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Sample records for radionuclides final rule

  1. Title XVII Final Rule | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Rule Title XVII Final Rule Title XVII Final Rule (107.56 KB) More Documents & Publications Final Rule (December 4, 2009) Notice of Proposed Rulemaking (August 6, 2009) Final Rule (October 23, 2007)

  2. Interim Final Rule and Proposed Rule | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Interim Final Rule and Proposed Rule Interim Final Rule and Proposed Rule Extracted Pages from the Interim Final Rule and Proposed Rule, September 19, 2008 Interim Final Rule and Proposed Rule (111.06 KB) More Documents & Publications Comments of the Staff of the public utilities commission of the state of California on the interim final rule Comments on Notice of Proposed Rulemaking for Coordination of Federal Authorizations for Electric Transmission Facilities Changes recommended by OIRA

  3. Final Rule (October 23, 2007)

    Energy.gov [DOE]

    Loan Guarantees for Projects That Employ Innovative Technologies; Final Rule: On May 16, 2007, the Department of Energy (DOE or the Department) published a Notice of Proposed Rulemaking and opportunity for comment (NOPR) to establish regulations for the loan guarantee program authorized by Title XVII of the Energy Policy Act of 2005 (Title XVII or the Act).

  4. Final Rule Technical Amendment | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Rule Technical Amendment Federal Register Announcement: The Department of Energy (DOE) is publishing this technical amendment to the regulations for the loan guarantee ...

  5. Radionuclides in Western coal. Final report

    SciTech Connect

    Abbott, D.T.; Styron, C.E.; Casella, V.R.

    1983-09-23

    The increase in domestic energy production coupled with the switch from oil and natural gas to coal as a boiler-fuel source have prompted various federal agencies to assess the potential environmental and health risks associated with coal-fired power plants. Because it has been suggested that Western coals contain more uranium than Eastern coals, particular concern has been expressed about radioactive emissions from the increasing number of power plants that burn low-sulfur Western coal. As a result, the radionuclides in coal program was established to analyze low-sulfur coal reserves in Western coal fields for radioactivity. Samples from seams of obvious commercial value were taken from 19 operating mines that represented 65% of Western coal production. Although the present study did not delve deeply into underlying causative factors, the following general conclusions were reached. Commercially exploited Western coals do not show any alarming pattern of radionuclide content and probably have lower radioactivity levels than Eastern coals. The materials that were present appeared to be in secular equilibrium in coal, and a detailed dose assessment failed to show a significant hazard associated with the combustion of Western coal. Flue gas desulfurization technology apparently has no significant impact on radionuclide availability, nor does it pose any significant radiologic health risks. This study has also shown that Western coals are not more radioactive than most soils and that most solid combustion products have emanation powers <1%, which greatly reduce dose estimates from this pathway. In summary, the current use of mined, Western coals in fossil-fueled power plants does not present any significant radiological hazard.

  6. 10 cfr 851 final rule

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    59 Federal Register / Vol. 71, No. 27 / Thursday, February 9, 2006 / Rules and Regulations On March 23, 2005, DOE held a televideo forum to provide DOE contractors, contractor employees, and their representatives with the opportunity to ask questions and receive clarification on the provisions of the supplemental proposed rule. The public comment period for the supplemental proposal ended on April 26, 2005. During this period, DOE received 62 comment letters from private individuals, DOE

  7. CONTRACTOR LEGAL MANAGEMENT REQUIREMENTS: FINAL RULE

    Energy.gov [DOE]

    The Department has issued a Final Rule revising the existing contractor regulations covering contractor legal management requirements at 10 C.F.R. 719 (Federal Register May 3, 2013; http://www.gpo.gov/fdsys/pkg/FR-2013-05-03/pdf/2013-10485.pdf). One unusual aspect of the Final Rule is that it requires Contracting Officers to attempt to execute bilateral modifications to existing affected contracts to apply the Final Rule's revisions to those contracts. We will issue an Acquisition Letter shortly with suggested contract modification language. (The Final Rule's revisions "… are designed to clarify and streamline existing requirements, improve efficiency of contractor legal management, and facilitate oversight over the expenditure of taxpayer dollars." The contract modifications will state the revisions will only apply to costs incurred from date the bilateral modifications are executed forward. The revisions are administrative in nature. Regarding costs contractors have not yet incurred, the revisions could have been communicated to contractors without using a Final Rule to incorporate them into current contracts. Consequently, the modifications do not require equitable adjustments.)

  8. Department of Energy Acquisition Regulation (DEAR) Final Rule...

    Energy.gov [DOE] (indexed site)

    Department of Energy Acquisition Regulation (DEAR) Final Rule for Subchapters A, B, and C ... Department of Energy Acquisition Regulation (DEAR) Final Rule for Subchapters A, B, ...

  9. Comments of NRDC on Department of Energy Interim Final Rule:...

    Office of Environmental Management (EM)

    NRDC on Department of Energy Interim Final Rule: Energy Conservation for New Federal ... Comments of NRDC on Department of Energy Interim Final Rule: Energy Conservation for New ...

  10. ATVM Interim Final Rule Correction | Department of Energy

    Energy.gov [DOE] (indexed site)

    A few corrections to the final rule regarding fuel economy numbers. ATVM Interim Final Rule Correction More Documents & Publications Updated Guidance For Applicants To Advanced...

  11. DOE Publishes Final Rule for Residential Furnace Fan Test Procedure...

    Energy Saver

    Final Rule for Residential Furnace Fan Test Procedure DOE Publishes Final Rule for Residential Furnace Fan Test Procedure January 3, 2014 - 12:00am Addthis The Department of Energy ...

  12. DOE Publishes Final Rule for Residential Furnace Fan Test Procedure

    Energy.gov [DOE]

    The Department of Energy (DOE) has published a final rule regarding test procedures for residential furnace fans.

  13. Federal Register Notice, CBDPP Final Rule | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Federal Register Notice, CBDPP Final Rule Federal Register Notice, CBDPP Final Rule December 8, 1999 Federal Register Notice, Final rule for 10 CFR part 850, CBDPP The Department of Energy (DOE) published a final rule to establish a chronic beryllium disease prevention program (CBDPP) to reduce the number of workers currently exposed to beryllium in the course of their work at DOE facilities managed by DOE or its contractors, minimize the levels of, and potential for, exposure to beryllium, and

  14. Energy Conservation Program: Final Rule; Test Procedures for...

    Energy.gov [DOE] (indexed site)

    Ceiling Fans TP FinalRule (601.19 KB) More Documents & Publications Energy Conservation Program: Energy Conservation Standards

  15. OSHA's Final Rule on Occupational Exposure to Respirable Crystalline

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Silica Presentation slides | Department of Energy OSHA's Final Rule on Occupational Exposure to Respirable Crystalline Silica Presentation slides OSHA's Final Rule on Occupational Exposure to Respirable Crystalline Silica Presentation slides May 12, 2016 David O'Connor's presentation of OSHA's Final Rule on Occupational Exposure to Respirable Crystalline Silica held during DOE's VTC/WebEx on May 12, 2016. OSHA's Final Rule on Occupational Exposure to Respirable Crystalline Silica

  16. Test Procedure for Compact Fluorescent Lamps: Final Rule | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Procedure for Compact Fluorescent Lamps: Final Rule Test Procedure for Compact Fluorescent Lamps: Final Rule This final rule amends the U.S. Department of Energy's (DOE) test procedures for medium base compact fluorescent lamps (MBCFLs) and adopts test procedures for new metrics for all CFLs including hybrid CFLs and CFLs with bases other than medium screw base. In this final rule, DOE replaces references to ENERGY STAR® testing requirements with references to the latest versions of

  17. Direct_Final_Rule_Bill.pdf | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    More Documents & Publications DOE Retrospective Review Plan Report May 2012 CONTRACTOR LEGAL MANAGEMENT REQUIREMENTS: FINAL RULE EA-1774-S1: Final Environmental Assessment and ...

  18. Energy Conservation Program: Final Rule; Test Procedures for Ceiling Fans |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Final Rule; Test Procedures for Ceiling Fans Energy Conservation Program: Final Rule; Test Procedures for Ceiling Fans Ceiling Fans TP Final_Rule (601.19 KB) More Documents & Publications Energy Conservation Program: Energy Conservation Standards for Ceiling Fans ISSUANCE 2015-05-26: Energy Conservation Program: Test Procedures for Ceiling Fans, Supplemental Notice of Proposed Rule 2014-09-19 Issuance: Energy Conservation Program for Consumer Products: Test Procedure

  19. DOE Publishes Final Rule for the Request for Exclusion of 100...

    Energy.gov [DOE] (indexed site)

    Articles DOE Publishes Final Rule for Residential Furnace Fan Test Procedure DOE Publishes Final Rule for Plumbing Products Test Procedures DOE Publishes Final Rule for Television...

  20. Publication of Final Rule for Department of Energy (DOE) Financial

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Assistance Regulations | Department of Energy Publication of Final Rule for Department of Energy (DOE) Financial Assistance Regulations Publication of Final Rule for Department of Energy (DOE) Financial Assistance Regulations PF2009-70.pdf (201.22 KB) More Documents & Publications Publication of Final Rule for Department of Energy (DOE) Financial Assistance Regulations Rescind Policy Flashes 2010-04 "Cease All Funding of the Association of Community Organizations for Reform Now

  1. CONTRACTOR LEGAL MANAGEMENT REQUIREMENTS: APPLYING THE FINAL RULE TO

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    EXISTING CONTRACTS | Department of Energy CONTRACTOR LEGAL MANAGEMENT REQUIREMENTS: APPLYING THE FINAL RULE TO EXISTING CONTRACTS CONTRACTOR LEGAL MANAGEMENT REQUIREMENTS: APPLYING THE FINAL RULE TO EXISTING CONTRACTS The Department issued a Final Rule revising the regulations covering contractor legal management requirements at 10 C.F.R. 719 (Federal Register May 3, 2013; http://www.gpo.gov/fdsys/pkg/FR-2013-05-03/pdf/2013-10485.pdf). It requires Contracting Officers to attempt to execute

  2. Code of Federal Regulations Occupational Radiation Protection; Final Rule |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Occupational Radiation Protection; Final Rule Code of Federal Regulations Occupational Radiation Protection; Final Rule The Department of Energy (DOE) is amending its primary standards for occupational radiation protection. This final rule is the culmination of a systematic analysis to identify the elements of a comprehensive radiation protection program and determine those elements of such a program that should be codified as DOE continues its transition from a system

  3. Interim Final Rule and Request for Comments, Federal Register...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Document displays the interim final rule and request for comments for Energy Conservation Standards for New Federal Commercial and Multi-Family High-Rise Residential Buildings and ...

  4. OSHA's Final Rule on Occupational Exposure to Respirable Crystalline...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    MB) More Documents & Publications Construction Safety Advisory Committee, Meeting Minutes - May 11, 2000 Federal Register Notice, CBDPP Final Rule Approaches to Safe Nanotechnology

  5. DOE Publishes Final Rule for Plumbing Products Test Procedures

    Energy.gov [DOE]

    The Department of Energy has published a final rule regarding test procedures for showerheads, faucets, water closets, urinals, and commercial prerinse spray valves.

  6. Final Rule on Amending Eligibility Provisions to Multifamily...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Rule on Amending Eligibility Provisions to Multifamily Buildings for the Weatherization Assistance Program U.S. Department of Energy (DOE) Office of Energy Efficiency and ...

  7. AMO Industrial Distributed Energy: Summary of EPA Final Rules...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Summary of EPA Final Rules for Air Toxic Standards for Industrial, Commercial, and Institutional (ICI) Boilers and Process Heaters ICF International for U.S. Department of Energy...

  8. Department of Energy Acquisition Regulation (DEAR) Final Rule...

    Energy.gov [DOE] (indexed site)

    Department of Energy Acquisition Regulation (DEAR) Final Rule for changes to Parts 908, ... More Documents & Publications Department of Energy Acquisition Regulation (DEAR) Technical ...

  9. DOE Publishes Final Rule for Television Test Procedure | Department...

    Energy.gov [DOE] (indexed site)

    DOE Publishes Final Rule for Plumbing Products Test Procedures DOE Publishes Notice of Proposed Rulemaking Regarding the Compliance Date for the Dehumidifier Test Procedure...

  10. DOE Issues Test Procedure Final Rule & Publishes Energy Conservation...

    Energy.gov [DOE] (indexed site)

    issued a pre-publication Federal Register final rule regarding test procedures for electric motors. For more information, please visit the rulemaking page. Test Procedure: All...

  11. DOE Publishes Final Rule Regarding Post-Employment Restrictions

    Energy.gov [DOE]

    The Department of Energy published a final rule establishing procedures under which a former employee of the executive branch may obtain approval to make communications to DOE solely for the...

  12. SUMMARY OF FINAL RULES Item Subject FAR Case

    Energy.gov [DOE] (indexed site)

    SUMMARY OF FINAL RULES Item Subject FAR Case FAC 56-Miscellaneous I. Women-Owned Small Business Program 2010-015 II. Proper Use and Management of Cost-Reimbursement Contracts...

  13. FEDERAL ACQUISITION CIRCULAR 2005-56 SUMMARY OF FINAL RULES

    Energy.gov [DOE] (indexed site)

    SUMMARY OF FINAL RULES Item Subject FAR Case I. Women-Owned Small Business Program 2010-015 II. Proper Use and Management of Cost-Reimbursement Contracts 2008-030 III....

  14. EPA Final Ground Water Rule Available Online, 3/07

    Office of Energy Efficiency and Renewable Energy (EERE)

    On November 8, 2006, the U.S. Environmental Protection Agency (EPA) published a final Ground Water Rule (GWR) to promote increased protection against microbial pathogens that may be present in...

  15. Final Rule (December 4, 2009) | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    December 4, 2009) Final Rule (December 4, 2009) Loan Guarantees for Projects that Employ Innovative Technologies: On October 23, 2007, the Department of Energy published a final rule establishing regulations for the loan guarantee program authorized by Section 1703 of Title XVII of the Energy Policy Act of 2005. Section 1703 of Title XVII authorizes the Secretary of Energy to make loan guarantees for projects that "avoid, reduce, or sequester air pollutants or anthropogenic emissions of

  16. Microsoft Word - CCE_Final_Rule_02-07-11 _Final Word_.docx | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy CCE_Final_Rule_02-07-11 _Final Word_.docx Microsoft Word - CCE_Final_Rule_02-07-11 _Final Word_.docx Energy Conservation Program: Certification, Compliance, and Enforcement for Consumer Products and Commercial and Industrial Equipment Microsoft Word - CCE_Final_Rule_02-07-11 _Final Word_.docx (962.39 KB) More Documents & Publications Federal Register Vol. 76 No. 44, 12422-12505 - Energy Conservation Program: Certification, Compliance, and Enforcement for Consumer Products and

  17. Microsoft Word - Final 1703 NOPR _supercedes Final rule_ _2_.doc

    Energy Saver

    Energy 1 Million Electric Vehicle Report Final Microsoft Word - 1 Million Electric Vehicle Report Final Microsoft Word - 1 Million Electric Vehicle Report Final (219.14 KB) More Documents & Publications FY 2012 Annual Progress Report for Energy Storage R&D Hybrid Electric Systems Revolution Now: The Future Arrives for Five Clean Energy Technologies-2015 Update

    5 Annual Report I. Basic Information Regarding Report. A. Abel Lopez, Director FOIA/Privacy Act Group, MA-74 Office of the

  18. Summary of EPA Final Rules for Air Toxic Standards for Industrial...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Summary of EPA Final Rules for Air Toxic Standards for Industrial, Commercial, and Institutional (ICI) Boilers and Process Heaters, February 2013 Summary of EPA Final Rules for Air ...

  19. WPN 10-15: Final Rule on Amending Eligibility Provisions to Multifamil...

    Energy Saver

    WPN 10-15: Final Rule on Amending Eligibility Provisions to Multifamily Buildings for the Weatherization Assistance Program WPN 10-15: Final Rule on Amending Eligibility Provisions...

  20. DOE NEPA Implementing Procedures: Final Rule (61 Fed Reg 36222) |

    Energy Saver

    Department of Energy 36222) DOE NEPA Implementing Procedures: Final Rule (61 Fed Reg 36222) DOE amended its existing regulations governing compliance with the National Environmental Policy Act (NEPA). The amendments incorporate changes that improve DOE's efficiency in implementing NEPA requirements by reducing costs and preparation time while maintaining quality, consistent with the DOE Secretarial Policy Statement on NEPA issued in June 1994. These amendments also incorporate changes

  1. DOE NEPA Implementing Procedures: Final Rule (61 Fed Reg 64603) |

    Energy Saver

    Department of Energy 64603) DOE NEPA Implementing Procedures: Final Rule (61 Fed Reg 64603) DOE amended its regulations governing compliance with the National Environmental Policy Act (NEPA). These amendments incorporate changes primarily related to DOE's power marketing activities, based on DOE's experience in applying the current NEPA regulations. The revised regulations are intended to improve DOE's efficiency in implementing NEPA requirements by reducing costs and preparation time, while

  2. Discovering The Folding Rules That Proteins Obey FY08 LDRD Final...

    Office of Scientific and Technical Information (OSTI)

    Discovering The Folding Rules That Proteins Obey FY08 LDRD Final Report Citation Details In-Document Search Title: Discovering The Folding Rules That Proteins Obey FY08 LDRD Final ...

  3. File:08-03-12 FINAL Negotiated Draft Rule 20.03.15.pdf | Open...

    OpenEI (Open Energy Information) [EERE & EIA]

    03-12 FINAL Negotiated Draft Rule 20.03.15.pdf Jump to: navigation, search File File history File usage File:08-03-12 FINAL Negotiated Draft Rule 20.03.15.pdf Size of this preview:...

  4. Environmental Assessment for Final Rule, 10 CFR 43

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    "Energy Efficiency Standards for New Federal Commercial and High-Rise Multi-Family Residential Buildings" and 10 CFR 435, "Energy Efficiency Standards for New Federal Residential Low-Rise Residential Buildings" Baseline Standards Update (DOE/EA-1871) March 16, 2011 2 Environmental Assessment for Final Rule, 10 CFR 433, "Energy Efficiency Standards for New Federal Commercial and High-Rise Multi-Family Residential Buildings" and 10 CFR 435, "Energy Efficiency

  5. ATVM Loan Program Interim Final Rule (November 12, 2008) | Department of

    Energy Saver

    Energy Loan Program Interim Final Rule (November 12, 2008) ATVM Loan Program Interim Final Rule (November 12, 2008) Advanced Technology Vehicles Manufacturing Incentive Program ATVM Loan Program Interim Final Rule (130.09 KB) More Documents & Publications Automotive Trade Policy Council: Proposed Interim Final Rule Updated Guidance For Applicants To Advanced Technology Vehicles Manufacturing Loan Program ATVM Guidance for Applicants 11.4.14

  6. 2015-12-30 Energy Conservation Program: Test Procedure for Pumps Final Rule

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    | Department of Energy Test Procedure for Pumps Final Rule 2015-12-30 Energy Conservation Program: Test Procedure for Pumps Final Rule Test Procedure for Pumps Final Rule Pumps Test Procedure Final Rule.pdf (1.85 MB) More Documents & Publications Energy Conservation Program: Test Procedure for Pumps, Notice of Proposed Rulemaking Draft PEI Calculator ISSUANCE 2016-08-26: Energy Conservation Program: Test Procedure for Dedicated-Purpose Pool Pumps, Notice of Proposed Rulemaking

  7. SBA Final Rule affecting the 8(a) Business Development Program | Department

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    of Energy SBA Final Rule affecting the 8(a) Business Development Program SBA Final Rule affecting the 8(a) Business Development Program On February 11, 2011, the Small Business Administration (SBA) issued the attached final rule revising the regulations governing the 8(a) Business Development program, small business size regulations, and Small Disadvantaged Business (SDB) status determinations. The rule incorporates technical changes and substantive changes that mirror existing or new

  8. Environmental Assessment for Final Rule 10 CFR 433 | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    433 Environmental Assessment for Final Rule 10 CFR 433 Document details the U.S. Department of Energy's environmental assessment for Final Rule 10 CFR Part 433, Energy Efficiency Standards for New Federal Commercial and Multi-Family High-Rise Residential Buildings. Download the environmental assessment for Final Rule 10 CFR Part 433. (307.24 KB) More Documents & Publications EA-1918: Final Environmental Assessment EA-1918: Finding of No Significant Impact EA-1778: Draft Environmental

  9. Regulatory assessment: Final rule on structural measures for existing single-hull tankers. Final report

    SciTech Connect

    1996-11-01

    This Final Regulatory Assessment examines certain alternative pollution prevention measures on a selected range of existing single-hull tank vessel categories. The final rule assessment studies the cost and benefit variations if certain existing tank vessels were required to fit protectively located spaces or hydrostatically load cargo to standards equivalent to those in Regulation 13G of Annex I of the International Convention for the Prevention of Pollution from Ships, 1973, as modified by the Protocol of 1978 (MARPOL). The cost and benefit study was broken down by vessel type (international or domestic), gross tonnage, and type of cargo carried.

  10. GSA Federal Advisory Committee Management; Final Rule -- 41CFR Parts 101-6

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    and 102-3 | Department of Energy GSA Federal Advisory Committee Management; Final Rule -- 41CFR Parts 101-6 and 102-3 GSA Federal Advisory Committee Management; Final Rule -- 41CFR Parts 101-6 and 102-3 Federal Register document for the General Services Administration (GSA) revision of Federal Property Management Regulations (FPMR) coverage on federal advisory committee management and moving it into the Federal Management Regulation (FMR). Federal Advisory Committee Management; Final Rule

  11. ISSUANCE 2015-12-11: Final Rule Regarding Test Procedures for...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Procedures for Small, Large, and Very Large Air-Cooled Commercial Package Air Conditioning and Heating Equipment ISSUANCE 2015-12-11: Final Rule Regarding Test Procedures for ...

  12. ISSUANCE 2015-07-15: Energy Conservation Program: Test Procedure for Refrigerated Bottled or Canned Beverage Vending Machines, Final Rule

    Office of Energy Efficiency and Renewable Energy (EERE)

    Energy Conservation Program: Test Procedure for Refrigerated Bottled or Canned Beverage Vending Machines, Final Rule

  13. ISSUANCE 2016-03-24: Energy Conservation Program: Clarification of Test Procedures for Fluorescent Lamps Ballasts, Final Rule

    Office of Energy Efficiency and Renewable Energy (EERE)

    Energy Conservation Program: Clarification of Test Procedures for Fluorescent Lamps Ballasts, Final Rule

  14. ISSUANCE 2016-10-4: Energy Conservation Program: Energy Conservation Standards for Miscellaneous Refrigeration Products, Direct Final Rule

    Energy.gov [DOE]

    Energy Conservation Program: Energy Conservation Standards for Miscellaneous Refrigeration Products, Direct Final Rule

  15. ISSUANCE 2015-12-29: Energy Conservation Program: Energy Conservation Standards for Commercial Prerinse Spray Valves, Final Rule

    Office of Energy Efficiency and Renewable Energy (EERE)

    Energy Conservation Program: Energy Conservation Standards for Commercial Prerinse Spray Valves, Final Rule

  16. ISSUANCE 2014-12-31: Energy Conservation Program: Energy Conservation Standards for Automatic Commercial Ice Makers, Final Rule

    Energy.gov [DOE]

    Energy Conservation Program: Energy Conservation Standards for Automatic Commercial Ice Makers, Final Rule

  17. DOE Finalizes New Rule to Protect Trade Secrets and Confidential...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    new rule adopting a common approach across various assistance programs. The Department's proposal, modeled on procedures used by the Department's Advanced Technology Vehicles...

  18. DOE NEPA Implementing Procedures: Final Rule (57 Fed Reg 15122)

    Energy.gov [DOE]

    DOE revised the existing rule at 10 CFR part 1021, titled "Compliance with the National Environmental Policy Act," to incorporate revised provision of DOE's Guidelines for Implementing the Procedural Provisions of the National Environmental Policy Act (NEPA).

  19. DOE Announces Final Rule for Loan Guarantee Program | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Rule for Loan Guarantee Program DOE Announces Final Rule for Loan Guarantee Program October 4, 2007 - 3:14pm Addthis Invites 16 Pre-Applicants to Submit Applications for Federal Support of Innovative Clean Energy Projects WASHINGTON, DC - Secretary of Energy Samuel W. Bodman today announced that the Department of Energy (DOE) has issued the final regulations for the loan guarantee program authorized by Title XVII of the Energy Policy Act of 2005 (EPAct). DOE's action today will pave the

  20. Interim Final Rule and Request for Comments, Federal Register, 71 FR 70275,

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    10 CFR Part 433, 434, and 435, December 4, 2006 | Department of Energy Interim Final Rule and Request for Comments, Federal Register, 71 FR 70275, 10 CFR Part 433, 434, and 435, December 4, 2006 Interim Final Rule and Request for Comments, Federal Register, 71 FR 70275, 10 CFR Part 433, 434, and 435, December 4, 2006 Document displays the interim final rule and request for comments for Energy Conservation Standards for New Federal Commercial and Multi-Family High-Rise Residential Buildings

  1. DOE Issues Final Rule for Section 133 of the Energy Independence Act (Fact Sheet)

    SciTech Connect

    Not Available

    2014-04-01

    This fact sheet provides a summary of the final rule under Section 133 of the Energy Independence and Security Act of 2007 (EISA) that the U.S. Department of Energy (DOE) issued in March 2014.

  2. 2014-02-03 Issuance: Energy Conservation Standards for External Power Supplies; Final Rule

    Energy.gov [DOE]

    This document is a pre-publication Federal Register final rule prescribing new energy conservation standards for external power supplies, as issued by the Assistant Secretary on February 3, 2014.

  3. 2014-04-10 Issuance: Test Procedures for Refrigerators, Refrigerator-Freezers, and Freezers; Final Rule

    Energy.gov [DOE]

    This document is a pre-publication Federal Register final rule regarding test procedures for residential refrigerators and freezers, as issued by the Deputy Assistant Secretary for Energy Efficiency on April 10, 2014.

  4. Department of Energy Acquisition Regulation (DEAR) Final Rule for Subchapters A, B, and C

    Office of Energy Efficiency and Renewable Energy (EERE)

    Department of Energy Acquisition Regulation (DEAR) Final Rule for Subchapters A, B, and C was published February 11, 2011, in the Federal Register 76 FR 7685. The changes are effective March 14, 2011.

  5. DOE Issues Test Procedure Final Rule & Publishes Energy Conservation Standards NOPR for Electric Motors

    Energy.gov [DOE]

    The Department of Energy (DOE) has issued a pre-publication Federal Register final rule regarding test procedures and published a notice of proposed rulemaking (NOPR) regarding energy conservation standards for electric motors.

  6. U.S. HDV GHG and Fuel Efficiency Final Rule | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    U.S. HDV GHG and Fuel Efficiency Final Rule Reviews medium- and heavy-duty truck fuel efficiency and greenhouse gas emissions standards and reducing fuel consumption in a diverse ...

  7. DOE Issues Final Rule for Alternative Efficiency Determination Methods and Alternative Rating Methods

    Energy.gov [DOE]

    The Department of Energy has issued a pre-publication Federal Register final rule revising its existing regulations governing the use of particular methods as alternatives to testing for commercial heating, ventilating, air-conditioning, water heating, and refrigeration equipment.

  8. Conceptual model for regional radionuclide transport from a basalt repository site. Final draft, technical memorandum

    SciTech Connect

    Walton, W.C.; Voorhees, M.L.; Prickett, T.A.

    1980-05-23

    This technical memorandum was prepared to: (1) describe a typical basalt radionuclide repository site, (2) describe geologic and hydrologic processes associated with regional radionuclide transport in basalts, (3) define the parameters required to model regional radionuclide transport from a basalt repository site, and (4) develop a ''conceptual model'' of radionuclide transport from a basalt repository site. In a general hydrological sense, basalts may be described as layered sequences of aquifers and aquitards. The Columbia River Basalt, centered near the semi-arid Pasco Basin, is considered by many to be typical basalt repository host rock. Detailed description of the flow system including flow velocities with high-low hydraulic conductivity sequences are not possible with existing data. However, according to theory, waste-transport routes are ultimately towards the Columbia River and the lengths of flow paths from the repository to the biosphere may be relatively short. There are many physical, chemical, thermal, and nuclear processes with associated parameters that together determine the possible pattern of radionuclide migration in basalts and surrounding formations. Brief process descriptions and associated parameter lists are provided. Emphasis has been placed on the use of the distribution coefficient in simulating ion exchange. The use of the distribution coefficient approach is limited because it takes into account only relatively fast mass transfer processes. In general, knowledge of hydrogeochemical processes is primitive.

  9. Environmental Assessment for Final Rule 10 CFR Parts 433 and 435 |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Parts 433 and 435 Environmental Assessment for Final Rule 10 CFR Parts 433 and 435 Document details the U.S. Department of Energy's environmental assessment for final rule, 10 CFR Part 433, Energy Efficiency Standards for New Federal Commercial and High-Rise Multi-Family Residential Buildings and 10 CFR Part 435, Energy Efficiency Standards for New Federal Residential Low-Rise Residential Buildings Baseline Standards Update (DOE/EA-1871). Download the Environmental

  10. Comments of NRDC on Department of Energy Interim Final Rule: Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Conservation for New Federal Commercial and Multi-Family High-Rise Residential Buildings and New Federal Low-Rise Residential Buildings | Department of Energy NRDC on Department of Energy Interim Final Rule: Energy Conservation for New Federal Commercial and Multi-Family High-Rise Residential Buildings and New Federal Low-Rise Residential Buildings Comments of NRDC on Department of Energy Interim Final Rule: Energy Conservation for New Federal Commercial and Multi-Family High-Rise

  11. WPN 10-15: Final Rule on Amending Eligibility Provisions to Multifamily

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Buildings for the Weatherization Assistance Program | Department of Energy 5: Final Rule on Amending Eligibility Provisions to Multifamily Buildings for the Weatherization Assistance Program WPN 10-15: Final Rule on Amending Eligibility Provisions to Multifamily Buildings for the Weatherization Assistance Program Effective: March 2, 2010 To issue guidance on implementing recent changes to the WAP requirements for determining eligibility of certain multifamily buildings as identified by HUD

  12. Estimate of radionuclide release characteristics into containment under severe accident conditions. Final report

    SciTech Connect

    Nourbakhsh, H.P.

    1993-11-01

    A detailed review of the available light water reactor source term information is presented as a technical basis for development of updated source terms into the containment under severe accident conditions. Simplified estimates of radionuclide release and transport characteristics are specified for each unique combination of the reactor coolant and containment system combinations. A quantitative uncertainty analysis in the release to the containment using NUREG-1150 methodology is also presented.

  13. 2014-04-07 Issuance: Energy Conservation Standards for Certain Consumer Products; Final Rule

    Energy.gov [DOE]

    This document is a pre-publication Federal Register final rule regarding the definitions for "through-the-wall central air conditioner" and "through-the-wall central air conditioning heat pump" that were established in section 5 of the American Energy Manufacturing Technical Corrections Act, as issued by the Assistant Secretary on April 7, 2014.

  14. ISSUANCE 2015-12-24: Energy Conservation Program: Energy Conservation Standards for Refrigerated Bottled or Canned Beverage Vending Machines, Final Rule

    Energy.gov [DOE]

    Energy Conservation Program: Energy Conservation Standards for Refrigerated Bottled or Canned Beverage Vending Machines, Final Rule

  15. Final Technical Report: Viral Infection of Subsurface Microorganisms and Metal/Radionuclide Transport

    SciTech Connect

    Weber, Karrie A.; Bender, Kelly S.; Li, Yusong

    2013-09-28

    Microbially mediated metabolisms have been identified as a significant factor either directly or indirectly impacting the fate and transport of heavy metal/radionuclide contaminants. To date microorganisms have been isolated from contaminated environments. Examination of annotated finished genome sequences of many of these subsurface isolates from DOE sites, revealed evidence of prior viral infection. To date the role that viruses play influencing microbial mortality and the resulting community structure which directly influences biogeochemical cycling in soils and sedimentary environments remains poorly understood. The objective of this exploratory study was to investigate the role of viral infection of subsurface bacteria and the formation of contaminant-bearing viral particles. This objective was approached by examining the following working hypotheses: (i) subsurface microorganisms are susceptible to viral infections by the indigenous subsurface viral community, and (ii) viral surfaces will adsorb heavy metals and radionuclides. Our results have addressed basic research needed to accomplish the BER Long Term Measure to provide sufficient scientific understanding such that DOE sites would be able to incorporate coupled physical, chemical and biological processes into decision making for environmental remediation or natural attenuation and long-term stewardship by establishing viral-microbial relationships on the subsequent fate and transport of heavy metals and radionuclides. Here we demonstrated that viruses play a significant role in microbial mortality and community structure in terrestrial subsurface sedimentary systems. The production of viral-like particles within subsurface sediments in response to biostimulation with dissolved organic carbon and a terminal electron acceptor resulted in the production of viral-like particles. Organic carbon alone did not result in significant viral production and required the addition of a terminal electron acceptor

  16. Surface and subsurface cleanup protocol for radionuclides, Gunnison, Colorado, UMTRA project processing site. Final [report

    SciTech Connect

    Not Available

    1993-09-01

    Surface and subsurface soil cleanup protocols for the Gunnison, Colorado, processing sits are summarized as follows: In accordance with EPA-promulgated land cleanup standards (40 CFR 192), in situ Ra-226 is to be cleaned up based on bulk concentrations not exceeding 5 and 15 pCi/g in 15-cm surface and subsurface depth increments, averaged over 100-m{sup 2} grid blocks, where the parent Ra-226 concentrations are greater than, or in secular equilibrium with, the Th-230 parent. A bulk interpretation of these EPA standards has been accepted by the Nuclear Regulatory Commission (NRC), and while the concentration of the finer-sized soil fraction less than a No. 4 mesh sieve contains the higher concentration of radioactivity, the bulk approach in effect integrates the total sample radioactivity over the entire sample mass. In locations where Th-230 has differentially migrated in subsoil relative to Ra-226, a Th-230 cleanup protocol has been developed in accordance with Supplemental Standard provisions of 40 CFR 192 for NRC/Colorado Department of Health (CDH) approval for timely implementation. Detailed elements of the protocol are contained in Appendix A, Generic Protocol from Thorium-230 Cleanup/Verification at UMTRA Project Processing Sites. The cleanup of other radionuclides or nonradiological hazards that pose a significant threat to the public and the environment will be determined and implemented in accordance with pathway analysis to assess impacts and the implications of ALARA specified in 40 CFR 192 relative to supplemental standards.

  17. Final Rule on Amending Eligibility Provisions to Multifamily Buildings for the Weatherization Assistance Program

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    WEATHERIZATION PROGRAM NOTICE 10-15 EFFECTIVE DATE: March 2, 2010 SUBJECT: FINAL RULE ON AMENDING ELIGIBILITY PROVISIONS TO MULTI-FAMILY BUILDINGS FOR THE WEATHERIZATION ASSISTANCE PROGRAM PURPOSE: To issue guidance on implementing recent changes to the Weatherization Assistance Program (WAP) requirements for determining eligibility of certain multi-family buildings as identified by the Department of Housing and Urban Development (HUD) and the Department of Agriculture (USDA). LEGAL AUTHORITY:

  18. 2015-01-28 Issuance: Test Procedure for Fluorescent Lamp Ballasts; Final Rule Correction

    Energy.gov [DOE]

    This document is a pre-publication Federal Register final rule correction regarding test procedures for fluorescent lamp ballasts, as issued by the Deputy Assistant Secretary for Energy Efficiency on January 28, 2014. Though it is not intended or expected, should any discrepancy occur between the document posted here and the document published in the Federal Register, the Federal Register publication controls. This document is being made available through the Internet solely as a means to facilitate the public's access to this document.

  19. 2014-11-24 Issuance: Test Procedures for Commercial Clothes Washers; Final Rule

    Energy.gov [DOE]

    This document is a pre-publication Federal Register Final Rule regarding test procedures for commercial clothes washers, as issued by the Deputy Assistant Secretary for Energy Efficiency on November 24, 2014. Though it is not intended or expected, should any discrepancy occur between the document posted here and the document published in the Federal Register, the Federal Register publication controls. This document is being made available through the Internet solely as a means to facilitate the public's access to this document.

  20. Scale-Dependent Fracture-Matrix Interactions And Their Impact on Radionuclide Transport - Final Report

    SciTech Connect

    Detwiler, Russell

    2014-06-30

    Matrix diffusion and adsorption within a rock matrix are widely regarded as important mechanisms for retarding the transport of radionuclides and other solutes in fractured rock (e.g., Neretnieks, 1980; Tang et al., 1981; Maloszewski and Zuber, 1985; Novakowski and Lapcevic, 1994; Jardine et al., 1999; Zhou and Xie, 2003; Reimus et al., 2003a,b). When remediation options are being evaluated for old sources of contamination, where a large fraction of contaminants reside within the rock matrix, slow diffusion out of the matrix greatly increases the difficulty and timeframe of remediation. Estimating the rates of solute exchange between fractures and the adjacent rock matrix is a critical factor in quantifying immobilization and/or remobilization of DOE-relevant contaminants within the subsurface. In principle, the most rigorous approach to modeling solute transport with fracture-matrix interaction would be based on local-scale coupled advection-diffusion/dispersion equations for the rock matrix and in discrete fractures that comprise the fracture network (Discrete Fracture Network and Matrix approach, hereinafter referred to as DFNM approach), fully resolving aperture variability in fractures and matrix property heterogeneity. However, such approaches are computationally demanding, and thus, many predictive models rely upon simplified models. These models typically idealize fracture rock masses as a single fracture or system of parallel fractures interacting with slabs of porous matrix or as a mobile-immobile or multi-rate mass transfer system. These idealizations provide tractable approaches for interpreting tracer tests and predicting contaminant mobility, but rely upon a fitted effective matrix diffusivity or mass-transfer coefficients. However, because these fitted parameters are based upon simplified conceptual models, their effectiveness at predicting long-term transport processes remains uncertain. Evidence of scale dependence of effective matrix diffusion

  1. Application of innovative policies for controlling radionuclide releases: The {open_quotes}open-market trading rule{close_quotes}

    SciTech Connect

    Moeller, D.W.

    1997-08-01

    In the past, most efforts for reducing airborne radio nuclide releases and controlling radioactive wastes have been directed to the development of new and improved technologies. Little attention has been paid to the possible application to these problems of new, innovative policies. Yet, experience in other fields shows that such applications could be beneficial. A prime example is the {open_quotes}open-market trading rule,{close_quotes} now being widely used in the U.S. for the control of a range of environmental problems. Through this rule, nuclear facility operators would be permitted to control airborne emissions in a more cost-effective manner, and those responsible for decommissioning and decontaminating nuclear facilities no longer in operation could do so at far lower costs while generating significantly smaller volumes of radioactive wastes. Application of such a policy would also significantly reduce the demands on existing, and the need for research to develop new, improved, control technologies. 16 refs.

  2. 2014-06-27 Issuance: Test Procedures for Residential and Commercial Water Heaters; Final Rule

    Office of Energy Efficiency and Renewable Energy (EERE)

    This document is a pre-publication Federal Register final rule regarding test procedures for residential and commercial water heaters, as issued by the Deputy Assistant Secretary for Energy Efficiency on June 27, 2014. Though it is not intended or expected, should any discrepancy occur between the document posted here and the document published in the Federal Register, the Federal Register publication controls. This document is being made available through the Internet solely as a means to facilitate the public's access to this document.

  3. ISSUANCE 2015-06-08: Energy Conservation Program: Test Procedures for Packaged Terminal Air Conditioners and Packaged Terminal Heat Pumps, Final Rule

    Office of Energy Efficiency and Renewable Energy (EERE)

    Energy Conservation Program: Test Procedures for Packaged Terminal Air Conditioners and Packaged Terminal Heat Pumps, Final Rule

  4. ISSUANCE 2015-06-30: Energy Conservation Program: Energy Conservation Standards for Packaged Terminal Air Conditioners and Packaged Terminal Heat Pumps, Final Rule

    Energy.gov [DOE]

    Energy Conservation Program: Energy Conservation Standards for Packaged Terminal Air Conditioners and Packaged Terminal Heat Pumps, Final Rule

  5. ISSUANCE 2015-8-28: Energy Conservation Program: Energy Conservation Standards for Single Package Vertical Air Conditioners and Single Package Vertical Heat Pumps, Final Rule

    Energy.gov [DOE]

    Energy Conservation Program: Energy Conservation Standards for Single Package Vertical Air Conditioners and Single Package Vertical Heat Pumps, Final Rule

  6. ISSUANCE 2014-12-23: Energy Conservation Program for Consumer Products: Test Procedures for Direct Heating Equipment and Pool Heaters, Final Rule

    Energy.gov [DOE]

    Energy Conservation Program for Consumer Products: Test Procedures for Direct Heating Equipment and Pool Heaters, Final Rule

  7. Estimates of health risks associated with radionuclide emissions from fossil-fueled steam-electric generating plants. Final report

    SciTech Connect

    Nelson, C.

    1995-08-01

    Under the Title III, Section 112 of the 1990 Clean Air Act Amendment, Congress directed the U.S. Environmental Protection Agency (EPA) to perform a study of the hazards to public resulting from pollutants emitted by electric utility system generating units. Radionuclides are among the groups of pollutants listed in the amendment. This report updates previously published data and estimates with more recently available information regarding the radionuclide contents of fossil fuels, associated emissions by steam-electric power plants, and potential health effects to exposed population groups.

  8. Radionuclide trap

    DOEpatents

    McGuire, Joseph C.

