated Data Base (IDB) Program has compiled historic data on inventories and characteristics of both commercial and DOE spent fuel; also, commercial and U.S. government-owned radioactive wastes through December 31, 1992. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest U.S. Department of Energy/Energy Information Administration (DOE/EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste (HLW), transuranic (TRU), waste, low-level waste (LLW), commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) LLW. For most of these categories, current and projected inventories are given through the calendar-year (CY) 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal.

  5. Using Carbon Dioxide to Enhance Recovery of Methane from Gas Hydrate Reservoirs: Final Summary Report

    SciTech Connect (OSTI)

    McGrail, B. Peter; Schaef, Herbert T.; White, Mark D.; Zhu, Tao; Kulkarni, Abhijeet S.; Hunter, Robert B.; Patil, Shirish L.; Owen, Antionette T.; Martin, P F.

    2007-09-01

    Carbon dioxide sequestration coupled with hydrocarbon resource recovery is often economically attractive. Use of CO2 for enhanced recovery of oil, conventional natural gas, and coal-bed methane are in various stages of common practice. In this report, we discuss a new technique utilizing CO2 for enhanced recovery of an unconventional but potentially very important source of natural gas, gas hydrate. We have focused our attention on the Alaska North Slope where approximately 640 Tcf of natural gas reserves in the form of gas hydrate have been identified. Alaska is also unique in that potential future CO2 sources are nearby, and petroleum infrastructure exists or is being planned that could bring the produced gas to market or for use locally. The EGHR (Enhanced Gas Hydrate Recovery) concept takes advantage of the physical and thermodynamic properties of mixtures in the H2O-CO2 system combined with controlled multiphase flow, heat, and mass transport processes in hydrate-bearing porous media. A chemical-free method is used to deliver a LCO2-Lw microemulsion into the gas hydrate bearing porous medium. The microemulsion is injected at a temperature higher than the stability point of methane hydrate, which upon contacting the methane hydrate decomposes its crystalline lattice and releases the enclathrated gas. Small scale column experiments show injection of the emulsion into a CH4 hydrate rich sand results in the release of CH4 gas and the formation of CO2 hydrate

  6. Water recovery using waste heat from coal fired power plants.

    SciTech Connect (OSTI)

    Webb, Stephen W.; Morrow, Charles W.; Altman, Susan Jeanne; Dwyer, Brian P.

    2011-01-01

    The potential to treat non-traditional water sources using power plant waste heat in conjunction with membrane distillation is assessed. Researchers and power plant designers continue to search for ways to use that waste heat from Rankine cycle power plants to recover water thereby reducing water net water consumption. Unfortunately, waste heat from a power plant is of poor quality. Membrane distillation (MD) systems may be a technology that can use the low temperature waste heat (<100 F) to treat water. By their nature, they operate at low temperature and usually low pressure. This study investigates the use of MD to recover water from typical power plants. It looks at recovery from three heat producing locations (boiler blow down, steam diverted from bleed streams, and the cooling water system) within a power plant, providing process sketches, heat and material balances and equipment sizing for recovery schemes using MD for each of these locations. It also provides insight into life cycle cost tradeoffs between power production and incremental capital costs.

  7. Corrosion resistant storage container for radioactive material

    DOE Patents [OSTI]

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

    1984-08-30

    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.

  8. System for handling and storing radioactive waste

    DOE Patents [OSTI]

    Anderson, J.K.; Lindemann, P.E.

    1982-07-19

    A system and method are claimed for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

  9. Proton radioactivity half lives with Skyrme interactions

    E-Print Network [OSTI]

    T. R. Routray; Abhishek Mishra; S. K. Tripathy; B. Behera; D. N. Basu

    2012-05-31

    The potential barrier impeding the spontaneous emission of protons in the proton radioactive nuclei is calculated as the sum of nuclear, Coulomb and centrifugal contributions. The nuclear part of the proton-nucleus interaction potential is obtained in the energy density formalism using Skyrme effective interaction that results into a simple algebraic expression. The half-lives of the proton emitters are calculated for the different Skyrme sets within the improved WKB framework. The results are found to be in reasonable agreement with the earlier results obtained for more complicated calculations involving finite range interactions.