    1978-01-01

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

  9. Department of Energy Acquisition Regulation (DEAR) Final Rule for changes to Parts 908, 945, 952, and 970 regarding Government Property

    Office of Energy Efficiency and Renewable Energy (EERE)

    Department of Energy Acquisition Regulation (DEAR) Final Rule for changes to Parts 908, 945, 952, and 970 regarding Government Property was published December 14, 2012, in the Federal Register 77 FR 74382 (attachment). The changes were effective January 14, 2013. The website has a searchable electronic DEAR.

  10. Policy Flash 2013-23 Department of Energy Acquisition Regulation (DEAR) Final Rule for changes to Parts 908, 945, 952, and 970 regarding Government Property

    Energy.gov [DOE]

    Attached is Policy Flash 2013-23 Department of Energy Acquisition Regulation (DEAR) Final Rule for changes to Parts 908, 945, 952, and 970 regarding Government Property.

  11. ISSUANCE 2015-12-11: Final Rule Regarding Test Procedures for Small, Large, and Very Large Air-Cooled Commercial Package Air Conditioning and Heating Equipment

    Energy.gov [DOE]

    Final Rule Regarding Test Procedures for Small, Large, and Very Large Air-Cooled Commercial Package Air Conditioning and Heating Equipment

  12. DOE Publishes Final Rule for the Request for Exclusion of 100 Watt R20 Short Incandescent Reflector Lamps from Energy Conservation Standards

    Energy.gov [DOE]

    The Department of Energy has published a final rule regarding the request for exclusion of 100 Watt R20 short incandescent reflector lamps from energy conservation standards.

  13. Effect of Water Radiolysis Caused by Dispersed Radionuclides on Oxidative Dissolution of Spent Fuel in a Final Repository

    SciTech Connect

    Liu Jinsong; Neretnieks, Ivars

    2001-08-15

    When released out of a canister, the radionuclides originally incorporated in the spent fuel can still deposit radiation energy (even more efficiently) into the pore water, cause water radiolysis, and produce oxidants in the buffering material. This phenomenon is termed secondary water radiolysis. The oxidants thus produced can possibly diffuse back to oxidize the spent fuel and to increase the oxidative dissolution rate of the fuel.The effect of the secondary water radiolysis has been identified and preliminarily addressed by a mass-balance model. To explore whether the effect is significant on spent-fuel dissolution, the upper-boundary limit of the effect has been set up by considering a scenario that is very unlikely to occur. Several extreme assumptions have been made: First, the canister fails completely 10{sup 3} yr after deposition; second, the spent fuel is oxidized instantaneously; and third, the radionuclides considered are those that dominantly contribute to radiolysis between 10{sup 3} to 10{sup 5} yr. With these assumptions, the spent-fuel dissolution rate can be increased dramatically if 10% or more of the oxidants produced by the secondary water radiolysis diffuse back to oxidize the spent fuel. It thus indicates that the effect of the secondary water radiolysis could be significant with some extreme assumptions. With more realistic assumptions, the effect could possibly become minimal. The subject is worth further investigation.

  14. 57 Fed Reg 15122: DOE NEPA Implementing Procedures-Final Rule

    Energy.gov [DOE]

    The Department of Energy (DOE) is revising the existing rule at 10 CFR part 1021, titled "Compliance with the National Environmental Policy Act," to incorporate revised provisions of DOE's...

  15. DOE Finalizes New Rule to Protect Trade Secrets and Confidential Business Information

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Department of Energy today announced that it has issued a new rule standardizing how private parties applying for DOE assistance should submit trade secrets and other confidential business...

  16. Surface and subsurface cleanup protocol for radionuclides Gunnison, Colorado, UMTRA Project Processing Site. Revision 3, Final report

    SciTech Connect

    Not Available

    1994-05-01

    The supplemental standards provisions of Title 40, Code of Federal Regulations, Part 192 (40 CFR Part 192) require the cleanup of radionuclides other than radium-226 (Ra-226) to levels ``as low as reasonably achievable`` (ALARA), taking into account site-specific conditions, if sufficient quantities and concentrations are present to constitute a significant radiation hazard. In this context, thorium-230 (Th-230) at the Gunnison, Colorado, processing site will require remediation. However, a seasonally fluctuating groundwater table at the site significantly complicates conventional remedial action with respect to cleanup. Characterization data indicate that in the offpile areas, the removal of residual in situ bulk Ra-226 and Th-230 such that the 1000-year projected Ra-226 concentration (Ra-226 concentration in 1000 years due to the decay of in situ Ra-226 and the in-growth of Ra-226 from in situ Th-230) complies with the US Environmental Protection Agency (EPA) cleanup standard for in situ Ra-226 and the cleanup protocol for in situ Th-230 can be readily achieved using conventional excavation techniques for bulk contamination without encountering significant impacts due to groundwater. The EPA cleanup standard and criterion for Ra-226 and the 1000-year projected Ra-226 are 5 and 15 picocuries per gram (pCi/g) above background, respectively, averaged over 15-centimeter (cm) deep surface and subsurface intervals and 100-square-meter (m{sup 2}) grid areas. Significant differential migration of Th-230 relative to Ra-226 has occurred over 40 percent of the subpile area. To effectively remediate the site with respect to Ra-226 and Th-230, supplemental standard is proposed and discussed in this report.

  17. Dandruff, seborrheic dermatitis, and psoriasis drug products containing coal tar and menthol for over-the-counter human use; amendment to the monograph. Final rule

    SciTech Connect

    2006-03-15

    The Food and Drug Administration (FDA) is issuing a final rule amending the final monograph (FM) for over-the-counter (OTC) dandruff, seborrheic dermatitis, and psoriasis drug products to include the combination of 1.8 percent coal tar solution and 1.5 percent menthol in a shampoo drug product to control dandruff. FDA did not receive any comments or data in response to its previously proposed rule to include this combination. This final rule is part of FDA's ongoing review of OTC drug products.

  18. Final Rule, Federal Register, 72 FR 72565, 10 CFR Parts 433,...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Document displays the final rulemaking for Energy Conservation Standards for New Federal Commercial and Multi-Family High-Rise Residential Buildings and New Federal Low-Rise ...

  19. Final Rule, Federal Register, 74 FR 10830, 10 CFR Part 436, March 13, 2009

    Energy.gov [DOE]

    Document details the final rulemaking for the Federal Procurement of Energy-Efficient Products, which was published in the Federal Register on March 13, 2009.

  20. 30 TAC, part 1, chapter 116, rule 116.137 Notification of Final...

    OpenEI (Open Energy Information) [EERE & EIA]

    provided of final action by the Texas Commission on Environmental Quality referencing air quality control permits. Published NA Year Signed or Took Effect 1993 Legal Citation...

  1. GSA Federal Advisory Committee Management; Final Rule -- 41CFR Parts 101-6 and 102-3

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    7:39 Jul 18, 2001 Jkt 194001 PO 00000 Frm 00001 Fmt 4717 Sfmt 4717 E:\FR\FM\19JYR2.SGM pfrm01 PsN: 19JYR2 Thursday, July 19, 2001 Part II General Services Administration 41 CFR Parts 101-6 and 102-3 Federal Advisory Committee Management; Final Rule VerDate 11<MAY>2000 17:39 Jul 18, 2001 Jkt 194001 PO 00000 Frm 00002 Fmt 4701 Sfmt 4700 E:\FR\FM\19JYR2.SGM pfrm01 PsN: 19JYR2 37728 Federal Register / Vol. 66, No. 139 / Thursday, July 19, 2001 / Rules and Regulations GENERAL SERVICES

  2. 2014-07-10 Issuance: Test Procedures for Refrigerators, Refrigerator-Freezers, and Freezers; Final Rule Correction

    Energy.gov [DOE]

    This document is a pre-publication Federal Register final rule correction regarding test procedures for refrigerators, refrigerator-freezers, and freezers, as issued by the Deputy Assistant Secretary for Energy Efficiency on July 10, 2014. Though it is not intended or expected, should any discrepancy occur between the document posted here and the document published in the Federal Register, the Federal Register publication controls. This document is being made available through the Internet solely as a means to facilitate the public's access to this document.

  3. Reactor-Produced Medical Radionuclides

    SciTech Connect

    Mirzadeh, Saed; Mausner, Leonard; Garland, Marc A

    2011-01-01

    The therapeutic use of radionuclides in nuclear medicine, oncology and cardiology is the most rapidly growing use of medical radionuclides. Since most therapeutic radionuclides are neutron rich and decay by beta emission, they are reactor-produced. This chapter deals mainly with production approaches with neutrons. Neutron interactions with matter, neutron transmission and activation rates, and neutron spectra of nuclear reactors are discussed in some detail. Further, a short discussion of the neutron-energy dependence of cross sections, reaction rates in thermal reactors, cross section measurements and flux monitoring, and general equations governing the reactor production of radionuclides are presented. Finally, the chapter is concluded by providing a number of examples encompassing the various possible reaction routes for production of a number of medical radionuclides in a reactor.

  4. Mobility of Source Zone Heavy Metals and Radionuclides: The Mixed Roles of Fermentative Activity on Fate and Transport of U and Cr. Final Report

    SciTech Connect

    Gerlach, Robin; Peyton, Brent M.; Apel, William A.

    2014-01-29

    Various U. S. Department of Energy (DOE) low and medium-level radioactive waste sites contain mixtures of heavy metals, radionuclides and assorted organic materials. In addition, there are numerous sites around the world that are contaminated with a mixture of organic and inorganic contaminants. In most sites, over time, water infiltrates the wastes, and releases metals, radionuclides and other contaminants causing transport into the surrounding environment. We investigated the role of fermentative microorganisms in such sites that may control metal, radionuclide and organics migration from source zones. The project was initiated based on the following overarching hypothesis: Metals, radionuclides and other contaminants can be mobilized by infiltration of water into waste storage sites. Microbial communities of lignocellulose degrading and fermenting microorganisms present in the subsurface of contaminated DOE sites can significantly impact migration by directly reducing and immobilizing metals and radionuclides while degrading complex organic matter to low molecular weight organic compounds. These low molecular weight organic acids and alcohols can increase metal and radionuclide mobility by chelation (i.e., certain organic acids) or decrease mobility by stimulating respiratory metal reducing microorganisms. We demonstrated that fermentative organisms capable of affecting the fate of Cr6+, U6+ and trinitrotoluene can be isolated from organic-rich low level waste sites as well as from less organic rich subsurface environments. The mechanisms, pathways and extent of contaminant transformation depend on a variety of factors related to the type of organisms present, the aqueous chemistry as well as the geochemistry and mineralogy. This work provides observations and quantitative data across multiple scales that identify and predict the coupled effects of fermentative carbon and electron flow on the transport of radionuclides, heavy metals and organic contaminants in

  5. Mathematical model for predicting the probability of acute mortality in a human population exposed to accidentally released airborne radionuclides. Final report for Phase I

    SciTech Connect

    Filipy, R.E.; Borst, F.J.; Cross, F.T.; Park, J.F.; Moss, O.R.; Roswell, R.L.; Stevens, D.L.

    1980-05-01

    A mathematical model was constructed for the purpose of predicting the fraction of human population which would die within 1 year of an accidental exposure to airborne radionuclides. The model is based on data from laboratory experiments with rats, dogs and baboons, and from human epidemiological data. Doses from external, whole-body irradiation and from inhaled, alpha- and beta-emitting radionuclides are calculated for several organs. The probabilities of death from radiation pneumonitis and from bone marrow irradiation are predicted from doses accumulated within 30 days of exposure to the radioactive aerosol. The model is compared with existing similar models under hypothetical exposure conditions. Suggestions for further experiments with inhaled radionuclides are included. 25 refs., 16 figs., 13 tabs.

  6. ISSUANCE 2015-06-30: Energy Conservation Program for Certain Industrial Equipment: Energy Conservation Standards and Test Procedures for Commercial Heating, Air-Conditioning, and Water-Heating Equipment, Final Rule

    Office of Energy Efficiency and Renewable Energy (EERE)

    Energy Conservation Program for Certain Industrial Equipment: Energy Conservation Standards and Test Procedures for Commercial Heating, Air-Conditioning, and Water-Heating Equipment, Final Rule

  7. Revised analyses of decommissioning for the reference pressurized Water Reactor Power Station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure, Volume 1, Final report

    SciTech Connect

    Konzek, G.J.; Smith, R.I.; Bierschbach, M.C.; McDuffie, P.N.

    1995-11-01

    With the issuance of the final Decommissioning Rule (July 27, 1988), owners and operators of licensed nuclear power plants are required to prepare, and submit to the US Nuclear Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. The NRC staff is in need of bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to provide some of the needed bases documentation. This report contains the results of a review and reevaluation of the {prime}978 PNL decommissioning study of the Trojan nuclear power plant (NUREG/CR-0130), including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the nuclear power plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5--7 year period during which time the spent fuel is stored in the spent fuel pool, prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a ``green field`` condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities.

  8. Revised analyses of decommissioning for the reference pressurized Water Reactor Power Station. Volume 2, Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure: Appendices, Final report

    SciTech Connect

    Konzek, G.J.; Smith, R.I.; Bierschbach, M.C.; McDuffie, P.N.

    1995-11-01

    With the issuance of the final Decommissioning Rule (July 27, 1998), owners and operators of licensed nuclear power plants are required to prepare, and submit to the US Nuclear Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. The NRC staff is in need of bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to provide some of the needed bases documentation. This report contains the results of a review and reevaluation of the 1978 PNL decommissioning study of the Trojan nuclear power plant (NUREG/CR-0130), including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the nuclear power plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5--7 year period during which time the spent fuel is stored in the spent fuel pool, prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a ``green field`` condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities.

  9. Reformulated Gasoline Foreign Refinery Rules

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    1995 Introduction On August 27, 1997, the EPA promulgated revised the rules that allow ... Notice Citation (1) Date Final Rule by EPA allows foreign refiners to establish ...

  10. Radionuclide deposition control

    DOEpatents

    Brehm, William F.; McGuire, Joseph C.

    1980-01-01

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

  11. Environmental Assessment for Final Rule, 10 CFR 433, "Energy Efficiency Standards for New Federal Commercial and Multi-Family High-Rise Residential Buildings" (DOE/EA-1918)

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Environmental Assessment for Final Rule, 10 CFR 433, "Energy Efficiency Standards for New Federal Commercial and Multi-Family High-Rise Residential Buildings" (DOE/EA-1918) June 28, 2013 1 Environmental Assessment for Final Rule, 10 CFR 433, "Energy Efficiency Standards for New Federal Commercial and Multi-Family High-Rise Residential Buildings" (DOE/EA-1918) SUMMARY The U.S. Department of Energy (DOE) has prepared this environmental assessment (EA) for DOE's Final Rule, 10

  12. 2014-12-22 Issuance: Alternative Efficiency Determination Methods, Basic Model Definition, and Compliance for Commercial HVAC, Refrigeration, and Water Heating Equipment; Final Rule

    Energy.gov [DOE]

    This document is a pre-publication Federal Register final rule regarding alternative efficiency determination methods, basic model definition, and compliance for commercial HVAC, refrigeration, and water heating equipment , as issued by the Deputy Assistant Secretary for Energy Efficiency on December 22, 2014. Though it is not intended or expected, should any discrepancy occur between the document posted here and the document published in the Federal Register, the Federal Register publication controls. This document is being made available through the Internet solely as a means to facilitate the public's access to this document.

  13. EA-1918: Final Rule, 10 CFR 433, "Energy Efficiency Standards for New Federal Commercial and MultiFamily High-Rise Residential Buildings" RIN 1904-AC60

    Energy.gov [DOE]

    This EA evaluates the environmental impacts of implementing provisions in the Energy Conservation and Production Act (ECPA) that require DOE to update the baseline Federal energy efficiency performance standards for the construction of new Federal buildings, including commercial and multi-family high-rise residential buildings. This EA addresses Federal commercial standard to the American Society of Heating, Refrigerating, and Air-Conditioning Engineers (ASHRAE) Standard 90.1-2010. The Final Rule was published in the Federal Register on July 9, 2013, 78 FR 40945.

  14. Implementation plan for Title 40 Code of Federal Regulations Parts 280 and 281; Final rules for underground storage tanks

    SciTech Connect

    Stupka, R.C.

    1989-04-01

    This report presents the schedules and methods required to comply with the newly promulgated Underground Storage Tank (UST) Regulations Title 40 Code of Federal Regulations (CFR) 280 and 281. These rules were promulgated by the US Environmental Protection Agency (EPA) on September 23, 1988, and became effective December 22, 1988. These regulations are required by Subtitle I of the Resource Conservation and Recovery Act of 1976. Their purpose is to protect the groundwater supplies of the United States in the following ways: Closing old tanks; detecting and remediating tank leaks and spills; establishing stringent standards for new tanks; and upgrade of existing tanks to new-tank standards. 3 refs., 5 tabs.

  15. Natural radionuclides in ground waters and cores

    SciTech Connect

    Laul, J.C.; Smith, M.R.; Maiti, T.C.

    1988-01-01

    Investigations of natural radionuclides of uranium and thorium decay series in site-specific ground waters and cores (water/rock interaction) can provide information on the expected migration behavior of their radioactive waste and analog radionuclides in the unlikely event of radioactive releases from a repository. These data in ground waters can provide in situ retardation and sorption/desorption parameters for transport models and their associated kinetics (residence time). These data in cores can also provide information on migration or leaching up to a period of about one million years. Finally, the natural radionuclide data can provide baseline information for future monitoring of possible radioactive waste releases. The natural radionuclides of interest are {sup 238}U, {sup 234}Th, {sup 234}U, {sup 230}Th, {sup 226}Ra, {sup 222}Rn, {sup 210}Pb, {sup 210}Bi, {sup 210}Po, {sup 232}Th, {sup 228}Ra, {sup 228}Th, and {sup 224}Ra. The half-lives of the daughter radionuclides range from 3 days to 2.5 x 10{sup 5} yr. The data discussed are for low ionic strength ground waters from the Hanford (basalt) site and briny ground waters (high ionic strength) and cores from the Deaf Smith salt site. Similar applications of the natural radionuclide data can be extended to the Nevada Tuff repository site and subseabed disposal site. The concentrations of uranium, thorium, radium, lead, and polonium radionuclides are generally very low in ground waters. However, significant differences in disequilibrium exist between basalt and briny ground waters.

  16. FINAL

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    2 FINAL ENVIRONMENTAL ASSESSMENT FOR EXIDE TECHNOLOGIES ELECTRIC DRIVE VEHICLE BATTERY AND COMPONENT MANUFACTURING INITIATIVE APPLICATION, BRISTOL, TN, AND COLUMBUS, GA U.S. Department of Energy National Energy Technology Laboratory March 2010 DOE/EA-1712 FINAL ENVIRONMENTAL ASSESSMENT FOR EXIDE TECHNOLOGIES ELECTRIC DRIVE VEHICLE BATTERY AND COMPONENT MANUFACTURING INITIATIVE APPLICATION, BRISTOL, TN, AND COLUMBUS, GA U.S. Department of Energy National Energy Technology Laboratory March 2010

  17. Model Development to Establish Integrated Operational Rule Curves for Hungry Horse and Libby Reservoirs - Montana, 1996 Final Report.

    SciTech Connect

    Marotz, Brian; Althen, Craig; Gustafson, Daniel

    1996-01-01

    Hungry Horse and Libby dams have profoundly affected the aquatic ecosystems in two major tributaries of the Columbia River by altering habitat and water quality, and by imposing barriers to fish migration. In 1980, the U.S. Congress passed the Pacific Northwest Electric Power Planning and Conservation Act, designed in part to balance hydropower development with other natural resources in the Columbia System. The Act formed the Northwest Power Planning Council (Council) who developed a program to protect, mitigate and enhance fish and wildlife on the Columbia River and its tributaries. Pursuant to the Council`s Fish and Wildlife Program for the Columbia River System (1987), we constructed computer models to simulate the trophic dynamics of the reservoir biota as related to dam operation. Results were used to develop strategies to minimize impacts and enhance the reservoir and riverine fisheries, following program measures 903(a)(1-4) and 903(b)(1-5). Two FORTRAN simulation models were developed for Hungry Horse and Libby reservoirs located in northwestern Montana. The models were designed to generate accurate, short-term predictions specific to two reservoirs and are not directly applicable to other waters. The modeling strategy, however, is portable to other reservoir systems where sufficient data are available. Reservoir operation guidelines were developed to balance fisheries concerns in the headwaters with anadromous species recovery actions in the lower Columbia (Biological Rule Curves). These BRCs were then integrated with power production and flood control to reduce the economic impact of basin-wide fisheries recovery actions. These Integrated Rule Curves (IRCs) were developed simultaneously in the Columbia Basin System Operation Review (SOR), the Council`s phase IV amendment process and recovery actions associated with endangered Columbia Basin fish species.

  18. Final Rule, Federal Register, 72 FR 72565, 10 CFR Parts 433, 434, and 435, December 21, 2007

    Energy.gov [DOE]

    Document displays the final rulemaking for Energy Conservation Standards for New Federal Commercial and Multi-Family High-Rise Residential Buildings and New Federal Low-Rise Residential Buildings, which was published in the Federal Register on December 21, 2007.

  19. Technology, safety and costs of decommissioning a reference boiling water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule

    SciTech Connect

    Konzek, G.J.; Smith, R.I.

    1988-07-01

    Preparation of the final Decommissioning Rule by the Nuclear Regulatory Commission (NRC) staff has been assisted by Pacific Northwest Laboratory (PNL) staff familiar with decommissioning matters. These efforts have included updating previous cost estimates developed during the series of studies of conceptually decommissioning reference licensed nuclear facilities for inclusion in the Final Generic Environmental Impact Statement (FGEIS) on decommissioning; documenting the cost updates; evaluating the cost and dose impacts of post-TMI-2 backfits on decommissioning; developing a revised scaling formula for estimating decommissioning costs for reactor plants different in size from the reference boiling water reactor (BWR) described in the earlier study; and defining a formula for adjusting current cost estimates to reflect future escalation in labor, materials, and waste disposal costs. This report presents the results of recent PNL studies to provide supporting information in three areas concerning decommissioning of the reference BWR: updating the previous cost estimates to January 1986 dollars; assessing the cost and dose impacts of post-TMI-2 backfits; and developing a scaling formula for plants different in size than the reference plant and an escalation formula for adjusting current cost estimates for future escalation.

  20. Radionuclide Behavior in Containments.

    Energy Science and Technology Software Center

    2000-02-14

    MATADOR analyzes the transport and deposition of radionuclides as vapor or aerosol through Light Water Reactor (LWR) containments during severe accidents and calculates environmental release fractions of radionuclides as a function of time. It is intended for use in system risk studies. The principal output is information on the timing and magnitude of radionuclide releases to the environment as a result of severely degraded core accidents. MATADOR considers the transport of radionuclides through the containmentmore » and their removal by natural deposition and the operation of engineered safety systems such as sprays. Input data on the source term from the primary system, the containment geometry, and thermal-hydraulic conditions are required.« less

  1. Summary of EPA Final Rules for Air Toxic Standards for Industrial, Commercial, and Institutional (ICI) Boilers and Process Heaters, February 2013

    Office of Energy Efficiency and Renewable Energy (EERE)

    Article overviewing key requirements for the reconsideration area and major source boiler MACT rules and estimated compliance cost impacts

  2. Method and apparatus for separating radionuclides from non-radionuclides

    DOEpatents

    Harp, Richard J. (18746 Viking Way, Cerritos, CA 90701)

    1990-01-01

    In an apparatus for separating radionuclides from non-radionuclides in a mixture of nuclear waste, a vessel is provided wherein the mixture is heated to a temperature greater than the temperature of vaporization for the non-radionuclides but less than the temperature of vaporization for the radionuclides. Consequently the non-radionuclides are vaporized while the non-radionuclides remain the solid or liquid state. The non-radionuclide vapors are withdrawn from the vessel and condensed to produce a flow of condensate. When this flow decreases the heat is reduced to prevent temperature spikes which might otherwise vaporize the radionuclides. The vessel is removed and capped with the radioactive components of the apparatus and multiple batches of the radionuclide residue disposed therein. Thus the vessel ultimately provides a burial vehicle for all of the radioactive components of the process.

  3. Radionuclide Retention in Concrete Wasteforms (Technical Report...

    Office of Scientific and Technical Information (OSTI)

    for radionuclide encasement requires knowledge of the radionuclide-cement interactions ... This knowledge will enable accurate prediction of radionuclide fate when the wasteforms ...

  4. Initial Radionuclide Inventories

    SciTech Connect

    H. Miller

    2004-09-19

    The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only. Bounding waste stream information and data were collected that capture probable limits. For commercially generated waste, this analysis considers alternative waste stream projections to bound the characteristics of wastes likely to be encountered using arrival scenarios that potentially impact the commercial spent nuclear fuel (CSNF) waste stream. For TSPA-LA, this radionuclide inventory analysis considers U.S. Department of Energy (DOE) high-level radioactive waste (DHLW) glass and two types of spent nuclear fuel (SNF): CSNF and DOE-owned (DSNF). These wastes are placed in two groups of waste packages: the CSNF waste package and the codisposal waste package (CDSP), which are designated to contain DHLW glass and DSNF, or DHLW glass only. The radionuclide inventory for naval SNF is provided separately in the classified ''Naval Nuclear Propulsion Program Technical Support Document'' for the License Application. As noted previously, the radionuclide inventory data presented here is intended only for TSPA-LA postclosure calculations. It is not applicable to preclosure safety calculations. Safe storage, transportation, and ultimate disposal of these wastes require safety analyses to support the design and licensing of repository equipment and facilities. These analyses will require radionuclide inventories to represent the radioactive source term that must be accommodated during handling, storage and disposition of these wastes. This analysis uses the best available information to identify the radionuclide inventory that is expected at the last year of last emplacement, currently identified as

  5. Initial Radionuclide Inventories

    SciTech Connect

    Miller, H

    2005-07-12

    The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only. Bounding waste stream information and data were collected that capture probable limits. For commercially generated waste, this analysis considers alternative waste stream projections to bound the characteristics of wastes likely to be encountered using arrival scenarios that potentially impact the commercial spent nuclear fuel (CSNF) waste stream. For TSPA-LA, this radionuclide inventory analysis considers U.S. Department of Energy (DOE) high-level radioactive waste (DHLW) glass and two types of spent nuclear fuel (SNF): CSNF and DOE-owned (DSNF). These wastes are placed in two groups of waste packages: the CSNF waste package and the codisposal waste package (CDSP), which are designated to contain DHLW glass and DSNF, or DHLW glass only. The radionuclide inventory for naval SNF is provided separately in the classified ''Naval Nuclear Propulsion Program Technical Support Document'' for the License Application. As noted previously, the radionuclide inventory data presented here is intended only for TSPA-LA postclosure calculations. It is not applicable to preclosure safety calculations. Safe storage, transportation, and ultimate disposal of these wastes require safety analyses to support the design and licensing of repository equipment and facilities. These analyses will require radionuclide inventories to represent the radioactive source term that must be accommodated during handling, storage and disposition of these wastes. This analysis uses the best available information to identify the radionuclide inventory that is expected at the last year of last emplacement, currently identified as

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

    SciTech Connect

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

    1982-12-01

    SERATRA, a transient, two-dimensional (laterally-averaged) computer model of sediment-contaminant transport in rivers, satisfactorily resolved the distribution of sediment and radionuclide concentrations in the Cattaraugus Creek stream system in New York. By modeling the physical processes of advection, diffusion, erosion, deposition, and bed armoring, SERATRA routed three sediment size fractions, including cohesive soils, to simulate three dynamic flow events. In conjunction with the sediment transport, SERATRA computed radionuclide levels in dissolved, suspended sediment, and bed sediment forms for four radionuclides (/sup 137/Cs, /sup 90/Sr, /sup 239/ /sup 240/Pu, and /sup 3/H). By accounting for time-dependent sediment-radionuclide interaction in the water column and bed, SERATA is a physically explicit model of radionuclide fate and migration. Sediment and radionuclide concentrations calculated by SERATA in the Cattaraugus Creek stream system are in reasonable agreement with measured values. SERATRA is in the field performance phase of an extensive testing program designed to establish the utility of the model as a site assessment tool. The model handles not only radionuclides but other contaminants such as pesticides, heavy metals and other toxic chemicals. Now that the model has been applied to four field sites, including the latest study of the Cattaraugus Creek stream system, it is recommended that a final model be validated through comparison of predicted results with field data from a carefully controlled tracer test at a field site. It is also recommended that a detailed laboratory flume be tested to study cohesive sediment transport, deposition, and erosion characteristics. The lack of current understanding of these characteristics is one of the weakest areas hindering the accurate assessment of the migration of radionuclides sorbed by fine sediments of silt and clay.

  7. Radionuclide Retention in Concrete Wasteforms (Technical Report...

    Office of Scientific and Technical Information (OSTI)

    likely to influence radionuclide migration; and (2) quantifies the rate of ... RADIOISOTOPES; RADIONUCLIDE MIGRATION; RETENTION; SORPTION; WASTE FORMS; ...

  8. EBS Radionuclide Transport Abstraction

    SciTech Connect

    J. Prouty

    2006-07-14

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

  9. Final Agenda

    Office of Environmental Management (EM)

    Abuse Programs at DOE Sites | Department of Energy Federal Register Notice, Amending 10 CFR part 707, Workplace Ssubustance Abuse Programs at DOE Sites Federal Register Notice, Amending 10 CFR part 707, Workplace Ssubustance Abuse Programs at DOE Sites January 23, 2008 The Department of Energy (DOE) today published a final rule to amend the Department's regulations to decrease the random drug testing rate of DOE contractor employees in testing designated positions (TDP). Today's final rule

  10. Radionuclides Allyn H. Seymour

    Office of Legacy Management (LM)

    Radionuclides Allyn H. Seymour in Air, Water, victor A. Nelson Laboratory of Radiation Ecology, University of and Biota Washington, Seattle, \\'ashington Air, water, and biological samples collected before and after the 1965, 1969, and 1971 underground nuclear detonations at Amchitka Island were analyzed for natural and fallout mdionrrclides b y gamma spectrometry. Selected samples were also analyzed for tritium, " ~ e , and 9 0 ~ r . The objectiues were t o search for and identify

  11. EBS Radionuclide Transport Abstraction

    SciTech Connect

    J.D. Schreiber

    2005-08-25

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

  12. Run Rules

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Run Rules Run Rules Crossroads/NERSC-9 Application Performance: Instructions and Run Rules Introduction Application performance is a key driver for the DOE's NNSA and Office of Science platform roadmaps. As such, application benchmarking and performance analysis will play a critical role in evaluation of the Offeror's proposal. The APEX application benchmarks have been carefully chosen to represent characteristics of the expected Crossroads and NERSC-9 workloads, both of which consist of solving

  13. Targeted radionuclide therapy

    SciTech Connect

    Williams, Lawrence E.; DeNardo, Gerald L.; Meredith, Ruby F.

    2008-07-15

    Targeted radionuclide therapy (TRT) seeks molecular and functional targets within patient tumor sites. A number of agents have been constructed and labeled with beta, alpha, and Auger emitters. Radionuclide carriers spanning a broad range of sizes; e.g., antibodies, liposomes, and constructs such as nanoparticles have been used in these studies. Uptake, in percent-injected dose per gram of malignant tissue, is used to evaluate the specificity of the targeting vehicle. Lymphoma (B-cell) has been the primary clinical application. Extension to solid tumors will require raising the macroscopic absorbed dose by several-fold over values found in present technology. Methods that may effect such changes include multistep targeting, simultaneous chemotherapy, and external sequestration of the agent. Toxicity has primarily involved red marrow so that marrow replacement can also be used to enhance future TRT treatments. Correlation of toxicities and treatment efficiency has been limited by relatively poor absorbed dose estimates partly because of using standard (phantom) organ sizes. These associations will be improved in the future by obtaining patient-specific organ size and activity data with hybrid SPECT/CT and PET/CT scanners.

  14. Natural radionuclides in groundwaters

    SciTech Connect

    Laul, J.C.

    1990-01-01

    The U-234 and Th-230 radionuclides are highly retarded by factors of 10{sup 4} to 10{sup 5} in basalt groundwater (Hanford) and briny groundwaters from Texas and geothermal brine from the Salton Sea Geothermal Field (SSGF). In basalt groundwaters (low ionic strength), Ra is highly sorbed, while in brines (high ionic strength), Ra is soluble. This is probably because the sorption sites are saturated with Na{sup +} and Cl{sup {minus}} ions and RaCl{sub 2} is soluble in brines. Pb-210 is soluble in SSGF brine, probably as a chloride complex. The U-234/Th-230 ratios in basalt groundwaters and brines from Texas and SSGF are nearly unity, indicating that U is in the +4 state, suggesting a reducing environment for these aquifers. 19 refs., 3 figs.

  15. Proposed Rules

    National Nuclear Security Administration (NNSA)

    4414 Federal Register / Vol. 78, No. 209 / Tuesday, October 29, 2013 / Proposed Rules NRC about the availability of information for the proposed Waste Confidence rule and DGEIS. You may access publicly available information related to these documents by any of the following methods: * Federal Rulemaking Web Site: Go to http://www.regulations.gov and search for Docket ID NRC-2012-0246. * NRC's Waste Confidence Web site: Go to http://www.nrc.gov/waste/spent- fuel-storage/wcd.html. * NRC's

  16. Proposed Rules

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    337 Federal Register / Vol. 81, No. 156 / Friday, August 12, 2016 / Proposed Rules 1 The use of the word ''order'' in this context refers to Compliance Orders issued under subpart Continued DEPARTMENT OF ENERGY 10 CFR Part 820 [Docket No. EA-RM-16-PRDNA] RIN 1992-AA52 Procedural Rules for DOE Nuclear Activities AGENCY: Office of Enterprise Assessments, Office of Enforcement, Office of Nuclear Safety Enforcement, Department of Energy. ACTION: Notice of proposed rulemaking. SUMMARY: The U.S.

  17. Anthropogenic radionuclides in the environment

    SciTech Connect

    Hu, Q; Weng, J; Wang, J

    2007-11-15

    Studies of radionuclides in the environment have entered a new era with the renaissance of nuclear energy and associated fuel reprocessing, geological disposal of high-level nuclear wastes, and concerns about national security with respect to nuclear non-proliferation. This work presents an overview of anthropogenic radionuclide contamination in the environment, as well as the salient geochemical behavior of important radionuclides. We first discuss the following major anthropogenic sources and current development that contribute to the radionuclide contamination of the environment: (1) nuclear weapons program; (2) nuclear weapons testing; (3) nuclear power plants; (4) commercial fuel reprocessing; (5) geological repository of high-level nuclear wastes, and (6) nuclear accidents. Then, we summarize the geochemical behavior for radionuclides {sup 99}Tc, {sup 129}I, and {sup 237}Np, because of their complex geochemical behavior, long half-lives, and presumably high mobility in the environment. Biogeochemical cycling and environment risk assessment must take into account speciation of these redox-sensitive radionuclides.

  18. Radionuclide Sensors for Water Monitoring

    SciTech Connect

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

    2004-06-29

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

  19. Radionuclide detection devices and associated methods

    DOEpatents

    Mann, Nicholas R. (Rigby, ID); Lister, Tedd E. (Idaho Falls, ID); Tranter, Troy J. (Idaho Falls, ID)

    2011-03-08

    Radionuclide detection devices comprise a fluid cell comprising a flow channel for a fluid stream. A radionuclide collector is positioned within the flow channel and configured to concentrate one or more radionuclides from the fluid stream onto at least a portion of the radionuclide collector. A scintillator for generating scintillation pulses responsive to an occurrence of a decay event is positioned proximate at least a portion of the radionuclide collector and adjacent to a detection system for detecting the scintillation pulses. Methods of selectively detecting a radionuclide are also provided.

  20. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure - appendices. Final report

    SciTech Connect

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.; McDuffie, P.N.

    1996-07-01

    The NRC staff is in need of decommissioning bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s Washington Nuclear Plant Two (WNP-2) located at Richland, Washington, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clear structures on the site and to restore the site to a {open_quotes}green field{close_quotes} condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities. Sensitivity of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances is also examined.

  1. Radionuclide labeled lymphocytes for therapeutic use

    DOEpatents

    Srivastava, Suresh C.; Fawwaz, Rashid A.; Richards, Powell

    1985-01-01

    Lymphocytes labelled with .beta.-emitting radionuclides are therapeutically useful, particularly for lymphoid ablation. They are prepared by incubation of the lymphocytes with the selected radionuclide-oxine complex.

  2. Radionuclide labeled lymphocytes for therapeutic use

    DOEpatents

    Srivastava, S.C.; Fawwaz, R.A.; Richards, P.

    1983-05-03

    Lymphocytes labelled with ..beta..-emitting radionuclides are therapeutically useful, particularly for lymphoid ablation. They are prepared by incubation of the lymphocytes with the selected radionuclide-oxine complex.

  3. Radionuclide Sensors for Subsurface Water Monitoring

    SciTech Connect

    Timothy DeVol

    2006-06-30

    Contamination of the subsurface by radionuclides is a persistent and vexing problem for the Department of Energy. These radionuclides must be measured in field studies and monitoed in the long term when they cannot be removed. However, no radionuclide sensors existed for groundwater monitoring prior to this team's research under the EMSP program Detection of a and b decays from radionuclides in water is difficult due to their short ranges in condensed media.

  4. Final Technical Report

    SciTech Connect

    Sobecky, Patricia A; Taillefert, Martial

    2013-03-29

    This final technical report describes results and findings from a research project to examine the role of microbial phosphohydrolase enzymes in naturally occurring subsurface microorganisms for the purpose of promoting the immobilization of the radionuclide uranium through the production of insoluble uranium phosphate minerals. The research project investigated the microbial mechanisms and the physical and chemical processes promoting uranium biomineralization and sequestration in oxygenated subsurface soils. Uranium biomineralization under aerobic conditions can provide a secondary biobarrier strategy to immobilize radionuclides should the metal precipitates formed by microbial dissimilatory mechanisms remobilize due to a change in redox state.

  5. Measurement of radionuclides in waste packages

    DOEpatents

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

    1984-09-12

    A method is described for non-destructively assaying the radionuclide content of solid waste in a sealed container by analysis of the waste's gamma-ray spectrum and neutron emissions. Some radionuclides are measured by characteristic photopeaks in the gamma-ray spectrum; transuranic nuclides are measured by neutron emission rate; other radionuclides are measured by correlation with those already measured.

  6. Measurement of radionuclides in waste packages

    DOEpatents

    Brodzinski, Ronald L.; Perkins, Richard W.; Rieck, Henry G.; Wogman, Ned A.

    1986-01-01

    A method is described for non-destructively assaying the radionuclide content of solid waste in a sealed container by analysis of the waste's gamma-ray spectrum and neutron emissions. Some radionuclides are measured by characteristic photopeaks in the gamma-ray spectrum; transuranic nuclides are measured by neutron emission rate; other radionuclides are measured by correlation with those already measured.

  7. Draft Environmental Assessment for Direct Final Rule, 10 CFR 434, Energy Standards for New Federal Commercial and High-Rise High-Rise Multi-FamilyResidential BuildingsŽ and 10 CFR 435, Energy Efficiency Standards for New Federal Residential Low-Rise Re

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Draft Environmental Assessment for Final Rule, 10 CFR Part 433, "Energy Efficiency Standards for New Federal Commercial and Multi-Family High- Rise Residential Buildings' Baseline Standards Update" (RIN 1904-AD39) (DOE/EA-2001) August 10, 2015 2 Draft Environmental Assessment for Final Rule, 10 CFR Part 433, "Energy Efficiency Standards for New Federal Commercial and Multi-Family High-Rise Residential Buildings' Baseline Standards Update"(RIN 1904-AD39) (DOE/EA-2001) SUMMARY

  8. Radionuclide Inventory Distribution Project Data Evaluation and Verification White Paper

    SciTech Connect

    NSTec Environmental Restoration

    2010-05-17

    Testing of nuclear explosives caused widespread contamination of surface soils on the Nevada Test Site (NTS). Atmospheric tests produced the majority of this contamination. The Radionuclide Inventory and Distribution Program (RIDP) was developed to determine distribution and total inventory of radionuclides in surface soils at the NTS to evaluate areas that may present long-term health hazards. The RIDP achieved this objective with aerial radiological surveys, soil sample results, and in situ gamma spectroscopy. This white paper presents the justification to support the use of RIDP data as a guide for future evaluation and to support closure of Soils Sub-Project sites under the purview of the Federal Facility Agreement and Consent Order. Use of the RIDP data as part of the Data Quality Objective process is expected to provide considerable cost savings and accelerate site closures. The following steps were completed: - Summarize the RIDP data set and evaluate the quality of the data. - Determine the current uses of the RIDP data and cautions associated with its use. - Provide recommendations for enhancing data use through field verification or other methods. The data quality is sufficient to utilize RIDP data during the planning process for site investigation and closure. Project planning activities may include estimating 25-millirem per industrial access year dose rate boundaries, optimizing characterization efforts, projecting final end states, and planning remedial actions. In addition, RIDP data may be used to identify specific radionuclide distributions, and augment other non-radionuclide dose rate data. Finally, the RIDP data can be used to estimate internal and external dose rates. The data quality is sufficient to utilize RIDP data during the planning process for site investigation and closure. Project planning activities may include estimating 25-millirem per industrial access year dose rate boundaries, optimizing characterization efforts, projecting final

  9. Natural chelates for radionuclide decorporation

    DOEpatents

    Premuzic, E.T.

    1983-08-25

    This invention relates to the method and resulting chelates of desorbing a radionuclide selected from thorium, uranium, and plutonium containing cultures in a bioavailable form involving pseudomonas or other microorganisms. A preferred microorganism is Pseudomonas aeruginosa which forms multiple chelates with thorium in the range of molecular weight 1000 to 1000 and also forms chelates with uranium of molecular weight in the area of 100 to 1000 and 1000 to 2000.

  10. Radionuclide behavior in the environment

    SciTech Connect

    Tveten, U. )

    1991-09-01

    The purpose of this report is to document the results of the following task: Review for quality and consistency the available data on measurements of initial ground contamination of Chernobyl radionuclides in various parts of Norway and subsequent concentrations of these radionuclides in various environmental media as functions of time. Utilize the data obtained to verify the existing models, or to improve them, for describing radionuclide behavior in the environment. Some of the processes standard were: migration into soil; weathering; resuspension; food-chain contamination; and loss or reconcentration by run-off. The task performed within this contract has been to use post-Chernobyl data from Norway to verify or find areas for possible improvement in the chronic exposure pathway models utilized in MACCS. Work has consisted mainly of collecting and evaluating post-Chernobyl information from Norway or other countries when relevant; but has also included experimental work performed specifically for the current task. In most connections the data available show the models and data in MACCS to be appropriate. A few areas where the data indicate that the MACCS approach is faulty or inadequate are, however, pointed out in the report. These should be examined carefully, and appropriate modifications should eventually be made. 14 refs., 12 figs., 22 tabs.

  11. Direct_Final_Rule_Bill.pdf

    Energy Saver

    Dingell_to_Bodman_0206.pdf Dingell_to_Bodman_0206.pdf Dingell_to_Bodman_0206.pdf (249.57 KB) More Documents & Publications Senator Dingell Letter to Secretary Bodman Bodman_to_Dingell_0215.pdf Docket_N._EO-05-01signedby_Secretary_Bodman-_dated_92806.PDF

    by Diné Power Authority Ben Hoisington, Project Administrator Presentation to Office of Energy and Efficiency and Renewable Energy TRIBAL ENERGY PROGRAM October 24, 2006 FY2006 Program Review Meeting Denver, CO PA D D I N E ' P O W E R A

  12. EA-1637: Final Environmental Assessment

    Office of Energy Efficiency and Renewable Energy (EERE)

    10 CFR 431 Energy Conservation Program for Commerical and Industrial Equipment: Packaged Terminal Air Conditioner and Packaged Terminal Heat Pump Energy Conservation Standards; Final Rule

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

    DOEpatents

    Bray, Lane A.; Ryan, Jack L.

    1998-01-01

    The present invention is a method of obtaining a radionuclide product selected from the group consisting of .sup.223 Ra and .sup.225 Ac, from a radionuclide "cow" of .sup.227 Ac or .sup.229 Th respectively. The method comprises the steps of a) permitting ingrowth of at least one radionuclide daughter from said radionuclide "cow" forming an ingrown mixture; b) insuring that the ingrown mixture is a nitric acid ingrown mixture; c) passing the nitric acid ingrown mixture through a first nitrate form ion exchange column which permits separating the "cow" from at least one radionuclide daughter; d) insuring that the at least one radionuclide daughter contains the radionuclide product; e) passing the at least one radionuclide daughter through a second ion exchange column and separating the at least one radionuclide daughter from the radionuclide product and f) recycling the at least one radionuclide daughter by adding it to the "cow". In one embodiment the radionuclide "cow" is the .sup.227 Ac, the at least one daughter radionuclide is a .sup.227 Th and the product radionuclide is the .sup.223 Ra and the first nitrate form ion exchange column passes the .sup.227 Ac and retains the .sup.227 Th. In another embodiment the radionuclide "cow"is the .sup.229 Th, the at least one daughter radionuclide is a .sup.225 Ra and said product radionuclide is the .sup.225 Ac and the .sup.225 Ac and nitrate form ion exchange column retains the .sup.229 Th and passes the .sup.225 Ra/Ac.

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

    DOEpatents

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

    1998-09-15

    The present invention is a method of obtaining a radionuclide product selected from the group consisting of {sup 223}Ra and {sup 225}Ac, from a radionuclide ``cow`` of {sup 227}Ac or {sup 229}Th respectively. The method comprises the steps of (a) permitting ingrowth of at least one radionuclide daughter from said radionuclide ``cow`` forming an ingrown mixture; (b) insuring that the ingrown mixture is a nitric acid ingrown mixture; (c) passing the nitric acid ingrown mixture through a first nitrate form ion exchange column which permits separating the ``cow`` from at least one radionuclide daughter; (d) insuring that the at least one radionuclide daughter contains the radionuclide product; (e) passing the at least one radionuclide daughter through a second ion exchange column and separating the at least one radionuclide daughter from the radionuclide product and (f) recycling the at least one radionuclide daughter by adding it to the ``cow``. In one embodiment the radionuclide ``cow`` is the {sup 227}Ac, the at least one daughter radionuclide is a {sup 227}Th and the product radionuclide is the {sup 223}Ra and the first nitrate form ion exchange column passes the {sup 227}Ac and retains the {sup 227}Th. In another embodiment the radionuclide ``cow`` is the {sup 229}Th, the at least one daughter radionuclide is a {sup 225}Ra and said product radionuclide is the {sup 225}Ac and the {sup 225}Ac and nitrate form ion exchange column retains the {sup 229}Th and passes the {sup 225}Ra/Ac. 8 figs.

  15. Microbial Transformations of Actinides and Other Radionuclides

    SciTech Connect

    Francis,A.J.; Dodge, C. J.

    2009-01-07

    Microorganisms can affect the stability and mobility of the actinides and other radionuclides released from nuclear fuel cycle and from nuclear fuel reprocessing plants. Under appropriate conditions, microorganisms can alter the chemical speciation, solubility and sorption properties and thus could increase or decrease the concentrations of radionuclides in solution in the environment and the bioavailability. Dissolution or immobilization of radionuclides is brought about by direct enzymatic action or indirect non-enzymatic action of microorganisms. Although the physical, chemical, and geochemical processes affecting dissolution, precipitation, and mobilization of radionuclides have been extensively investigated, we have only limited information on the effects of microbial processes and biochemical mechanisms which affect the stability and mobility of radionuclides. The mechanisms of microbial transformations of the major and minor actinides U, Pu, Cm, Am, Np, the fission products and other radionuclides such as Ra, Tc, I, Cs, Sr, under aerobic and anaerobic conditions in the presence of electron donors and acceptors are reviewed.

  16. Colloid labelled with radionuclide and method

    DOEpatents

    Atcher, R.W.; Hines, J.J.

    1990-11-13

    A ferric hydroxide colloid having an alpha-emitting radionuclide essentially on the outer surfaces and a method of forming same. The method includes oxidizing a ferrous hydroxide to ferric hydroxide in the presence of a preselected radionuclide to form a colloid having the radionuclide on the outer surface thereof, and thereafter washing the colloid, and suspending the washed colloid in a suitable solution. The labelled colloid is useful in cancer therapy and for the treatment of inflamed joints. No Drawings

  17. Colloid labelled with radionuclide and method

    DOEpatents

    Atcher, Robert W.; Hines, John J.

    1990-01-01

    A ferric hydroxide colloid having an alpha-emitting radionuclide essentially on the outer surfaces and a method of forming same. The method includes oxidizing a ferrous hydroxide to ferric hydroxide in the presence of a preselected radionuclide to form a colloid having the radionuclide on the outer surface thereof, and thereafter washing the colloid, and suspending the washed colloid in a suitable solution. The labelled colloid is useful in cancer therapy and for the treatment of inflamed joints.

  18. Method of making colloid labeled with radionuclide

    DOEpatents

    Atcher, Robert W.; Hines, John J.

    1991-01-01

    A ferric hydroxide colloid having an alpha-emitting radionuclide essentially on the outer surfaces and a method of forming same. The method includes oxidizing a ferrous hydroxide to ferric hydroxide in the presence of a preselected radionuclide to form a colloid having the radionuclide on the outer surface thereof, and thereafter washing the colloid, and suspending the washed colloid in a suitable solution. The labelled colloid is useful in cancer therapy and for the treatment of inflamed joints.

  19. Radionuclide Retention in Concrete Wasteforms (Technical Report...

    Office of Scientific and Technical Information (OSTI)

    This knowledge will enable accurate prediction of radionuclide fate when the wasteforms ... Country of Publication: United States Language: English Subject: 12 MANAGEMENT OF ...

  20. Ion binding compounds, radionuclide complexes, methods of making radionuclide complexes, methods of extracting radionuclides, and methods of delivering radionuclides to target locations

    DOEpatents

    Chen, Xiaoyuan; Wai, Chien M.; Fisher, Darrell R.

    2000-01-01

    The invention pertains to compounds for binding lanthanide ions and actinide ions. The invention further pertains to compounds for binding radionuclides, and to methods of making radionuclide complexes. Also, the invention pertains to methods of extracting radionuclides. Additionally, the invention pertains to methods of delivering radionuclides to target locations. In one aspect, the invention includes a compound comprising: a) a calix[n]arene group, wherein n is an integer greater than 3, the calix[n]arene group comprising an upper rim and a lower rim; b) at least one ionizable group attached to the lower rim; and c) an ion selected from the group consisting of lanthanide and actinide elements bound to the ionizable group. In another aspect, the invention includes a method of extracting a radionuclide, comprising: a) providing a sample comprising a radionuclide; b) providing a calix[n]arene compound in contact with the sample, wherein n is an integer greater than 3; and c) extracting radionuclide from the sample into the calix[n]arene compound. In yet another aspect, the invention includes a method of delivering a radionuclide to a target location, comprising: a) providing a calix[n]arene compound, wherein n is an integer greater than 3, the calix[n]arene compound comprising at least one ionizable group; b) providing a radionuclide bound to the calix[n]arene compound; and c) providing an antibody attached to the calix[n]arene compound, the antibody being specific for a material found at the target location.

  1. Assessment of radionuclides (uranium and thorium) atmospheric...

    Office of Scientific and Technical Information (OSTI)

    Title: Assessment of radionuclides (uranium and thorium) atmospheric pollution around Manjung district, Perak using moss as bio-indicator Bio-monitoring method using mosses have ...

  2. EA-1871: Environmental Assessment for Final Rule, 10 CFR 433, “EE Standards for New Federal Commercial and High-Rise Multi-Family Residential Buildings” and 10 CFR 435, “EE Standards for New Federal Residential Low-Rise Residential Buildings"

    Energy.gov [DOE]

    The U.S. Department of Energy (DOE) has prepared this Environmental Assessment (EA) for DOE‘s Final Rule, 10 CFR 433, ―Energy Efficiency Standards for New Federal Commercial and High-Rise Multi-Family Residential Buildings‖ and 10 CFR 435, ―Energy Efficiency Standards for New Federal Residential Low-Rise Residential Buildings‖ Baseline Standards Update. The final rule updates the baseline standards in 10 CFR 433 and 10 CFR 435 to the latest private sector standards based on the cost-effectiveness of the latest private sector standards and DOE‘s determination that energy efficiency has been improved in these codes as required by 42 U.S.C 6831 et seq. DOE is issuing its final determinations on American National Standards Institute (ANSI)/American Society of Heating, Refrigerating and Air-Conditioning Engineers, Inc. (ASHRAE)/Illuminating Engineering Society of North America (IESNA) Standard 90.1-2007 (ASHRAE 2007) and the International Code Council‘s 2009 International Energy Conservation Code (IECC) in the same edition of the Federal Register as this final rule.

  3. Detecting low levels of radionuclides in fluids

    DOEpatents

    Patch, Keith D.; Morgan, Dean T.

    2000-01-01

    An apparatus and method for detecting low levels of one or more radionuclides in a fluid sample uses a substrate that includes an ion exchange resin or other sorbent material to collect the radionuclides. A collecting apparatus includes a collecting chamber that exposes the substrate to a measured amount of the fluid sample such that radionuclides in the fluid sample are collected by the ion exchange resin. A drying apparatus, which can include a drying chamber, then dries the substrate. A measuring apparatus measures emissions from radionuclides collected on the substrate. The substrate is positioned in a measuring chamber proximate to a detector, which provides a signal in response to emissions from the radionuclides. Other analysis methods can be used to detect non-radioactive analytes, which can be collected with other types of sorbent materials.

  4. Drift-Scale Radionuclide Transport

    SciTech Connect

    P.R. Dixon

    2004-02-17

    The purpose of this Model Report is to document two models for drift-scale radionuclide transport. This has been developed in accordance with ''Technical Work Plan for: Performance Assessment Unsaturated Zone'' (Bechtel SAIC Company, LLC (BSC) 2002 [160819]), which includes planning documents for the technical work scope, content, and management of this Model Report in Section 1.15, Work Package AUZM11, ''Drift-Scale Radionuclide Transport.'' The technical work scope for this Model Report calls for development of a process-level model and an abstraction model representing diffusive release from the invert to the rocks, partitioned between fracture and matrix, as compared to the fracture-release approach used in the Site Recommendation. The invert is the structure constructed in a drift to provide the floor of that drift. The plan for validation of the models documented in this Model Report is given in Section I-5 of Attachment I in BSC (2002 [160819]). Note that the model validation presented in Section 7 deviates from the technical work plan (BSC 2002 [160819], Section I-5) in that an independent technical review specifically for model validation has not been conducted, nor publication in a peer-reviewed journal. Model validation presented in Section 7 is based on corroboration with alternative mathematical models, which is also called out by the technical work plan (BSC 2002 [160819], Section I-5), and is sufficient based on the requirements of AP-SIII.10Q for model validation. See Section 7 for additional discussion. The phenomenon of flow and transport in the vicinity of the waste emplacement drift are evaluated in this model report under ambient thermal, chemical, and mechanical conditions. This includes the effects of water diversion around an emplacement drift and the flow and transport behavior expected in a fractured rock below the drift. The reason for a separate assessment of drift-scale transport is that the effects of waste emplacement drifts on flow

  5. EERE Success Story-Rule to Support Increased Energy Measurement...

    Office of Environmental Management (EM)

    final rule that requires verified energy and water performance for new and retrofitted federal buildings that are certified by private sector green building certification systems. ...

  6. Radionuclide Releases During Normal Operations for Ventilated Tanks

    SciTech Connect

    Blunt, B.

    2001-09-24

    This calculation estimates the design emissions of radionuclides from Ventilated Tanks used by various facilities. The calculation includes emissions due to processing and storage of radionuclide material.

  7. An assessment of natural radionuclides in water of Langat River...

    Office of Scientific and Technical Information (OSTI)

    An assessment of natural radionuclides in water of Langat River estuary, Selangor Citation Details In-Document Search Title: An assessment of natural radionuclides in water of ...

  8. Transverse section radionuclide scanning system

    DOEpatents

    Kuhl, David E.; Edwards, Roy Q.

    1976-01-01

    This invention provides a transverse section radionuclide scanning system for high-sensitivity quantification of brain radioactivity in cross-section picture format in order to permit accurate assessment of regional brain function localized in three-dimensions. High sensitivity crucially depends on overcoming the heretofore known raster type scanning, which requires back and forth detector movement involving dead-time or partial enclosure of the scan field. Accordingly, this invention provides a detector array having no back and forth movement by interlaced detectors that enclose the scan field and rotate as an integral unit around one axis of rotation in a slip ring that continuously transmits the detector data by means of laser emitting diodes, with the advantages that increased amounts of data can be continuously collected, processed and displayed with increased sensitivity according to a suitable computer program.

  9. Illicit Trafficking of Natural Radionuclides

    SciTech Connect

    Friedrich, Steinhaeusler; Lyudmila, Zaitseva

    2008-08-07

    Natural radionuclides have been subject to trafficking worldwide, involving natural uranium ore (U 238), processed uranium (yellow cake), low enriched uranium (<20% U 235) or highly enriched uranium (>20% U 235), radium (Ra 226), polonium (Po 210), and natural thorium ore (Th 232). An important prerequisite to successful illicit trafficking activities is access to a suitable logistical infrastructure enabling an undercover shipment of radioactive materials and, in case of trafficking natural uranium or thorium ore, capable of transporting large volumes of material. Covert en route diversion of an authorised uranium transport, together with covert diversion of uranium concentrate from an operating or closed uranium mines or mills, are subject of case studies. Such cases, involving Israel, Iran, Pakistan and Libya, have been analyzed in terms of international actors involved and methods deployed. Using international incident data contained in the Database on Nuclear Smuggling, Theft and Orphan Radiation Sources (DSTO) and international experience gained from the fight against drug trafficking, a generic Trafficking Pathway Model (TPM) is developed for trafficking of natural radionuclides. The TPM covers the complete trafficking cycle, ranging from material diversion, covert material transport, material concealment, and all associated operational procedures. The model subdivides the trafficking cycle into five phases: (1) Material diversion by insider(s) or initiation by outsider(s); (2) Covert transport; (3) Material brokerage; (4) Material sale; (5) Material delivery. An Action Plan is recommended, addressing the strengthening of the national infrastructure for material protection and accounting, development of higher standards of good governance, and needs for improving the control system deployed by customs, border guards and security forces.

  10. 2009 LANL radionuclide air emissions report

    SciTech Connect

    Fuehne, David P.

    2010-06-01

    The emissions of radionuclides from Department of Energy Facilities such as Los Alamos National Laboratory (LANL) are regulated by the Amendments to the Clean Air Act of 1990, National Emissions Standards for Hazardous Air Pollutants (40 CFR 61 Subpart H). These regulations established an annual dose limit of 10 mrem to the maximally exposed member of the public attributable to emissions of radionuclides. This document describes the emissions of radionuclides from LANL and the dose calculations resulting from these emissions for calendar year 2009. This report meets the reporting requirements established in the regulations.

  11. 2010 LANL radionuclide air emissions report /

    SciTech Connect

    Fuehne, David P.

    2011-06-01

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

  12. Radionuclide analysis using solid phase extraction disks

    SciTech Connect

    Beals, D.M; Britt, W.G.; Bibler, J.P.; Brooks, D.A.

    1996-12-31

    The use of solid phase extraction disks was studied for the quantification of selected radionuclides in aqueous solutions. The extraction of four radionuclides using six types (two commercial, four test materials) of 3M Empore{trademark} RAD disks was studied. The radionuclides studied were: technetium-99 (two types of disks), cesium-137 (two types), strontium-90 (one type), plutonium-238 (one type). Extractions were tested from DI water, river water and seawater. Extraction efficiency, kinetics (flow rate past the disk), capacity, and potential interferences were studied as well as quantification methods.

  13. 2008 LANL radionuclide air emissions report

    SciTech Connect

    Fuehne, David P.

    2009-06-01

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

  14. System and method for assaying a radionuclide

    DOEpatents

    Cadieux, James R; King, III, George S; Fugate, Glenn A

    2014-12-23

    A system for assaying a radionuclide includes a liquid scintillation detector, an analyzer connected to the liquid scintillation detector, and a delay circuit connected to the analyzer. A gamma detector and a multi-channel analyzer are connected to the delay circuit and the gamma detector. The multi-channel analyzer produces a signal reflective of the radionuclide in the sample. A method for assaying a radionuclide includes selecting a sample, detecting alpha or beta emissions from the sample with a liquid scintillation detector, producing a first signal reflective of the alpha or beta emissions, and delaying the first signal a predetermined time. The method further includes detecting gamma emissions from the sample, producing a second signal reflective of the gamma emissions, and combining the delayed first signal with the second signal to produce a third signal reflective of the radionuclide.

  15. Natural radionuclides in Hanford site ground waters

    SciTech Connect

    Smith, M.R.; Laul, J.C.; Johnson, V.G.

    1987-10-01

    Uranium, Th, Ra, Rn, Pb and Po radionuclide concentrations in ground waters from the Hanford Site indicate that U, Th, and Ra are highly sorbed. Relative to Rn, these radionuclides are low by factors of 10/sup -3/ to 10/sup -6/. Uranium sorption is likely due to its reduction from the +6 state, where it is introduced via surface waters, to the +4 state found in the confined aquifers. The distribution of radionuclides is very similar in all of the confined aquifers and significantly different from the distribution observed in the unconfined and surface waters. Barium correlates well with Ra over three orders of magnitude, indicating that stable element analogs may be useful for inferring the behavior of radioactive waste radionuclides in this candidate geologic repository. 8 refs., 7 figs., 1 tab.

  16. Treatment of radionuclide contaminated soils

    SciTech Connect

    Pettis, S.A.; Kallas, A.J.; Kochen, R.L.; McGlochlin, S.C.

    1988-06-01

    Rockwell, International, Rocky Flats Plants, is committed to remediating within the scope of RCRA/CERCLA, Solid Waste Managements Units (SWMUs) at Rocky Flats found to be contaminated with hazardous substances. SWMUs fund to have radionuclide (uranium, plutonium, and/or americium) concentrations in the soils and/or groundwater that exceed background levels or regulatory limits will also be included in this remediation effort. This paper briefly summarizes past and present efforts by Rockwell International, Rocky Flats Plant, to identify treatment technologies appropriate for remediating actinide contaminated soils. Many of the promising soil treatments evaluated in Rocky Flats' laboratories during the late 1970's and early 1980's are currently being revisited. These technologies are generally directed toward substantially reducing the volume of contaminated soils, with the subsequent intention of disposing of a small remaining concentrated fraction of contaminated soil in a facility approved to receive radioactive wastes. Treatment processes currently will be treated to remove actinides, and recycled back to the process. Past investigations have included evaluations of dry screening, wet screening, scrubbing, ultrasonics, chemical oxidation, calcination, desliming, flotation, and heavy-liquid density separation. 8 refs., 2 figs.

  17. Radionuclide scintigraphy of bacterial nephritis

    SciTech Connect

    Conway, J.J.; Weiss, S.C.; Shkolnik, A.; Yogev, R.; Firlit, C.; Traisman, E.S.

    1984-01-01

    Pyelonephritis is a leading cause of renal failure and is expected to cost as much as three billion dollars in 1984. The diagnosis of urinary tract infection is usually not difficult. However, localization of the infection within the renal parenchyma as opposed to the collecting system is much more difficult. Flank pain, fever, bacteiuria and evidence of parenchymal involvement by intravenous urography may be absent or unrecognized particularly in the infant. Ultrasound and Nuclear Medicine are advocated as better methods to define parenchymal involvement. Such definition is important in the consideration of treatment since parenchymal involvement of the kidney carries a much more ominous potential outcome than infection restricted to within the collecting system. 38 children with a clinical diagnosis of urinary tract infection were studied. 26 of the patients demonstrated abnormal renal parenchymal findings with Gallium-67 Citrate or Tc-99m Glucoheptonate scintigraphy. Intravenous urography was notably ineffective with only 5 of the 20 interpreted as abnormal due to parenchymal disease or decreased function. 11 were entirely normal while only 5 demonstrated scars or hydronephrosis. Only 10 of 17 patients demonstrated intranvesicoureteral reflux on x-ray or nuclear cystography. Ultrasound depicted 6 of 20 patients as having parenchymal abnormalities. Seven were normal. Nonspecific findings such as dilitation of the renal pelvis or renal enlargement was noted in 11 of the 20 patients. Radionuclide Scintigraphy is the most efficacious modality to detect since acute bacterial nephritis.

  18. (Radiological assessments of radionuclide releases)

    SciTech Connect

    Hoffman, F.O.

    1990-12-28

    As a consequence of the Chernobyl accident, data have been obtained throughout the Northern Hemisphere on the concentrations of radionuclides in air, vegetation, soil, water, and foodstuffs that could be important means of human exposure. At the IAEA's invitation, the traveler reviewed recently published data and handbook summaries. The traveler evaluated the need for revising the default values recommended in Chapter 5, Terrestrial and Aquatic Food Chain Transport,'' of IAEA Safety Series No. 57. All attempts at revision were made to keep the mathematical complexity of the models to a minimum without substantial underestimation of dose to critical population subgroups. The traveler also served as chairman of the Multiple Pathways Working Group of the Coordinated Research Program on VAMP. This group has been established to test predictions of models assessing multiple exposure pathways potentially leading to human exposure to {sup 137}Cs. Testing is carried out for major components of assessment models that predict deposition, environmental transport, food chain bioaccumulation, and subsequent uptake and retention in the human body and dose due to exposure to external gamma radiation.

  19. Hydroxyapatite Barriers for Radionuclide Containment - Energy Innovation

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Portal Industrial Technologies Industrial Technologies Find More Like This Return to Search Hydroxyapatite Barriers for Radionuclide Containment Sandia National Laboratories Contact SNL About This Technology Publications: PDF Document Publication Market Sheet (1,049 KB) Technology Marketing SummaryApatite, which has been shown to effectively bind and immobilize radionuclides, can also be used to form barriers in water and soil in contaminated environments. The apatite barrier is formed in

  20. DOE Adopts Rules to Improve Energy Efficiency Enforcement | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Adopts Rules to Improve Energy Efficiency Enforcement DOE Adopts Rules to Improve Energy Efficiency Enforcement February 7, 2011 - 5:50pm Addthis Today, the Department of Energy adopted final rules to improve the enforcement of DOE's efficiency requirements for appliances, lighting and other products. Overhauling the certification and enforcement process, the new rules are designed to encourage compliance and prevent manufacturers who break the law from gaining a competitive advantage

  1. Position Paper on Practicable Performance Criteria for the Removal Efficiency of Volatile Radionuclides

    SciTech Connect

    R. T. Jubin; N. Soelberg; D. M. Strachan

    2012-03-01

    As a result of fuel reprocessing, volatile radionuclides may be released from the facility stack if no processes are put in place to remove them. The radionuclides that are of concern in this document are 3H, 14C, 85Kr, and 129I. The question we attempted to answer is how efficient must this removal process be for each of these radionuclides? To answer this question, we examined the three regulations that may impact the degree to which these radionuclides must be reduced before process gases can be released from the facility. These regulations are 40 CFR 61 (EPA 2010a), 40 CFR 190(EPA 2010b), and 10 CFR 20 (NRC 2012). These regulations apply to the total radionuclide release and to a particular organ - the thyroid. Because these doses can be divided amongst all the radionuclides in different ways and even within the four radionuclides in question, we provided several cases. We first looked at the inventories for these radionuclides for three fuel types (PWR UOX, PWR MOX, and AHTGR), several burn-up values, and time out of reactor extending to 200 y. We calculated doses to the maximum exposed individual (MEI) with the EPA code CAP-88 (Rosnick 1992). Finally, we looked at two dose cases. Allocating all of the allowable dose to be used by the volatile radionuclides is one case, but, perhaps, unrealistic. In lieu of this, we arbitrarily selected a value of 10% of the allowable dose to be assigned to the volatile radionuclides. We calculated the required decontamination factors (DFs) for both of these cases, including the case for the thyroid dose for which 14C and 129I were the main contributors. With respect to 129I doses, we found that the highest dose was calculated with iodine as a fine particulate. The dose scaled as the fraction of the total 129I that was particulate. Therefore, we assumed for all of our calculations that 100% of the 129I was particulate and allow the user of the results given here to scale our calculated doses to their needs.

  2. CONTRACTOR LEGAL MANAGEMENT REQUIREMENTS: APPLYING THE FINAL...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Attached is Acquisition Letter 2013-07, which provides suggested modification language. (The Final Rule's revisions are administrative in nature. Regarding costs contractors have ...

  3. Preparation of Radiopharmaceuticals Labeled with Metal Radionuclides

    SciTech Connect

    Welch, M.J.

    2012-02-16

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

  4. Radionuclide Retention in Concrete Waste Forms

    SciTech Connect

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

    2010-09-30

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

  5. PUREX low-level waste radionuclide characterization

    SciTech Connect

    Ellis, M.W.; LeBaron, G.J.

    1995-01-16

    The PUREX low-level waste (LLW) radionuclide characterization document describes the methodology for the characterization of solid LLW and solid low-level mixed waste (MW) with the respect to radiological characteristics. This document only serves as an overview of the PUREX radionuclide characterization methodology and provides specific examples for how the radionuclide distribution is derived. It would be impractical to provide all background information in this document. If further clarification and background information is required, consult the PUREX Regulatory Compliance group files. This document applies to only that waste generated in or is the responsibility of the PUREX facilities. The US Department of Energy (DOE) establishes the requirements for radioactive solid waste in DOE Order 5820.2A Radioactive Waste Management. Chapters 2 and 3 from DOE Order 5820.2A requires that generators of solid wastes in the LLW categories and the radioactive mixed waste subcategories: (1) identify the major radionuclides in each solid waste matrix and (2) determine the radionuclide concentrations and waste classes of their solid wastes. In addition, the Order also requires each generator to carry out a compliance program that ensures the proper certification of the solid waste generated.

  6. Radionuclide Retention in Concrete Wasteforms - FY13

    SciTech Connect

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

    2013-10-15

    Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how wasteform performance is affected by the full range of environmental conditions within the disposal facility; the process of wasteform aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of wasteform aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the wasteforms come in contact with groundwater. Data collected throughout the course of this work will be used to quantify the efficacy of concrete wasteforms, similar to those used in the disposal of low-level waste and mixed low-level waste, for the immobilization of key radionuclides (i.e., uranium, technetium, and iodine). Data collected will also be used to quantify the physical and chemical properties of the concrete affecting radionuclide retention.

  7. Distribution of radionuclides during melting of carbon steel

    SciTech Connect

    Thurber, W.C.; MacKinney, J.

    1997-02-01

    During the melting of steel with radioactive contamination, radionuclides may be distributed among the metal product, the home scrap, the slag, the furnace lining and the off-gas collection system. In addition, some radionuclides will pass through the furnace system and vent to the atmosphere. To estimate radiological impacts of recycling radioactive scrap steel, it is essential to understand how radionuclides are distributed within the furnace system. For example, an isotope of a gaseous element (e.g., radon) will exhaust directly from the furnace system into the atmosphere while a relatively non-volatile element (e.g., manganese) can be distributed among all the other possible media. This distribution of radioactive contaminants is a complex process that can be influenced by numerous chemical and physical factors, including composition of the steel bath, chemistry of the slag, vapor pressure of the particular element of interest, solubility of the element in molten iron, density of the oxide(s), steel melting temperature and melting practice (e.g., furnace type and size, melting time, method of carbon adjustment and method of alloy additions). This paper discusses the distribution of various elements with particular reference to electric arc furnace steelmaking. The first two sections consider the calculation of partition ratios for elements between metal and slag based on thermodynamic considerations. The third section presents laboratory and production measurements of the distribution of various elements among slag, metal, and the off-gas collection system; and the final section provides recommendations for the assumed distribution of each element of interest.

  8. 2014 LANL Radionuclide Air Emissions Report

    SciTech Connect

    Fuehne, David Patrick

    2015-07-21

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

  9. Data Authentication Demonstration for Radionuclide Stations

    SciTech Connect

    Harris, Mark; Herrington, Pres; Miley, Harry; Ellis, J. Edward; McKinnon, David; St. Pierre, Devon

    1999-08-03

    Data authentication is required for certification of sensor stations in the International Monitoring System (IMS). Authentication capability has been previously demonstrated for continuous waveform stations (seismic and infrasound). This paper addresses data surety for the radionuclide stations in the IMS, in particular the Radionuclide Aerosol Sampler/Analyzer (RASA) system developed by Pacific Northwest National Laboratory (PNNL). Radionuclide stations communicate data by electronic mail using formats defined in IMS 1.0, Formats and Protocols for Messages. An open message authentication standard exists, called S/MIME (Secure/Multipurpose Internet Mail Extensions), which has been proposed for use with all IMS radionuclide station message communications. This standard specifies adding a digital signature and public key certificate as a MIME attachment to the e-mail message. It is advantageous because it allows authentication to be added to all IMS 1.0 messages in a standard format and is commercially supported in e-mail software. For command and control, the RASA system uses a networked Graphical User Interface (GUI) based upon Common Object Request Broker Architecture (CORBA) communications, which requires special authentication procedures. The authors have modified the RASA system to meet CTBTO authentication guidelines, using a FORTEZZA card for authentication functions. They demonstrated signing radionuclide data messages at the RASA, then sending, receiving, and verifying the messages at a data center. They demonstrated authenticating command messages and responses from the data center GUI to the RASA. Also, the particular authentication system command to change the private/public key pair and retrieve the new public key was demonstrated. This work shows that data surety meeting IMS guidelines may be immediately applied to IMS radionuclide systems.

  10. Laboratory studies of radionuclide migration in tuff

    SciTech Connect

    Rundberg, R.S.; Mitchell, A.J.; Ott, M.A.; Thompson, J.L.; Triay, I.R.

    1989-10-01

    The movement of selected radionuclides has been observed in crushed tuff, intact tuff, and fractured tuff columns. Retardation factors and dispersivities were determined from the elution profiles. Retardation factors have been compared with those predicted on the basis of batch sorption studies. This comparison forms a basis for either validating distribution coefficients or providing evidence of speciation, including colloid formation. Dispersivities measured as a function of velocity provide a means of determining the effect of sorption kinetics or mass transfer on radionuclide migration. Dispersion is also being studied in the context of scaling symmetry to develop a basis for extrapolating from the laboratory scale to the field. 21 refs., 6 figs., 2 tabs.

  11. Quality Assurance Rule

    Energy.gov [DOE]

    This rule establishes quality assurance requirements for contractors conducting activities, including providing items or services which affect, or may affect, nuclear safety of DOE nuclear facilities.

  12. Assessment of Radionuclides in the Savannah River Site Environment Summary

    SciTech Connect

    Carlton, W.H.

    1999-01-26

    This document summarizes the impact of radionuclide releases from Savannah River Site (SRS) facilities from 1954 through 1996. The radionuclides reported here are those whose release resulted in the highest dose to people living near SRS.

  13. RADIONUCLIDE TRANSPORT MODELS UNDER AMBIENT CONDITIONS

    SciTech Connect

    S. Magnuson

    2004-11-01

    The purpose of this model report is to document the unsaturated zone (UZ) radionuclide transport model, which evaluates, by means of three-dimensional numerical models, the transport of radioactive solutes and colloids in the UZ, under ambient conditions, from the repository horizon to the water table at Yucca Mountain, Nevada.

  14. 2006 LANL Radionuclide Air Emissions Report

    SciTech Connect

    David P. Fuehne

    2007-06-30

    This report describes the impacts from emissions of radionuclides at Los Alamos National Laboratory (LANL) for calendar year 2006. This report fulfills the requirements established by the Radionuclide National Emissions Standards for Hazardous Air Pollutants (Rad-NESHAP). This report is prepared by LANL's Rad-NESHAP compliance team, part of the Environmental Protection Division. The information in this report is required under the Clean Air Act and is being reported to the U.S. Environmental Protection Agency (EPA). The highest effective dose equivalent (EDE) to an off-site member of the public was calculated using procedures specified by the EPA and described in this report. LANL's EDE was 0.47 mrem for 2006. The annual limit established by the EPA is 10 mrem per year. During calendar year 2006, LANL continuously monitored radionuclide emissions at 28 release points, or stacks. The Laboratory estimates emissions from an additional 58 release points using radionuclide usage source terms. Also, LANL uses a network of air samplers around the Laboratory perimeter to monitor ambient airborne levels of radionuclides. To provide data for dispersion modeling and dose assessment, LANL maintains and operates meteorological monitoring systems. From these measurement systems, a comprehensive evaluation is conducted to calculate the EDE for the Laboratory. The EDE is evaluated as any member of the public at any off-site location where there is a residence, school, business, or office. In 2006, this location was the Los Alamos Airport Terminal. The majority of this dose is due to ambient air sampling of plutonium emitted from 2006 clean-up activities at an environmental restoration site (73-002-99; ash pile). Doses reported to the EPA for the past 10 years are shown in Table E1.

  15. Institutional Change Process Step 2: Assess Institutional Rules, Roles, and

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Tools | Department of Energy 2: Assess Institutional Rules, Roles, and Tools Institutional Change Process Step 2: Assess Institutional Rules, Roles, and Tools Graphic of the Institutional Change Continuous Improvement Process gear. The steps begin with Determine Goals and move to Assess Institutional Rules, Roles and Tools then to Develop Action Plan then to Implement Plan then finally to Measure and Evaluate. The process begins again with Determine Goals. Determine Goals Develop Action Plan

  16. Natural Radionuclides and Isotopic Signatures for Determining Carbonaceous Aerosol Sources, Aerosol Lifetimes, and Washout Processes

    SciTech Connect

    Gaffney, Jeffrey

    2012-12-12

    This is the final technical report. The project description is as follows: to determine the role of aerosol radiative forcing on climate, the processes that control their atmospheric concentrations must be understood, and aerosol sources need to be determined for mitigation. Measurements of naturally occurring radionuclides and stable isotopic signatures allow the sources, removal and transport processes, as well as atmospheric lifetimes of fine carbonaceous aerosols, to be evaluated.

  17. Uptake by plants of radionuclides from FUSRAP waste materials

    SciTech Connect

    Knight, M.J.

    1983-04-01

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

  18. Rule to Support Increased Energy Measurement and Efficient Building Design

    Energy.gov [DOE]

    In 2014, EEREs Federal Energy Management Program issued a final rule that requires verified energy and water performance for new and retrofitted federal buildings that are certified by private...

  19. Rule Issued to Prohibit Importation of Products that Fail To...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    the U.S. Customs and Border Protection ("CBP") and the U.S. Department of the Treasury issued a final rule last week that allows CBP to refuse admission into the customs territory ...

  20. Radionuclide partitioning in the modified Unex process

    SciTech Connect

    Babain, V.; Smirnov, I.; Alyapyshev, M.; Todd, T.A.; Law, J.D.; Herbst, R.S.; Paulenova, A.

    2008-07-01

    The Universal Extraction (UNEX) process has been developed for simultaneous extraction of long-lived radionuclides (cesium, strontium, actinides, and lanthanides) from acidic solutions in one extraction cycle. Modification of this organic solvent through the use of diamides of dipicolinic acid instead of CMPO increases the extraction capacity of UNEX solvent toward lanthanides and actinide metals, allowing for the processing of spent nuclear fuel. The possibility of radionuclide group separation using the modified UNEX solvent [HCCD (chlorinated cobalt dicarbollide), TBDPA (tetrabutyl-diamide of dipicolinic acid), PEG in FS-1 3 (phenyl-trifluoromethyl-sulfone)] is being investigated. Individual strip products, including a) actinides and lanthanides, b) strontium, and c) cesium, can be obtained by selective stripping from UNEX solvent. Such partitioning will make it possible to transform the Cs/Sr product into the most stable matrices for long-term storage and to further process the actinide/lanthanide product for recycling to a nuclear reactor. (authors)

  1. Improving cancer treatment with cyclotron produced radionuclides

    SciTech Connect

    Larson, S.M. Finn, R.D.

    1992-08-04

    This report describes the author's continuing long term goal of promoting nuclear medicine applications by improving the scientific basis for tumor diagnosis treatment and treatment follow-up based on the use of cyclotron produced radiotracers in oncology. The program has 3 interactive components: Radiochemistry /Cyclotron; Pharmacology; and Immunology. An essential strategy is as follows: novel radionuclides and radiotracers developed in the Radiochemistry/Cyclotron section under the DOE grant during the 1989--1992 grant period, will be employed in the Pharmacology and Immunology sections of the DOE grant during the 1992--1995 grant period. The development of novel radionuclides and tracers is of course useful in and of itself, but their utility is greatly enhanced by the interaction with the immunology and pharmacology components of the program.

  2. Methods and systems for detection of radionuclides

    DOEpatents

    Coates, Jr., John T.; DeVol, Timothy A.

    2010-05-25

    Disclosed are materials and systems useful in determining the existence of radionuclides in an aqueous sample. The materials provide the dual function of both extraction and scintillation to the systems. The systems can be both portable and simple to use, and as such can beneficially be utilized to determine presence and optionally concentration of radionuclide contamination in an aqueous sample at any desired location and according to a relatively simple process without the necessity of complicated sample handling techniques. The disclosed systems include a one-step process, providing simultaneous extraction and detection capability, and a two-step process, providing a first extraction step that can be carried out in a remote field location, followed by a second detection step that can be carried out in a different location.

  3. Radionuclide Air Emission Report for 2007

    SciTech Connect

    Wahl, Linnea; Wahl, Linnea

    2008-06-13

    Berkeley Lab operates facilities where radionuclides are handled and stored. These facilities are subject to the U.S. Environmental Protection Agency (EPA) radioactive air emission regulations in Code of Federal Regulations (CFR) Title 40, Part 61, Subpart H (EPA 1989). The EPA regulates radionuclide emissions that may be released from stacks or vents on buildings where radionuclide production or use is authorized or that may be emitted as diffuse sources. In 2007, all Berkeley Lab sources were minor stack or building emissions sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.001 mSv/yr]), there were no diffuse emissions, and there were no unplanned emissions. Emissions from minor sources either were measured by sampling or monitoring or were calculated based on quantities received for use or produced during the year. Using measured and calculated emissions, and building-specific and common parameters, Laboratory personnel applied the EPA-approved computer code, CAP88-PC, Version 3.0, to calculate the effective dose equivalent to the maximally exposed individual (MEI). The effective dose equivalent from all sources at Berkeley Lab in 2007 is 1.2 x 10{sup -2} mrem/yr (1.2 x 10{sup -4} mSv/yr) to the MEI, well below the 10 mrem/yr (0.1 mSv/yr) EPA dose standard. The location of the MEI is at the University of California (UC) Lawrence Hall of Science, a public science museum about 1500 ft (460 m) east of Berkeley Lab's Building 56. The estimated collective effective dose equivalent to persons living within 50 mi (80 km) of Berkeley Lab is 3.1 x 10{sup -1} person-rem (3.1 x 10{sup -3} person-Sv) attributable to the Lab's airborne emissions in 2007.