  10. Astrophysics experiments with radioactive beams at ATLAS

    SciTech Connect (OSTI)

    Back, B. B.; Clark, J. A.; Pardo, R. C.; Rehm, K. E., E-mail: rehm@anl.gov; Savard, G. [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States)] [Physics Division, Argonne National Laboratory, Argonne, IL 60439 (United States)

    2014-04-15

    Reactions involving short-lived nuclei play an important role in nuclear astrophysics, especially in explosive scenarios which occur in novae, supernovae or X-ray bursts. This article describes the nuclear astrophysics program with radioactive ion beams at the ATLAS accelerator at Argonne National Laboratory. The CARIBU facility as well as recent improvements for the in-flight technique are discussed. New detectors which are important for studies of the rapid proton or the rapid neutron-capture processes are described. At the end we briefly mention plans for future upgrades to enhance the intensity, purity and the range of in-flight and CARIBU beams.

  11. Hanford Site radioactive hazardous materials packaging directory

    SciTech Connect (OSTI)

    McCarthy, T.L.

    1995-12-01

    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.

  12. System for handling and storing radioactive waste

    DOE Patents [OSTI]

    Anderson, John K. (San Diego, CA); Lindemann, Paul E. (Escondido, CA)

    1984-01-01

    A system and method for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

  13. Fusion Induced by Radioactive Ion Beams

    E-Print Network [OSTI]

    J. F. Liang; C. Signorini

    2005-04-26

    The use of radioactive beams opens a new frontier for fusion studies. The coupling to the continuum can be explored with very loosely bound nuclei. Experiments were performed with beams of nuclei at or near the proton and neutron drip-lines to measure fusion and associated reactions in the vicinity of the Coulomb barrier. In addition, the fusion yield is predicted to be enhanced in reactions involving very neutron-rich unstable nuclei. Experimental measurements were carried out to investigate if it is feasible to use such beams to produce new heavy elements. The current status of these experimental activities is given in this review.

  14. The environmental impact of radioactive effluents from a university reactor†

    E-Print Network [OSTI]

    Hamiter, Floyd Raymond

    1975-01-01

    of the radioactive cloud were then determined to a distance of 50 miles from the reactor. With the aid of population projections for the reactor environs, annual population doses due to gaseous effluents were estimated. Concentration of radioactive liquid waste... 13 3, Exposure pathways to man 17 INTRODUCTION Prior to World War II, little was known about radioactivity in the environment. The information available was exchanged among a rel- atively few specialized laboratories equipped to measure natural...

  15. Karlsruhe Database for Radioactive Wastes (KADABRA) - Accounting and Management System for Radioactive Waste Treatment - 12275

    SciTech Connect (OSTI)

    Himmerkus, Felix; Rittmeyer, Cornelia [WAK Rueckbau- und Entsorgungs- GmbH, 76339 Eggenstein-Leopoldshafen (Germany)

    2012-07-01

    The data management system KADABRA was designed according to the purposes of the Cen-tral Decontamination Department (HDB) of the Wiederaufarbeitungsanlage Karlsruhe Rueckbau- und Entsorgungs-GmbH (WAK GmbH), which is specialized in the treatment and conditioning of radioactive waste. The layout considers the major treatment processes of the HDB as well as regulatory and legal requirements. KADABRA is designed as an SAG ADABAS application on IBM system Z mainframe. The main function of the system is the data management of all processes related to treatment, transfer and storage of radioactive material within HDB. KADABRA records the relevant data concerning radioactive residues, interim products and waste products as well as the production parameters relevant for final disposal. Analytical data from the laboratory and non destructive assay systems, that describe the chemical and radiological properties of residues, production batches, interim products as well as final waste products, can be linked to the respective dataset for documentation and declaration. The system enables the operator to trace the radioactive material through processing and storage. Information on the actual sta-tus of the material as well as radiological data and storage position can be gained immediately on request. A variety of programs accessed to the database allow the generation of individual reports on periodic or special request. KADABRA offers a high security standard and is constantly adapted to the recent requirements of the organization. (authors)