  4. Radionuclide Air Emission Report for 2008

    SciTech Connect

    Wahl, Linnea

    2009-05-21

    Berkeley Lab operates facilities where radionuclides are handled and stored. These facilities are subject to the U.S. Environmental Protection Agency (EPA) radioactive air emission regulations in Code of Federal Regulations (CFR) Title 40, Part 61, Subpart H (EPA 1989). Radionuclides may be emitted from stacks or vents on buildings where radionuclide production or use is authorized or they may be emitted as diffuse sources. In 2008, all Berkeley Lab sources were minor sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.001 mSv/yr]). These minor sources include more than 100 stack sources and one source of diffuse emissions. There were no unplanned emissions from the Berkeley Lab site. Emissions from minor sources (stacks and diffuse emissions) either were measured by sampling or monitoring or were calculated based on quantities used, received for use, or produced during the year. Using measured and calculated emissions, and building-specific and common parameters, Laboratory personnel applied the EPA-approved computer code, CAP88-PC, to calculate the effective dose equivalent to the maximally exposed individual (MEI). The effective dose equivalent from all sources at Berkeley Lab in 2008 is 5.2 x 10{sup -3} mrem/yr (5.2 x 10{sup -5} mSv/yr) to the MEI, well below the 10 mrem/yr (0.1 mSv/yr) dose standard. The location of the MEI is at the University of California (UC) Lawrence Hall of Science, a public science museum about 1500 ft (460 m) east of Berkeley Lab's Building 56. The estimated collective effective dose equivalent to persons living within 50 mi (80 km) of Berkeley Lab is 1.1 x 10{sup -1} person-rem (1.1 x 10{sup -3} person-Sv) attributable to the Lab's airborne emissions in 2008.

  5. Radionuclide Air Emission Report for 2009

    SciTech Connect

    Wahl, Linnea

    2010-06-01

    Berkeley Lab operates facilities where radionuclides are handled and stored. These facilities are subject to the EPA radioactive air emission regulations in 40CFR61, Subpart H (EPA 1989). Radionuclides may be emitted from stacks or vents on buildings where radionuclide production or use is authorized or they may be emitted as diffuse sources. In 2009, all Berkeley Lab sources were minor sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.001 mSv/yr]). These minor sources included more than 100 stack sources and one source of diffuse emissions. There were no unplanned emissions from the Berkeley Lab site. Emissions from minor sources (stacks and diffuse emissions) either were measured by sampling or monitoring or were calculated based on quantities used, received for use, or produced during the year. Using measured and calculated emissions, and building-specific and common parameters, Laboratory personnel applied the EPA-approved computer code, CAP88-PC, to calculate the effective dose equivalent to the maximally exposed individual (MEI). The effective dose equivalent from all sources at Berkeley Lab in 2009 is 7.0 x 10{sup -3} mrem/yr (7.0 x 10{sup -5} mSv/yr) to the MEI, well below the 10 mrem/yr (0.1 mSv/yr) dose standard. The location of the MEI is at the University of California (UC) Lawrence Hall of Science, a public science museum about 1500 ft (460 m) east of Berkeley Lab's Building 56. The estimated collective effective dose equivalent to persons living within 50 mi (80 km) of Berkeley Lab is 1.5 x 10{sup -1} person-rem (1.5 x 10{sup -3} person-Sv) attributable to the Lab's airborne emissions in 2009.

  6. UPTAKE OF RADIONUCLIDE METALS BY SPME FIBERS

    SciTech Connect

    Duff, M; S Crump, S; Robert02 Ray, R; Keisha Martin, K; Donna Beals, D

    2006-08-28

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

  7. Concrete Property and Radionuclide Migration Tests

    SciTech Connect

    Wellman, Dawn M.; Mattigod, Shas V.; Powers, Laura; Parker, Kent E.; Clayton, Libby N.; Wood, Marcus I.

    2008-10-01

    The Waste Management Project provides safe, compliant, and cost-effective waste management services for the Hanford Site and the DOE Complex. Part of theses services includes safe disposal of LLW and MLLW at the Hanford Low-Level Waste Burial Grounds (LLBG) in accordance with the requirements listed in DOE Order 435.1, Radioactive Waste Management. To partially satisfy these requirements, a Performance Assessment (PA) analyses were completed and approved. DOE Order 435.1 also requires that continuing data collection be conducted to enhance confidence in the critical assumptions used in these analyses to characterize the operational features of the disposal facility that are relied upon to satisfy the performance objectives identified in the Order. One critical assumption is that concrete will frequently be used as waste form or container material to control and minimize the release of radionuclide constituents in waste into the surrounding environment. Data was collected to (1) quantify radionuclide migration through concrete materials similar to those used to encapsulate waste in the LLBG, (2) measure the properties of the concrete materials, especially those likely to influence radionuclide migration, and (3) quantify the stability of U-bearing solid phases of limited solubility in concrete.

  8. Acquisition & Financial Assistance Rules Status | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Acquisition & Financial Assistance Rules Status Acquisition & Financial Assistance Rules Status Subscribe to Acquisition & Financial Assistance Rules Status Updates PDF icon ...

  9. Use of natural radionuclides to predict the behavior of radwaste radionuclides in far-field aquifiers

    SciTech Connect

    Hubbard, N.; Laul, J.C.; Perkins, R.W.

    1983-10-01

    In appropriate aquifers the natural radionuclides of the U and Th decay series are important sources of information about the behavior of radwaste radionuclides in far-field aquifers. The Wolfcamp Carbonate, Pennsylvanian Carbonate and Granite Wash aquifers in the Palo Duro Basin of the Texas Panhandle are prime examples of such aquifers. Sampling and analysis for key radionuclides in the ground waters of these aquifers are quite feasible and have been accomplished. Key early results are: (1) Ra does not appear to be retarded by sorption, (2) Th appears to be strongly sorbed, (3) kinetics seem to be different on time scales of days to months than on ones of hundreds of thousands of years, and (4) U and Th behave similarily when the time scales (half-lives) are similar, leading to the suggestion that uranium is in the +4 valence state in these aquifers. 10 references, 9 figures.

  10. Use of natural radionuclides to predict the behavior of radwaste radionuclides in far-field aquifers

    SciTech Connect

    Hubbard, N.; Laul, J.C.; Perkins, R.W.

    1984-01-01

    In appropriate aquifers the natural radionuclides of the U and Th decay series are important sources of information about the behavior of radwaste radionuclides in far-field aquifers. The Wolfcamp Carbonate, Pennsylvanian Carbonate and Granite Wash aquifers in the Palo Duro Basin of the Texas Panhandle are prime examples of such aquifers. Sampling and analysis for key radionuclides in the ground waters of these aquifers are quite feasible and have been accomplished. Key early results are: (1) Ra does not appear to be retarded by sorption, (2) Th appears to be strongly sorbed, (3) kinetics seem to be different on time scales of days to months than on ones of hundreds of thousands of years, and (4) U and Th behave similarly when the time scales (half-lives) are similar, leading to the suggestion that uranium is in the +4 valence state in these aquifers. 10 references, 3 figures.

  11. Trace Metals in Groundwater and Vadose Zone Calcite: In Situ Containment and Stabilization of Stronthium-90 and Other Divalent Metals and Radionuclides at Arid Western DOE Sites: Final Report for Award Number DE-FG07-02ER63486 to the University of Idaho (RW Smith) Environmental Management Science Program Project Number 87016

    SciTech Connect

    Smith, Robert W.; Fujita, Yoshiko

    2007-11-07

    Radionuclide and metal contaminants are present in the vadose zone and groundwater throughout the U.S. Department of Energy (DOE) energy research and weapons complex. In situ containment and stabilization of these contaminants represents a cost-effective treatment strategy that minimizes workers’ exposure to hazardous substances, does not require removal or transport of contaminants, and generally does not generate a secondary waste stream. We have investigated an in situ bioremediation approach that immobilizes radionuclides or contaminant metals (e.g., strontium-90) by their microbially facilitated co-precipitation with calcium carbonate in groundwater and vadose zone systems. Calcite, a common mineral in many aquifers and vadose zones in the arid west, can incorporate divalent metals such as strontium, cadmium, lead, and cobalt into its crystal structure by the formation of a solid solution. Collaborative research undertaken by the Idaho National Laboratory (INL), University of Idaho, and University of Toronto as part of this Environmental Management Science Program project has focused on in situ microbially-catalyzed urea hydrolysis, which results in an increase in pH, carbonate alkalinity, ammonium, calcite precipitation, and co-precipitation of divalent cations. In calcite-saturated aquifers, microbially facilitated co-precipitation with calcium carbonate represents a potential long-term contaminant sequestration mechanism. Key results of the project include: **Demonstrating the linkage between urea hydrolysis and calcite precipitation in field and laboratory experiments **Observing strontium incorporation into calcite precipitate by urea hydrolyzers with higher distribution coefficient than in abiotic **Developing and applying molecular methods for characterizing microbial urease activity in groundwater including a quantitative PCR method for enumerating ureolytic bacteria **Applying the suite of developed molecular methods to assess the feasibility of the

  12. Mobility of Source Zone Heavy Metals and Radionuclides: The Mixed...

    Office of Scientific and Technical Information (OSTI)

    Various U. S. Department of Energy (DOE) low and medium-level radioactive waste sites contain mixtures of heavy metals, radionuclides and assorted organic materials. Over time, ...

  13. Potential for radionuclide redistribution due to biotic intrusion...

    Office of Scientific and Technical Information (OSTI)

    Potential for radionuclide redistribution due to biotic intrusion: Aboveground biomass ... due to biotic intrusion: Aboveground biomass study at the Los Alamos National ...

  14. Investigation of CTBT OSI Radionuclide Techniques at the DILUTED...

    Office of Scientific and Technical Information (OSTI)

    WATERS Nuclear Test Site Citation Details In-Document Search Title: Investigation of CTBT OSI Radionuclide Techniques at the DILUTED WATERS Nuclear Test Site Under the ...

  15. Mobility of Source Zone Heavy Metals and Radionuclides: The Mixed...

    Office of Scientific and Technical Information (OSTI)

    In the first mechanism, products of the fermentation process can act as chelators for metals and radionuclides increasing their transport through underlying geological media. The ...

  16. Accumulation of radionuclides in selected marine biota from Manjung...

    Office of Scientific and Technical Information (OSTI)

    Radionuclides presence in the marine ecosystem can be adversely affect human health when ... factor (TF), ingestion dose rate (D) and health risk index (HRI) to monitor radiological ...

  17. Transuranic radionuclides dispersed into the aquatic environment, a bibliography

    SciTech Connect

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

    1994-04-01

    The purpose of this project was to compile a bibliography of references containing environmental transuranic radionuclide data. Our intent was to identify those parameters affecting transuranic radionuclide transport that may be generic and those that may be dependent on chemical form and/or environmental conditions (i.e., site specific) in terrestrial, aquatic and atmospheric environments An understanding of the unique characteristics and similarities between source terms and environmental conditions relative to transuranic radionuclide transport and cycling will provide the ability to assess and predict the long term impact on man and the environment. An additional goal of our literature review, was to extract the ranges of environmental transuranic radionuclide data from the identified references for inclusion in a data base. Related to source term, these ranges of data can be used to calculate the dose to man from the radionuclides, and to perform uncertainty analyses on these dose assessments. On the basis of our reviews, we have arbitrarily outlined five general source terms. These are fallout, fuel cycle waste, accidents, disposal sites and resuspension. Resuspension of the transuranic radionuclides is a unique source term, in that the radionuclides can originate from any of the other source terms. If these transuranic radionuclides become resuspended into the air, they then become important as a source of inhaled radionuclides.

  18. LONG-TERM DYNAMICS OF RADIONUCLIDE VERTICAL MIGRATION IN SOILS...

    Office of Scientific and Technical Information (OSTI)

    NUCLEAR POWER PLANT EXCLUSION ZONE Citation Details In-Document Search Title: LONG-TERM DYNAMICS OF RADIONUCLIDE VERTICAL MIGRATION IN SOILS OF THE CHERNOBYL NUCLEAR POWER ...

  19. Selected radionuclides important to low-level radioactive waste management

    SciTech Connect

    1996-11-01

    The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). This report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237.

  20. Reference Material for Radionuclides in Sediment, IAEA-384 (Fangataufa Lagoon Sediment)

    SciTech Connect

    Povinec, P; Pham, M; Barci-Funel, G; Bojanawski, R; Boshkova, T; Burnett, W; Carvalho, F; Chapeyron, B; Cunha, I; Dahlgaard, H; Galabov, N; Gastaud, J; Geering, J; Gomez, I; Green, N; Hamilton, T; Ibanez, F; Majah, M I; John, M; Kanisch, G; Kenna, T; Kloster, M; Korun, M; Wee Kwong, L L; La Rosa, J; Lee, S; Levy-Palomo, I; Malatova, M; Maruo, Y; Mitchell, P; Murciano, I; Nelson, R; Oh, J; Oregioni, B; Petit, G L; Pettersson, H; Reineking, A; Smedley, P; Suckow, A; der Struijs, T v; Voors, P; Yoshimizu, K; Wyse, E

    2005-09-23

    The IAEA Marine Environment Laboratory (IAEA-MEL) in Monaco has conducted intercomparison exercises on radionuclides in marine samples for many years as part of its contribution to the IAEA's program of Analytical Quality Control Services (AQCS). An important part of the AQCS program has been a production of Reference Materials (RMs) and their provision to radioanalytical laboratories. The RMs have been developed for different marine matrices (sediment, water, biota), with accuracy and precision required for the present state of the art of radiometrics and mass spectrometry methods. The RMs have been produced as the final products of world-wide intercomparison exercises organized during last 30 years. A total of 44 intercomparison exercises were undertaken and 39 RMs were produced for radionuclides in the marine environment. All required matrices (seawater, biota, sediment) have been covered with radionuclide concentrations ranging from typical environmental levels to elevated levels affected by discharges from nuclear reprocessing plants. The long-term availability of RMs (over 10 years) requires the use of very specific techniques to collect and pretreat large quantities of material (e.g., in excess of 100 kg) in order to ensure sample stability and homogenization of any analytes of interest. The production of a RM is therefore a long process, covering the identification of needs, sample collection, pre-treatment, homogenization, bottling, distribution to laboratories, evaluation of data, preliminary reporting, additional analyses in expert laboratories, certification of the material, and finally issuing the RM. In this paper we describe a reference material IAEA-384, Fangataufa lagoon sediment, designed for determination of anthropogenic and natural radionuclides in the marine environment. This RM has been prepared with the aim of testing the performance of analytical laboratories to measure the activity of these radionuclides in a sediment sample contaminated

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

    DOEpatents

    Bray, Lane A.; Ryan, Jack L.

    1999-01-01

    The present invention is a method of removing an impurity of plutonium, lead or a combination thereof from a mixture of radionuclides that contains the impurity and at least one parent radionuclide. The method has the steps of (a) insuring that the mixture is a hydrochloric acid mixture; (b) oxidizing the acidic mixture and specifically oxidizing the impurity to its highest oxidation state; and (c) passing the oxidized mixture through a chloride form anion exchange column whereupon the oxidized impurity absorbs to the chloride form anion exchange column and the 22.sup.9 Th or 2.sup.27 Ac "cow" radionuclide passes through the chloride form anion exchange column. The plutonium is removed for the purpose of obtaining other alpha emitting radionuclides in a highly purified form suitable for medical therapy. In addition to plutonium; lead, iron, cobalt, copper, uranium, and other metallic cations that form chloride anionic complexes that may be present in the mixture; are removed from the mixture on the chloride form anion exchange column.

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

    DOEpatents

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

    1999-03-23

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

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

    SciTech Connect

    Onishi, Y.; Serne, R.J.; Arnold, E.M.; Cowan, C.E.; Thompson, F.L.

    1981-01-01

    This report describes the results of a detailed literature review of radionuclide transport models applicable to rivers, estuaries, coastal waters, the Great Lakes, and impoundments. Some representatives sediment transport and water quality models were also reviewed to evaluate if they can be readily adapted to radionuclide transport modeling. The review showed that most available transport models were developed for dissolved radionuclide in rivers. These models include the mechanisms of advection, dispersion, and radionuclide decay. Since the models do not include sediment and radionuclide interactions, they are best suited for simulating short-term radionuclide migration where: (1) radionuclides have small distribution coefficients; (2) sediment concentrations in receiving water bodies are very low. Only 5 of the reviewed models include full sediment and radionuclide interactions: CHMSED developed by Fields; FETRA SERATRA, and TODAM developed by Onishi et al, and a model developed by Shull and Gloyna. The 5 models are applicable to cases where: (1) the distribution coefficient is large; (2) sediment concentrations are high; or (3) long-term migration and accumulation are under consideration. The report also discusses radionuclide absorption/desorption distribution ratios and addresses adsorption/desorption mechanisms and their controlling processes for 25 elements under surface water conditions. These elements are: Am, Sb, C, Ce, Cm, Co, Cr, Cs, Eu, I, Fe, Mn, Np, P, Pu, Pm, Ra, Ru, Sr, Tc, Th, {sup 3}H, U, Zn and Zr.

  4. Test Procedures for Integrated Light-Emitting Diode Lamps; Final...

    Energy.gov [DOE] (indexed site)

    Test Procedures for Integrated Light-Emitting Diode Lamps - Final Rule (532.58 KB) More Documents & Publications ISSUANCE 2015-06-25: Energy Conservation Program: Test Procedures ...

  5. Traces of natural radionuclides in animal food

    SciTech Connect

    Merli, Isabella Desan; Guazzelli da Silveira, Marcilei A.; Medina, Nilberto H.

    2014-11-11

    Naturally occurring radioactive materials are present everywhere, e.g., in soil, air, housing materials, food, etc. Therefore, human beings and animals receive internal exposure from radioactive elements inside their bodies through breathing and alimentation. Gamma radiation has enough energy to remove an electron from the atom and compromise the rearrangement of electrons in the search for a more stable configuration which can disturb molecule chemical bonding. Food ingestion is one of the most common forms of radioisotopes absorption. The goal of this work is the measurement of natural gamma radiation rates from natural radioisotopes present in animal food. To determine the concentration of natural radionuclides present in animal food gamma-ray spectrometry was applied. We have prepared animal food samples for poultry, fish, dogs, cats and cattle. The two highest total ingestion effective doses observed refers to a sample of mineral salt cattle, 95.3(15) ?Sv/year, rabbit chow, with a value of 48(5) ?Sv/year, and cattle mineral salt, with a value of 69(7) ?Sv/year, while the annual total dose value from terrestrial intake radionuclide is of the order of 290 ?Sv/year.

  6. Reuse of Material Containing Natural Radionuclides - 12444

    SciTech Connect

    Metlyaev, E.G.; Novikova, N.J.

    2012-07-01

    Disposal of and use of wastes containing natural radioactive material (NORM) or technologically enhanced natural radioactive material (TENORM) with excessive natural background as a building material is very important in the supervision body activity. At the present time, the residents of Octyabrsky village are under resettlement. This village is located just near the Priargunsky mining and chemical combine (Ltd. 'PPGHO'), one of the oldest uranium mines in our country. The vacated wooden houses in the village are demolished and partly used as a building material. To address the issue of potential radiation hazard of the wooden beams originating from demolition of houses in Octyabrsky village, the contents of the natural radionuclides (K-40, Th-232, Ra-226, U- 238) are being determined in samples of the wooden beams of houses. The NORM contents in the wooden house samples are higher, on average, than their content in the reference sample of the fresh wood shavings, but the range of values is rather large. According to the classification of waste containing the natural radionuclides, its evaluation is based on the effective specific activity. At the effective specific activity lower 1.5 kBq/kg and gamma dose rate lower 70 μR/h, the material is not considered as waste and can be used in building by 1 - 3 classes depending upon A{sub eff} value. At 1.5 kBq/kg < A{sub eff} ≤ 4 kBq/kg (4 class), the wooden beams might be used for the purpose of the industrial building, if sum of ratios between the radionuclide specific activity and its specific activity of minimum significance is lower than unit. The material classified as the waste containing the natural radionuclides has A{sub eff} higher 1.5 kBq /kg, and its usage for the purpose of house-building and road construction is forbidden. As for the ash classification and its future usage, such usage is unreasonable, because, according to the provided material, more than 50% of ash samples are considered as radioactive

  7. Natural Radionuclide Activity Concentrations In Spas Of Argentina

    SciTech Connect

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

    2008-08-07

    Geothermal waters have been used on a large scale for bathing, drinking and medical purposes. These waters can contain natural radionuclides that may increase the exposure to people. In this work the most important natural radionuclide activity concentrations in different thermal spas of Argentina were measured to characterize waters and to evaluate the exposure of workers and members of the public.

  8. Proposed Rules IV. Conclusion

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    686 Federal Register / Vol. 81, No. 44 / Monday, March 7, 2016 / Proposed Rules IV. Conclusion For the reasons cited in this document, the NRC is denying PRM- 50-106. The NRC is denying this petition because the current regulations already address environmental qualification in both mild and design basis event conditions of electrical equipment located both inside and outside of the containment building that is important to safety, and the petitioners did not provide significant new or

  9. Radionuclide chain transport through heterogeneous media

    SciTech Connect

    Hadermann, J.; Patry, J.

    1982-04-01

    A one-dimensional radionuclide chain transport model is developed, taking into account sorption, longitudinal dispersion, and arbitrary repository concentrations. For piecewise constant geologic parameters, a semianalytic solution can be written down, when, at the layer boundaries, mass conservation is considered rigorously and flux conservation to a good approximation. The solution consists of a superposition of terms that are easily interpreted and is invariant under layer permutation and parameter scaling. A corresponding computer code RANCH has been developed. The /sup 245/Cm chain has been investigated for a broad variation of parameters of a three-layer geology. For very small retention factors only, /sup 245/Cm and /sup 241/Am can survive migration in the geologic medium, while /sup 237/Np is reduced by at most three orders of magnitude.

  10. Chancellor Water Colloids: Characterization and Radionuclide Association

    SciTech Connect

    Abdel-Fattah, Amr I.

    2012-06-18

    Concluding remarks about this paper are: (1) Gravitational settling, zeta potential, and ultrafiltration data indicate the existence of a colloidal phase of both the alpha and beta emitters in the Chancellor water; (2) The low activity combined with high dispersion homogeneity of the Chancellor water indicate that both alpha and beta emitters are not intrinsic colloids; (3) Radionuclides in the Chancellor water, particularly Pu, coexist as dissolved aqueous and sorbed phases - in other words the radionuclides are partitioned between the aqueous phase and the colloidal phase; (4) The presence of Pu as a dissolved species in the aqueous phase, suggests the possibility of Pu in the (V) oxidation state - this conclusion is supported by the similarity of the k{sub d} value of Pu determined in the current study to that determined for Pu(V) sorbed onto smectite colloids, and the similar electrokinetic behavior of the Chancellor water colloids to smectite colloids; (5) About 50% of the Pu(V) is in the aqueous phase and 50% is sorbed on colloids (mass concentration of colloids in the Chancellor water is 0.12 g/L); (6) The k{sub d} of the Pu and the beta emitters (fission products) between aqueous and colloidal phases in the Chancellor water is {approx}8.0 x 10{sup 3} mL/g using two different activity measurement techniques (LSC and alpha spectroscopy); (7) The gravitational settling and size distributions of the association colloids indicate that the properties (at least the physical ones) of the colloids to which the alpha emitters are associated with seem to be different that the properties of the colloids to which the beta emitters are associated with - the beta emitters are associated with very small particles ({approx}50 - 120 nm), while the alpha emitters are associated with relatively larger particles; and (8) The Chancellor water colloids are extremely stable under the natural pH and ionic strength conditions, indicating high potential for transport in the

  11. The limits on combining recursive horn rules with description logics

    SciTech Connect

    Levy, A.Y.; Rousset, M.C.

    1996-12-31

    Horn rule languages have formed the basis for many Artificial Intelligence application languages, but are not expressive enough to model domains with a rich hierarchical structure. Description logics have been designed especially to model rich hierarchies. Several applications would significantly benefit from combining the expressive power of both formalisms. This paper focuses on combining recursive function-free Horn rules with the expressive description logic ALCNR, and shows exactly when a hybrid language with decidable inference can be obtained. First, we show that several of the core constructors of description logics lead by themselves to undecidability of inference when combined with recursive function-free Horn rules. We then show that without these constructors we obtain a maximal subset of ALCNRR that yields a decidable hybrid language. Finally, we describe a restriction on the Horn rules that guarantees decidable inference when combined with all of ALCNR, and covers many of the common usages of recursive rules.

  12. Charm and bottom hadronic form factors with QCD sum rules

    SciTech Connect

    Bracco, M. E.; Rodrigues, B. O.; Cerqueira, A. Jr.

    2013-03-25

    We present a brief review of some calculations of form factors and coupling constants in vertices with charm and bottom mesons in the framework of QCD sum rules. We first discuss the motivation for this work, describing possible applications of these form factors to charm and bottom decays processes. We first make a summarize of the QCD sum rules method. We give special attention to the uncertainties of the method introducing by the intrinsic variation of the parameters. Finally we conclude.

  13. DOE Issues Final Appliance Test Procedure Rule | Department of...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    fans and ceiling fan light kits; illuminated exit signs; torchieres; low-voltage dry-type distribution transformers; traffic signal modules and pedestrian modules; unit heaters; ...

  14. Draft Environmental Assessment for Direct Final Rule, 10 CFR...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Act EGU electric generating unit EPA Environmental Protection Agency EUI energy ... Continued exposure to high NO 2 levels can lead to acute bronchitis (EPA 1994) Sources ...

  15. Automotive Trade Policy Council: Proposed Interim Final Rule | Department

    Energy Saver

    Department of Energy Authorize_Changes_Contractor_Work_Force_Restructuring_Policy.pdf Authorize_Changes_Contractor_Work_Force_Restructuring_Policy.pdf Authorize_Changes_Contractor_Work_Force_Restructuring_Policy.pdf (137.48 KB) More Documents & Publications Workforce Restructuring Policy Draft Policy and Planning Guidance for Community Transition Activities General Workforce Restructuring Plan Template

    (AO) Authorizing Official (AO) keyboard-621831_960_720.jpg The Authorizing Official

  16. FERC Order No. 2003 - Final Rule | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    through June 2, 2014. Published NA Year Signed or Took Effect 2003 Legal Citation 68 FR 49846 DOI Not Provided Check for DOI availability: http:crossref.org Citation FERC...

  17. Department of Energy Issues Final Rule on Loan Guarantees | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    more projects at a better value to taxpayers," said ... As an example, export credit agencies and other financial ... This approach will result in lowered risk and potential ...

  18. Draft Environmental Assessment for Direct Final Rule, 10 CFR...

    Energy Saver

    ... to the prescriptive-based requirements in that both ... (HVAC), service hot water systems, mechanical ... These upstream activities comprise extraction, processing, ...

  19. Draft Environmental Assessment for Direct Final Rule, 10 CFR...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... Impacts Sources Particulate Matter Lung cancer, bronchitis, and respiratory infections. ... in breathed air can deposit and stay in the lungs, sometimes contributing to lung cancer. ...

  20. Draft Environmental Assessment for Direct Final Rule, 10 CFR...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... Energy EPA Environmental Protection Agency EUI Energy use intensity, kBtuft2-yr FR ... Table 2 shows the national average energy savings in terms of energy use intensity (EUI) ...

  1. Draft Environmental Assessment for Direct Final Rule, 10 CFR...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... unit EPA Environmental Protection Agency EUI Energy use intensity, kBtuft2-yr FR ... Energy Use Intensity (EUI) is the energy consumed by a building per square foot per year. ...

  2. GSA Federal Advisory Committee Management; Final Rule -- 41CFR...

    Office of Environmental Management (EM)

    (GSA) revision of Federal Property Management Regulations (FPMR) coverage on federal advisory committee management and moving it into the Federal Management Regulation (FMR). ...

  3. DOE Issues Final Rule on Loan Guarantees | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    provide loan guarantees to projects with multiple participants. As an example, export credit agencies and other financial institutions will now be able to provide financing to...

  4. American Transmission Company Comments- 216h Interim Final Rules

    Office of Energy Efficiency and Renewable Energy (EERE)

    American Transmission Company LLC, by its corporate manager, ATC Management Inc. (collectively “ATCLLC”) is pleased to have the opportunity to provide the following comments on the additional...

  5. DOE Issues Final Rule for Alternative Efficiency Determination...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    regulations governing the use of particular methods as alternatives to testing for commercial heating, ventilating, air-conditioning, water heating, and refrigeration equipment. ...

  6. IWARS Final

    Energy Saver

    Appendices 1. Objective, Scope, and Methodology ......Finally, management felt that an expanded audit scope could have provided a more complete ...

  7. Final Optics

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    final optics Final Optics Schematic layout of NIF's final optics assembly (FOA). The suite of optics for one beamline is on the right. The final optics assemblies (FOAs) are the last element of the main laser system and the first of the target area systems. Each FOA contains four integrated optics modules (IOMs) that incorporate beam conditioning, frequency conversion, focusing, diagnostic sampling, and debris shielding capabilities into a single compact assembly. These optics are shown in the

  8. Identify Institutional Change Rules for Sustainability | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Rules for Sustainability Identify Institutional Change Rules for Sustainability It is important to analyze formal and informal workplace rules governing the behavior of individuals ...

  9. Dynamics and transformations of radionuclides in soils and ecosystem health

    SciTech Connect

    Fellows, Robert J. ); Ainsworth, Calvin C. ); Driver, Crystal J. ); Cataldo, Dominic A. )

    1998-12-01

    The chemical behavior of radionuclides can vary widely in soil and sediment environments. Equally important, for a given radionuclide the physico-chemical properties of the solids and aqueous phase can greatly influence a radionuclides behavior. Radionuclides can conceivably occur in soils as soluble-free, inorganic-soluble-complexed, organic-soluble, complexed, adsorbed, precipitated, coprecipitated, or solid structural species. While it is clear that an assessment of a radionuclide?s soil chemistry and potential shifts in speciation will yield a considerable understanding of its behavior in the natural environment, it does not directly translate to bioavailability or its impact on ecosystems health. The soil chemical factors have to be linked to food chain considerations and other ecological parameters that directly tie to an analysis of ecosystem health. In general, the movement of radionuclides from lower to higher trophic levels diminishes with each trophic level in both aqua tic and terrestrial systems. In some cases, transfer is limited because of low absorption/assimilation by successive trophic organisms (Pu, U); for other radionuclides (Tc, H) assimilation may be high but rapid metabolic turnover and low retention greatly reduce tissue concentrations available to predator species. Still others are chemical analogs of essential elements whose concentrations are maintained under strict metabolic control in tissues (Cs) or are stored in tissues seldom consumed by other organisms (Sr storage in exoskeleton, shells, and bone). Therefore, the organisms that receive the greatest ingestion exposures are those in lower trophic positions or are in higher trophic levels but within simple, short food chains. Food source, behavior, and habitat influence the accumulation of radionuclides in animals.

  10. Radionuclide transport through engineered barrier system alteration products

    SciTech Connect

    Viani, B.E.; Torretto, P.C.; Matzen, S.L.

    1997-12-01

    The primary rationale for studying the transport behavior of radionuclides through the Engineered Barrier system / Near Field Environment (EBS/NFE) is to ascertain whether the material properties of the introduced and altered host rock can significantly affect the transport of radionuclides from the waste container to the far field. The intent of this report is to present data and modeling results that can be used to assess the importance of canister corrosion products and cementitious materials to transport of radionuclides to the far field.

  11. Radionuclide Transport Models Under Ambient Conditions

    SciTech Connect

    G. Moridis; Q. Hu

    2000-03-12

    The purpose of this Analysis/Model Report (AMR) is to evaluate (by means of 2-D semianalytical and 3-D numerical models) the transport of radioactive solutes and colloids in the unsaturated zone (UZ) under ambient conditions from the potential repository horizon to the water table at Yucca Mountain (YM), Nevada. This is in accordance with the ''AMR Development Plan U0060, Radionuclide Transport Models Under Ambient Conditions'' (CRWMS M and O 1999a). This AMR supports the UZ Flow and Transport Process Model Report (PMR). This AMR documents the UZ Radionuclide Transport Model (RTM). This model considers: the transport of radionuclides through fractured tuffs; the effects of changes in the intensity and configuration of fracturing from hydrogeologic unit to unit; colloid transport; physical and retardation processes and the effects of perched water. In this AMR they document the capabilities of the UZ RTM, which can describe flow (saturated and/or unsaturated) and transport, and accounts for (a) advection, (b) molecular diffusion, (c) hydrodynamic dispersion (with full 3-D tensorial representation), (d) kinetic or equilibrium physical and/or chemical sorption (linear, Langmuir, Freundlich or combined), (e) first-order linear chemical reaction, (f) radioactive decay and tracking of daughters, (g) colloid filtration (equilibrium, kinetic or combined), and (h) colloid-assisted solute transport. Simulations of transport of radioactive solutes and colloids (incorporating the processes described above) from the repository horizon to the water table are performed to support model development and support studies for Performance Assessment (PA). The input files for these simulations include transport parameters obtained from other AMRs (i.e., CRWMS M and O 1999d, e, f, g, h; 2000a, b, c, d). When not available, the parameter values used are obtained from the literature. The results of the simulations are used to evaluate the transport of radioactive solutes and colloids, and

  12. SLUDGE BATCH 7 ACCEPTANCE EVALUATION: RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB7 QUALIFICATION SAMPLE PREPARED AT SRNL

    SciTech Connect

    Pareizs, J.; Hay, M.

    2011-02-22

    Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Seven (SB7) for processing in the Defense Waste Processing Facility (DWPF). The SB7 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB6. The radionuclide concentrations were measured or estimated in the Tank 51 SB7 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter qualification sample of Tank 51 sludge slurry (HTF-51-10-125) received on September 18, 2010. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. With consultation from the Liquid Waste Organization, the qualification sample was then modified by several washes and decants, which included addition of Pu from H Canyon and sodium nitrite per the Tank Farm corrosion control program. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Tank 40. Determining the radionuclide concentrations in this Tank 51 SB7 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2010-0031. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task I.2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task III.2.) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB7 will be taken and transferred to SRNL for measurement of these radionuclides

  13. Radionuclide Migration at the Rio Blanco Site, A Nuclear-stimulated Low-permeability Natural Gas Reservoir

    SciTech Connect

    Clay A. Cooper; Ming Ye; Jenny Chapman; Craig Shirley

    2005-10-01

    The U.S. Department of Energy and its predecessor agencies conducted a program in the 1960s and 1970s that evaluated technology for the nuclear stimulation of low-permeability gas reservoirs. The third and final project in the program, Project Rio Blanco, was conducted in Rio Blanco County, in northwestern Colorado. In this experiment, three 33-kiloton nuclear explosives were simultaneously detonated in a single emplacement well in the Mesaverde Group and Fort Union Formation, at depths of 1,780, 1,899, and 2,039 m below land surface on May 17, 1973. The objective of this work is to estimate lateral distances that tritium released from the detonations may have traveled in the subsurface and evaluate the possible effect of postulated natural-gas development on radionuclide migration. Other radionuclides were considered in the analysis, but the majority occur in relatively immobile forms (such as nuclear melt glass). Of the radionuclides present in the gas phase, tritium dominates in terms of quantity of radioactivity in the long term and contribution to possible whole body exposure. One simulation is performed for {sup 85}Kr, the second most abundant gaseous radionuclide produced after tritium.

  14. Idaho Administrative Rules 20.03.15 Rules Governing Geothermal...

    OpenEI (Open Energy Information) [EERE & EIA]

    Leasing on State LandLegal Abstract Idaho regulation governing the rules and procedures for geothermal leasing on state lands. Published NA Year Signed or Took Effect 2012...

  15. Mobility of Source Zone Heavy Metals and Radionuclides: The...

    Office of Scientific and Technical Information (OSTI)

    ... Field, E.K. , P. Haun, R. Gerlach, B.M. Peyton, W.A. Apel, and B.D. Lee (2006): The Influence of Cellulose Utilization on Metal and Radionuclide Mobility and Reduction. ...

  16. The Production & Generation of Radionuclides from Deuterium-Deuterium...

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    invention is for the generation and production of radionuclides generated by D-D and D-T nuclear reactions in fusion reactors and fusion devices for medical, industry and research...

  17. SRNL RADIONUCLIDE FIELD LYSIMETER EXPERIMENT: BASELINE CONSTRUCTION AND IMPLEMENTATION

    SciTech Connect

    Roberts, K.; Kaplan, D.; Bagwell, L.; Powell, B.; Almond, P.; Emerson, H.; Hixon, A.; Jablonski, J.; Buchanan, C.; Waterhouse, T.

    2012-10-17

    The purpose of this document is to compile information regarding experimental design, facility design, construction, radionuclide source preparation, and path forward for the ten year Savannah River National Laboratory (SRNL) Radionuclide Field Lysimeter Experiment at the Savannah River Site (SRS). This is a collaborative effort by researchers at SRNL and Clemson University. The scientific objectives of this study are to: Study long-term radionuclide transport under conditions more representative of vadose zone conditions than laboratory experiments; Provide more realistic quantification of radionuclide transport and geochemistry in the vadose zone, providing better information pertinent to radioactive waste storage solutions than presently exists; Reduce uncertainty and improve justification for geochemical models such as those used in performance assessments and composite analyses.

  18. Natural chelating agents for radionuclide decorporation

    DOEpatents

    Premuzic, E.T.

    1985-06-11

    This invention relates to the production of metal-binding compounds useful for the therapy of heavy metal poisoning, for biological mining and for decorporation of radionuclides. The present invention deals with an orderly and effective method of producing new therapeutically effective chelating agents. This method uses challenge biosynthesis for the production of chelating agents that are specific for a particular metal. In this approach, the desired chelating agents are prepared from microorganisms challenged by the metal that the chelating agent is designed to detoxify. This challenge induces the formation of specific or highly selective chelating agents. The present invention involves the use of the challenge biosynthetic method to produce new complexing/chelating agents that are therapeutically useful to detoxify uranium, plutonium, thorium and other toxic metals. The Pseudomonas aeruginosa family of organisms is the referred family of microorganisms to be used in the present invention to produce the new chelating agent because this family is known to elaborate strains resistant to toxic metals.

  19. Radionuclide Interaction and Transport in Representative Geologic Media |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Radionuclide Interaction and Transport in Representative Geologic Media Radionuclide Interaction and Transport in Representative Geologic Media The report presents information related to the development of a fundamental understanding of disposal-system performance in a range of environments for potential wastes that could arise from future nuclear fuel cycle alternatives. It addresses selected aspects of the development of computational modeling capability for the

  20. Naturally occurring radionuclides in agricultural products: An overview

    SciTech Connect

    Hanlon, E.A.

    1994-07-01

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

  1. Statistical analyses of plume composition and deposited radionuclide mixture ratios

    SciTech Connect

    Kraus, Terrence D.; Sallaberry, Cedric Jean-Marie; Eckert-Gallup, Aubrey Celia; Brito, Roxanne; Hunt, Brian D.; Osborn, Douglas M.

    2014-01-01

    A proposed method is considered to classify the regions in the close neighborhood of selected measurements according to the ratio of two radionuclides measured from either a radioactive plume or a deposited radionuclide mixture. The subsequent associated locations are then considered in the area of interest with a representative ratio class. This method allows for a more comprehensive and meaningful understanding of the data sampled following a radiological incident.

  2. Final EA

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Lane-Wendson No. 1 Transmission Line Rebuild Project Final Environmental Assessment 1 In cooperation with the Bureau of Land Management Lane-Wendson No. 1 Transmission Line Rebuild Project Final Environmental Assessment DEPARTMENT OF ENERGY Bonneville Power Administration DOE/EA-1952 April 2016 This document is the final Environmental Assessment (EA) for the proposed Lane-Wendson No. 1 Transmission Line Rebuild Project. Bonneville Power Administration (BPA) prepared this document as an

  3. FINAL REPORT

    Office of Scientific and Technical Information (OSTI)

    FINAL REPORT Analytical and Elemental Analysis of Air and Soil Samples Facility and Public ... Information 4 Background 5 Stormwater Pollution 5 Erosion and Sediment Control Workshop ...

  4. The Clean Air Interstate Rule

    SciTech Connect

    Debra Jezouit; Frank Rambo

    2005-07-01

    On May 12, 2005, EPA promulgated the Clean Air Interstate Rule, which overhauls and expands the scope of air emissions trading programs in the eastern United States. The rule imposes statewide caps on emissions of nitrogen oxides and sulfur dioxide to be introduced in two phases, beginning in 2009. This article briefly explains the background leading up to the rule and summarizes its key findings and requirements. 2 refs., 1 fig., 1 tab.

  5. Benchmark Distribution & Run Rules

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Rules Benchmark Distribution & Run Rules Applications and micro-benchmarks for the Crossroads/NERSC-9 procurement. You can find more information by clicking on the header for each of the topics listed below. Change Log Change and update notes for the benchmark suite. Application Benchmarks The following applications will be used by the Sustained System Improvement metric in measuring the performance improvement of proposed systems relative to NERSC's Edison platform. General Run Rules

  6. Screening Risk Assessment for Possible Radionuclides in the Amchitka Marine Environment

    SciTech Connect

    NNSA /NV

    2002-10-31

    As part of its environmental stewardship program the U.S. Department of Energy (DOE) is reevaluating three sites where underground nuclear tests were conducted in the deep subsurface of Amchitka Island, Alaska. The tests (i.e., Long Shot, Milrow, and Cannikin) were conducted in 1965, 1969, and 1971, respectively. Extensive investigations were conducted on these tests and their effect on the environment. Evaluations at the time of testing indicated limited release of radionuclides and absence of risk related to the testing; however, these are being reevaluated under the current DOE environmental stewardship program. A screening risk assessment of potential radionuclide release into the marine environment is an important part of this reevaluation. The risk assessment is one of three interrelated activities: a groundwater model and this screening risk assessment, both of which guide the decisions in the third activity, the site closure plan. Thus, the overall objective of the work is to understand, and subsequently manage, any risk to humans and the environment through a closure and long-term stewardship plan. The objective of this screening risk assessment is to predict whether possible releases of radionuclides at the ocean floor would represent potential risks to Native Alaskans by consumption of marine subsistence species. In addition, risks were predicted for consumers of commercial catches of marine organisms. These risks were calculated beginning with estimates of possible radionuclide release at the seafloor (from a groundwater modeling study), into the seawater, through possible uptake by marine organisms, and finally possible consumption by humans. The risk assessment model has 11 elements, progressing from potential release at the seafloor through water and food chains to human intake. Data for each of these elements were systematically found and synthesized from many sources, and represent the best available knowledge. Whenever precise data were lacking

  7. FINAL RELEASE

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    RELEASE AWARDEE: ____________________________________________________ The work under Award No. DE-__________________________, dated ______________, between the United States of America (represented by the Department of Energy, National Energy Technology Laboratory, and the undersigned awardee, having been completed and finally accepted , and in consideration of Final Payment thereunder, the United States of America, its officers, agents and employees are hereby released from all liabilities,

  8. Calculation of Accumulated Radiation Doses to Man from Radionuclides Found in Food Products and from Radionuclides in the Environment.