  16. EIS-0286: Hanford Solid (Radioactive and Hazardous) Waste Program

    Broader source: Energy.gov [DOE]

    The Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement (HSW EIS) analyzes the proposed waste management practices at the Hanford Site.

  17. Hanford Site Shares Lessons Learned in Retrieving Highly Radioactive...

    Energy Savers [EERE]

    radioactive sludge at the Hanford site. This pump was modified to fit the underwater environment where the sludge is stored. Representatives from the Oak Ridge Office of...

  18. The radioactive Substances (Prepared Uranium Thorium Compounds) Exemption Order 1962†

    E-Print Network [OSTI]

    Joseph, Keith

    1962-01-01

    STATUTORY INSTRUMENTS 1962 No. 2711 ATOMIC ENERGY AND RADIOACI1VE SUBSTANCES The Radioactive Substances (prepared Uranium and Thorium Compounds) Exemption Order 1962

  19. Base Technology for Radioactive Material Transportation Packaging Systems

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

    1992-07-08

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

  20. Hanford Site Solid (Radioactive and Hazardous) Waste Program...

    Office of Environmental Management (EM)

    Office 2 3 TITLE: 4 Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact 5 Statement, Richland, Benton County, Washington (DOE...

  1. Revised Draft Hanford Site Solid (Radioactive and Hazardous)...

    Office of Environmental Management (EM)

    Operations Office TITLE: Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Benton County, Washington (DOE...

  2. Final Hanford Site Solid (Radioactive and Hazardous) Waste Program...

    Office of Environmental Management (EM)

    Richland Operations Office TITLE: Final Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Benton County, Washington (DOE...

  3. Office of Civilian Radioactive Waste Management-Quality Assurance...

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

    and description of the Quality Assurance program. Office of Civilian Radioactive Waste Management-Quality Assurance Requirements and Description More Documents &...

  4. EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive...

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

    environmental and cost impacts of strategic managment alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result...

  5. Cyclotrons to Make Neutrons & Radioactive Targets for SBSS at...

    Office of Science (SC) Website

    Cyclotrons to Make Neutrons & Radioactive Targets for SBSS at LBNL Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Applications of Nuclear...

  6. Applying Risk Communication to the Transportation of Radioactive...

    Office of Environmental Management (EM)

    to keep messages focused Applying Risk Communication to the Transportation of Radioactive Materials More Documents & Publications Status and Future of TRANSCOM Department of Energy...

  7. Geological Problems in Radioactive Waste Isolation: Second Worldwide Review

    E-Print Network [OSTI]

    2010-01-01

    radioac- tive waste repository construction and operation,and Construction of Underground Repositories for Radioactive Wastes,suitable for the construction of deep waste repositories and

  8. Huizenga leads safety of spent fuel management, radioactive waste...

    National Nuclear Security Administration (NNSA)

    Huizenga leads safety of spent fuel management, radioactive waste management meeting in Vienna | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People...

  9. Methods for enhancing mapping of thermal fronts in oil recovery

    DOE Patents [OSTI]

    Lee, D.O.; Montoya, P.C.; Wayland, J.R. Jr.