    Energy Science and Technology Software Center

    1981-02-17

    PABLM calculates internal radiation doses to man from radionuclides in food products and external radiation doses from radionuclides in the environment. It can be used to calculate accumulated doses to 23 possible body organs or tissues for any one or a combination of radionuclides. Radiation doses from radionuclides in the environment may be calculated from deposition on the soil or plants during an atmospheric or liquid release, or from exposure to residual radionuclides in themore » environment after the releases have ended. Radioactive decay is considered during the release of radionuclides, after they are deposited on the plants or ground, and during holdup of food after harvest. A chain decay scheme is used; it includes branching to account for transitions to and from isomeric states. Doses may be calculated for either a maximum-exposed individual or for a population group. The doses calculated are accumulated doses from continuous chronic exposure. A first-year committed dose is calculated as well as an integrated dose for a selected number of years.« less

  9. Evaluating Radionuclide Air Emission Stack Sampling Systems

    SciTech Connect

    Ballinger, Marcel Y.

    2002-12-16

    The Pacific Northwest National Laboratory (PNNL) operates a number of research and development (R&D) facilities for the U.S. Department of Energy at the Hanford Site, Washington. These facilities are subject to Clean Air Act regulations that require sampling of radionuclide air emissions from some of these facilities. A revision to an American National Standards Institute (ANSI) standard on sampling radioactive air emissions has recently been incorporated into federal and state regulations and a re-evaluation of affected facilities is being performed to determine the impact. The revised standard requires a well-mixed sampling location that must be demonstrated through tests specified in the standard. It also carries a number of maintenance requirements, including inspections and cleaning of the sampling system. Evaluations were performed in 2000 2002 on two PNNL facilities to determine the operational and design impacts of the new requirements. The evaluation included inspection and cleaning maintenance activities plus testing to determine if the current sampling locations meet criteria in the revised standard. Results show a wide range of complexity in inspection and cleaning activities depending on accessibility of the system, ease of removal, and potential impact on building operations (need for outages). As expected, these High Efficiency Particulate Air (HEPA)-filtered systems did not show deposition significant enough to cause concerns with blocking of the nozzle or other parts of the system. The tests for sampling system location in the revised standard also varied in complexity depending on accessibility of the sample site and use of a scale model can alleviate many issues. Previous criteria to locate sampling systems at eight duct diameters downstream and two duct diameters upstream of the nearest disturbances is no guarantee of meeting criteria in the revised standard. A computational fluid dynamics model was helpful in understanding flow and

  10. The Clean Air Mercury Rule

    SciTech Connect

    Michael Rossler

    2005-07-01

    Coming into force on July 15, 2005, the US Clean Air Mercury Rule will use a market-based cap-and-trade approach under Section 111 of the Clean Air Act to reduce mercury emissions from the electric power sector. This article provides a comprehensive summary of the new rule. 14 refs., 2 tabs.

  11. Notice of Final Rulemaking | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Rulemaking Notice of Final Rulemaking Revisions to U.S. Department of Energy (DOE) regulations governing compliance with the National Environmental Policy Act (NEPA) were published in the Federal Register on October 13, 2011, and will be effective on November 14. The revision (76 FR 63763) can be viewed using the link below. Final Rule - 76 FR 63763 - Oct 13 2011_0.pdf (297.74 KB) More Documents & Publications Department of Energy Technical Support Document National Environmental

  12. Final Report

    SciTech Connect

    Gurney, Kevin R

    2015-01-12

    This document constitutes the final report under DOE grant DE-FG-08ER64649. The organization of this document is as follows: first, I will review the original scope of the proposed research. Second, I will present the current draft of a paper nearing submission to Nature Climate Change on the initial results of this funded effort. Finally, I will present the last phase of the research under this grant which has supported a Ph.D. student. To that end, I will present the graduate student’s proposed research, a portion of which is completed and reflected in the paper nearing submission. This final work phase will be completed in the next 12 months. This final workphase will likely result in 1-2 additional publications and we consider the results (as exemplified by the current paper) high quality. The continuing results will acknowledge the funding provided by DOE grant DE-FG-08ER64649.

  13. Final Report

    SciTech Connect

    Biros, George

    2014-08-18

    This the final report for the project "Large-Scale Optimization for Bayesian Inference in Complex Systems," for the work in the group of the co-PI George Biros.

  14. Final Report

    SciTech Connect

    DeTar, Carleton

    2012-12-10

    This document constitutes the Final Report for award DE-FC02-06ER41446 as required by the Office of Science. It summarizes accomplishments and provides copies of scientific publications with significant contribution from this award.

  15. REPORTABLE RADIONUCLIDES IN DWPF SLUDGE BATCH 7A (MACROBATCH 8)

    SciTech Connect

    Reboul, S.; Diprete, D.; Click, D.; Bannochie, C.

    2011-12-20

    The Waste Acceptance Product Specifications (WAPS) 1.2 require that the waste producer 'shall report the curie inventory of radionuclides that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115.' As part of the strategy to meet WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type all radionuclides that have half-lives longer than 10 years and contribute greater than 0.01 percent of the total curie inventory from the time of production through the 1100 year period from 2015 through 3115. The initial list of radionuclides to be reported is based on the design-basis glass identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report. However, it is required that the list be expanded if other radionuclides with half-lives greater than 10 years are identified that meet the 'greater than 0.01% of the curie inventory' criterion. Specification 1.6 of the WAPS, International Atomic Energy Agency Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, and U-238; and Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete list of reportable radionuclides must also include these sets of U and Pu isotopes - and the U and Pu isotopic mass distributions must be identified. The DWPF receives HLW sludge slurry from Savannah River Site (SRS) Tank 40. For Sludge Batch 7a (SB7a), the waste in Tank 40 contained a blend of the heel from Sludge Batch 6 (SB6) and the Sludge Batch 7 (SB7) material transferred to Tank 40 from Tank 51. This sludge blend is also referred to as Macrobatch 8. Laboratory analyses of a Tank 40 sludge sample were performed to quantify the concentrations of pertinent radionuclides in the SB7a waste. Subsequently, radiological decay and in

  16. Court decision dropping toxic substance rules stands

    SciTech Connect

    Bryant, C.R.

    1993-06-01

    In a somewhat surprising move, the U.S. Department of Labor has decided not to appeal a court decision essentially dropping regulations established by the Occupational Safety and Health Administration (OSHA) for about 400 hazardous substances. The decision leaves unregulated or subject to reduced standards substances that range from carbon monoxide to perchloroethylene. The Labor Department had until March 22, 1993, to appeal the court decision. On July 8, 1992, the U.S. Court of Appeals for the 11th Circuit overturned OSHA's final Air Contaminants Standard, which was promulgated in 1989. The standard established permissible exposure limits (PELs) for 428 toxic substances. In AFL-CIO vs. OSHA, the Court ruled that OSHA failed to make a separate scientific case for evaluating health risks of each chemical. Because of the decision not to appeal, PELs for more than half of the substances regulated by OSHA now are removed from the books or revert to the voluntary industry standards adopted by OSHA in 1970 and in force prior to the 1989 final rule.

  17. A model for radionuclide transport in the Cooling Water System

    SciTech Connect

    Kahook, S.D.

    1992-08-01

    A radionuclide transport model developed to assess radiological levels in the K-reactor Cooling Water System (CWS) in the event of an inadvertent process water (PW) leakage to the cooling water (CW) in the heat exchangers (HX) is described. During and following a process water leak, the radionuclide transport model determines the time-dependent release rates of radionuclide from the cooling water system to the environment via evaporation to the atmosphere and blow-down to the Savannah River. The developed model allows for delay times associated with the transport of the cooling water radioactivity through cooling water system components. Additionally, this model simulates the time-dependent behavior of radionuclides levels in various CWS components. The developed model is incorporated into the K-reactor Cooling Tower Activity (KCTA) code. KCTA allows the accident (heat exchanger leak rate) and the cooling tower blow-down and evaporation rates to be described as time-dependent functions. Thus, the postulated leak and the consequence of the assumed leak can be modelled realistically. This model is the first of three models to be ultimately assembled to form a comprehensive Liquid Pathway Activity System (LPAS). LPAS will offer integrated formation, transport, deposition, and release estimates for radionuclides formed in a SRS facility. Process water and river water modules are forthcoming as input and downstream components, respectively, for KCTA.

  18. EERE Success Story-Rule to Support Increased Energy Measurement and

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Efficient Building Design | Department of Energy Rule to Support Increased Energy Measurement and Efficient Building Design EERE Success Story-Rule to Support Increased Energy Measurement and Efficient Building Design February 12, 2015 - 12:10pm Addthis In 2014, EERE's Federal Energy Management Program issued a final rule that requires verified energy and water performance for new and retrofitted federal buildings that are certified by private sector green building certification systems. The

  19. Texas - PUC Substantive Rule 22 - Procedural Rules | Open Energy...

    OpenEI (Open Energy Information) [EERE & EIA]

    Procedural RulesLegal Abstract The purpose of this chapter is to provide a system of procedures for practice before the Public Utilities Commission of Texas. Published NA Year...

  20. Deriving cleanup guidelines for radionuclides at Brookhaven National Laboratory

    SciTech Connect

    Meinhold, A.F.; Morris, S.C.; Dionne, B.; Moskowitz, P.D.

    1997-01-01

    Past activities at Brookhaven National Laboratory (BNL) resulted in soil and groundwater contamination. As a result, BNL was designated a Superfund site under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). BNL`s Office of Environmental Restoration (OER) is overseeing environmental restoration activities at the Laboratory. With the exception of radium, there are no regulations or guidelines to establish cleanup guidelines for radionuclides in soils at BNL. BNL must derive radionuclide soil cleanup guidelines for a number of Operable Units (OUs) and Areas of Concern (AOCs). These guidelines are required by DOE under a proposed regulation for radiation protection of public health and the environment as well as to satisfy the requirements of CERCLA. The objective of this report is to propose a standard approach to deriving risk-based cleanup guidelines for radionuclides in soil at BNL. Implementation of the approach is briefly discussed.

  1. MICROBIAL TRANSFORMATIONS OF RADIONUCLIDES RELEASED FROM NUCLEAR FUEL REPROCESSING PLANTS.

    SciTech Connect

    FRANCIS,A.J.

    2006-10-18

    Microorganisms can affect the stability and mobility of the actinides U, Pu, Cm, Am, Np, and the fission products Tc, I, Cs, Sr, released from nuclear fuel reprocessing plants. Under appropriate conditions, microorganisms can alter the chemical speciation, solubility and sorption properties and thus could increase or decrease the concentrations of radionuclides in solution and the bioavailability. Dissolution or immobilization of radionuclides is brought about by direct enzymatic action or indirect non-enzymatic action of microorganisms. Although the physical, chemical, and geochemical processes affecting dissolution, precipitation, and mobilization of radionuclides have been investigated, we have only limited information on the effects of microbial processes. The mechanisms of microbial transformations of the major and minor actinides and the fission products under aerobic and anaerobic conditions in the presence of electron donors and acceptors are reviewed.

  2. Radionuclides in plankton from the South Pacific Basin

    SciTech Connect

    Marsh, K.V.; Buddemeier, R.W.

    1984-03-23

    We have initiated an investigation of the utility of marine plankton as bioconcentrating samplers of low-level marine radioactivity in the southern hemisphere. A literature review has shown that both freshwater and marine plankton have trace element and radionuclide concentration factors (relative to water) of up to 10/sup 4/. We participated in Operations Deepfreeze 1981 and 1982, collecting a total of 48 plankton samples from the USCGC Glacier on its Antarctic cruises. Battelle Pacific Northwest Laboratories sampled air, water, rain, and fallout. We were able to measure concentrations in plankton of the naturally-occurring radionuclides /sup 7/Be, /sup 40/K, and the U and Th series, and we believe that we have detected low levels of /sup 144/Ce and /sup 95/Nb in seven samples ranging as far south as 68/sup 0/. Biological identification of the plankton suggests a possible correlation between radionuclide concentration and the protozoa content of the samples. 7 references, 5 figures.

  3. Assessment of the impact of radionuclides in coal ash

    SciTech Connect

    Styron, C.E.; Bishop, C.T.; Casella, V.R.; Jenkins, P.H.; Yanko, W.H.

    1981-01-01

    An assessment of the potential environmental and health impacts of radionuclides in the coal fuel cycle is being conducted at Mound. This paper describes our studies evaluating the potential for migration of radionuclides from ash disposal sites. Studies at a power plant burning western US coal dealt with an assessment of potential radiation doses from coal ash ponds and leachate discharges of radionuclides from the ponds. Emanation of radon-222 from the ash is relatively low. The emanation of radon-222 from the ash pond (radium-226 at 4.5 pCi/g) is predicted to be about six times less than from soil (radium-226 at 1 pCi/g). Ash with radium-226 at 25 pCi/g would approximate emanation of radon-222 from soil. At 1000 m from the center of the ash pond area, radon-222 from the ash pond is predicted to be 1000 to 6000 times less than background (0.1 to 0.5 pCi/liter). Pathways exist for transport of radionuclides leached from ash into the aquifer beneath the holding ponds, but concentrations of radionuclides in water leaving the pond are lower than concentrations in groundwater which is upgradient of the ponds. Leachability of the ash is quite low, on the order of 0.002% in one month, and flow of ash sluicing water (3% of the volume of the ponds each day) has actually diluted normal background concentrations of radionuclides in the aquifer between the ponds and the adjacent river.

  4. Influence of speciation on the geospheric migration of radionuclides

    SciTech Connect

    Hadermann, J.

    1982-01-01

    Radionuclides in ground water can exist as different species whose retention factors may be strongly different. For one-dimensional transport in a porous medium, conditions for the existence of equilibrium between two species are given. In most cases, these conditions are probably well fulfilled when time scales of geosphere transport are considered. In these cases, the total concentration migrates independently of a particular speciation with an effective retention factor. Such an effective retention factor can also be defined if more than two species in liquid phase are in equilibrium. As a consequence, existing radionuclide transport models can be readily used by properly redefining the retention factor.

  5. U.S. DOE 2004 LANL Radionuclide Air Emissions

    SciTech Connect

    K.W. Jacobson

    2005-08-12

    Amendments to the Clean Air Act, which added radionuclides to the National Emissions Standards for Hazardous Air Pollutants (NESHAP), went into effect in 1990. Specifically, a subpart (H) of 40 CFR 61 established an annual limit on the impact to the public attributable to emissions of radionuclides from U.S. Department of Energy facilities, such as the Los Alamos National Laboratory (LANL). As part of the new NESHAP regulations, LANL must submit an annual report to the U.S. Environmental Protection Agency headquarters and the regional office in Dallas by June 30. This report includes results of monitoring at LANL and the dose calculations for the calendar year 2004.

  6. Method for image reconstruction of moving radionuclide source distribution

    DOEpatents

    Stolin, Alexander V.; McKisson, John E.; Lee, Seung Joon; Smith, Mark Frederick

    2012-12-18

    A method for image reconstruction of moving radionuclide distributions. Its particular embodiment is for single photon emission computed tomography (SPECT) imaging of awake animals, though its techniques are general enough to be applied to other moving radionuclide distributions as well. The invention eliminates motion and blurring artifacts for image reconstructions of moving source distributions. This opens new avenues in the area of small animal brain imaging with radiotracers, which can now be performed without the perturbing influences of anesthesia or physical restraint on the biological system.

  7. ORISE: Dose Coefficients for Intakes of Radionuclides via Contaminated Wounds

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Dose CoeffiCients for intakes of raDionuCliDes via ContaminateD WounDs R. E. Toohey*, L. Bertelli + , S. L. Sugarman*, A. L. Wiley* and D. M. Christensen* *Radiation Emergency Assistance Center/Training Site, Oak Ridge Institute for Science and Education, Oak Ridge, TN 37031-0117; + Radiation Protection Division, Los Alamos National Laboratory, Los Alamos, New Mexico 87545. Ver. 2, Aug 2014 The NCRP Wound Model describing the retention of selected radionuclides at the site of a contaminated

  8. Weatherization Rules and Regulations Resources

    Energy.gov [DOE]

    Federal regulations provide the framework for the Weatherization Assistance Program. These rules and regulations give state and local weatherization programs guidelines to provide the energy efficiency improvements to low-income dwellings.

  9. Final Signed Letters to EM SSAB Chairs' Recommendation 2013-01.041513updated.pdf

    Office of Environmental Management (EM)

    (October 23, 2007) Final Rule (October 23, 2007) Loan Guarantees for Projects That Employ Innovative Technologies; Final Rule: On May 16, 2007, the Department of Energy (DOE or the Department) published a Notice of Proposed Rulemaking and opportunity for comment (NOPR) to establish regulations for the loan guarantee program authorized by Title XVII of the Energy Policy Act of 2005 (Title XVII or the Act). Final Rule (231.04 KB) More Documents & Publications Notice of Proposed Rulemaking

  10. Radionuclides in bats using a contaminated pond on the Nevada National Security Site, USA

    DOE PAGES [OSTI]

    Warren, Ronald W.; Hall, Derek B.; Greger, Paul D.

    2014-01-03

    In this study, perched groundwater percolating through radionuclide contamination in the E Tunnel Complex on the Nevada National Security Site, formerly the Nevada Test Site, emerges and is stored in a series of ponds making it available to wildlife, including bats. Since many bat species using the ponds are considered sensitive or protected/regulated and little information is available on dose to bats from radioactive water sources, bats were sampled to determine if the dose they were receiving exceeded the United States Department of Energy dose limit of 1.0E-3 Gy/day. Radionuclide concentrations in water, sediment, and flying insects were also measuredmore » as input parameters to the dose rate model and to examine trophic level relationships. The RESRAD-Biota model was used to calculate dose rates to bats using different screening levels. Efficacy of RESRAD-Biota and suggested improvements are discussed. Finally, dose to bats foraging and drinking at these ponds is well below the dose limit set to protect terrestrial biota populations.« less

  11. Radionuclides in bats using a contaminated pond on the Nevada National Security Site, USA

    SciTech Connect

    Warren, Ronald W.; Hall, Derek B.; Greger, Paul D.

    2014-01-03

    In this study, perched groundwater percolating through radionuclide contamination in the E Tunnel Complex on the Nevada National Security Site, formerly the Nevada Test Site, emerges and is stored in a series of ponds making it available to wildlife, including bats. Since many bat species using the ponds are considered sensitive or protected/regulated and little information is available on dose to bats from radioactive water sources, bats were sampled to determine if the dose they were receiving exceeded the United States Department of Energy dose limit of 1.0E-3 Gy/day. Radionuclide concentrations in water, sediment, and flying insects were also measured as input parameters to the dose rate model and to examine trophic level relationships. The RESRAD-Biota model was used to calculate dose rates to bats using different screening levels. Efficacy of RESRAD-Biota and suggested improvements are discussed. Finally, dose to bats foraging and drinking at these ponds is well below the dose limit set to protect terrestrial biota populations.

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

    SciTech Connect

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

    2008-10-30

    The overall objective of this study was to measure a number of key input parameters quantifying geochemical processes in the subsurface environment of the Savannah River Site's (SRS's) Saltstone Facility. For the first time, sorption (K{sub d}) values of numerous radionuclides were measured with Saltstone and Vault 2 concrete. Particular attention was directed at understanding how Tc adsorbs and desorbs from these cementitious materials with the intent to demonstrate that desorption occurs at a much slower rate than adsorption, thus permitting the use of kinetic terms instead of (or along with) the steady state K{sub d} term. Another very important parameter measured was the reduction capacity of these materials. This parameter is used to estimate the duration that the Saltstone facility remains in a reduced chemical state, a condition that maintains several otherwise mobile radionuclides in an immobile form. Key findings of this study follow. K{sub d} values for Am, Cd, Ce, Co, Cs, Hg, I, Np, Pa, Pu, Se, Sn, Tc, U, and Y for Saltstone and Vault 2 concrete were measured under oxidized and reduced conditions. Precipitation of several of the higher valence state radionuclides was observed. There was little evidence that the Vault 2 and Saltstone K{sub d} values differed from previous SRS K{sub d} values measured with reducing grout (Kaplan and Coates 2007). These values also supported a previous finding that K{sub d} values of slag-containing cementitious materials, tend to be greater for cations and about the same for anions, than regular cementitious materials without slag. Based on these new findings, it was suggested that all previous reducing concrete K{sub d} values be used in future PAs, except Np(V) and Pu(IV) K{sub d} values, which should be increased, and I values, which should be slightly decreased in all three stages of concrete aging. The reduction capacity of Saltstone, consisting of 23 wt-% blast furnace slag, was 821.8 microequivalents per gram

  13. Vermont Stormwater Management Rule | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    LibraryAdd to library Legal Document- RegulationRegulation: Vermont Stormwater Management RuleLegal Abstract This Rule: (1) Establishes a state permit program for...

  14. Permit by Rule Guide | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Permit by Rule GuideLegal Abstract California Department of Toxic Substance Control Permit by Rule Guide, current through August 7, 2014. Published NA Year Signed or...

  15. Hawaii Administrative Rules | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Not provided DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for Hawaii Administrative Rules Citation Hawaii Administrative Rules (2014)....

  16. Idaho Appellate Rules | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Not provided DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for Idaho Appellate Rules Citation Idaho Appellate Rules (2014). Retrieved from...

  17. Oregon Administrative Rules | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Not provided DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for Oregon Administrative Rules Citation Oregon Administrative Rules (2014)....

  18. Clean Air Nonroad Diesel Rule (released in AEO2005)

    Reports and Publications

    2005-01-01

    On June 29, 2004, the Environmental Protection Agency issued a comprehensive final rule regulating emissions from nonroad diesel engines and sulfur content in nonroad diesel fuel. The nonroad fuel market makes up more than 18% of the total distillate pool. The rule applies to new equipment covering a broad range of engine sizes, power ratings, and equipment types. There are currently about 6 million pieces of nonroad equipment operating in the United States, and more than 650,000 new units are sold each year.

  19. Phase 2 sampling for radionuclides and metal distribution in L-lake sediments. Final report

    SciTech Connect

    Koch, J.W. II

    1996-10-01

    Science Applications International Corporation (SAIC) was tasked by Westinghouse Savannah River Company under subcontract C001015P to provide environmental sampling services on L-Lake at the Savannah River site. Athena Technologies, Inc. was subcontracted by SAIC to provide vibracoring services. The project consisted of vibracore sampling of lake bottom sediments at 23 locations within L-Lake. Field activities were performed from August 8 through August 22, 1996. This report describes the activities associated with the task.

  20. Dosimetry and quantitative radionuclide imaging in radioimmunotherapy: Final report, July 15, 1992-July 14, 1996

    SciTech Connect

    Leichner, P.K.

    1996-09-01

    Brief summaries of the principal accomplishments of this project on the development of quantitative SPECT for high energy photons (87Y, 19F) and stability testing of 87Y-labeled antibodies in the nude mouse model, development of an unified approach to photon and beta particle dosimetry, quantitative SPECT for nonuniform attenuation, and development of patient-specific dosimetry in radioimmunotherapy.

  1. Isonitrile radionuclide complexes for labelling and imaging agents

    DOEpatents

    Jones, Alun G.; Davison, Alan; Abrams, Michael J.

    1984-06-04

    A coordination complex of an isonitrile ligand and radionuclide such as Tc, Ru, Co, Pt, Fe, Os, Ir, W, Re, Cr, Mo, Mn, Ni, Rh, Pd, Nb and Ta, is useful as a diagnostic agent for labelling liposomes or vesicles, and selected living cells containing lipid membranes, such as blood clots, myocardial tissue, gall bladder tissue, etc.

  2. New Catalytic DNA Biosensors for Radionuclides and Metal ion

    SciTech Connect

    Yi Lu

    2008-03-01

    We aim to develop new DNA biosensors for simultaneous detection and quantification of bioavailable radionuclides, such as uranium, technetium, and plutonium, and metal contaminants, such as lead, chromium, and mercury. The sensors will be highly sensitive and selective. They will be applied to on-site, real-time assessment of concentration, speciation, and stability of the individual contaminants before and during bioremediation, and for long-term monitoring of DOE contaminated sites. To achieve this goal, we have employed a combinatorial method called in vitro selection to search from a large DNA library (~ 1015 different molecules) for catalytic DNA molecules that are highly specific for radionuclides or other metal ions through intricate 3-dimensional interactions as in metalloproteins. Comprehensive biochemical and biophysical studies have been performed on the selected DNA molecules. The findings from these studies have helped to elucidate fundamental principles for designing effective sensors for radionuclides and metal ions. Based on the study, the DNA have been converted to fluorescent or colorimetric sensors by attaching to it fluorescent donor/acceptor pairs or gold nanoparticles, with 11 part-per-trillion detection limit (for uranium) and over million fold selectivity (over other radionuclides and metal ions tested). Practical application of the biosensors for samples from the Environmental Remediation Sciences Program (ERSP) Field Research Center (FRC) at Oak Ridge has also been demonstrated.

  3. Waste site reclamation with recovery of radionuclides and metals

    DOEpatents

    Francis, A.J.; Dodge, C.J.

    1994-03-08

    A method for decontaminating radionuclides and other toxic metal-contaminate The U.S. government has certain rights in this invention pursuant to Contract Number DE-AC02-76CH00016 between the U.S. Department of Energy and Associated Universities, Inc.

  4. Waste site reclamation with recovery of radionuclides and metals

    DOEpatents

    Francis, Arokiasamy J.; Dodge, Cleveland J.

    1994-01-01

    A method for decontaminating radionuclides and other toxic metal-contaminate The U.S. government has certain rights in this invention pursuant to Contract Number DE-AC02-76CH00016 between the U.S. Department of Energy and Associated Universities, Inc.

  5. Differences in the regulation of chemicals and radionuclides

    SciTech Connect

    Travis, C.C.

    1993-12-01

    Government regulations limiting public exposure to radionuclides and chemicals have historically been developed by regulatory agencies using different approaches with the result that levels of protection vary for the two classes of contaminants. These differences create difficulties in determining equitable regulatory measures when both radionuclides and chemical pollutants are involved. Generally, radiation exposure is not regulated as stringently as chemical exposure (Travis et al, 1989). The International commission on Radiological Protection (ICRP) recommends limiting excess environmental radiation exposure to the general public to 100 millirem per year (mrem/yr) (ICRP, 1991), a lifetime cancer risk of about 3.5E-3. An acceptable level of risk for chemical exposures is generally considered to be below 1E-6. Differences in regulatory approach for radionuclides and chemicals evoke debate over why they are different and which regulation strategy is better. Because these pollutants often coexist (mixed waste sites, contaminated metals and facilities, etc.), it is important to analyze inconsistencies in the regulation of chemicals and radionuclides and establish a more consistent approach to defining an acceptable level of exposure for these contaminants.

  6. SLUDGE BATCH 5 ACCEPTANCE EVALUATION RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB5 QUALIFICATION SAMPLE PREPARED AT SRNL

    SciTech Connect

    Bannochie, C; Ned Bibler, N; David Diprete, D

    2008-07-28

    Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Five (SB5) for processing in the Defense Waste Processing Facility (DWPF). Part of this SB5 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40 to complete the formation of SB5. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB4. The radionuclide concentrations were measured or estimated in the Tank 51 SB5 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter sample of Tank 51 sludge slurry taken on March 21, 2008. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. Under direction of the Liquid Waste Organization it was then modified by five washes, six decants, an addition of Pu/Be from Canyon Tank 16.4, and an addition of NaNO2. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Ta Determining the radionuclide concentrations in this Tank 51 SB5 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2008-0010. The work with this qualification sample is covered by a Task Technical and Quality Assurance Plan and an Analytical Study Plan. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task 2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task 5) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB5 will be taken and

  7. Final Report

    SciTech Connect

    Marchant, Gary E.

    2013-04-23

    This is the final report of a two year project entitled "Governing Nanotechnology Risks and Benefits in the Transition to Regulation: Innovative Public and Private Approaches." This project examined the role of new governance or "soft law" mechanisms such as codes of conduct, voluntary programs and partnership agreements to manage the risks of emerging technologies such as nanotechnology. A series of published or in publication papers and book chapters are attached.

  8. SOLIEX: A Novel Solid-Liquid Method of Radionuclides Extraction from Radioactive Waste Solutions - 13486

    SciTech Connect

    Shilova, E.; Viel, P.; Huc, V.

    2013-07-01

    This paper describes recent developments in new solid-liquid extraction method, called SOLIEX, to remove cesium from alkaline solutions. SOLIEX relies on the use of a reversible complexing system comprising a carbon felt bearing molecular traps (calixarenes). This complexing system exhibits a high selectivity for Cs, and is thus expected to be helpful for the treatment of highly diluted cesium wastes even with a high concentration of competing alkali metal cations. As additional advantage, this complexing system can be adapted by molecular engineering to capture other radionuclides, such as Sr, Eu, Am. Finally, this complexing system can be easily and efficiently regenerated by using a cost effective stripping procedure, which limits further generation of waste to meet 'zero liquid' discharge requirements for nuclear facilities. (authors)

  9. Radionuclide Transport in Fracture-Granite Interface Zones

    SciTech Connect

    Hu, Q; Mori, A

    2007-09-12

    In situ radionuclide migration experiments, followed by excavation and sample characterization, were conducted in a water-conducting shear zone at the Grimsel Test Site (GTS) in Switzerland to study diffusion paths of radionuclides in fractured granite. In this work, we employed a micro-scale mapping technique that interfaces laser ablation sampling with inductively coupled plasma-mass spectrometry (LA/ICP-MS) to measure the fine-scale (micron-range) distribution of actinides ({sup 234}U, {sup 235}U, and {sup 237}Np) in the fracture-granite interface zones. Long-lived {sup 234}U, {sup 235}U, and {sup 237}Np were detected in flow channels, as well as in the adjacent rock matrix, using the sensitive, feature-based mapping of the LA/ICP-MS technique. The injected sorbing actinides are mainly located within the advective flowing fractures and the immediately adjacent regions. The water-conducting fracture studied in this work is bounded on one side by mylonite and the other by granitic matrix regions. These actinides did not penetrate into the mylonite side as much as the relatively higher-porosity granite matrix, most likely due to the low porosity, hydraulic conductivity, and diffusivity of the fracture wall (a thickness of about 0.4 mm separates the mylonite region from the fracture) and the mylonite region itself. Overall, the maximum penetration depth detected with this technique for the more diffusive {sup 237}Np over the field experimental time scale of about 60 days was about 10 mm in the granitic matrix, illustrating the importance of matrix diffusion in retarding radionuclide transport from the advective fractures. Laboratory tests and numerical modeling of radionuclide diffusion into granitic matrix was conducted to complement and help interpret the field results. Measured apparent diffusivity of multiple tracers in granite provided consistent predictions for radionuclide transport in the fractured granitic rock.

  10. Environmental Assessment for Direct Final Rule, 10 CFR 434, Energy Standards for New Federal Commercial and High-Rise Multi-FamilyResidential BuildingsŽ and 10 CFR 435, Energy Efficiency Standards for New Federal Residential Low-Rise Residential Buildings"

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Proposed Rule, 10 CFR 433, "Sustainable Design and Energy Efficiency Standards for New Federal Commercial and High-Rise Multi-Family Residential Buildings" and 10 CFR 435, "Sustainable Design and Energy Efficiency Standards for New Federal Residential Low-Rise Residential Buildings" (DOE/EA-1463) 2 SUMMARY The U.S. Department of Energy (DOE) has prepared this Environmental Assessment (EA) for DOE's Proposed Rule, 10 CFR 433, "Sustainable Design and Energy Efficiency

  11. Final Report

    SciTech Connect

    R Paul Drake

    2004-01-12

    OAK-B135 This is the final report from the project Hydrodynamics by High-Energy-Density Plasma Flow and Hydrodynamics and Radiation Hydrodynamics with Astrophysical Applications. This project supported a group at the University of Michigan in the invention, design, performance, and analysis of experiments using high-energy-density research facilities. The experiments explored compressible nonlinear hydrodynamics, in particular at decelerating interfaces, and the radiation hydrodynamics of strong shock waves. It has application to supernovae, astrophysical jets, shock-cloud interactions, and radiative shock waves.

  12. Parallel machine architecture for production rule systems

    DOEpatents

    Allen, Jr., John D.; Butler, Philip L.

    1989-01-01

    A parallel processing system for production rule programs utilizes a host processor for storing production rule right hand sides (RHS) and a plurality of rule processors for storing left hand sides (LHS). The rule processors operate in parallel in the recognize phase of the system recognize -Act Cycle to match their respective LHS's against a stored list of working memory elements (WME) in order to find a self consistent set of WME's. The list of WME is dynamically varied during the Act phase of the system in which the host executes or fires rule RHS's for those rules for which a self-consistent set has been found by the rule processors. The host transmits instructions for creating or deleting working memory elements as dictated by the rule firings until the rule processors are unable to find any further self-consistent working memory element sets at which time the production rule system is halted.

  13. Users view gas ruling: problems now, gains later

    SciTech Connect

    Hume, M.

    1985-05-20

    Although recent court decisions about natural gas carriage and discount sales programs may cause problems for users in the short term, in the long run they could provide open access on non-discriminatory terms. The programs will continue current operation until July, and the final impact of the decisions will depend upon the response of the Federal Energy Regulatory Commission (FERC) to the court's nullification of its programs. A lapse before establishing new rules could be disruptive. Arguments that the programs boost pipeline profits and unfairly aid dual-fuel users led to the court decision. Refusal to transport gas could generate anti-trust suits against pipelines. FERC expects to issue final rules by the end of summer.

  14. Radionuclide mass balance for the TMI-2 accident: data-base system and preliminary mass balance. Volume 2

    SciTech Connect

    Goldman, M I; Davis, R J; Strahl, J F; Arcieri, W C; Tonkay, D W

    1983-04-01

    Tables are presented which represent the radionuclide levels following the Three Mile Island-2 reactor accident.

  15. Situ formation of apatite for sequestering radionuclides and heavy metals

    DOEpatents

    Moore, Robert C.

    2003-07-15

    Methods for in situ formation in soil of a permeable reactive barrier or zone comprising a phosphate precipitate, such as apatite or hydroxyapatite, which is capable of selectively trapping and removing radionuclides and heavy metal contaminants from the soil, while allowing water or other compounds to pass through. A preparation of a phosphate reagent and a chelated calcium reagent is mixed aboveground and injected into the soil. Subsequently, the chelated calcium reagent biodegrades and slowly releases free calcium. The free calcium reacts with the phosphate reagent to form a phosphate precipitate. Under the proper chemical conditions, apatite or hydroxyapatite can form. Radionuclide and heavy metal contaminants, including lead, strontium, lanthanides, and uranium are then selectively sequestered by sorbing them onto the phosphate precipitate. A reducing agent can be added for reduction and selective sequestration of technetium or selenium contaminants.

  16. Radio-nuclide mixture identification using medium energy resolution detectors

    SciTech Connect

    Nelson, Karl Einar

    2013-09-17

    According to one embodiment, a method for identifying radio-nuclides includes receiving spectral data, extracting a feature set from the spectral data comparable to a plurality of templates in a template library, and using a branch and bound method to determine a probable template match based on the feature set and templates in the template library. In another embodiment, a device for identifying unknown radio-nuclides includes a processor, a multi-channel analyzer, and a memory operatively coupled to the processor, the memory having computer readable code stored thereon. The computer readable code is configured, when executed by the processor, to receive spectral data, to extract a feature set from the spectral data comparable to a plurality of templates in a template library, and to use a branch and bound method to determine a probable template match based on the feature set and templates in the template library.

  17. LITERATURE REVIEW ON MAXIMUM LOADING OF RADIONUCLIDES ON CRYSTALLINE SILICOTITANATE

    SciTech Connect

    Adu-Wusu, K.; Pennebaker, F.

    2010-10-13

    Plans are underway to use small column ion exchange (SCIX) units installed in high-level waste tanks to remove Cs-137 from highly alkaline salt solutions at Savannah River Site. The ion exchange material slated for the SCIX project is engineered or granular crystalline silicotitanate (CST). Information on the maximum loading of radionuclides on CST is needed by Savannah River Remediation for safety evaluations. A literature review has been conducted that culminated in the estimation of the maximum loading of all but one of the radionuclides of interest (Cs-137, Sr-90, Ba-137m, Pu-238, Pu-239, Pu-240, Pu-241, Am-241, and Cm-244). No data was found for Cm-244.

  18. SLUDGE BATCH 6 ACCEPTANCE EVALUATION: RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB6 QUALIFICATION SAMPLE PREPARED AT SRNL

    SciTech Connect

    Bannochie, C.; Bibler, N.; Diprete, D.

    2010-05-21

    Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Six (SB6) for processing in the Defense Waste Processing Facility (DWPF). The SB6 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB5. The radionuclide concentrations were measured or estimated in the Tank 51 SB6 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter sample of Tank 51 sludge slurry (HTF-51-09-110) taken on October 8, 2009. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. Under the direction of the Liquid Waste Organization it was then modified by eight washes, nine decants, an addition of Pu from Canyon Tank 16.3, and an addition of NaNO{sub 2}. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Tank 40. Determining the radionuclide concentrations in this Tank 51 SB6 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2009-0014. The work with this qualification sample is covered by a Task Technical and Quality Assurance Plan and an Analytical Study Plan. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task I.2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task II.2.) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB6 will be taken and transferred

  19. Summary Report for the Development of Materials for Volatile Radionuclides

    SciTech Connect

    Strachan, Denis M.; Chun, Jaehun; Henager, Charles H.; Matyas, Josef; Riley, Brian J.; Ryan, Joseph V.; Thallapally, Praveen K.

    2010-11-22

    The materials development summarized here is in support of the Waste Forms campaign, Volatile Radionuclide task. Specifically, materials are being developed for the removal and immobilization of iodine and krypton, specifically 129I and 85Kr. During FY 2010, aerogel materials were investigated for removal and immobilization of 129I. Two aerogel formulations were investigated, one based on silica aerogels and the second on chalcogenides. For 85Kr, metal organic framework (MOF) structures were investigated.

  20. CRITICAL RADIONUCLIDE AND PATHWAY ANALYSIS FOR THE SAVANNAH RIVER SITE

    SciTech Connect

    Jannik, T.

    2011-08-30

    This report is an update to the analysis, Assessment of SRS Radiological Liquid and Airborne Contaminants and Pathways, that was performed in 1997. An electronic version of this large original report is included in the attached CD to this report. During the operational history (1954 to the present) of the Savannah River Site (SRS), many different radionuclides have been released to the environment from the various production facilities. However, as will be shown by this updated radiological critical contaminant/critical pathway analysis, only a small number of the released radionuclides have been significant contributors to potential doses and risks to offsite people. The analysis covers radiological releases to the atmosphere and to surface waters, the principal media that carry contaminants offsite. These releases potentially result in exposure to offsite people. The groundwater monitoring performed at the site shows that an estimated 5 to 10% of SRS has been contaminated by radionuclides, no evidence exists from the extensive monitoring performed that groundwater contaminated with these constituents has migrated off the site (SRS 2011). Therefore, with the notable exception of radiological source terms originating from shallow surface water migration into site streams, onsite groundwater was not considered as a potential exposure pathway to offsite people. In addition, in response to the Department of Energy's (DOE) Order 435.1, several Performance Assessments (WSRC 2008; LWO 2009; SRR 2010; SRR 2011) and a Comprehensive SRS Composite Analysis (SRNO 2010) have recently been completed at SRS. The critical radionuclides and pathways identified in these extensive reports are discussed and, where applicable, included in this analysis.

  1. Monitoring Trace Radionuclides by ICP Mass Spectrometry with Femtosecond

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Laser Ablation | The Ames Laboratory Monitoring Trace Radionuclides by ICP Mass Spectrometry with Femtosecond Laser Ablation FWP/Project Description: This project will develop analytical methodology for the use of femtosecond laser ablation sampling and analysis techniques for the rapid screening of samples derived from detection of clandestine nuclear operations, and nuclear non-proliferation and safeguards activities. A state-of-the-art femtosecond laser ablation system in conjunction with

  2. Single-photon ultrashort-lived radionuclides: symposium proceedings

    SciTech Connect

    Paras, P.; Thiessen, J.W. (eds.)