    1984-03-30

    A method for enhancing the resistivity contrasts of a thermal front in an oil recovery production field as measured by the controlled source audio frequency magnetotelluric (CSAMT) technique is disclosed. This method includes the steps of: (1) preparing a CSAMT-determined topological resistivity map of the production field; (2) introducing a solution of a dopant material into the production field at a concentration effective to alter the resistivity associated with the thermal front; said dopant material having a high cation exchange capacity which might be selected from the group consisting of montmorillonite, illite, and chlorite clays; said material being soluble in the conate water of the production field; (3) preparing a CSAMT-determined topological resistivity map of the production field while said dopant material is moving therethrough; and (4) mathematically comparing the maps from step (1) and step (3) to determine the location of the thermal front. This method is effective with the steam flood, fire flood and water flood techniques.

  10. Inherently safe in situ uranium recovery

    DOE Patents [OSTI]

    Krumhansl, James L; Brady, Patrick V

    2014-04-29

    An in situ recovery of uranium operation involves circulating reactive fluids through an underground uranium deposit. These fluids contain chemicals that dissolve the uranium ore. Uranium is recovered from the fluids after they are pumped back to the surface. Chemicals used to accomplish this include complexing agents that are organic, readily degradable, and/or have a predictable lifetime in an aquifer. Efficiency is increased through development of organic agents targeted to complexing tetravalent uranium rather than hexavalent uranium. The operation provides for in situ immobilization of some oxy-anion pollutants under oxidizing conditions as well as reducing conditions. The operation also artificially reestablishes reducing conditions on the aquifer after uranium recovery is completed. With the ability to have the impacted aquifer reliably remediated, the uranium recovery operation can be considered inherently safe.

  11. Alternate Materials for Recovery Boiler Superheater Tubes

    SciTech Connect (OSTI)

    Keiser, James R [ORNL; Kish, Joseph [McMaster University; Singbeil, Douglas [FPInnovations

    2009-01-01

    The ever escalating demands for increased efficiency of all types of boilers would most sensibly be realized by an increase in the steam parameters of temperature and pressure. However, materials and corrosion limitations in the steam generating components, particularly the superheater tubes, present major obstacles to boiler designers in achieving systems that can operate under the more severe conditions. This paper will address the issues associated with superheater tube selection for many types of boilers; particularly chemical recovery boilers, but also addressing the similarities in issues for biomass and coal fired boilers. It will also review our recent study of materials for recovery boiler superheaters. Additional, more extensive studies, both laboratory and field, are needed to gain a better understanding of the variables that affect superheater tube corrosion and to better determine the best means to control this corrosion to ultimately permit operation of recovery boilers at higher temperatures and pressures.

  12. DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS

    SciTech Connect (OSTI)

    NA

    2004-11-22

    The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this modeling activity is to predict dissolved concentrations or solubility limits for 14 elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) important to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are in the form of tabulated functions with pH and log (line integral) CO{sub 2} as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. The output data from this report are fundamental inputs for Total System Performance Assessment for the License Application (TSPA-LA) to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for all of the actinides. These models cover broad ranges of environmental conditions so that they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or otherwise addressed.

  13. Management of low-level radioactive wastes around the world

    SciTech Connect (OSTI)

    Lakey, L.T.; Harmon, K.M.; Colombo, P.

    1985-04-01

    This paper reviews the status of various practices used throughout the world for managing low-level radioactive wastes. Most of the information in this review was obtained through the DOE-sponsored International Program Support Office (IPSO) activities at Pacific Northwest Laboratory (PNL) at Richland, Washington. The objective of IPSO is to collect, evaluate, and disseminate information on international waste management and nuclear fuel cycle activities. The center's sources of information vary widely and include the proceedings of international symposia, papers presented at technical society meetings, published topical reports, foreign trip reports, and the news media. Periodically, the information is published in topical reports. Much of the information contained in this report was presented at the Fifth Annual Participants' Information Meeting sponsored by DOE's Low-Level Waste Management Program Office at Denver, Colorado, in September of 1983. Subsequent to that presentation, the information has been updated, particularly with information provided by Dr. P. Colombo of Brookhaven National Laboratory who corresponded with low-level waste management specialists in many countries. The practices reviewed in this paper generally represent actual operations. However, major R and D activities, along with future plans, are also discussed. 98 refs., 6 tabls.