    1985-01-01

    The purpose was to define the current role and state-of-the-art regarding the development, clinical applications, and usefulness of generator-produced single-photon ultrashort-lived radionuclides (SPUSLR's) and to predict their future impact on medicine. Special emphasis was placed on the generator production of iridium-191, gold-195, and krypton-81. This report contains expanded summaries of the included papers. (ACR)

  3. Improving the Availability of the Therapeutic Radionuclide Astatine-211 |

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    U.S. DOE Office of Science (SC) Improving the Availability of the Therapeutic Radionuclide Astatine-211 Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Funding Opportunities Nuclear Science Advisory Committee (NSAC) Community Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-3613 F: (301) 903-3833 E: Email Us More Information » 11.01.14

  4. Yucca Mountain Project - Science & Technology Radionuclide Absorbers Development Program Overview

    SciTech Connect

    Hong-Nian Jow; R.C. Moore; K.B. Helean; S. Mattigod; M. Hochella; A.R. Felmy; J. Liu; K. Rosso; G. Fryxell; J. Krumhansl; Y. Wang

    2005-01-14

    The proposed Yucca Mountain repository is anticipated to be the first facility for long-term disposal of commercial spent nuclear fuel and high-level radioactive waste in the United States. The facility, located in the southern Nevada desert, is currently in the planning stages with initial exploratory excavations completed. It is an underground facility mined into the tuffaceous volcanic rocks that sit above the local water table. The focus of the work described in this paper is the development of radionuclide absorbers or ''getter'' materials for neptunium (Np), iodine (I), and technetium (Tc) for potential deployment in the repository. ''Getter'' materials retard the migration of radionuclides through sorption, reduction, or other chemical and physical processes, thereby slowing or preventing the release and transport of radionuclides. An overview of the objectives and approaches utilized in this work with respect to materials selection and modeling of ion ''getters'' is presented. The benefits of the ''getter'' development program to the United States Department of Energy (US DOE) are outlined.

  5. Application of Monte Carlo Methods in Molecular Targeted Radionuclide Therapy

    SciTech Connect

    Hartmann Siantar, C; Descalle, M-A; DeNardo, G L; Nigg, D W

    2002-02-19

    Targeted radionuclide therapy promises to expand the role of radiation beyond the treatment of localized tumors. This novel form of therapy targets metastatic cancers by combining radioactive isotopes with tumor-seeking molecules such as monoclonal antibodies and custom-designed synthetic agents. Ultimately, like conventional radiotherapy, the effectiveness of targeted radionuclide therapy is limited by the maximum dose that can be given to a critical, normal tissue, such as bone marrow, kidneys, and lungs. Because radionuclide therapy relies on biological delivery of radiation, its optimization and characterization are necessarily different than for conventional radiation therapy. We have initiated the development of a new, Monte Carlo transport-based treatment planning system for molecular targeted radiation therapy as part of the MINERVA treatment planning system. This system calculates patient-specific radiation dose estimates using a set of computed tomography scans to describe the 3D patient anatomy, combined with 2D (planar image) and 3D (SPECT, or single photon emission computed tomography) to describe the time-dependent radiation source. The accuracy of such a dose calculation is limited primarily by the accuracy of the initial radiation source distribution, overlaid on the patient's anatomy. This presentation provides an overview of MINERVA functionality for molecular targeted radiation therapy, and describes early validation and implementation results of Monte Carlo simulations.

  6. Environmental radionuclide distribution in Georgia after the Chernobyl accident

    SciTech Connect

    Mosulishvili, L.M.; Shoniya, N.I.; Katamadze, N.M.

    1994-01-01

    Atmospheric Chernobyl-released radioactivity, assessed at about 2 x 10{sup 18} Bq, caused global environmental contamination. Contaminated air masses appeared in the Transcaucasian region in early May, 1986. Rains that month promoted intense radionuclide deposition all over Georgia. The contamination level of western Georgia considerably exceeded the contamination level of eastern Georgia. The Black Sea coast of Georgia suffered from the Chernobyl accident as much as did strongly contaminated areas of the Ukraine and Belarus`. Unfortunately, governmental decrees on countermeasures against the consequences of the Chernobyl accident at that time did not even refer to the coast of Georgia. The authors observed the first increase in radioactivity background in rainfall samples collected on May 2, 1986, in Tbilisi. {gamma}-Spectrometric measurements of aerosol filters, vegetation, food stuffs, and other objects, in addition to rainfall, persistently confirmed the occurrence of short-lived radionuclides, including {sup 131}I. At first, this fact seemed unbelievable, because the Chernobyl accident had occurred only 4-5 days earlier and far from Georgia. However, these arguments proved to be faulty. Soon, environmental monitoring of radiation in Georgia became urgent. Environmental radionuclide distribution in Georgia shortly after the Chernobyl accident, as well as the methods of analysis, are reported in this paper.

  7. Radionuclide inventory for the Waste Isolation Pilot Plant

    SciTech Connect

    Not Available

    1991-12-31

    This report updates the information previously submitted in the draft report DOE/WIPP 88-005, Radionuclide Source Term for the WIPP, dated 1987 (reference 1). The information in this report provides the projected radionuclide inventory at the WIPP based on the projected waste receipts through the year 2013. The information is based on the 1991 TRU Program Data submittals for the Integrated Data Base (DOE/RW-0006, Rev. 7) from each of the DOE sites generating or storing TRU waste for shipment to the WIPP. The data is based on existing characterization data on the waste in interim storage, waste estimates based on projected programs during the 1991 through 2013 time period, projected treatment processes required to meet WIPP Waste Acceptance Criteria (WAC), and a projection of the waste that will be declared low level waste when it is assayed as part of the certification program for waste shipments to WIPP. This data will serve as a standard reference for WIPP programs requiring radionuclide data, including safety programs, performance assessment, and regulatory compliance. These projections will continue to be periodically updated as the waste data estimates are refined by the generator sites as they participate in the annual update of the Integrated Data Base (IDB).

  8. Surface charge accumulation of particles containing radionuclides in open air

    DOE PAGES [OSTI]

    Kim, Yong-ha; Yiacoumi, Sotira; Tsouris, Costas

    2015-05-01

    Radioactivity can induce charge accumulation on radioactive particles. But, electrostatic interactions caused by radioactivity are typically neglected in transport modeling of radioactive plumes because it is assumed that ionizing radiation leads to charge neutralization. The assumption that electrostatic interactions caused by radioactivity are negligible is evaluated here by examining charge accumulation and neutralization on particles containing radionuclides in open air. Moreover, a charge-balance model is employed to predict charge accumulation on radioactive particles. It is shown that particles containing short-lived radionuclides can be charged with multiple elementary charges through radioactive decay. The presence of radioactive particles can significantly modify themore » particle charge distribution in open air and yield an asymmetric bimodal charge distribution, suggesting that strong electrostatic particle interactions may occur during short- and long-range transport of radioactive particles. Possible effects of transported radioactive particles on electrical properties of the local atmosphere are reported. Our study offers insight into transport characteristics of airborne radionuclides. Results are useful in atmospheric transport modeling of radioactive plumes.« less

  9. Surface charge accumulation of particles containing radionuclides in open air

    SciTech Connect

    Kim, Yong-ha; Yiacoumi, Sotira; Tsouris, Costas

    2015-05-01

    Radioactivity can induce charge accumulation on radioactive particles. But, electrostatic interactions caused by radioactivity are typically neglected in transport modeling of radioactive plumes because it is assumed that ionizing radiation leads to charge neutralization. The assumption that electrostatic interactions caused by radioactivity are negligible is evaluated here by examining charge accumulation and neutralization on particles containing radionuclides in open air. Moreover, a charge-balance model is employed to predict charge accumulation on radioactive particles. It is shown that particles containing short-lived radionuclides can be charged with multiple elementary charges through radioactive decay. The presence of radioactive particles can significantly modify the particle charge distribution in open air and yield an asymmetric bimodal charge distribution, suggesting that strong electrostatic particle interactions may occur during short- and long-range transport of radioactive particles. Possible effects of transported radioactive particles on electrical properties of the local atmosphere are reported. Our study offers insight into transport characteristics of airborne radionuclides. Results are useful in atmospheric transport modeling of radioactive plumes.

  10. Phosphate-Mediated Remediation of Metals and Radionuclides

    DOE PAGES [OSTI]

    Martinez, Robert J.; Beazley, Melanie J.; Sobecky, Patricia A.

    2014-01-01

    Worldwide industrialization activities create vast amounts of organic and inorganic waste streams that frequently result in significant soil and groundwater contamination. Metals and radionuclides are of particular concern due to their mobility and long-term persistence in aquatic and terrestrial environments. As the global population increases, the demand for safe, contaminant-free soil and groundwater will increase as will the need for effective and inexpensive remediation strategies. Remediation strategies that include physical and chemical methods (i.e., abiotic) or biological activities have been shown to impede the migration of radionuclide and metal contaminants within soil and groundwater. However, abiotic remediation methods aremore » often too costly owing to the quantities and volumes of soils and/or groundwater requiring treatment. The in situ sequestration of metals and radionuclides mediated by biological activities associated with microbial phosphorus metabolism is a promising and less costly addition to our existing remediation methods. This review highlights the current strategies for abiotic and microbial phosphate-mediated techniques for uranium and metal remediation.« less

  11. Effect of Concrete Waste Form Properties on Radionuclide Migration

    SciTech Connect

    Mattigod, Shas V.; Bovaird, Chase C.; Wellman, Dawn M.; Skinner, De'Chauna J.; Cordova, Elsa A.; Wood, Marcus I.

    2009-09-30

    Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation) the mechanism of contaminant release, the significance of contaminant release pathways, how waste form performance is affected by the full range of environmental conditions within the disposal facility, the process of waste form aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility, the effect of waste form aging on chemical, physical, and radiological properties and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the waste forms come in contact with groundwater. Numerous sets of tests were initiated in fiscal years (FY) 2006-2009 to evaluate (1) diffusion of iodine (I) and technetium (Tc) from concrete into uncontaminated soil after 1 and 2 years, (2) I and rhenium (Re) diffusion from contaminated soil into fractured concrete, (3) I and Re (set 1) and Tc (set 2) diffusion from fractured concrete into uncontaminated soil, (4) evaluate the moisture distribution profile within the sediment half-cell, (5) the reactivity and speciation of uranium (VI) (U(VI)) compounds in concrete porewaters, (6) the rate of dissolution of concrete monoliths, and (7) the diffusion of simulated tank waste into concrete.

  12. Final Report

    SciTech Connect

    Webb, Robert C.; Kamon, Teruki; Toback, David; Safonov, Alexei; Dutta, Bhaskar; Dimitri, Nanopoulos; Pope, Christopher; White, James

    2013-11-18

    Overview The High Energy Physics Group at Texas A&M University is submitting this final report for our grant number DE-FG02-95ER40917. This grant has supported our wide range of research activities for over a decade. The reports contained here summarize the latest work done by our research team. Task A (Collider Physics Program): CMS & CDF Profs. T. Kamon, A. Safonov, and D. Toback co-lead the Texas A&M (TAMU) collider program focusing on CDF and CMS experiments. Task D: Particle Physics Theory Our particle physics theory task is the combined effort of Profs. B. Dutta, D. Nanopoulos, and C. Pope. Task E (Underground Physics): LUX & NEXT Profs. R. Webb and J. White(deceased) lead the Xenon-based underground research program consisting of two main thrusts: the first, participation in the LUX two-phase xenon dark matter search experiment and the second, detector R&D primarily aimed at developing future detectors for underground physics (e.g. NEXT and LZ).

  13. RADIONUCLIDE AIR EMISSIONS REPORT FOR THE HANFORD SITE CY2003

    SciTech Connect

    ROKKAN, D.J.

    2004-06-11

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

  14. Montana Rule 36.2.10 General State Land Rules | Open Energy Informatio...

    OpenEI (Open Energy Information) [EERE & EIA]

    State Land RulesLegal Abstract Montana regulation governing general rules for the administration of state lands. Published NA Year Signed or Took Effect 2014 Legal Citation...

  15. SOLID PHASE MICROEXTRACTION SAMPLING OF HIGH EXPLOSIVE RESIDUES IN THE PRESENCE OF RADIONUCLIDES AND RADIONUCLIDE SURROGATE METALS

    SciTech Connect

    Duff, M; S Crump, S; Robert02 Ray, R; Donna Beals, D

    2007-04-13

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

  16. Autonomous Rule Creation for Intrusion Detection

    SciTech Connect

    Todd Vollmer; Jim Alves-Foss; Milos Manic

    2011-04-01

    Many computational intelligence techniques for anomaly based network intrusion detection can be found in literature. Translating a newly discovered intrusion recognition criteria into a distributable rule can be a human intensive effort. This paper explores a multi-modal genetic algorithm solution for autonomous rule creation. This algorithm focuses on the process of creating rules once an intrusion has been identified, rather than the evolution of rules to provide a solution for intrusion detection. The algorithm was demonstrated on anomalous ICMP network packets (input) and Snort rules (output of the algorithm). Output rules were sorted according to a fitness value and any duplicates were removed. The experimental results on ten test cases demonstrated a 100 percent rule alert rate. Out of 33,804 test packets 3 produced false positives. Each test case produced a minimum of three rule variations that could be used as candidates for a production system.

  17. Business rule enforcement via natural language modeling

    SciTech Connect

    Sharp, J.

    1997-11-01

    This report contains viewgraphs on business rule enforcement by natural language modeling procedures. A number of examples are given.

  18. Binary translation using peephole translation rules

    DOEpatents

    Bansal, Sorav; Aiken, Alex

    2010-05-04

    An efficient binary translator uses peephole translation rules to directly translate executable code from one instruction set to another. In a preferred embodiment, the translation rules are generated using superoptimization techniques that enable the translator to automatically learn translation rules for translating code from the source to target instruction set architecture.

  19. Method for immobilizing mixed waste chloride salts containing radionuclides and other hazardous wastes

    DOEpatents

    Lewis, Michele A.; Johnson, Terry R.

    1993-01-01

    The invention is a method for the encapsulation of soluble radioactive waste chloride salts containing radionuclides such as strontium, cesium and hazardous wastes such as barium so that they may be permanently stored without future threat to the environment. The process consists of contacting the salts containing the radionuclides and hazardous wastes with certain zeolites which have been found to ion exchange with the radionuclides and to occlude the chloride salts so that the resulting product is leach resistant.

  20. Microbial stabilization and mass reduction of wastes containing radionuclides and toxic metals

    DOEpatents

    Francis, A.J.; Dodge, C.J.; Gillow, J.B.

    1991-09-10

    A process is provided to treat wastes containing radionuclides and toxic metals with Clostridium sp. BFGl to release a large fraction of the waste solids into solution and convert the radionuclides and toxic metals to a more concentrated and stable form with concurrent volume and mass reduction. The radionuclides and toxic metals being in a more stable form are available for recovery, recycling and disposal. 18 figures.

  1. Microbial stabilization and mass reduction of wastes containing radionuclides and toxic metals

    DOEpatents

    Francis, Arokiasamy J.; Dodge, Cleveland J.; Gillow, Jeffrey B.

    1991-01-01

    A process is provided to treat wastes containing radionuclides and toxic metals with Clostridium sp. BFGl to release a large fraction of the waste solids into solutin and convert the radionuclides and toxic metals to a more concentrated and stable form with concurrent volume and mass reduction. The radionuclides and toxic metals being in a more stable form are available for recovery, recycling and disposal.

  2. Method for immobilizing mixed waste chloride salts containing radionuclides and other hazardous wastes

    DOEpatents

    Lewis, Michele A.; Johnson, Terry R.

    1993-09-07

    The invention is a method for the encapsulation of soluble radioactive waste chloride salts containing radionuclides such as strontium, cesium and hazardous wastes such as barium so that they may be permanently stored without future threat to the environment. The process consists of contacting the salts containing the radionuclides and hazardous wastes with certain zeolites which have been found to ion exchange with the radionuclides and to occlude the chloride salts so that the resulting product is leach resistant.

  3. Method for preparing radionuclide-labeled chelating agent-ligand complexes

    DOEpatents

    Meares, Claude F.; Li, Min; DeNardo, Sally J.

    1999-01-01

    Radionuclide-labeled chelating agent-ligand complexes that are useful in medical diagnosis or therapy are prepared by reacting a radionuclide, such as .sup.90 Y or .sup.111 In, with a polyfunctional chelating agent to form a radionuclide chelate that is electrically neutral; purifying the chelate by anion exchange chromatography; and reacting the purified chelate with a targeting molecule, such as a monoclonal antibody, to form the complex.

  4. Chair, CTBT working group B Radionuclide Expert Group and the U.S.

    National Nuclear Security Administration (NNSA)

    Radionuclide Subgroup of the Verification Monitoring Task Force, Pacific Northwest National Laboratory | National Nuclear Security Administration | (NNSA) Chair, CTBT working group B Radionuclide Expert Group and the U.S. Radionuclide Subgroup of the Verification Monitoring Task Force, Pacific Northwest National Laboratory Ted Bowyer Ted Bowyer Ted Bowyer has been appointed a member of the National Academy of Sciences Comprehensive Nuclear Test-Ban Treaty panel. With the Obama Administration

  5. Apparatus for the measurement of radionuclide transport rates in rock cores

    SciTech Connect

    Weed, H.C.; Koszykowski, R.F.; Dibley, L.L.; Murray, I.

    1981-09-01

    An apparatus and procedure for the study of radionuclide transport in intact rock cores are presented in this report. This equipment more closely simulates natural conditions of radionuclide transport than do crushed rock columns. The apparatus and the procedure from rock core preparation through data analysis are described. The retardation factors measured are the ratio of the transport rate of a non-retarded radionuclide, such as /sup 3/H, to the transport rate of a retarded radionuclide. Sample results from a study of the transport of /sup 95m/Tc and /sup 85/Sr in brine through a sandstone core are included.

  6. 300 AREA PACIFIC NORTHWEST NATIONAL LABORATORY FACILITY RADIONUCLIDE EMISSION POINTS AND SAMPLING SYSTEMS

    SciTech Connect

    Barfuss, Brad C.; Barnett, J. M.; Harbinson, L Jill

    2006-08-28

    Radionuclide emission points for 300 Area and Battelle Private facilities are presented herein. The sampling systems and associated emission specifics are detailed.

  7. The use of Eupatorium Odoratum as bio-monitor for radionuclides...

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Search Results Journal Article: The use of ... radionuclides from soil, commonly as soil-to-plant ... Ahmad 1 ; Institute of Science, Universiti Teknologi ...

  8. Radionuclide-binding compound, a radionuclide delivery system, a method of making a radium complexing compound, a method of extracting a radionuclide, and a method of delivering a radionuclide

    DOEpatents

    Fisher, Darrell R.; Wai, Chien M.; Chen, Xiaoyuan

    2000-01-01

    The invention pertains to compounds which specifically bind radionuclides, and to methods of making radionuclide complexing compounds. In one aspect, the invention includes a radionuclide delivery system comprising: a) a calix[n]arene-crown-[m]-ether compound, wherein n is an integer greater than 3, and wherein m is an integer greater than 3, the calix[n]arene-crown-[m]-ether compound comprising at least two ionizable groups; and b) an antibody attached to the calix[n]arene-crown-[m]-ether compound. In another aspect, the invention includes a method of making a radium complexing compound, comprising: a) providing a calix[n]arene compound, wherein n is an integer greater than 3, the calix[n]arene compound comprising n phenolic hydroxyl groups; b) providing a crown ether precursor, the crown ether precursor comprising a pair of tosylated ends; c) reacting the pair of tosylated ends with a pair of the phenolic hydroxyl groups to convert said pair of phenolic hydroxyl groups to ether linkages, the ether linkages connecting the crown ether precursor to the calix[n]arene to form a calix[n]arene-crown-[m]-ether compound, wherein m is an integer greater than 3; d) converting remaining phenolic hydroxyl groups to esters; e) converting the esters to acids, the acids being proximate a crown-[m]-ether portion of the calix[n]arene-crown-[m]-ether compound; and f) providing a Ra.sup.2+ ion within the crown-[m]-ether portion of the calix[n]arene-crown-[m]-ether compound.

  9. Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure: Appendices, draft report for comment. Volume 2

    SciTech Connect

    Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.

    1994-09-01

    On June 27, 1988, the U.S. Nuclear Regulatory Commission (NRC) published in the Federal Register (53 FR 24018) the final rule for the General Requirements for Decommissioning Nuclear Facilities. With the issuance of the final rule, owners and operators of licensed nuclear power plants are required to prepare, and submit to the NRC for review, decommissioning plans and cost estimates. The NRC staff is in need of updated bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s WNP-2, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives, which now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste. Costs for labor, materials, transport, and disposal activities are given in 1993 dollars. Sensitivities of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances are also examined.

  10. Radionuclide Migration through Sediment and Concrete: 16 Years of Investigations

    SciTech Connect

    Golovich, Elizabeth C.; Mattigod, Shas V.; Snyder, Michelle MV; Powers, Laura; Whyatt, Greg A.; Wellman, Dawn M.

    2014-11-01

    The Waste Management Project provides safe, compliant, and cost-effective waste management services for the Hanford Site and the U.S. Department of Energy (DOE) complex. Part of these services includes safe disposal of low-level waste and mixed low-level waste at the Hanford Low-Level Waste Burial Grounds in accordance with the requirements of DOE Order 435.1, Radioactive Waste Management. To partially satisfy these requirements, performance assessment analyses were completed and approved. DOE Order 435.1 also requires continuing data collection to increase confidence in the critical assumptions used in these analyses to characterize the operational features of the disposal facility that are relied on to satisfy the performance objectives identified in the order. Cement-based solidification and stabilization is considered for hazardous waste disposal because it is easily done and cost-efficient. One critical assumption is that concrete will be used as a waste form or container material at the Hanford Site to control and minimize the release of radionuclide constituents in waste into the surrounding environment. Concrete encasement would contain and isolate the waste packages from the hydrologic environment and act as an intrusion barrier. Any failure of concrete encasement may result in water intrusion and consequent mobilization of radionuclides from the waste packages. The radionuclides iodine-129, selenium-75, technetium-99, and uranium-238 have been identified as long-term dose contributors (Mann et al. 2001; Wood et al. 1995). Because of their anionic nature in aqueous solutions, these constituents of potential concern may be released from the encased concrete by mass flow and/or diffusion and migrate into the surrounding subsurface environment (Serne et al. 1989; 1992; 1993a, b; 1995). Therefore, it is necessary to assess the performance of the concrete encasement structure and the ability of the surrounding soil to retard radionuclide migration. Each of the

  11. U.S. Department of Energy Issues Rules for Auto Loan Program | Department

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    of Energy Issues Rules for Auto Loan Program U.S. Department of Energy Issues Rules for Auto Loan Program November 5, 2008 - 4:47pm Addthis WASHINGTON, DC - Today the U.S. Department of Energy issued an Interim Final Rule that implements the Advanced Technology Vehicles Manufacturing Incentive Program authorized by section 136 of the Energy Independence and Security Act of 2007 (EISA). The FY09 Continuing Resolution provided DOE with funding to make up to $25 billion in direct loans to

  12. Corporate planning for compliance with EPA`s proposed risk management program rule

    SciTech Connect

    Mannan, M.; Keeney, R.C.

    1995-12-31

    On October 20, 1993, the US Environmental Protection Agency (EPA) published in the Federal Register the proposed rule entitled Risk Management Programs for Chemical Accidental Release Prevention (40 CFR 68). Subsequently, on January 31, 1994, EPA published in the Federal Register the finalized list of 77 regulated toxic substances and 63 regulated flammable substances that are to be covered under the rule along with the associated threshold quantities for each substance. This list of substances will dictate which stationary sources will have to comply with the requirements of the proposed risk management program rule. The risk management program rule will most likely be finalized sometime after mid-1995. Covered facilities will then have a total of three years to achieve complete compliance with the requirements of the rule. This paper presents an approach for corporations with multiple sites to develop action plans for implementation of the risk management program rule. The process starts with a determination of which facilities are potentially covered, development of a matrix of requirements that each facility must comply with, and finally, common strategies that may be used in achieving compliance. Thus, a multi-facility corporation can develop a baseline compliance guideline document that individual plants can use in developing and implementing their risk management programs.

  13. Reliability of Current Biokinetic and Dosimetric Models for Radionuclides: A Pilot Study

    SciTech Connect

    Leggett, Richard Wayne; Eckerman, Keith F; Meck, Robert A.

    2008-10-01

    This report describes the results of a pilot study of the reliability of the biokinetic and dosimetric models currently used by the U.S. Nuclear Regulatory Commission (NRC) as predictors of dose per unit internal or external exposure to radionuclides. The study examines the feasibility of critically evaluating the accuracy of these models for a comprehensive set of radionuclides of concern to the NRC. Each critical evaluation would include: identification of discrepancies between the models and current databases; characterization of uncertainties in model predictions of dose per unit intake or unit external exposure; characterization of variability in dose per unit intake or unit external exposure; and evaluation of prospects for development of more accurate models. Uncertainty refers here to the level of knowledge of a central value for a population, and variability refers to quantitative differences between different members of a population. This pilot study provides a critical assessment of models for selected radionuclides representing different levels of knowledge of dose per unit exposure. The main conclusions of this study are as follows: (1) To optimize the use of available NRC resources, the full study should focus on radionuclides most frequently encountered in the workplace or environment. A list of 50 radionuclides is proposed. (2) The reliability of a dose coefficient for inhalation or ingestion of a radionuclide (i.e., an estimate of dose per unit intake) may depend strongly on the specific application. Multiple characterizations of the uncertainty in a dose coefficient for inhalation or ingestion of a radionuclide may be needed for different forms of the radionuclide and different levels of information of that form available to the dose analyst. (3) A meaningful characterization of variability in dose per unit intake of a radionuclide requires detailed information on the biokinetics of the radionuclide and hence is not feasible for many infrequently

  14. Risk Due to Radiological Terror Attacks With Natural Radionuclides

    SciTech Connect

    Friedrich, Steinhaeusler; Lyudmila, Zaitseva; Stan, Rydell

    2008-08-07

    The naturally occurring radionuclides radium (Ra-226) and polonium (Po-210) have the potential to be used for criminal acts. Analysis of international incident data contained in the Database on Nuclear Smuggling, Theft and Orphan Radiation Sources (CSTO), operated at the University of Salzburg, shows that several acts of murder and terrorism with natural radionuclides have already been carried out in Europe and Russia. Five different modes of attack (T) are possible: (1) Covert irradiation of an individual in order to deliver a high individual dose; (2) Covert irradiation of a group of persons delivering a large collective dose; (3) Contamination of food or drink; (4) Generation of radioactive aerosols or solutions; (5) Combination of Ra-226 with conventional explosives (Dirty Bomb).This paper assesses the risk (R) of such criminal acts in terms of: (a) Probability of terrorist motivation deploying a certain attack mode T; (b) Probability of success by the terrorists for the selected attack mode T; (c) Primary damage consequence (C) to the attacked target (activity, dose); (d) Secondary damage consequence (C') to the attacked target (psychological and socio-economic effects); (e) Probability that the consequences (C, C') cannot be brought under control, resulting in a failure to manage successfully the emergency situation due to logistical and/or technical deficits in implementing adequate countermeasures. Extensive computer modelling is used to determine the potential impact of such a criminal attack on directly affected victims and on the environment.

  15. Laboratory studies of radionuclide transport in fractured Climax granite

    SciTech Connect

    Failor, R.; Isherwood, D.; Raber, E.; Vandergraaf, T.

    1982-06-01

    This report documents our laboratory studies of radionuclide transport in fractured granite cores. To simulate natural conditions, our laboratory studies used naturally fractured cores and natural ground water from the Climax Granite Stock at the Nevada Test Site. For comparison, additional tests used artificially fractured granite cores or distilled water. Relative to the flow of tritiated water, {sup 85}Sr and /sup 95m/Tc showed little or no retardation, whereas {sup 137}Cs was retarded. After the transport runs the cores retained varying amounts of the injected radionuclides along the fracture. Autoradiography revealed some correlation between sorption and the fracture fill material. Strontium and cesium retention increased when the change was made from natural ground water to distilled water. Artificial fractures retained less {sup 137}Cs than most natural fractures. Estimated fracture apertures from 18 to 60 {mu}m and hydraulic conductivities from 1.7 to 26 x 10{sup -3} m/s were calculated from the core measurements.

  16. Radionuclide release from low-level waste in field lysimeters

    SciTech Connect

    Oblath, S B

    1986-01-01

    A field program has been in operation for 8 years at the Savannah River Plant (SRP) to determine the leaching/migration behavior of low-level radioactive waste using lysimeters. The lysimeters are soil-filled caissons containing well characterized wastes, with each lysimeter serving as a model of a shallow land burial trench. Sampling and analysis of percolate water and vegetation from the lysimeters provide a determination of the release rates of the radionuclides from the waste/soil system. Vegetative uptake appears to be a major pathway for migration. Fractional release rates from the waste/soil system are less than 0.01% per year. Waste-to-soil leach rates up to 10% per year have been determined by coring several of the lysimeters. The leaching of solidified wasteforms under unsaturated field conditions has agreed well with static, immersion leaching of the same type waste in the laboratory. However, releases from the waste/soil system in the lysimeter may be greater than predicted based on leaching alone, due to complexation of the radionuclides by other components leached from the wastes to form mobile, anionic species.

  17. Chalcogen-Based Aerogels as Sorbents for Radionuclide Remediation

    SciTech Connect

    Riley, Brian J.; Chun, Jaehun; Um, Wooyong; Lepry, William C.; Matyas, Josef; Olszta, Matthew J.; Li, Xiaohong; Polychronopoulou, Kyriaki; Kanatzidis, Mercouri G.

    2013-06-13

    The efficient capture of radionuclides having long half-lives such as technetium-99 (99Tc), uranium-238 (238U), and iodine-129 (129I) is pivotal to prevent their transport into groundwater and/or release into the atmosphere. While different sorbents have been considered for capturing each of them, in the current work, a new nanostructured chalcogen-based aerogel, called a chalcogel, is shown to be very effective to capture ionic forms of 99Tc and 238U, as well as nonradioactive gaseous iodine (i.e., a surrogate for 129I), irrespective of the sorbent polarity. Some of the chalcogels performed better than others but the PtGeS sorbent performed the best with capture efficiencies of 98% and 99.4% for 99Tc and 238U, respectively. All sorbents showed >99% capture efficiency for iodine over the test duration. This unified sorbent would be an attractive option in environmental remediation for various radionuclides associated with legacy wastes from nuclear weapons production, wastes from nuclear power production, or potential future nuclear fuel reprocessing.

  18. 1998 INEEL National Emission Standard for Hazardous Air Pollutants - Radionuclides

    SciTech Connect

    J. W. Tkachyk

    1999-06-01

    Under Section 61.94 of Title 40, Code of Federal Regulations (CFR), Part 61, Subpart H, ''National Emission Standards for Emission of Radionuclides Other Than Radon From Department of Energy Facilities,'' each Department of Energy (DOE) facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at the Idaho National Engineering and Environmental Laboratory (INEEL) for calendar year (CY) 1998. The Idaho Operations Office of the DOE is the primary contract concerning compliance with the National Emission Standards for Hazardous Air Pollutants (NESHAPs) at the INEEL. For CY 1998, airborne radionuclide emissions from the INEEL operations were calculated to result in a maximum individual dose to a member of the public of 7.92E-03 mrem (7.92E-08 Sievert). This effective dose equivalent (EDE) is well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year).

  19. Proceedings of the Radionuclide Contamination in Water Resources Workshop

    SciTech Connect

    Richardson, J H; Duisebayev, B; Janecky, D R; Knapp, R; Rosenburg, N D; Smith, D K; Tompson, A F B; Tyupkina, O; Veselov, V V

    2001-07-26

    A workshop entitled ''Radionuclide Contamination in Water Resources'' was held in Almaty, Kazakhstan from Tuesday 29 May through Friday 1 June. This workshop was co-sponsored by the U.S. Department of Energy, Lawrence Livermore National Laboratory, and three organizations from the Republic of Kazakhstan: the Institute of Nonproliferation, the Institute of Hydrogeology and Hydrophysics, and KazAtomProm. Representatives from the U.S. Department of Energy, three national laboratories, and 13 different organizations from the Republic of Kazakhstan attended the workshop. A complete list of attendees, the workshop program, and information on the background and motivation for this workshop are provided in this report. The objective of the workshop was to identify critical problems, discover what is known about the problems related to radionuclide contamination of groundwater resources, form collaborative teams, and produce a small number proposals that both address further characterization and assess risk via contaminant fate and transport modeling. We plan to present these proposals to U.S. government agencies and international sponsors for funding.

  20. 1999 INEEL National Emission Standards for Hazardous Air Pollutants - Radionuclides

    SciTech Connect

    J. W. Tkachyk

    2000-06-01

    Under Section 61.94 of Title 40, Code of Federal Regulations (CFR), Part 61, Subpart H, ''National Emission Standards for Emission of Radionuclides Other Than Radon From Department of Energy Facilities,'' each Department of Energy (DOE) facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at the Idaho National Engineering and Environmental Laboratory (INEEL) for calendar year (CY) 1999. The Idaho Operations Office of the DOE is the primary contract concerning compliance with the National Emission Standards for Hazardous Air Pollutants (NESHAPs) at the INEEL. For CY 1999, airborne radionuclide emissions from the INEEL operations were calculated to result in a maximum individual dose to a member of the public of 7.92E-03 mrem (7.92E-08 Sievert). This effective dose equivalent (EDE) is well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year).

  1. EA-1871: Final Environmental Assessment | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Final Environmental Assessment EA-1871: Final Environmental Assessment Energy Efficiency Design Standards for New Federal Commercial and Multi-Family High-Rise Residential Buildings and New Federal Low-Rise Residential Buildings This EA evaluates the potential environmental impacts of revising the Federal building energy efficiency standars to ASHRAE 90.1-2007 and IECC 2009. EA-1871-FEA-2011.pdf (295.14 KB) More Documents & Publications Environmental Assessment for Final Rule 10 CFR Parts

  2. Use of depleted uranium silicate glass to minimize release of radionuclides from spent nuclear fuel waste packages

    SciTech Connect

    Forsberg, C.W.

    1996-01-20

    A Depleted Uranium Silicate Container Backfill System (DUSCOBS) is proposed that would use small, isotopically-depleted uranium silicate glass beads as a backfill material inside repository waste packages containing spent nuclear fuel (SNF). The uranium silicate glass beads would fill the void space inside the package including the coolant channels inside SNF assemblies. Based on preliminary analysis, the following benefits have been identified. DUSCOBS improves repository waste package performance by three mechanisms. First, it reduces the radionuclide releases from SNF when water enters the waste package by creating a local uranium silicate saturated groundwater environment that suppresses (a) the dissolution and/or transformation of uranium dioxide fuel pellets and, hence, (b) the release of radionuclides incorporated into the SNF pellets. Second, the potential for long-term nuclear criticality is reduced by isotopic exchange of enriched uranium in SNF with the depleted uranium (DU) in the glass. Third, the backfill reduces radiation interactions between SNF and the local environment (package and local geology) and thus reduces generation of hydrogen, acids, and other chemicals that degrade the waste package system. Finally, DUSCOBS provides a potential method to dispose of significant quantities of excess DU from uranium enrichment plants at potential economic savings. DUSCOBS is a new concept. Consequently, the concept has not been optimized or demonstrated in laboratory experiments.

  3. An Innovative Approach for the Calculation of Exposure Point Concentrations for Large Areas of Surface Radionuclide Contamination

    SciTech Connect

    Winchester Chromec, F.; Myers, Jeffrey C.

    2008-01-15

    The Department of Energy Rocky Flats site was designated as a wildlife refuge by the Rocky Flats National Wildlife Refuge Act of 2001. Rocky Flats was considered to be one of the most highly contaminated radiological sites in the country. Some portions of the site have low-level radionuclide contamination in surface soils. A site-wide risk and dose assessment to evaluate threats to human health and the environment were performed, so that the site could be released for this land use. The aggressive accelerated action program combined with defensible and innovative risk assessment methods resulted in there being no radionuclides of concern in the final comprehensive risk assessment (DOE 2006). An innovative approach for delineating functional exposure areas and area-weighted exposure point concentration-activities (EPCs) was negotiated with the regulatory agencies in Colorado. This procedure leads to realistic estimates of risk and dose to workers and visitors. This innovative approach to the calculation of EPCs was negotiated with both State and Federal regulators. The value of developing and maintaining good working relationships with regulators responsible for a site can not be overestimated. The building of trust and confidence among responsible parties and regulators is essential for the development and implementation of innovative methods and technologies.

  4. Radionuclide release from PWR spent fuel specimens with induced cladding defects

    SciTech Connect

    Wilson, C.N.; Oversby, V.M.

    1984-03-01

    Radionuclide releases from pressurized water reactor (PWR) spent fuel rod specimens containing various artificially induced cladding defects were compared by leach testing. The study was conducted in support of the Nevada Nuclear Waste Storage Investigations (NNWSI) Waste Package Task to evaluate the effectiveness of failed cladding as a barrier to radionuclide release. Test description and results are presented. 6 references, 4 figures.

  5. Radionuclide release from PWR spent fuel specimens with induced cladding defects

    SciTech Connect

    Wilson, C.N.; Oversby, V.M.

    1984-03-01

    Radionuclide releases from pressurized water reactor (PWR) spent fuel rod specimens containing various artificially induced cladding defects were compared by leach testing. The study was conducted in support of the Nevada Nuclear Waste Storage Investigations (NNWSI) Waste Package Task to evaluate the effectiveness of failed cladding as a barrier to radionuclide release. Test description and results are presented.

  6. Computerized Radiological Risk Investigation System for Assessing Doses and Health Risks from Atmospheric Releases of Radionuclides.

    Energy Science and Technology Software Center

    1998-11-10

    Version: 00 CRRIS consists of eight fully integrated computer codes which calculate environmental transport of atmospheric releases of radionuclides and resulting doses and health risks to individuals or populations. Each code may be used alone for various assessment applications. Because of its modular structure, CRRIS allows assessments to be tailored to the user's needs. Radionuclides are handled by CRRIS either in terms of the released radionuclides or the exposure radionuclides which consist of both themore » released nuclides and decay products that build up during environmental transport. Atmospheric dispersion calculations are performed by the ANEMOS computer code for distances less than 100 km and by the RETADD-II computer code for regional-scale distances. Both codes estimate annual-average air concentrations and ground deposition rates by location. SUMIT will translate and scale multiple ANEMOS runs onto a master grid. TERRA reads radionuclide air concentrations and deposition rates to estimate concentrations of radionuclides in food and surface soil. Radiologic decay and ingrowth, soil leaching, and transport through the food chain are included in the calculations. MLSOIL computes an effective radionuclide ground-surface concentration to be used in computing external health effects. The five-layer model of radionuclide transport through soil in MLSOIL provides an alternative to the single-layer model used in TERRA. DFSOIL computes dose factors used in MLSOIL to compute doses from the five soil layers and from the ground surface. ANDROS reads environmental concentrations of radionuclides computed by the other CRRIS codes and produces tables of doses and risks to individuals or populations from atmospheric releases of radionuclides.« less

  7. Potential Application Of Radionuclide Scaling Factors To High Level Waste Characterization

    SciTech Connect

    Reboul, S. H.

    2013-09-30

    Production sources, radiological properties, relative solubilities in waste, and laboratory analysis techniques for the forty-five radionuclides identified in Hanford�s Waste Treatment and Immobilization Plant (WTP) Feed Acceptance Data Quality Objectives (DQO) document are addressed in this report. Based on Savannah River Site (SRS) experience and waste characteristics, thirteen of the radionuclides are judged to be candidates for potential scaling in High Level Waste (HLW) based on the concentrations of other radionuclides as determined through laboratory measurements. The thirteen radionuclides conducive to potential scaling are: Ni-59, Zr-93, Nb-93m, Cd-113m, Sn-121m, Sn-126, Cs-135, Sm-151, Ra-226, Ra-228, Ac-227, Pa-231, and Th-229. The ability to scale radionuclides is useful from two primary perspectives: 1) it provides a means of checking the radionuclide concentrations that have been determined by laboratory analysis; and 2) it provides a means of estimating radionuclide concentrations in the absence of a laboratory analysis technique or when a complex laboratory analysis technique fails. Along with the rationale for identifying and applying the potential scaling factors, this report also provides examples of using the scaling factors to estimate concentrations of radionuclides in current SRS waste and into the future. Also included in the report are examples of independent laboratory analysis techniques that can be used to check results of key radionuclide analyses. Effective utilization of radionuclide scaling factors requires understanding of the applicable production sources and the chemistry of the waste. As such, the potential scaling approaches identified in this report should be assessed from the perspective of the Hanford waste before reaching a decision regarding WTP applicability.

  8. Rules of thumb for passive solar heating

    SciTech Connect

    Balcomb, J.D.

    1980-01-01

    Rules of thumb are given for passive solar systems for: (1) sizing solar glazing for 219 cities, (2) sizing thermal storage mass, and (3) building orientation.

  9. Hawaii Administrative Rules Pertaining to Historic Preservation...

    OpenEI (Open Energy Information) [EERE & EIA]

    Not Provided DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for Hawaii Administrative Rules Pertaining to Historic Preservation Citation...

  10. A Computer Program To Calculate The Leaching of Radionuclides and the Corrosion of Cemented Waste Forms in Water or Brine

    Energy Science and Technology Software Center

    1990-12-01

    DIFMOD calculates the leaching of radionuclides and the corrosion of cemented waste forms in contact with water or brine.