  14. Impact of Sorption Isotherms on the Simulation of CO2-Enhanced Gas Recovery and Storage Process in Marcellus Shale

    E-Print Network [OSTI]

    Mohaghegh, Shahab

    Continuous, low-permeability, fractured, organic-rich gas shale units are widespread and are possible, organic-rich rocks that are both the source and trap for natural gas (primarily methane). In shale gas1 Impact of Sorption Isotherms on the Simulation of CO2-Enhanced Gas Recovery and Storage Process

  15. Radioactive Waste Storage Facility at the Armenian NPP - 12462

    SciTech Connect (OSTI)

    Grigoryan, G.; Amirjanyan, A.; Gondakyan, Y. [Nuclear and Radiation Safety Center (NRSC), 4 Tigran Mets, 375010 Yerevan (Armenia); Stepanyan, A. [Armenian Nuclear Regulatory Authority(ANRA), 4 Tigran Mets, 375010 Yerevan (Armenia)

    2012-07-01

    We present a detailed contaminant transfer dynamics model for radionuclide in geosphere and biosphere medium. The model describes the transport of radionuclides using full equation for the processes of advection, diffusion, decay and sorption. The overall objective is to establish, from a post-closure radiological safety point of view, whether it is practical to convert an existing radioactive waste storage facility at Armenian NPP, to a waste disposal facility. The calculation includes: - Data sources for: the operational waste-source term; options for refurbishment and completion of the waste storage facility as a waste disposal facility; the site and its environs; - Development of an assessment context for the safety assessment, and identification of waste treatment options; - A description of the conceptual and mathematical models, and results calculated for the base case scenario relating to the release of contaminants via the groundwater pathway and also precipitation especially important for this site. The results of the calculations showed that the peak individual dose is < 7 E-8 Sv/y arising principally from I-129 after 700 years post closure. Other significant radionuclides, in terms of their contribution to the total dose are I-129, Tc-99 and in little C-14 (U- 234 and Po-210 are not relevant). The study does not explore all issues that might be expected to be presented in a safety case for a near surface disposal facility it mainly focuses on post- closure dose impacts. Most emphasis has been placed on the development of scenarios and conceptual models rather than the presentation and analyses of results and confidence building (only deterministic results are presented). The calculations suggest that, from a perspective the conversion of the waste-storage facility is feasible such that all the predicted doses are well below internationally recognized targets, as well as provisional Armenian regulatory objectives. This conclusion applies to the disposal of the ANPP present and future arising of L/ILW operating wastes. (authors)

  16. Carbon isotopic evidence for biodegradation of organic contaminants in the shallow vadose zone of the radioactive waste management complex

    E-Print Network [OSTI]

    Conrad, Mark E.; DePaolo, Donald J.

    2003-01-01

    at the Radioactive Waste Management Complex, Idaho NationalSciences. 1995. Radioactive Waste Management Complex organicat the Radioactive Waste Management Complex. Lockheed Martin

  17. Methane Digesters and Biogas Recovery - Masking the Environmental Consequences of Industrial Concentrated Livestock Production

    E-Print Network [OSTI]

    Di Camillo, Nicole G.

    2011-01-01

    Methane Digesters and Biogas Recovery-Masking theII. METHANE DIGESTERS AND BIOGAs RECOVERY- IN THE2011] METHANE DIGESTERS AND BIOGAS RECOVERY methane, and 64%

  18. Art appreciation for veterans with severe mental illness in a VA Psychosocial Rehabilitation and Recovery Center

    E-Print Network [OSTI]

    Ketch, RA; Rubin, RT; Baker, MR; Sones, AC; Ames, D

    2015-01-01

    2011). Psychosocial rehabilitation and recovery centers (in a VA Psychosocial Rehabilitation and Recovery Center a bWest L.A. Psychosocial Rehabilitation and Recovery Center,

  19. Inherently safe in situ uranium recovery (Patent) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Inherently safe in situ uranium recovery Citation Details In-Document Search Title: Inherently safe in situ uranium recovery An in situ recovery of uranium operation involves...