  11. Technical and Policy Challenges in Deep Vadose Zone Remediation of Metals and Radionuclides - 12025

    SciTech Connect

    Wellman, Dawn M.; Truex, Michael J.; Freshley, Mark; Cantrell, Kirk J.; Dresel, P. Evan

    2012-07-01

    Deep vadose zone contamination is a significant issue facing the U.S. Department of Energy's (DOE) Office of Environmental Management (EM). Contamination in the deep vadose zone is isolated from exposure such that direct contact is not a factor in risk to human health and the environment. Transport of deep vadose zone contamination and discharge to the groundwater creates the potential for exposure and risk to receptors, so limiting flux to groundwater is key for protection of groundwater resources. Remediation approaches for the deep vadose zone need to be considered within the regulatory context, targeted at mitigating the source of contamination and reducing contaminant flux to groundwater. Processes for deep vadose zone metal and radionuclide remediation are discussed, as well as challenges and opportunities for implementation. It may be useful to consider the risk and challenges with leaving contaminants in place as part of a flux-control remedy in comparison with risks associated with contaminant removal and final disposition elsewhere. Understanding and quantifying the ramifications of contaminant removal and disposition options are therefore warranted. While this review suggests that some additional development work is needed for deep vadose zone remediation techniques, the benefits of applying vadose zone remediation for groundwater protection are compelling and worthy of continued development. (authors)

  12. Radionuclide Partitioning in an Underground Nuclear Test Cavity

    SciTech Connect

    Rose, T P; Hu, Q; Zhao, P; Conrado, C L; Dickerson, R; Eaton, G F; Kersting, A B; Moran, J E; Nimz, G; Powell, B A; Ramon, E C; Ryerson, F J; Williams, R W; Wooddy, P T; Zavarin, M

    2009-01-09

    In 2004, a borehole was drilled into the 1983 Chancellor underground nuclear test cavity to investigate the distribution of radionuclides within the cavity. Sidewall core samples were collected from a range of depths within the re-entry hole and two sidetrack holes. Upon completion of drilling, casing was installed and a submersible pump was used to collect groundwater samples. Test debris and groundwater samples were analyzed for a variety of radionuclides including the fission products {sup 99}Tc, {sup 125}Sb, {sup 129}I, {sup 137}Cs, and {sup 155}Eu, the activation products {sup 60}Co, {sup 152}Eu, and {sup 154}Eu, and the actinides U, Pu, and Am. In addition, the physical and bulk chemical properties of the test debris were characterized using Scanning Electron Microscopy (SEM) and Electron Microprobe measurements. Analytical results were used to evaluate the partitioning of radionuclides between the melt glass, rubble, and groundwater phases in the Chancellor test cavity. Three comparative approaches were used to calculate partitioning values, though each method could not be applied to every nuclide. These approaches are based on: (1) the average Area 19 inventory from Bowen et al. (2001); (2) melt glass, rubble, and groundwater mass estimates from Zhao et al. (2008); and (3) fission product mass yield data from England and Rider (1994). The U and Pu analyses of the test debris are classified and partitioning estimates for these elements were calculated directly from the classified Miller et al. (2002) inventory for the Chancellor test. The partitioning results from this study were compared to partitioning data that were previously published by the IAEA (1998). Predictions of radionuclide distributions from the two studies are in agreement for a majority of the nuclides under consideration. Substantial differences were noted in the partitioning values for {sup 99}Tc, {sup 125}Sb, {sup 129}I, and uranium. These differences are attributable to two factors

  13. Carboxy, carboalkoxy and carbamile substituted isonitrile radionuclide complexes

    DOEpatents

    Jones, Alun G.; Davison, Alan; Kronauge, James; Abrams, Michael J.

    1988-04-05

    A coordination complex comprising a radionuclide selected from the class consisting of radioactive isotopes of Tc, Ru, Co, Pt and Re and an isonitrile ligand of the formula: (CNX)R, where X is a lower alkyl group having 1 to 4 carbon atoms, wherein R is selected from the group consisting of COOR.sup.1 and CONR.sup.2 R.sup.3 where R.sup.1 can be H, a pharmaceutically acceptable cation, or a substituted or unsubstituted alkyl group having 1 to 4 carbon atoms, R.sup.2, and R.sup.3 can be H, or a substituted or unsubstituted alkyl group having 1 to 4 carbon atoms, and R.sup.2 and R.sup.3 can be the same or different is disclosed. Kits that can be used to form these complexes are also disclosed.

  14. Carboxy, carboalkoxy and carbamile substituted isonitrile radionuclide complexes

    DOEpatents

    Jones, Alun G.; Davison, Alan; Kronauge, James; Abrams, Michael J.

    1989-01-01

    A coordination complex comprising a radionuclide selected from the class consisting of radioactive isotopes of Tc, Ru, Co, Pt and Re and an isonitrile ligand of the formula: (CNX)R, where X is a lower alkyl group having 1 to 4 carbon atoms, wherein R is selected from the group consisting of COOR.sup.1 and CONR.sup.2 R.sup.3 where R.sup.1 can be H, a pharmaceutically acceptable cation, or a substituted or unsubstituted alkyl group having 1 to 4 carbon atoms. R.sup.2, and R.sup.3 can be H, or a substituted or unsubstituted alkyl group having 1 to 4 carbon atoms, and R.sup.2 and R.sup.3 can be the same of different is disclosed. Kits that can be used to form these complexes are also disclosed.

  15. Noble gases and cosmogenic radionuclides in the Eltanin Pacific meteorite

    SciTech Connect

    Bogard, D D; Garrison, D H; Caffee, M W; Kyte, F; Nishiizumi, K

    2000-01-14

    A 1.5 cm long, 1.2 g specimen of the Eltanin meteorite was found at 10.97 m depth in Polarstern piston core PS2704-1. The early studies indicated that the small fragments of the Eltanin meteorite was debris from a km-sized asteroid which impacted into the deep-ocean basin. In this study, the authors measured {sup 39}Ar-{sup 40}Ar age, noble gases, and cosmogenic radionuclides in splits of specimen as a part of consortium studies of Eltanin meteorite. They concluded that the specimen was about 3 m deep from the asteroid surface. The exposure age of the Eltanin asteroid was about 20 Myr.

  16. Biogeochemical Mechanisms Controlling Reduced Radionuclide Particle Properties and Stability

    SciTech Connect

    Jim K. Fredrickson; John M. Zachara; Matthew J. Marshall; Alex S. Beliaev

    2006-06-01

    Uranium and Technetium are the major risk-driving contaminants at Hanford and other DOE sites. These radionuclides have been shown to be reduced by dissimilatory metal reducing bacteria (DMRB) under anoxic conditions. Laboratory studies have demonstrated that reduction results in the formation of poorly soluble hydrous oxides, UO2(s) and TcO2n?H2O(s), that are believed to limit mobility in the environment. The mechanisms of microbial reduction of U and Tc have been the focus of considerable research in the Environmental Remediation Sciences Program (ERSP). In spite of equal or greater importance in terms of controlling the environmental fate of the contaminants relatively little is known regarding the precipitation mechanism(s), reactivity, persistence, and transport of biogenic UO2(s) and TcO2(s).

  17. Chancellor Water Colloids: Characterization and Radionuclide Associated Transport

    SciTech Connect

    Reimus, Paul William; Boukhalfa, Hakim

    2014-09-26

    Column transport experiments were conducted in which water from the Chancellor nuclear test cavity was transported through crushed volcanic tuff from Pahute Mesa. In one experiment, the cavity water was spiked with solute 137Cs, and in another it was spiked with 239/240Pu(IV) nanocolloids. A third column experiment was conducted with no radionuclide spike at all, although the 137Cs concentrations in the water were still high enough to quantify in the column effluent. The radionuclides strongly partitioned to natural colloids present in the water, which were characterized for size distribution, mass concentration, zeta potential/surface charge, critical coagulation concentration, and qualitative mineralogy. In the spiked water experiments, the unanalyzed portion of the high-concentration column effluent samples were combined and re-injected into the respective columns as a second pulse. This procedure was repeated again for a third injection. Measurable filtration of the colloids was observed after each initial injection of the Chancellor water into the columns, but the subsequent injections (spiked water experiments only) exhibited no apparent filtration, suggesting that the colloids that remained mobile after relatively short transport distances were more resistant to filtration than the initial population of colloids. It was also observed that while significant desorption of 137Cs from the colloids occurred after the first injection in both the spiked and unspiked waters, subsequent injections of the spiked water exhibited much less 137Cs desorption (much greater 137Cs colloid-associated transport). This result suggests that the 137Cs that remained associated with colloids during the first injection represented a fraction that was more strongly adsorbed to the mobile colloids than the initial 137Cs associated with the colloids. A greater amount of the 239/240

  18. Targets and methods for target preparation for radionuclide production

    DOEpatents

    Zhuikov, Boris L; Konyakhin, Nicolai A; Kokhanyuk, Vladimir M; Srivastava, Suresh C

    2012-10-16

    The invention relates to nuclear technology, and to irradiation targets and their preparation. One embodiment of the present invention includes a method for preparation of a target containing intermetallic composition of antimony Ti--Sb, Al--Sb, Cu--Sb, or Ni--Sb in order to produce radionuclides (e.g., tin-117 m) with a beam of accelerated particles. The intermetallic compounds of antimony can be welded by means of diffusion welding to a copper backing cooled during irradiation on the beam of accelerated particles. Another target can be encapsulated into a shell made of metallic niobium, stainless steel, nickel or titanium cooled outside by water during irradiation. Titanium shell can be plated outside by nickel to avoid interaction with the cooling water.

  19. Remote sensing of soil radionuclide fluxes in a tropical ecosystem

    SciTech Connect

    Clegg, B.; Koranda, J.; Robinson, W.; Holladay, G.

    1980-11-06

    We are using a transponding geostationary satellite to collect surface environmental data to describe the fate of soil-borne radionuclides. The remote, former atomic testing grounds at the Eniwetok and Bikini Atolls present a difficult environment in which to collect continuous field data. Our land-based, solar-powered microprocessor and environmental data systems remotely acquire measurements of net and total solar radiation, rain, humidity, temperature, and soil-water potentials. For the past year, our water flux model predicts wet season plant transpiration rates nearly equal to the 6 to 7 mm/d evaporation pan rate, which decreases to 2 to 3 mm/d for the dry season. Radioisotopic analysis confirms the microclimate-estimated 1:3 to 1:20 soil to plant /sup 137/Cs dry matter concentration ratio. This ratio exacerbates the dose to man from intake of food plants. Nephelometer measurements of airborne particulates presently indicate a minimum respiratory radiological dose.

  20. Radionuclide release calculations for selected severe accident scenarios

    SciTech Connect

    Denning, R.S.; Leonard, M.T.; Cybulskis, P.; Lee, K.W.; Kelly, R.F.; Jordan, H.; Schumacher, P.M.; Curtis, L.A. )

    1990-08-01

    This report provides the results of source term calculations that were performed in support of the NUREG-1150 study. Severe Accident Risks: An Assessment for Five US Nuclear Power Plants.'' This is the sixth volume of a series of reports. It supplements results presented in the earlier volumes. Analyses were performed for three of the NUREG-1150 plants: Peach Bottom, a Mark I, boiling water reactor; Surry, a subatmospheric containment, pressurized water reactor; and Sequoyah, an ice condenser containment, pressurized water reactor. Complete source term results are presented for the following sequences: short term station blackout with failure of the ADS system in the Peach Bottom plant; station blackout with a pump seal LOCA for the Surry plant; station blackout with a pump seal LOCA in the Sequoyah plant; and a very small break with loss of ECC and spray recirculation in the Sequoyah plant. In addition, some partial analyses were performed which did not require running all of the modules of the Source Term Code Package. A series of MARCH3 analyses were performed for the Surry and Sequoyah plants to evaluate the effects of alternative emergency operating procedures involving primary and secondary depressurization on the progress of the accident. Only thermal-hydraulic results are provided for these analyses. In addition, three accident sequences were analyzed for the Surry plant for accident-induced failure of steam generator tubes. In these analyses, only the transport of radionuclides within the primary system and failed steam generator were examined. The release of radionuclides to the environment is presented for the phase of the accident preceding vessel meltthrough. 17 refs., 176 figs., 113 tabs.

  1. Automated sample collection and processing for radionuclide effluent monitoring

    SciTech Connect

    Beals, D.M.; Crandall, B.S.; Fledderman, P.D.

    1998-12-31

    In the United States, all nuclear facilities must provide for environmental monitoring of effluent points for radionuclides that have the potential for release to the environment. For the US Department of Energy (DOE) this means thousands of surface water analyses are performed each year at a cost of millions of dollars per year. Analytical costs for radiochemical analyses are often high due to the lengthy chemical separations required prior to counting for the selected analyte. At the Savannah River Site, a DOE facility located in South Carolina, a new technique has been demonstrated whereby samples are collected and processed in the field, at the time of collection, for selected radionuclides. The technique makes use of ion selective solid-phase extraction (SPE) disks being placed in a portable automatic aqueous sampler. Water from a surface stream or effluent sampling point is collected via an ISCO, Inc., 3710 SPX portable sampler. Weekly or biweekly (depending on the sampling requirements), the SPE disks are collected and returned to the laboratory for activity determination. The analytes that are currently being monitored by the new method are {sup 99}Tc, {sup 80}Sr, {sup 137}Cs, {sup 58}Co, and {sup 60}Co. The RAD SPE disks have been shown to be effective for the extraction of technetium, strontium, and cesium and cobalt from aqueous systems. The {sup 99}Tc and {sup 90}Sr activities are determined by direct counting of the SPE disk by gas flow beta proportional techniques; the {sup 137}Cs and radiocobalt activities are determined by direct counting of the SPE disk by gamma spectrometry. Because of the specificity of the SPE disks, there is no additional chemical separation required prior to counting the SPE disks for the selected activity determination.

  2. Deadline near for compliance with U. S. oil spill liability rules

    SciTech Connect

    Not Available

    1994-08-01

    The petroleum industry is keeping a close watch on the approaching deadline for compliance with tough new US rules on fiscal liability for oil spills. Interim final rules scheduled to go into effect Dec. 28 stem from the Oil Pollution Act of 1990 (OPA90). The designation of interim final'' rules leaves room for final adjustments on narrow issues. But in general, the rule swill stand as presently structured. OPA90 imposes liability for oil discharges from US and non-US flagged tankers, as well as ports, terminals, and offshore pipelines and other facilities. Tanker operators have voiced the most vigorous opposition to OPA90 because it could expose them to unlimited liability for damage caused by spills and will impose a phaseout on single hull tankers plying US waters. Scheduled to replace such takers are double hull vessels that carry a much bigger price tag. The paper describes provisions of OPA90, the current situation related to insurance coverage, pro and cons to the new rule, cost issues, oil firms, views, new insurers, and the mandatory excess insurance facility proposal.

  3. Technical support for the EPA cleanup rule on radioactively contaminated sites

    SciTech Connect

    Hull, H.B.; Newman, A.; Wolbarst, A.B.

    1995-12-31

    The U.S. Environmental Protection Agency (EPA) is developing a radiation site cleanup regulation for the protection of the public from radionuclide contamination at sites that are to be cleaned up and released for public use. The regulation will apply to sites under the control of Federal agencies, and to sites licensed by the Nuclear Regulatory Commission (NRC) or NRC Agreement States. The agency is therefore conducting a comprehensive technical analysis aimed at developing information that will be used to support the rule. This presentation describes the regulation and the approach developed to determine how radiological health impacts and volumes of soil requiring remediation vary as functions of the possible cleanup dose or risk level.

  4. Forward Compton scattering with weak neutral current: Constraints from sum rules

    DOE PAGES [OSTI]

    Gorchtein, Mikhail; Zhang, Xilin

    2015-06-09

    We generalize forward real Compton amplitude to the case of the interference of the electromagnetic and weak neutral current, formulate a low-energy theorem, relate the new amplitudes to the interference structure functions and obtain a new set of sum rules. Furthermore, we address a possible new sum rule that relates the product of the axial charge and magnetic moment of the nucleon to the 0th moment of the structure function g5(ν, 0). For the dispersive γ Z-box correction to the proton’s weak charge, the application of the GDH sum rule allows us to reduce the uncertainty due to resonance contributionsmore » by a factor of two. Finally, the finite energy sum rule helps addressing the uncertainty in that calculation due to possible duality violations.« less

  5. Identify Institutional Change Rules for Sustainability

    Energy.gov [DOE]

    It is important to analyze formal and informal workplace rules governing the behavior of individuals and organizations to meet a federal agency's institutional change goals for sustainability. It is also important to determine how these rules actually affect people filling different roles in the organization, and how they mesh with the technologies, systems, and processes that constitute tools.

  6. Basement Fill Model Evaluation of Maximum Radionuclide Concentrations for Initial Suite of Radionuclides. Zion Station Restoration Project

    SciTech Connect

    Sullivan, Terry

    2014-12-10

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant in order to establish a new water treatment plant. There is some residual radioactive particles from the plant which need to be brought down to levels so an individual who receives water from the new treatment plant does not receive a radioactive dose in excess of 25 mrem/y⁻¹ as specified in 10 CFR 20 Subpart E. The objectives of this report are: (a) To present a simplified conceptual model for release from the buildings with residual subsurface structures that can be used to provide an upper bound on radionuclide concentrations in the fill material and the water in the interstitial spaces of the fill. (b) Provide maximum water concentrations and the corresponding amount of mass sorbed to the solid fill material that could occur in each building for use by ZSRP in selecting ROCs for detailed dose assessment calculations.

  7. Determination Of Reportable Radionuclides For DWPF Sludge Batch 7B (Macrobatch 9)

    SciTech Connect

    Crawford, C. L.; Diprete, D. P.

    2012-12-17

    The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Sludge Batch 7a (SB7a) and Sludge Batch 7b (SB7b) that was transferred to Tank 40 from Tank 51. The blend of sludge in Tank 40 is also referred to as Macrobatch 9 (MB9). This report develops the list of reportable radionuclides and associated activities as a function of time. Twenty-seven radionuclides have been identified as reportable for DWPF SB7b. Each of these radionuclides has a half-life greater than ten years and contributes more than 0.01% of the radioactivity on a Curie basis at some point from production through the 1100 year period between 2015 and 3115. For SB7b, all of the radionuclides in the Design Basis glass are reportable except for three radionuclides: Pd-107, Cs-135, and Th-230. At no time during the 1100- year period between 2015 and 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. The radionuclide measurements made for SB7b are the most extensive conducted to date. Some method development/refinement occurred during the conduct of these measurements, leading to lower detection limits and more accurate measurement of some isotopes than was previously possible.

  8. Rescuing the Born rule for quantum cosmology

    SciTech Connect

    Cooperman, Joshua H.

    2011-02-01

    Page has recently argued that the Born rule does not suffice for computing all probabilities in quantum cosmology. He further asserts that the Born rule's failure gives rise to the cosmological measure problem. Here I contend that Page's result stems from his use of an overly restrictive definition of the Born rule. In particular, I demonstrate that all of the probabilities he wishes to compute follow from the Born rule when generalized measurements are permitted. I also register two comments on Page's theoretical setting, relating respectively to Hilbert space dimensionality and permutation symmetry. These considerations lead me to conclude that the claimed insufficiency of the Born rule is by no means specific to the cosmological context.

  9. National low-level waste management program radionuclide report series, Volume 15: Uranium-238

    SciTech Connect

    Adams, J.P.

    1995-09-01

    This report, Volume 15 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of uranium-238 ({sup 238}U). The purpose of the National Low-Level Waste Management Program Radionuclide Report Series is to provide information to state representatives and developers of low-level radioactive waste disposal facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the waste disposal facility environment. This report also includes discussions about waste types and forms in which {sup 238}U can be found, and {sup 238}U behavior in the environment and in the human body.

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

    SciTech Connect

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

    1990-10-01

    This report provides the background documentation to support applications for approval to construct and operate new radionuclide emission sources at the Hanford Waste Vitrification Plant (HWVP) near Richland, Washington. The HWVP is required to obtain permits under federal and state statutes for atmospheric discharges of radionuclides. Since these permits must be issued prior to construction of the facility, draft permit applications are being prepared, as well as documentation to support these permits. This report addresses the applicable requirements and demonstrates that the preferred design meets energy, environmental, and economic criteria for Best Available Radionuclide Control Technology (BARCT) at HWVP. 22 refs., 11 figs., 25 tabs.

  11. Final Rulemaking, 10 CFR Part 1021, with Amendments Shown In Tracked Changes

    Office of Energy Efficiency and Renewable Energy (EERE)

    This document presents the final rule as issued September 27, 2011, amendments shown with changes tracked (additions in blue, deletions in red). Categorical exclusions are listed in Appendices A...

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

    SciTech Connect

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

    2013-08-01

    This report compares three different radiation dosimetry systems currently applied by various U.S. Federal agencies and dose estimates based on these three dosimetry systems for a set of radionuclides often identified in power reactor effluents. These dosimetry systems were developed and applied by the International Commission on Radiological Protection at different times over the past six decades. Two primary modes of intake of radionuclides are addressed: ingestion in drinking water and inhalation. Estimated doses to individual organs and to the whole body based on each dosimetry system are compared for each of four age groups: infant, child, teenager, and adult. Substantial differences between dosimetry systems in estimated dose per unit intake are found for some individual radionuclides, but differences in estimated dose per unit intake generally are modest for mixtures of radionuclides typically found in nuclear power plant effluents.

  13. Evaluation and selection of aqueous-based technology for partitioning radionuclides from ICPP calcine

    SciTech Connect

    Olson, A.L.; Schulz, W.W.; Burchfield, L.A.; Carlson, C.D.; Swanson, J.L.; Thompson, M.C.

    1993-02-01

    Early in 1993 Westinghouse Idaho Nuclear Company (WINCO) chartered a Panel of Nuclear Separations Experts. The purpose of this Panel was to assist WINCO scientists and engineers in selecting, evaluating, and ranking candidate aqueous-based processes and technologies for potential use in partitioning selected radionuclides from nitric acid solutions of retrieved Idaho Chemical Processing Plant (ICPP) calcine. Radionuclides of interest are all transuranium elements, {sup 90}Sr, {sup 99}Tc, {sup 129}I, and {sup 137}Cs. The six man Panel met for 4 days (February 16--19, 1993) on the campus of the Idaho State University in Pocatello, Idaho. Principal topics addressed included: Available radionuclide removal technology; applicability of separations technology and processes to ICPP calcine; and potential integrated radionuclide partitioning schemes. This report, prepared from contributions from all Panel members, presents a comprehensive account of the proceedings and significant findings of the February, 1993 meeting in Pocatello.

  14. Proceedings of Soil Decon `93: Technology targeting radionuclides and heavy metals

    SciTech Connect

    Not Available

    1993-09-01

    The principal objective for convening this workshop was to exchange ideas and discuss with scientists and engineers methods for removing radionuclides and/or toxic metals from soils. Over the years there have been numerous symposia, conferences, and workshops directed at soil remediation. However, this may be the first where the scope was narrowed to the removal of radionuclides and toxic metals from soils. The intent was to focus on the separation processes controlling the removal of the radionuclide and/or metal from soil. Its purpose was not intended to be a soil washing/leaching workshop, but rather to identify a variety or combination of processes (chemical, physical, and biological) that can be used in concert with the applicable engineering approaches to decontaminate soils of radionuclides and toxic metals. Abstracts and visual aids used by the speakers of the workshop are presented in this document.

  15. Pacific Northwest Laboratory facilities radionuclide inventory assessment CY 1992-1993

    SciTech Connect

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

    1994-09-01

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

  16. An SAR-compliant radionuclide inventory management system for a DOE research and development laboratory

    SciTech Connect

    O'Kula, K.R.; Lux, C.R.; Clements, J.A.

    2000-07-01

    The US Department of Energy Complex contains many laboratories that require inventory management and control of large stores of radionuclides. While the overall quantities of radionuclides are bounded by Authorization-Basis (AB) documents, the spatial distribution may change rapidly according to facility experimentation and storage limits. Thus, the consequences of postulated accident events may be difficult to quantify as the location of radiological species becomes uncertain. Furthermore, a situation of this nature may be compounded by management of fissile materials in the same laboratory. Although radionuclide inventory management, fissile material control, and compliance with AB limits may be handled individually, a systematic and consistent approach would be to integrate all three functions. A system with these characteristics, an upgraded Radionuclide Inventory and Administrative Control (RI-AC) System, has been implemented for the Savannah River Technology Center (SRTC) located on the Savannah River Site (SRS), and is summarized in this paper.

  17. Sequim Site Radionuclide Air Emissions Report for Calendar Year 2012

    SciTech Connect

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

    2013-04-01

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

  18. Radionuclide gas transport through nuclear explosion-generated fracture networks

    DOE PAGES [OSTI]

    Jordan, Amy B.; Stauffer, Philip H.; Knight, Earl E.; Rougier, Esteban; Anderson, Dale N.

    2015-12-17

    Underground nuclear weapon testing produces radionuclide gases which may seep to the surface. Barometric pumping of gas through explosion-fractured rock is investigated using a new sequentially-coupled hydrodynamic rock damage/gas transport model. Fracture networks are produced for two rock types (granite and tuff) and three depths of burial. The fracture networks are integrated into a flow and transport numerical model driven by surface pressure signals of differing amplitude and variability. There are major differences between predictions using a realistic fracture network and prior results that used a simplified geometry. Matrix porosity and maximum fracture aperture have the greatest impact on gasmore » breakthrough time and window of opportunity for detection, with different effects between granite and tuff simulations highlighting the importance of accurately simulating the fracture network. In particular, maximum fracture aperture has an opposite effect on tuff and granite, due to different damage patterns and their effect on the barometric pumping process. From stochastic simulations using randomly generated hydrogeologic parameters, normalized detection curves are presented to show differences in optimal sampling time for granite and tuff simulations. In conclusion, seasonal and location-based effects on breakthrough, which occur due to differences in barometric forcing, are stronger where the barometric signal is highly variable.« less

  19. New Catalytic DNA Biosensors for Radionuclides and Metal ions

    SciTech Connect

    Lu, Yi

    2003-06-01

    The goals of the project are to develop new catalytic DNA biosensors for simultaneous detection and quantification of bioavailable radionuclides and metal ions, and apply the sensors for on-site, real-time assessment of concentration, speciation and stability of the individual contaminants during and after bioremediation. A negative selection strategy was tested and validated. In vitro selection was shown to yield highly active and specific transition metal ion-dependent catalytic DNA/RNA. A fluorescence resonance energy transfer (FRET) study of in vitro selected DNA demonstrated that the trifluorophore labeled system is a simple and powerful tool in studying complex biomolecules structure and dynamics, and is capable of revealing new sophisticated structural changes. New fluorophore/quenchers in a single fluorosensor yielded improved signal to noise ratio in detection, identification and quantification of metal contaminants. Catalytic DNA fluorescent and colorimetric sensors were shown useful in sensing lead in lake water and in leaded paint. Project results were described in two papers and two patents, and won an international prize.

  20. New Catalytic DNA Biosensors for Radionuclides and Metal ions

    SciTech Connect

    Lu, Yi

    2002-06-01

    The goals of the project are to develop new catalytic DNA biosensors for simultaneous detection and quantification of bioavailable radionuclides and metal ions, and apply the sensors for on-site, real-time assessment of concentration, speciation and stability of the individual contaminants during and after bioremediation. A negative selection strategy was tested and validated. In vitro selection was shown to yield highly active and specific transition metal ion-dependent catalytic DNA/RNA. A fluorescence resonance energy transfer (FRET) study of in vitro selected DNA demonstrated that the trifluorophore labeled system is a simple and powerful tool in studying complex biomolecules structure and dynamics, and is capable of revealing new sophisticated structural changes. New fluorophore/quenchers in a single fluorosensor yielded improved signal to noise ratio in detection, identification and quantification of metal contaminants. Catalytic DNA fluorescent and colorimetric sensors were shown useful in sensing lead in lake water and in leaded paint. Project results were described in two papers and two patents, and won an international prize.

  1. Radionuclide gas transport through nuclear explosion-generated fracture networks

    SciTech Connect

    Jordan, Amy B.; Stauffer, Philip H.; Knight, Earl E.; Rougier, Esteban; Anderson, Dale N.

    2015-12-17

    Underground nuclear weapon testing produces radionuclide gases which may seep to the surface. Barometric pumping of gas through explosion-fractured rock is investigated using a new sequentially-coupled hydrodynamic rock damage/gas transport model. Fracture networks are produced for two rock types (granite and tuff) and three depths of burial. The fracture networks are integrated into a flow and transport numerical model driven by surface pressure signals of differing amplitude and variability. There are major differences between predictions using a realistic fracture network and prior results that used a simplified geometry. Matrix porosity and maximum fracture aperture have the greatest impact on gas breakthrough time and window of opportunity for detection, with different effects between granite and tuff simulations highlighting the importance of accurately simulating the fracture network. In particular, maximum fracture aperture has an opposite effect on tuff and granite, due to different damage patterns and their effect on the barometric pumping process. From stochastic simulations using randomly generated hydrogeologic parameters, normalized detection curves are presented to show differences in optimal sampling time for granite and tuff simulations. In conclusion, seasonal and location-based effects on breakthrough, which occur due to differences in barometric forcing, are stronger where the barometric signal is highly variable.

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

    SciTech Connect

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

    1992-11-01

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

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

    SciTech Connect

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

    1992-11-01

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

  4. Remediation of Deep Vadose Zone Radionuclide and Metal Contamination: Status and Issues

    SciTech Connect

    Dresel, P. Evan; Truex, Michael J.; Cantrell, Keri

    2008-12-30

    This report documents the results of a PNNL literature review to report on the state of maturity of deep vadose zone remediation technologies for metal contaminants including some radionuclides. Its recommendations feed into decisionmakers need for scientific information and cost-effective in situ remediation technlogies needed under DOE's Environmental Management initiative Enhanced Remediation Methods: Scientific & Technical Basis for In Stu Treatment Systems for Metals and Radionuclides.

  5. Decontamination of Terrorist-Dispersed Radionuclides from Surfaces in Urban Environments

    SciTech Connect

    Fischer, Robert; Sutton, Mark; Gates-Anderson, Dianne; Gray, Jeremy; Hu, Qinhong; McNab, Walt; Viani, Brian

    2008-01-15

    Research is currently underway at Lawrence Livermore National Laboratory (LLNL) to advance the basic scientific knowledge of radionuclide-substrate interactions in the urban environment. Investigations have focused on more optimized decontamination agents for cesium (Cs) and americium (Am) specifically for use in mass transit infrastructure and urban environments. This project is designed to enhance the capability of the United States to effectively respond to a Radiological Dispersal Device (RDD) attack. The work addresses recognized data gaps by advancing the basic scientific knowledge of radionuclide-substrate interactions in the urban environment and provides a solution to a national need. The research is focused in four major areas: (1) a better understanding of urban surface conditions that influence the efficacy of decontamination processes, (2) development of prototype decontamination agents for Am and Cs optimized for use in urban environments, (3) the development of capabilities to realistically contaminate surfaces at both the real world and laboratory scale and (4) a validated model for radionuclide-surface interactions. The decontamination of urban surfaces following the detonation of an RDD presents a number of challenges. The following key points are found to be critical for the efficiency of decontamination agents in an urban environment: - Particle size and surface deposition of radionuclide particles on urban surface materials. - Interactions between radionuclides and urban materials. - The presence of grime and carbonation/alteration layers on the surface of urban surfaces. - Post-detonation penetration of radionuclides strongly affected by the dynamic wetting/drying processes. A laboratory scale contamination system has been developed allowing for samples to be contaminated and radionuclide interactions to be studied. In combination with laboratory scale experiments, a real scale outdoor test is scheduled for the spring of 2007. In conclusion

  6. Production of Radionuclide Molybdenum 99 in a Distributed and In Sit

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Fashion.---- Inventor(s): Charles Gentile, Adam B. Cohen and George Ascione. | Princeton Plasma Physics Lab Production of Radionuclide Molybdenum 99 in a Distributed and In Sit Fashion.---- Inventor(s): Charles Gentile, Adam B. Cohen and George Ascione. This patent application is for the distributed production of Tc-99m, a radionuclide extensively used in diagnostic medicine. Central to the invention is the generation of high energy gamma rays which can be produced by the interaction of

  7. Radionuclide air emissions report for the Hanford site, Calendar year 1994

    SciTech Connect

    Gleckler, B.P.; Diediker, L.P.; Jette, S.J.; Rhoads, K.; Soldat, S.K.

    1995-06-01

    This report documents radionuclide air emissions from the Hanford Site in 1994, and the resulting effective dose equivalent to the maximally exposed member of the public, referred to as the ``MEI.`` The report has been prepared and will be submitted in accordance with reporting requirements in the Code of Federal Regulations, title 40, Protection of the Environment, Part 61, ``National Emissions Standards for Hazardous Air Pollutants,`` Subpart H, ``National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.``

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

    SciTech Connect

    Mark Verdoorn; Tom Haney

    2011-06-01

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

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

    SciTech Connect

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

    1993-06-01

    This report documents radionuclide air emissions from the Hanford Site in 1992 and the resulting effective dose equivalent to an member of the public. The report has been prepared and will be submitted in accordance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, ``National Emissions Standards for Hazardous Air Pollutants,`` Subpart H, ``National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.``

  10. PABLM: a computer program to calculate accumulated radiation doses from radionuclides in the environment

    SciTech Connect

    Napier, B.A.; Kennedy, W.E. Jr.; Soldat, J.K.

    1980-03-01

    A computer program, PABLM, was written to facilitate the calculation of internal radiation doses to man from radionuclides in food products and external radiation doses from radionuclides in the environment. This report contains details of mathematical models used and calculational procedures required to run the computer program. Radiation doses from radionuclides in the environment may be calculated from deposition on the soil or plants during an atmospheric or liquid release, or from exposure to residual radionuclides in the environment after the releases have ended. Radioactive decay is considered during the release of radionuclides, after they are deposited on the plants or ground, and during holdup of food after harvest. The radiation dose models consider several exposure pathways. Doses may be calculated for either a maximum-exposed individual or for a population group. The doses calculated are accumulated doses from continuous chronic exposure. A first-year committed dose is calculated as well as an integrated dose for a selected number of years. The equations for calculating internal radiation doses are derived from those given by the International Commission on Radiological Protection (ICRP) for body burdens and MPC's of each radionuclide. The radiation doses from external exposure to contaminated water and soil are calculated using the basic assumption that the contaminated medium is large enough to be considered an infinite volume or plane relative to the range of the emitted radiations. The equations for calculations of the radiation dose from external exposure to shoreline sediments include a correction for the finite width of the contaminated beach.

  11. Review of radionuclide source terms used for performance-assessment analyses; Yucca Mountain Site Characterization Project

    SciTech Connect

    Barnard, R.W.

    1993-06-01

    Two aspects of the radionuclide source terms used for total-system performance assessment (TSPA) analyses have been reviewed. First, a detailed radionuclide inventory (i.e., one in which the reactor type, decay, and burnup are specified) is compared with the standard source-term inventory used in prior analyses. The latter assumes a fixed ratio of pressurized-water reactor (PWR) to boiling-water reactor (BWR) spent fuel, at specific amounts of burnup and at 10-year decay. TSPA analyses have been used to compare the simplified source term with the detailed one. The TSPA-91 analyses did not show a significant difference between the source terms. Second, the radionuclides used in source terms for TSPA aqueous-transport analyses have been reviewed to select ones that are representative of the entire inventory. It is recommended that two actinide decay chains be included (the 4n+2 ``uranium`` and 4n+3 ``actinium`` decay series), since these include several radionuclides that have potentially important release and dose characteristics. In addition, several fission products are recommended for the same reason. The choice of radionuclides should be influenced by other parameter assumptions, such as the solubility and retardation of the radionuclides.

  12. Geochemical effects on the behavior of LLW radionuclides in soil/groundwater environments

    SciTech Connect

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

    1995-12-31

    Assessing the migration potential of radionuclides leached from low-level radioactive waste (LLW) and decommissioning sites necessitates information on the effects of sorption and precipitation on the concentrations of dissolved radionuclides. Such an assessment requires that the geochemical processes of aqueous speciation, complexation, oxidation/reduction, and ion exchange be taken into account. The Pacific Northwest National Laboratory (PNNL) is providing technical support to the U.S. Nuclear Regulatory Commission (NRC) for defining the solubility and sorption behavior of radionuclides in soil/ground-water environments associated with engineered cementitious LLW disposal systems and decommissioning sites. Geochemical modeling is being used to predict solubility limits for radionuclides under geochemical conditions associated with these environments. The solubility limits are being used as maximum concentration limits in performance assessment calculations describing the release of contaminants from waste sources. Available data were compiled regarding the sorption potential of radionuclides onto {open_quotes}fresh{close_quotes} cement/concrete where the expected pH of the cement pore waters will equal to or exceed 10. Based on information gleaned from the literature, a list of preferred minimum distribution coefficients (Kd`s) was developed for these radionuclides. The K{sub d} values are specific to the chemical environments associated with the evolution of the compositions of cement/concrete pore waters.

  13. Alternatives to the 15% Rule

    SciTech Connect

    Broderick, Robert Joseph; Quiroz, Jimmy Edward; Reno, Matthew J.; Munoz-Ramos, Karina; Smith, Jeff; Rylander, Matthew; Rogers, Lindsey; Dugan, Roger; Mather, Barry; Coddington, Michael; Gotseff, Peter; Ding, Fei

    2015-11-01

    The third solicitation of the California Solar Initiative (CSI) Research, Development, Demonstration and Deployment (RD&D) Program established by the California Public Utility Commission (CPUC) is supporting the Electric Power Research Institute (EPRI), National Renewable Energy Laboratory (NREL), and Sandia National Laboratories (SNL) with collaboration from Pacific Gas and Electric (PG&E), Southern California Edison (SCE), and San Diego Gas and Electric (SDG&E), in research to improve the Utility Application Review and Approval process for interconnecting distributed energy resources to the distribution system. Currently this process is the most time - consuming of any step on the path to generating power on the distribution system. This CSI RD&D solicitation three project has completed the tasks of collecting data from the three utilities, clustering feeder characteristic data to attain representative feeders, detailed modeling of 16 representative feeders, analysis of PV impacts to those feeders, refinement of current screening processes, and validation of those suggested refinements. In this report each task is summarized to produce a final summary of all components of the overall project.

  14. Acquisition & Financial Assistance Rules Status | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Acquisition & Financial Assistance Rules Status Acquisition & Financial Assistance Rules Status Subscribe to Acquisition & Financial Assistance Rules Status Updates Department of Energy, Office of Acquisition Management Proposed Rules Current as of 11/4/16 Regulation Identifier Number Title / Subject / Purpose Rule Type Status 1901-AB37 Enforcement of Classified Information Security Requirements: The proposed rule amends DOE's statutory prescribed regulation, which sets forth the

  15. Proposed EPA Rules Will Cut Carbon Pollution While Maintaining...

    Energy Saver

    Proposed EPA Rules Will Cut Carbon Pollution While Maintaining Reliability Proposed EPA Rules Will Cut Carbon Pollution While Maintaining Reliability June 3, 2014 - 4:20pm Addthis ...

  16. EPA Mobile Source Rule Update | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Mobile Source Rule Update EPA Mobile Source Rule Update 2003 DEER Conference Presentation: ... More Documents & Publications EPA Diesel Update Technical Challenges and Opportunities ...

  17. Notices and Rules Related to Federal Energy Management | Department...

    Energy.gov [DOE] (indexed site)

    DOE's Federal Energy Management Program (FEMP) issues notices and rules related to federal ... The following notices and rules were announced by DOE, FEMP, and BTO through the Federal ...

  18. Appendix B: Rules and Directives Applicable to Nuclear Facilities...

    Energy Saver

    Appendix B: Rules and Directives Applicable to Nuclear Facilities Line Management Oversight Appendix B: Rules and Directives Applicable to Nuclear Facilities Line Management ...

  19. DOE Issues Landmark Rule for Risk Insurance for Advanced Nuclear...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Landmark Rule for Risk Insurance for Advanced Nuclear Facilities DOE Issues Landmark Rule for Risk Insurance for Advanced Nuclear Facilities May 8, 2006 - 10:36am Addthis ...

  20. Vermont Stormwater Management Rule for Stormwater-Impaired Waters...

    OpenEI (Open Energy Information) [EERE & EIA]

    LibraryAdd to library Legal Document- RegulationRegulation: Vermont Stormwater Management Rule for Stormwater-Impaired WatersLegal Abstract This Rule enhances the management...

  1. Proposed Rule Correction, Federal Register, 75 FR 66008, October...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Proposed Rule Correction, Federal Register, 75 FR 66008, October 27, 2010 Proposed Rule Correction, Federal Register, 75 FR 66008, October 27, 2010 Document displays a correction ...

  2. Worker Safety and Health Rules, Directives, and Technical Standards...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Worker Safety and Health Rules, Directives, and Technical Standards Worker Safety and Health Rules, Directives, and Technical Standards Document Number Title Date 10 CFR 707 ...

  3. Collegiate Wind Competition 2016 Rules and Regulations | Department...

    Energy Saver

    Collegiate Wind Competition 2016 Rules and Regulations Collegiate Wind Competition 2016 Rules and Regulations The competition challenges interdisciplinary teams of undergraduate ...

  4. DOE Preliminary Plan for Retrospective Analysis of Existing Rules...

    Energy Saver

    Preliminary Plan for Retrospective Analysis of Existing Rules DOE Preliminary Plan for Retrospective Analysis of Existing Rules On January 18, 2011, the President issued Executive ...

  5. Preliminary Plan for Retrospective Analysis of Existing Rules

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    ... office will remove email addresses and other ... DOE has already developed its first candidate list of rules ... to its rules, guidance documents, and paperwork ...

  6. Historic Energy Efficiency Rules Would Save Consumers Money and...

    Energy Saver

    Historic Energy Efficiency Rules Would Save Consumers Money and Cut Carbon Emissions Historic Energy Efficiency Rules Would Save Consumers Money and Cut Carbon Emissions August 29, ...

  7. Ground Water Management District Rules | Open Energy Information

    OpenEI (Open Energy Information) [EERE & EIA]

    Water Management District Rules Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Ground Water Management District Rules Abstract This webpage provides...

  8. Design rules for dislocation filters (Journal Article) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Design rules for dislocation filters Citation Details In-Document Search Title: Design rules for dislocation filters The efficacy of strained layer threading dislocation filter...

  9. Processing Exemptions to Nuclear Safety Rules and Approval of...

    Office of Environmental Management (EM)

    STD-1083-2009 June 2009 DOE STANDARD PROCESSING EXEMPTIONS TO NUCLEAR SAFETY RULES AND ... and granting exemptions to DOE nuclear safety rules and b. requesting and ...