  20. RF power recovery feedback circulator

    DOE Patents [OSTI]

    Sharamentov, Sergey I. (Bolingbrook, IL)

    2011-03-29

    A device and method for improving the efficiency of RF systems having a Reflective Load. In the preferred embodiment, Reflected Energy from a superconducting resonator of a particle accelerator is reintroduced to the resonator after the phase of the Reflected Energy is aligned with the phase of the Supply Energy from a RF Energy Source. In one embodiment, a Circulator is used to transfer Reflected Energy from the Reflective Load into a Phase Adjuster which aligns the phase of the Reflected Energy with that of the Supply Energy. The phase-aligned energy is then combined with the Supply Energy, and reintroduced into the Reflective Load. In systems having a constant phase shift, the Phase Adjuster may be designed to shift the phase of the Reflected Energy by a constant amount using a Phase Shifter. In systems having a variety (variable) phase shifts, a Phase Shifter controlled by a phase feedback loop comprising a Phase Detector and a Feedback Controller to account for the various phase shifts is preferable.

  1. Radioactive air emissions notice of construction for deactivation of the PUREX storage tunnel number 2

    SciTech Connect (OSTI)

    JOHNSON, R.E.

    1999-10-11

    The Plutonium-Uranium Extraction (PUREX) Plant Storage Tunnel Number 2 (hereafter referred to as the PUREX Tunnel) was built in 1964. Since that time, the PUREX Tunnel has been used for storage of radioactive and mixed waste. In 1991, the PUREX Plant ceased operations and was transitioned to deactivation. The PUREX Tunnel continued to receive PUREX Plant waste material for storage during transition activities. Before 1995, a decision was made to store radioactive and mixed waste in the PUREX Tunnel generated from other onsite sources, on a case-by-case basis. This notice of construction (NOC) describes the activities associated with the reactivation of the PUREX Tunnel ventilation system and the transfer of up to 3.5 million curies (MCi) of radioactive waste to the PUREX Tunnel from any location on the Hanford Site. The unabated total effective dose equivalent (TEDE) estimated for the hypothetical offsite maximally exposed individual (MEI) is 5.6 E-2 millirem (mrem). The abated TEDE conservatively is estimated to account for 1.9 E-5 mrem to the MEI. The following text provides information requirements of Appendix A of Washington Administrative Code (WAC) 246-247 (requirements 1 through 18).

  2. Composite tube cracking in kraft recovery boilers: A state-of-the-art review

    SciTech Connect (OSTI)

    Singbeil, D.L.; Prescott, R.; Keiser, J.R.; Swindeman, R.W.

    1997-07-01

    Beginning in the mid-1960s, increasing energy costs in Finland and Sweden made energy recovery more critical to the cost-effective operation of a kraft pulp mill. Boiler designers responded to this need by raising the steam operating pressure, but almost immediately the wall tubes in these new boilers began to corrode rapidly. Test panels installed in the walls of the most severely corroding boiler identified austenitic stainless steel as sufficiently resistant to the new corrosive conditions, and discussions with Sandvik AB, a Swedish tube manufacturer, led to the suggestion that coextruded tubes be used for water wall service in kraft recovery boilers. Replacement of carbon steel by coextruded tubes has solved most of the corrosion problems experienced by carbon steel wall tubes, however, these tubes have not been problem-free. Beginning in early 1995, a multidisciplinary research program funded by the US Department of Energy was established to investigate the cause of cracking in coextruded tubes and to develop improved materials for use in water walls and floors of kraft recovery boilers. One portion of that program, a state-of-the-art review of public- and private-domain documents related to coextruded tube cracking in kraft recovery boilers is reported here. Sources of information that were consulted for this review include the following: tube manufacturers, boiler manufacturers, public-domain literature, companies operating kraft recovery boilers, consultants and failure analysis laboratories, and failure analyses conducted specifically for this project. Much of the information contained in this report involves cracking problems experienced in recovery boiler floors and those aspects of spout and air-port-opening cracking not readily attributable to thermal fatigue. 61 refs.

  3. Search for correlations between solar flares and decay rate of radioactive nuclei

    E-Print Network [OSTI]

    E. Bellotti; C. Broggini; G. Di Carlo; M. Laubenstein; R. Menegazzo

    2013-02-05

    The deacay rate of three different radioactive sources 40K, 137Cs and natTh has been measured with NaI and Ge detectors. Data have been analyzed to search for possible variations in coincidence with the two strongest solar flares of the years 2011 and 2012. No significant deviations from standard expectation have been observed, with a few 10-4 sensitivity. As a consequence, we could not find any effect like that recently reported by Jenkins and Fischbach: a few per mil decrease in the decay rate of 54Mn during solar flares in December 2006.

  4. 1 INSTRODUCTION In the concept of geological radioactive waste disposal,

    E-Print Network [OSTI]

    Boyer, Edmond

    1 INSTRODUCTION In the concept of geological radioactive waste disposal, argillite is being-hydro-mechanical characterization of Opalinus clay are presented. The material is one of the argillites being studied in several research projects in Europe in the context of geological radioactive waste disposal. 2 MATERIAL STUDIED

  5. STUDY OF RADIOACTIVE IMPURITIES IN SOLIDS PART ONE : RADIATION CHARACTERISTICS

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    285 STUDY OF RADIOACTIVE IMPURITIES IN SOLIDS PART ONE : RADIATION CHARACTERISTICS F. HARTMANN problem of the emission of radiation by radioactive nuclei is usually treated in a very general form for the computation of relaxation and radiofrequency effects. LE JOURNAL DE PHYSIQUE TOME 33, F√?VRIER-MARS 1972

  6. GEONEUTRINOS AND THE RADIOACTIVE POWER OF THE EARTH

    E-Print Network [OSTI]

    Mcdonough, William F.

    % of this radioactive power (3≠8 TW) escapes to space in the form of geoneutrinos. The remaining 11≠38 TW heats observations in Japan and Italy find consistent values of radiogenic heat- ing. The combined result mildlyGEONEUTRINOS AND THE RADIOACTIVE POWER OF THE EARTH S. T. Dye1,2 Received 4 April 2012; revised 15

  7. Radioactive Effluents from Nuclear Power Plants Annual Report 2008

    SciTech Connect (OSTI)

    U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

    2010-12-10

    This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2008. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

  8. Radioactive Effluents from Nuclear Power Plants Annual Report 2007

    SciTech Connect (OSTI)

    U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

    2010-12-10

    This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2007. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

  9. A Regulators' Guide to the Management of Radioactive

    E-Print Network [OSTI]

    Innovation); Fred Ferate (U.S. Department of Transportation, Radioactive Materials Branch); and CatherineA Regulators' Guide to the Management of Radioactive Residuals from Drinking Water Treatment (U.S. EPA's Office of Solid Waste and Emergency Response, Office of Site Remediation and Technology

  10. Radioactive Waste Information for 1998 and Record-To-Date

    SciTech Connect (OSTI)

    D. L. French; R. E. Tallman; K. A. Taylor

    1999-07-01

    This document presents detailed data, bar graphs, and pie charts on volume, radioactivity; isotopic identity, origin, and status of radioactive waste for calendar year 1998 at the Idaho National Engineering and Environmental Laboratory (INEEL). The data presented are from the INEEL Integrated Waste Information System.

  11. Crude Distillation Unit Heat Recovery Study†

    E-Print Network [OSTI]

    John, P.

    1979-01-01

    Baytown's Pipe Still 3 is a 95,000 barrel per day crude distillation unit. A comprehensive heat recovery and energy utilization study was done on Pipe Still 3 after a preliminary cursory study had indicated that an overall look at the total picture...

  12. Sparse Brain Network Recovery under Compressed Sensing

    E-Print Network [OSTI]

    Chung, Moo K.

    a small set of noisy measurements. We briefly show that the penalized linear regression for partial for a sparse brain network recovery. As an illustration, we construct sparse brain networks of 97 regions the government of Korea to M.K.C., by grant No. R31-2008-000-10103-0 from the WCU project of the MEST and the NRF

  13. Indirect Cost Recovery (ICR) Sharing Policy Introduction

    E-Print Network [OSTI]

    Indiana University

    Indirect Cost Recovery (ICR) Sharing Policy Introduction The school receives the majority (~95 to have annual gross research expenditures (direct + indirect costs) greater than $500,000. The percentage explanation. ICR Return to Large Centers with Additional Operational Costs (NEW 7/1/2013) Once research

  14. Disaster Resiliency and Recovery: Capabilities (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2012-11-01

    The National Renewable Energy Laboratory (NREL) is the nation's leader in energy efficient and renewable energy technologies, practices, and strategies. For the last 15 years, NREL has provided expertise, tools, and innovations to private industry; federal, state, and local governments; non-profit organizations; and communities during the planning, recovery, and rebuilding stages after disaster strikes.

  15. An Integrated Low Level Heat Recovery System†

    E-Print Network [OSTI]

    Sierra, A. V., Jr.

    1981-01-01

    A large amount of low level thermal energy is lost to air or water in a typical petroleum refinery. This paper discusses a complex integrated low level heat recovery system that is being engineered for installation in a large petroleum refinery...

  16. Energy Recovery from Potato Chip Fryers†

    E-Print Network [OSTI]

    McKee, H. B.; Kympton, H. W.; Arnold, J. W.; Paisan, J. J.

    1980-01-01

    permits heat recovery from the fryer cooking fumes. The fumes consist primarily of water vapor (11 psia) and air (3.7 psia) at a temperature of 275 F. About 10% of the available energy is dissipated in a scrubber which removes particulate material...

  17. Recovery Act Weekly Video: 200 West Drilling

    ScienceCinema (OSTI)

    None

    2012-06-14

    President of Cascade Drilling, Bruce, talks about his contract with the Department of Energy and what his team is doing to improve water treatment and environmental cleanup. The small business owner hits on how the Recovery Act saved him from downsizing and helped him stay competitive and safe on site.

  18. Rankine cycle waste heat recovery system

    DOE Patents [OSTI]

    Ernst, Timothy C.; Nelson, Christopher R.

    2014-08-12

    This disclosure relates to a waste heat recovery (WHR) system and to a system and method for regulation of a fluid inventory in a condenser and a receiver of a Rankine cycle WHR system. Such regulation includes the ability to regulate the pressure in a WHR system to control cavitation and energy conversion.

  19. Asynchronous intrusion recovery for interconnected web services

    E-Print Network [OSTI]

    Sabatini, David M.

    Asynchronous intrusion recovery for interconnected web services Ramesh Chandra, Taesoo Kim, and tracking down and recovering from such an attack re- quires significant manual effort. Web services for such web services. Aire addresses several challenges, such as propagating repair across services when some

  20. Characterization of Class A low-level radioactive waste 1986--1990. Volume 3: Main report -- Part B

    SciTech Connect (OSTI)

    Dehmel, J.C.; Loomis, D.; Mauro, J. [S. Cohen & Associates, Inc., McLean, VA (United States); Kaplan, M. [Eastern Research Group, Inc., Lexington, MA (United States)

    1994-01-01

    Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG&G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the waste from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 to 7 contain Appendices A to P with supporting information.