  10. Institutional Change Process Step 2: Assess Institutional Rules...

    Office of Environmental Management (EM)

    2: Assess Institutional Rules, Roles, and Tools Institutional Change Process Step 2: Assess Institutional Rules, Roles, and Tools Graphic of the Institutional Change Continuous ...

  11. Rules and Regulations of the Wyoming Industrial Siting Council...

    OpenEI (Open Energy Information) [EERE & EIA]

    Document- RegulationRegulation: Rules and Regulations of the Wyoming Industrial Siting Council - Chapter 1Legal Abstract Industrial development information and siting rules and...

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    OpenEI (Open Energy Information) [EERE & EIA]

    Document- RegulationRegulation: Rules and Regulations of the Wyoming Industrial Siting Council - Chapter 2Legal Abstract Rules of practice and proceedures of the Industrial Siting...

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    OpenEI (Open Energy Information) [EERE & EIA]

    Help Apps Datasets Community Login | Sign Up Search Page Edit with form History Texas PUCT Substantive Rule 25.101, Certification Criteria, Electric Substantive Rules Jump...

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    OpenEI (Open Energy Information) [EERE & EIA]

    RegulationRegulation: Oregon Rules of Appellate ProcedureLegal Abstract These rules set forth the procedure for hearings before the state courts of appeals. Published NA Year...

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    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Proposes New Rules to Protect Trade Secrets and Confidential Business Information DOE Proposes New Rules to Protect Trade Secrets and Confidential Business Information March 8,...

  16. Full Final Report

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    REPOR FULL FINAL REPOR T T SECTION III SECTION III FULL FINAL REPORT SECTION III Individual Project Summaries Table of Contents Algal Biology ..................................................................................................3 Cultivation ...................................................................................................41 Harvesting and Extraction .............................................................................65 Fuel Conversion

  17. Final EIS Volume 3

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Volume 3 Final Environmental Impact Statement for Decommissioning and/or Long-Term Stewardship at the West Valley Demonstration Project and Western New York Nuclear Service Center DOE/EIS-0226 January 2010 The West Valley Site Comment Response Document Final Environmental Impact Statement for AVAILABILITY OF THE FINAL EIS FOR DECOMMISSIONING AND/OR LONG- TERM STEWARDSHIP AT THE WEST VALLEY DEMONSTRATION PROJECT AND WESTERN NEW YORK NUCLEAR SERVICE CENTER For further information on this Final

  18. Montana Rule 36.25.4 Geothermal Rules and Regulations | Open...

    OpenEI (Open Energy Information) [EERE & EIA]

    Geothermal Rules and RegulationsLegal Abstract Montana regulation governing administration of geothermal resources in the state. Published NA Year Signed or Took Effect...

  19. Microsoft Word - Loan Guarantee NOPR -Final_5-09-07_FR 2 _2_.doc |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Loan Guarantee NOPR -Final_5-09-07_FR 2 _2_.doc Microsoft Word - Loan Guarantee NOPR -Final_5-09-07_FR 2 _2_.doc Microsoft Word - Loan Guarantee NOPR -Final_5-09-07_FR 2 _2_.doc (160.81 KB) More Documents & Publications Notice of Proposed Rulemaking (August 6, 2009) Notice of Proposed Rulemaking (May 16, 2007) Final Rule (December 4, 2009)

  20. Radionuclide characterization and associated dose from long-lived radionuclides in close-in fallout delivered to the marine environment at Bikini and Enewetak Atoll

    SciTech Connect

    Noshkin, V. E.; Robison, W. L.

    1998-09-01

    Between June 1946 and October 1958, Enewetak and Bikini Atolls were used by the United States as testing grounds for 66 nuclear devices. The combined explosive yield from these tests was 107 Mt (Mt TNT equivalents). This testing produced close-in fallout debris that was contaminated with quantities of radioactive fission and particle activated products, and unspent radioactive nuclear fuel that entered the aquatic environment of the atolls. Today, the sediments in the lagoons are reservoirs for 10's of TBq of the transuranics and some long-lived fission and activation products. The larger amounts of contamination are associated with fine and coarse sediment material adjacent to the locations of the high yield explosions. Radionuclides are also distributed vertically in the sediment column to various depths in all regions of the lagoons. Concentrations greater than fallout background levels are found in filtered water sampled over several decades from all locations and depths in the lagoons. This is a direct indication that the radionuclides are continuously mobilized to solution from the solid phases. Of particular importance is the fact that the long-lived radionuclides are accumulated to different levels by indigenous aquatic plants and organisms that are used as food by resident people. One might anticipate finding continuous high contamination levels in many of the edible marine organisms from the lagoons, since the radionuclides associated with the sediments are not contained and are available to the different organisms in a relatively shallow water environment. This is not the case. We estimate that the radiological dose from consumption of the edible parts of marine foods at Enewetak and Bikini is presently about 0.05% of the total 50-year integral effective dose from all other exposure pathways that include ingestion of terrestrial foods and drinking water, external exposure and inhalation. The total radiological dose from the marine pathway is dominated by

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

    SciTech Connect

    Hiergesell, R.; Phifer, M.

    2014-04-29

    As a condition to the Department of Energy (DOE) Low Level Waste Disposal Federal Facility Review Group (LFRG) review team approving the Savannah River Site (SRS) Composite Analysis (CA), SRS agreed to follow up on a secondary issue, which consisted of the consolidation of several observations that the team concluded, when evaluated collectively, could potentially impact the integration of the CA results. This report addresses secondary issue observations 4 and 21, which identify the need to improve the CA sensitivity and uncertainty analysis specifically by improving the CA inventory and the estimate of its uncertainty. The purpose of the work described herein was to be responsive to these secondary issue observations by re-examining the radionuclide inventories of the Integrator Operable Units (IOUs), as documented in ERD 2001 and Hiergesell, et. al. 2008. The LFRG concern has been partially addressed already for the Lower Three Runs (LTR) IOU (Hiergesell and Phifer, 2012). The work described in this investigation is a continuation of the effort to address the LFRG concerns by re-examining the radionuclide inventories associated with Fourmile Branch (FMB) IOU, Pen Branch (PB) IOU and Steel Creek (SC) IOU. The overall approach to computing radionuclide inventories for each of the IOUs involved the following components: Defining contaminated reaches of sediments along the IOU waterways Identifying separate segments within each IOU waterway to evaluate individually Computing the volume and mass of contaminated soil associated with each segment, or compartment Obtaining the available and appropriate Sediment and Sediment/Soil analytical results associated with each IOU Standardizing all radionuclide activity by decay-correcting all sample analytical results from sample date to the current point in time, Computing representative concentrations for all radionuclides associated with each compartment in each of the IOUs Computing the radionuclide

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

    SciTech Connect

    Hiergesell, R.; Phifer, M.

    2014-04-29

    As a condition to the Department of Energy (DOE) Low Level Waste Disposal Federal Facility Review Group (LFRG) review team approving the Savannah River Site (SRS) Composite Analysis (CA), SRS agreed to follow up on a secondary issue, which consisted of the consolidation of several observations that the team concluded, when evaluated collectively, could potentially impact the integration of the CA results. This report addresses secondary issue observations 4 and 21, which identify the need to improve the CA sensitivity and uncertainty analysis specifically by improving the CA inventory and the estimate of its uncertainty. The purpose of the work described herein was to be responsive to these secondary issue observations by re-examining the radionuclide inventories of the Integrator Operable Units (IOUs), as documented in ERD 2001 and Hiergesell, et. al. 2008. The LFRG concern has been partially addressed already for the Lower Three Runs (LTR) IOU (Hiergesell and Phifer, 2012). The work described in this investigation is a continuation of the effort to address the LFRG concerns by re-examining the radionuclide inventories associated with Fourmile Branch (FMB) IOU, Pen Branch (PB) IOU and Steel Creek (SC) IOU. The overall approach to computing radionuclide inventories for each of the IOUs involved the following components: • Defining contaminated reaches of sediments along the IOU waterways • Identifying separate segments within each IOU waterway to evaluate individually • Computing the volume and mass of contaminated soil associated with each segment, or “compartment” • Obtaining the available and appropriate Sediment and Sediment/Soil analytical results associated with each IOU • Standardizing all radionuclide activity by decay-correcting all sample analytical results from sample date to the current point in time, • Computing representative concentrations for all radionuclides associated with each compartment in each of the IOUs • Computing the

  3. Radionuclide releases to the Columbia River from Hanford Operations, 1944--1971. Hanford Environmental Dose Reconstruction Project

    SciTech Connect

    Heeb, C.M.; Bates, D.J.

    1994-01-01

    The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of radionuclide emissions since 1944 from the Hanford Site. One source of radionuclide releases to the Columbia River was from production reactor operations. This report provides a quantitative estimate of the amount of radioactivity released each month (1944--1971) to the Columbia River from eleven radionuclides as well as from gross beta activity.

  4. Radionuclide releases to the Columbia River from Hanford Operations, 1944--1971. Hanford Environmental Dose Reconstruction Project

    SciTech Connect

    Heeb, C.M.; Bates, D.J.

    1994-05-01

    The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of radionuclide emissions since 1944 from the Hanford Site. One source of radionuclide releases to the Columbia River was from production reactor operations. This report provides a quantitative estimate of the amount of radioactivity released each month (1944--1971) to the Columbia River from eleven radionuclides as well as from gross beta activity.

  5. Radionuclide release from spent fuel under geologic disposal conditions: An overview of experimental and theoretical work through 1985

    SciTech Connect

    Reimus, P.W.; Simonson, S.A.

    1988-04-01

    This report presents an overview of experimental and theoretical work on radionuclide release from spent fuel and uranium dioxide (UO/sub 2/) under geologic disposal conditions. The purpose of the report is to provide a source book of information that can be used to develop models that describe radionuclide release from spent fuel waste packages. Modeling activities of this nature will be conducted within the Waste Package Program (WPP) of the Department of Energy's Salt Repository Project (SRP). The topics discussed include experimental methods for investigating radionuclide release, how results have been reported from radionuclide release experiments, theoretical studies of UO/sub 2/ and actinide solubility, results of experimental studies of radionuclide release from spent fuel and UO/sub 2/ (i.e., the effects of different variables on radionuclide release), characteristics of spent fuel pertinent to radionuclide release, and status of modeling of radionuclide release from spent fuel. Appendix A presents tables of data from spent fuel radionuclide release experiments. These data have been digitized from graphs that appear in the literature. An annotated bibliography of literature on spent fuel characterization is provided in Appendix B.

  6. Characterization of radionuclide-chelating agent complexes found in low-level radioactive decontamination waste. Literature review

    SciTech Connect

    Serne, R.J.; Felmy, A.R.; Cantrell, K.J.; Krupka, K.M.; Campbell, J.A.; Bolton, H. Jr.; Fredrickson, J.K.

    1996-03-01

    The US Nuclear Regulatory Commission is responsible for regulating the safe land disposal of low-level radioactive wastes that may contain organic chelating agents. Such agents include ethylenediaminetetraacetic acid (EDTA), diethylenetriaminepentaacetic acid (DTPA), picolinic acid, oxalic acid, and citric acid, and can form radionuclide-chelate complexes that may enhance the migration of radionuclides from disposal sites. Data from the available literature indicate that chelates can leach from solidified decontamination wastes in moderate concentration (1--100 ppm) and can potentially complex certain radionuclides in the leachates. In general it appears that both EDTA and DTPA have the potential to mobilize radionuclides from waste disposal sites because such chelates can leach in moderate concentration, form strong radionuclide-chelate complexes, and can be recalcitrant to biodegradation. It also appears that oxalic acid and citric acid will not greatly enhance the mobility of radionuclides from waste disposal sites because these chelates do not appear to leach in high concentration, tend to form relatively weak radionuclide-chelate complexes, and can be readily biodegraded. In the case of picolinic acid, insufficient data are available on adsorption, complexation of key radionuclides (such as the actinides), and biodegradation to make definitive predictions, although the available data indicate that picolinic acid can chelate certain radionuclides in the leachates.

  7. Radionuclide inventories : ORIGEN2.2 isotopic depletion calculation for high burnup low-enriched uranium and weapons-grade mixed-oxide pressurized-water reactor fuel assemblies.

    SciTech Connect

    Gauntt, Randall O.; Ross, Kyle W.; Smith, James Dean; Longmire, Pamela

    2010-04-01

    The Oak Ridge National Laboratory computer code, ORIGEN2.2 (CCC-371, 2002), was used to obtain the elemental composition of irradiated low-enriched uranium (LEU)/mixed-oxide (MOX) pressurized-water reactor fuel assemblies. Described in this report are the input parameters for the ORIGEN2.2 calculations. The rationale for performing the ORIGEN2.2 calculation was to generate inventories to be used to populate MELCOR radionuclide classes. Therefore the ORIGEN2.2 output was subsequently manipulated. The procedures performed in this data reduction process are also described herein. A listing of the ORIGEN2.2 input deck for two-cycle MOX is provided in the appendix. The final output from this data reduction process was three tables containing the radionuclide inventories for LEU/MOX in elemental form. Masses, thermal powers, and activities were reported for each category.

  8. Systematics of strength function sum rules

    DOE PAGES [OSTI]

    Johnson, Calvin W.

    2015-08-28

    Sum rules provide useful insights into transition strength functions and are often expressed as expectation values of an operator. In this letter I demonstrate that non-energy-weighted transition sum rules have strong secular dependences on the energy of the initial state. Such non-trivial systematics have consequences: the simplification suggested by the generalized Brink–Axel hypothesis, for example, does not hold for most cases, though it weakly holds in at least some cases for electric dipole transitions. Furthermore, I show the systematics can be understood through spectral distribution theory, calculated via traces of operators and of products of operators. Seen through this lens,more » violation of the generalized Brink–Axel hypothesis is unsurprising: one expectssum rules to evolve with excitation energy. Moreover, to lowest order the slope of the secular evolution can be traced to a component of the Hamiltonian being positive (repulsive) or negative (attractive).« less

  9. DETERMINATION OF THE DISTRIBUTION AND INVENTORY OF RADIONUCLIDES WITHIN A SAVANNAH RIVER SITE WATERWAY

    SciTech Connect

    Hiergesell, R.; Phifer, M.

    2012-11-09

    An investigation was conducted to evaluate the radionuclide inventory within the Lower Three Runs (LTR) Integrator Operable Unit (IOU) at the U.S. Department of Energy’s (DOE’s) Savannah River Site (SRS). The scope of this effort included the analysis of previously existing sampling and analysis data as well as additional streambed and floodplain sampling and analysis data acquired to delineate horizontal and vertical distributions of the radionuclide as part of the ongoing SRS environmental restoration program, and specifically for the LTR IOU program. While cesium-137 (Cs-137) is the most significant and abundant radionuclide associated with the LTR IOU it is not the only radionuclide, hence the scope included evaluating all radionuclides present and includes an evaluation of inventory uncertainty for use in sensitivity and uncertainty analyses. The scope involved evaluation of the radionuclide inventory in the P-Reactor and RReactor cooling water effluent canal systems, PAR Pond (including Pond C) and the floodplain and stream sediment sections of LTR between the PAR Pond Dam and the Savannah River. The approach taken was to examine all of the available Sediment and Sediment/Soil analysis data available along the P- and R-Reactor cooling water re-circulation canal system, the ponds situated along those canal reaches and along the length of LTR below Par Pond dam. By breaking the IOU into a series of sub-components and sub-sections, the mass of contaminated material was estimated and a representative central concentration of each radionuclide was computed for each compartment. The radionuclide inventory associated with each sub-compartment was then aggregated to determine the total radionuclide inventory that represented the full LTR IOU. Of special interest was the inventory of Cs-137 due to its role in contributing to the potential dose to an offsite member of the public. The overall LTR IOU inventory of Cs-137 was determined to be 75.5 Ci, which is similar

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

    SciTech Connect

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

    2014-01-07

    In 2010 a Composite Analysis (CA) of the U.S. Department of Energy’s (DOE’s) Savannah River Site (SRS) was completed. This investigation evaluated the dose impact of the anticipated SRS End State residual sources of radionuclides to offsite members of the public. Doses were assessed at the locations where SRS site streams discharge into the Savannah River at the perimeter of the SRS. Although the model developed to perform this computation indicated that the dose constraint of 0.3 mSv/yr (30 mrem/yr), associated with CA, was not approached at the Points of Assessment (POAs), a significant contribution to the total computed dose was derived from the radionuclides (primarily Cs-137) bound-up in the soil and sediment of the drainage corridors of several SRS streams. DOE’s Low Level Waste Federal Review Group (LFRG) reviewed the 2010 CA and identified several items to be addressed in the SRS Maintenance Program. One of the items recognized Cs-137 in the Lower Three Runs (LTR) Integrator Operable Unit (IOU), as a significant CA dose driver. The item made the recommendation that SRS update the estimated radionuclide inventory, including Cs-137, in the LTR IOU. That initial work has been completed and its radionuclide inventory refined. There are five additional streams at SRS and the next phase of the response to the LFRG concern was to obtain a more accurate inventory and distribution of radionuclides in three of those streams, Fourmile Branch (FMB), Pen Branch (PB) and Steel Creek (SC). Each of these streams is designated as an IOU, which are defined for the purpose of this investigation as the surface water bodies and associated wetlands, including the channel sediment, floodplain sed/soil, and related biota. If present, radionuclides associated with IOUs are adsorbed to the streambed sediment and soils of the shallow floodplains that lie immediately adjacent to stream channels. The scope of this effort included the evaluation of any previous sampling and

  11. Determination of the Distribution and Inventory of Radionuclides within a Savannah River Site Waterway - 13202

    SciTech Connect

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

    2013-07-01

    An investigation was conducted to evaluate the radionuclide inventory within the Lower Three Runs (LTR) Integrator Operable Unit (IOU) at the U.S. Department of Energy's (DOE's) Savannah River Site (SRS). The scope of this effort included the analysis of previously existing sampling and analysis data as well as additional stream bed and flood plain sampling and analysis data acquired to delineate horizontal and vertical distributions of the radionuclide as part of the ongoing SRS environmental restoration program, and specifically for the LTR IOU program. While cesium-137 (Cs-137) is the most significant and abundant radionuclide associated with the LTR IOU it is not the only radionuclide, hence the scope included evaluating all radionuclides present and includes an evaluation of inventory uncertainty for use in sensitivity and uncertainty analyses. The scope involved evaluation of the radionuclide inventory in the P-Reactor and R-Reactor cooling water effluent canal systems, PAR Pond (including Pond C) and the flood plain and stream sediment sections of LTR between the PAR Pond Dam and the Savannah River. The approach taken was to examine all of the available Sediment and Sediment/Soil analysis data available along the P- and R-Reactor cooling water re-circulation canal system, the ponds situated along those canal reaches and along the length of LTR below Par Pond dam. By breaking the IOU into a series of sub-components and sub-sections, the mass of contaminated material was estimated and a representative central concentration of each radionuclide was computed for each compartment. The radionuclide inventory associated with each sub-compartment was then aggregated to determine the total radionuclide inventory that represented the full LTR IOU. Of special interest was the inventory of Cs-137 due to its role in contributing to the potential dose to an offsite member of the public. The overall LTR IOU inventory of Cs-137 was determined to be 2.87 E+02 GBq, which is

  12. Notices and Rules Related to Federal Energy Management

    Energy.gov [DOE]

    The Federal Energy Management Program (FEMP) issues notices and rules related to federal energy management.

  13. Google Rules of Behavior Form | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Google Rules of Behavior Form Google Rules of Behavior Form Google Rules of Behavior Form Google Drive for Work Rules of Behavior Form (46.01 KB) More Documents & Publications Audit Report: DOE-OIG-16-12 April 2014 Cybersecurity Awareness Campaign - Malware Front Burner - Issue 16

  14. Assessment of the radiological impact of coal utilization. II. Radionuclides in western coal ash

    SciTech Connect

    Styron, C.E.; Bishop, C.T.; Casella, V.R.; Jenkins, P.H.; Yanko, W.H.

    1981-04-03

    A project has been initiated at Mound Facility specifically to evaluate the potential radiological impact of coal utilization. Phase I of the project included a survey of western US coal mines and an assessment of emissions from a power plant burning Western coal. Concentrations of uranium in coal from operating Western mines were slightly below the national average and roughly comparable to Eastern coal. Environmental deposition of radionuclides from stack emissions over a 20-year accumulation at a power plant burning Western coal was estimated to be 0.1 to 1.0% of measured background. Phase II of the project, the subject of the present report, has involved an interlaboratory comparison of results of radioanalytical procedures, determining partitioning coefficients for radionuclides in bottom ash and fly ash, and an assessment of the potential for migration of radionuclides from ash disposal sites. Results from the various laboratories for uranium-238, uranium-234, thorium-230, radium-226, polonium-210, thorium-232, thorium-228, and uranium-235 were generally in very good agreement. However, values for lead-210 in coal varied widely. Essentially all the nonvolatile radionuclides (uranium, radium, and thorium) from feed coal were accounted for in fly ash and bottom ash. However, 20 to 50% of the volatile radionuclides (lead and polonium) from subbituminous and lignitic coals could not be accounted for in ash, and it is assumed that this fraction exits via the stack. At the power plant burning bituminous coal, essentially all the lead and most of the polonium remained with the ash.

  15. Natural analogue studies of the role of colloids, natural organics and microorganisms on radionuclide transport

    SciTech Connect

    McCarthy, J.F.

    1994-10-01

    Colloids may be important as a geochemical transport mechanism for radionuclides at geological repositories if they are (1) present in the groundwater, (2) stable with respect to both colloidal and chemical stabilities, (3) capable of adsorbing radionuclides, especially if the sorption is irreversible, and (4) mobile in the subsurface. The available evidence from natural analogue and other field studies relevant to these issues is reviewed, as is the potential role of mobile microorganisms ({open_quotes}biocolloids{close_quotes}) on radionuclide migration. Studies have demonstrated that colloids are ubiquitous in groundwater, although colloid concentrations in deep, geochemically stable systems may be too low to affect radionuclide transport. However, even low colloid populations cannot be dismissed as a potential concern because colloids appear to be stable, and many radionuclides that adsorb to colloids are not readily desorbed over long periods. Field studies offer somewhat equivocal evidence concerning colloid mobility and cannot prove or disprove the significance of colloid transport in the far-field environment. Additional research is needed at new sites to properly represent a repository far-field. Performance assessment would benefit from natural analogue studies to examine colloid behavior at sites encompassing a suite of probable groundwater chemistries and that mimic the types of formations selected for radioactive waste repositories.

  16. Marine plankton as an indicator of low-level radionuclide contamination in the Southern Ocean

    SciTech Connect

    Marsh, K.V.; Buddemeier, R.W.

    1984-07-01

    We have initiated an investigation of the utility of marine plankton as bioconcentrating samplers of low-level marine radioactivity in the southern hemisphere. A literature review shows that both freshwater and marine plankton have trace element and radionuclide concentration factors (relative to water) of up to 10/sup 4/. In the years 1956-1958, considerable work was done on the accumulation and distribution of a variety of fission and activation products produced by the nuclear tests in the Marshall Islands. Since then, studies have largely been confined to a few selected radionuclides, and by far most of this work has been done in the northern hemisphere. We participated in Operation Deepfreeze 1981, collecting 32 plankton samples from the U.S. Coast Guard Cutter Glacier on its Antarctic cruise, while Battelle Pacific Northwest Laboratories concurrently sampled air, water, rain and fallout. We were able to measure concentrations of the naturally occurring radionuclides /sup 7/Be, /sup 40/K and the U and th series, and we believe that we have detected low levels of /sup 144/Ce and /sup 95/Nb in seven samples ranging as far south as 68/sup 0/. There is a definite association between the radionuclide content of plankton and air filters, suggesting that aerosol resuspension of marine radioactivity may be occurring. Biological identification of the plankton suggests a possible correlation between radionuclide concentration and foraminifera content of the samples. 38 references, 7 figures, 3 tables.

  17. Java implementation of Class Association Rule algorithms

    Energy Science and Technology Software Center

    2007-08-30

    Java implementation of three Class Association Rule mining algorithms, NETCAR, CARapriori, and clustering based rule mining. NETCAR algorithm is a novel algorithm developed by Makio Tamura. The algorithm is discussed in a paper: UCRL-JRNL-232466-DRAFT, and would be published in a peer review scientific journal. The software is used to extract combinations of genes relevant with a phenotype from a phylogenetic profile and a phenotype profile. The phylogenetic profiles is represented by a binary matrix andmore » a phenotype profile is represented by a binary vector. The present application of this software will be in genome analysis, however, it could be applied more generally.« less

  18. Collegiate Wind Competition 2014 Rules and Regulations | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Collegiate Wind Competition 2014 Rules and Regulations Collegiate Wind Competition 2014 Rules and Regulations This document outlines the rules and regulations for the inaugural Collegiate Wind Competition in 2014. U.S. Department of Energy Collegiate Wind Competition 2014 Rules and Regulations (1.62 MB) More Documents & Publications U.S. Department of Energy 2017 Collegiate Wind Competition Technical Challenge Rules and Requirements U.S. Department of Energy Collegiate Wind

  19. Regulations.gov - Proposed Rule Document | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Regulations.gov - Proposed Rule Document Regulations.gov - Proposed Rule Document In response to your phone call and e-mail below the proposed rule that you reference below regarding energy efficiency standards for manufactured housing has not been issued yet by the Department of Energy (DOE) and therefore we are still in the process of drafting a proposed rule and any necessary definitions. Proposed Rule Email (197.68 KB) More Documents & Publications ISSUANCE 2015-02-04: Energy

  20. SunShot Prize Competition Rules | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Competition Rules SunShot Prize Competition Rules This document provides the SunShot Prize competition rules updated on July 20, 2015 by the SunShot Initiative. SunShot Prize Official Rules July 2015.pdf (1.19 MB) More Documents & Publications SunShot Prize Frequently Asked Questions SunShot Prize Race to 7-Day Solar SunShot Catalyst Prize Rules

  1. Final Project Report

    SciTech Connect

    Wang, Qiang; Dandy, David S.

    2015-05-15

    This is the final technical report of the DOE project DE-FG02-07ER46448 awarded to Colorado State University.

  2. National Science Bowl Finals

    ScienceCinema

    None

    2016-07-12

    National Science Bowl finals and awards at the National Building Museum in Washington D.C. Monday 5/3/2010

  3. DOE Final Report

    SciTech Connect

    Hinzman, Larry D.; Long, James; Newby, Greg B.

    2014-01-08

    This final report contains a summary of work accomplished in the establishment of a Climate Data Center at the International Arctic Research Center, University of Alaska Fairbanks.

  4. Final Technical Report

    SciTech Connect

    Mattes, M. Jules

    2005-06-10

    The best summary of our results is probably provided by the list of publications based on work supported by this grant, which is given below. In general, the objectives were realized, and we have demonstrated, for the first time, that radiolabeled Abs can kill single tumor cells very effectively, and that they can also be effective in treating models of human tumors growing as xenografts in SCID mice. Our original work, as proposed in the application, was with Abs to B-lymphoma cells, namely anti-CD20 and anti-HLA-DR. After our successful efforts with these Abs, we decided to extend the results to other tumor types. Accordingly, carcinomas of the breast, ovary and other tissues were treated with radiolabeled Abs to EGFr and HER-2. These tumors cells were also effectively killed in vitro with radiolabeled Abs. This is significant because these Abs are widely used, and successful, in the clinic (unlabeled) and because the flattened shape of the cells, in vitro, is expected to make them considerably more difficult to kill than the spherical lymphoma cells. A major goal was to compare radionuclides emitting different types of radiation, namely low energy electrons (Auger and conversion electrons), {beta}-particles, and {alpha}-particles. All three types could effectively kill cells in vitro with considerable specificity. However, the low energy electrons, which we abbreviate LEEs, have significant advantages, mainly due to their lower level of non-specific toxicity. This was demonstrated both in vitro and in vivo. Thus, {beta}-particle emitters conjugated to anti-CD20 could protect mice against the growth of B-lymphoma tumor cells, but the therapeutic effect was limited by the maximum dose that could be administered, without killing the mouse. In contrast, the LEE emitters were more effective, largely because the toxicity was much less, allowing an approximately 10-fold higher {mu}Ci dose to be injected. Conjugates with {alpha}-particle emitters were also less

  5. Bounding Radionuclide Inventory and Accident Consequence Calculation for the 1L Target

    SciTech Connect

    Kelsey, Charles T. IV

    2011-01-01

    A bounding radionuclide inventory for the tungsten of the Los Alamos Neutron Science Center (LANSCE) IL Target is calculated. Based on the bounding inventory, the dose resulting from the maximum credible incident (MCI) is calculated for the maximally exposed offsite individual (MEOl). The design basis accident involves tungsten target oxidation following a loss of cooling accident. Also calculated for the bounding radionuclide inventory is the ratio to the LANSCE inventory threshold for purposes of inventory control as described in the target inventory control policy. A bounding radionuclide inventory calculation for the lL Target was completed using the MCNPX and CINDER'90 codes. Continuous beam delivery at 200 {micro}A to 2500 mA{center_dot}h was assumed. The total calculated activity following this irradiation period is 205,000 Ci. The dose to the MEOI from the MCI is 213 mrem for the bounding inventory. The LANSCE inventory control threshold ratio is 132.

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

    SciTech Connect

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

    1996-12-01

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

  7. Pacific Northwest National Laboratory Facility Radionuclide Emission Points and Sampling Systems

    SciTech Connect

    Barfuss, Brad C.; Barnett, J. M.; Ballinger, Marcel Y.

    2009-04-08

    BattellePacific Northwest Division operates numerous research and development laboratories in Richland, Washington, including those associated with the Pacific Northwest National Laboratory (PNNL) on the Department of Energys Hanford Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all effluent release points that have the potential for radionuclide emissions. Potential emissions are assessed annually. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission point system performance, operation, and design information. A description of the buildings, exhaust points, control technologies, and sample extraction details is provided for each registered or deregistered facility emission point. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided.

  8. Workshop on development of radionuclide getters for the Yucca Mountain waste repository: proceedings.

    SciTech Connect

    Moore, Robert Charles; Lukens, Wayne W. (Lawrence Berkeley National Laboratory)

    2006-03-01

    The proposed Yucca Mountain repository, located in southern Nevada, is to be the first facility for permanent disposal of spent reactor fuel and high-level radioactive waste in the United States. Total Systems Performance Assessment (TSPA) analysis has indicated that among the major radionuclides contributing to dose are technetium, iodine, and neptunium, all of which are highly mobile in the environment. Containment of these radionuclides within the repository is a priority for the Yucca Mountain Project (YMP). These proceedings review current research and technology efforts for sequestration of the radionuclides with a focus on technetium, iodine, and neptunium. This workshop also covered issues concerning the Yucca Mountain environment and getter characteristics required for potential placement into the repository.

  9. Conceptual model for regional radionuclide transport from a salt dome repository: a technical memorandum

    SciTech Connect

    Kier, R.S.; Showalter, P.A.; Dettinger, M.D.

    1980-05-30

    Disposal of high-level radioactive wastes is a major environmental problem influencing further development of nuclear energy in this country. Salt domes in the Gulf Coast Basin are being investigated as repository sites. A major concern is geologic and hydrologic stability of candidate domes and potential transport of radionuclides by groundwater to the biosphere prior to their degradation to harmless levels of activity. This report conceptualizes a regional geohydrologic model for transport of radionuclides from a salt dome repository. The model considers transport pathways and the physical and chemical changes that would occur through time prior to the radionuclides reaching the biosphere. Necessary, but unknown inputs to the regional model involve entry and movement of fluids through the repository dome and across the dome-country rock interface and the effect on the dome and surrounding strata of heat generated by the radioactive wastes.

  10. Apparatus for real-time airborne particulate radionuclide collection and analysis

    DOEpatents

    Smart, John E.; Perkins, Richard W.

    2001-01-01

    An improved apparatus for collecting and analyzing an airborne particulate radionuclide having a filter mounted in a housing, the housing having an air inlet upstream of the filter and an air outlet downstream of the filter, wherein an air stream flows therethrough. The air inlet receives the air stream, the filter collects the airborne particulate radionuclide and permits a filtered air stream to pass through the air outlet. The improvement which permits real time counting is a gamma detecting germanium diode mounted downstream of the filter in the filtered air stream. The gamma detecting germanium diode is spaced apart from a downstream side of the filter a minimum distance for a substantially maximum counting detection while permitting substantially free air flow through the filter and uniform particulate radionuclide deposition on the filter.

  11. Nuclear and Facility Safety Policy Rules

    Office of Energy Efficiency and Renewable Energy (EERE)

    DOE provides safety requirements and guidance in a number of forms. One form in which we publish requirements is through rulemaking. Federal rules and regulations are published in the Code of Federal Regulations (CFR) and are noticed for review and comment by members of the public in the Federal Register (FR) consistent with the Administrative Procedures Act.

  12. A dynamic model for evaluating radionuclide distribution in forests from nuclear accidents

    SciTech Connect

    Schell, W.R.; Linkov, I.; Myttenaere, C.

    1996-03-01

    The Chernobyl Nuclear Power Plant accident in 1986 caused radionuclide contamination in most countries in Eastern and Western Europe. A prime example is Belarus where 23% of the total land area received chronic levels; about 1.5 X 10{sup 6} ha of forested lands were contaminated with 40-190 kBq m{sup -2} and 2.5 X 10{sup 4} ha received greater than 1,480 kBq m{sup -2} of {sup 137}Cs and other long-lived radionuclides such as {sup 90}Sr and {sup 239,240}Pu. Since the radiological dose to the forest ecosystem will tend to accumulate over long time periods (decades to centuries), we need to determine what countermeasures can be taken to limit this dose so that the affected regions can, once again, safely provide habitat and natural forest products. To address some of these problems, our initial objective is to formulate a generic model, FORESTPATH, which describes the major kinetic processes and pathways of radionuclide movement in forests and natural ecosystems and which can be used to predict future radionuclide concentrations. The model calculates the time-dependent radionuclide concentrations in different compartments of the forest ecosystem based on the information available on residence half-times in two forest types: coniferous and deciduous. The results show that the model reproduces well the radionuclide cycling pattern found in the literature for deciduous and coniferous forests. Variability analysis was used to access the relative importance of specific parameter values in the generic model performance. The FORESTPASTH model can be easily adjusted for site-specific applications. 92 refs., 5 figs., 6 tabs.

  13. Assessment of hydrologic transport of radionuclides from the Rio Blanco underground nuclear test site, Colorado

    SciTech Connect

    Chapman, J.; Earman, S.; Andricevic, R.

    1996-10-01

    DOE is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations used for nuclear testing. Evaluation of radionuclide transport by groundwater is part of preliminary risk analysis. These evaluations allow prioritization of test areas in terms of risk, provide a basis for discussions with regulators and the public about future work, and provide a framework for assessing site characterization data needs. The Rio Blanco site in Colorado was the location of the simultaneous detonation of three 30-kiloton nuclear devices. The devices were located 1780, 1899, and 2039 below ground surface in the Fort Union and Mesaverde formations. Although all the bedrock formations at the site are thought to contain water, those below the Green River Formation (below 1000 in depth) are also gas-bearing, and have very low permeabilities. The transport scenario evaluated was the migration of radionuclides from the blast-created cavity through the Fort Union Formation. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides from the test are contained entirely within the area currently administered by DOE. This modeling was performed to investigate how the uncertainty in various physical parameters affect radionuclide transport at the site, and to serve as a starting point for discussion regarding further investigation; it was not intended to be a definitive simulation of migration pathways or radionuclide concentration values. Given the sparse data, the modeling results may differ significantly from reality. Confidence in transport predictions can be increased by obtaining more site data, including the amount of radionuclides which would have been available for transport (i.e., not trapped in melt glass or vented during gas flow testing), and the hydraulic properties of the formation. 38 refs., 6 figs., 1 tab.

  14. SHPCS14_FINAL

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Science, Open Security Scott Campbell National Energy Research Scientific Computing Center Lawrence Berkeley National Lab Berkeley, CA, USA scampbell@lbl.gov Abstract- We propose that to address the growing problems with complexity and data volumes in HPC security wee need to refactor how we look at data by creating tools that not only select data, but analyze and represent it in a manner well suited for intuitive analysis. We propose a set of rules describing what this means, and provide a

  15. 2015-12-29 Consumer Furnaces and Boilers Test Procedures Final Rule

    Energy.gov [DOE]

    Energy Conservation Program for Consumer Products: Test Procedures for Consumer Furnaces and Boilers

  16. Policy Flash: 2013-52 Contractor Legal Management Requirements: Final Rule

    Energy.gov [DOE]

    Questions concerning this policy flash should be directed to Michael Righi of the Contract and Financial Assistance

  17. Final-HRP-Memo-712-Clarifications-Under-the-Existing-Rule-Signed-8-20-13

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    August 20, 2013 MEMORANDUM Fo 0 fo'ISTRIBUTIO I ~ { f FROM: 'c:;\e:_q:, '. , \J_;, lC L _ LARRY . WILCHER DIRECTOR, OFFICE OF SECURITY OFFICE OF HEALTH, SAFETY AND SECURITY SUBJECT: Clarification of Requirements for Certification in Title 10 Code of Federal Regulations Part 712, Human Reliability Program The Human Reliability Program (HRP), a combination of two earlier programs (the Personnel Assurance Program and the Persmmel Security Assurance Program), was codified in 2004 at Title 10 Code of

  18. Final-HRP-Memo-712-Clarifications-Under-the-Existing-Rule-Signed...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... Jim O'Brien, HS-30 John Boulden, HS-40 Larry D. Wilcher, HS-50 Regina Cano, HS-50 Mike Zimmerman, HS-90 David Bivans, EM-44 Gene Runkle, SC-3 Earl Hicks, SC-31.3 Michael Lempke, ...

  19. Microsoft Word - ASC Rules of Procedure_FINAL_05-22-2012

    U.S. Department of Energy (DOE) - all webpages (Extended Search)

    Northwest Power Act requires the Bonneville Power Administration (BPA) to develop a methodology for determining a utility's average system cost (ASC) for the purpose of selling...

  20. Final Rule on Amending Eligibility Provisions to Multifamily Buildings for the Weatherization Assistance Program

    Energy.gov [DOE]

    U.S. Department of Energy (DOE) Office of Energy Efficiency and Renewable Energy (EERE) Weatherization Assistance Program (WAP) Program Guidance 10-14 dealing with HUD multifamily buildings eligibility for weatherization services.

  1. Final Rule, Federal Register, 74 FR 10830, 10 CFR Part 436, March...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Product Procurement: Executive, Legislative and Regulatory Requirements, Actions and Mandates Sample Contract Language for Construction Using Energy-Efficient Products

  2. Discovering The Folding Rules That Proteins Obey FY08 LDRD Final...

    Office of Scientific and Technical Information (OSTI)

    Sponsoring Org: USDOE Country of Publication: United States Language: English Subject: 59 BASIC BIOLOGICAL SCIENCES Word Cloud More Like This Full Text preview image File size N...

  3. Statement by Secretary Moniz on Release of Final Clean Power Plan Rules |

    Energy Saver

    Of Patricia Hoffman Assistant Secretary For Electricity Delivery and Energy Reliability U.S. Department of Energy Before The United States House of Representatives Appropriations Subcommittee on Energy and Water Development March 25, 2014 Mr. Chairman and Members of the Committee, thank you for the opportunity to appear before you today to discuss the President's Fiscal Year (FY) 2015 budget for the Department of Energy's (DOE) Office of Electricity Delivery and Energy Reliability (OE). It is

  4. New Strategies for 0.5 mm Resolution, High Sensitivity, Multi- Radionuclide Imaging

    SciTech Connect

    Levin, Craig S; Levin, Craig

    2015-02-28

    This project constitutes a 0.5-millimeter resolution radionuclide detector system built from CZT. (1) A novel dual-crystal photon detector module design with cross-strip electrode patterns was developed; (2) The module mechanical assembly was built; (3) A data acquisition (DAQ) chain for the module was produced; (4) A software tool was developed to incorporate novel time and energy measurement calibration techniques. (5) A small multi-detector prototype of the radionuclide imaging system was built from this module for system-level characterizations.

  5. Monitoring the fate of radionuclides released to the environment: May 1991 report

    SciTech Connect

    Bauer, L.R.

    1992-08-13

    A review of the radiological effluent and environmental monitoring practices in use at Mound has been conducted. The radionuclides under consideration were HT, Pu-239, U-233,234, U-238, Th-230, Th-232, Co-60, Cs-137, and Ac-227. It is concluded from this analysis that additional continuous monitoring programs are not warranted. Dose contributions from these radionuclides are negligible. Further, in many cases environmental surveillance would not be practical due to the extremely low concentrations encountered in the offsite environment. For these reasons, it is believed that no additional action is required in response to DOE Tiger Team Finding R/CF-1.

  6. Determination Of Reportable Radionuclides For DWPF Sludge Batch 7B (Macrobatch 9)

    SciTech Connect

    Crawford, C. L.; DiPrete, D. P.

    2013-08-22

    The Waste Acceptance Product Specifications (WAPS) 1.2 require that “The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115”. As part of the strategy to comply with WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type, all radionuclides (with half-lives greater than 10 years) that have concentrations greater than 0.01 percent of the total inventory from time of production through the 1100 year period from 2015 through 3115. The initial listing of radionuclides to be included is based on the design-basis glass as identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report (WQR). However, it is required that this list be expanded if other radionuclides with half-lives greater than 10 years are identified that may meet the greater than 0.01% criterion for Curie content. Specification 1.6 of the WAPS, International Atomic Energy Agency (IAEA) Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete set of reportable radionuclides must also include this set of U and Pu isotopes. The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Sludge Batch 7a (SB7a) and Sludge Batch 7b (SB7b) that was transferred to Tank 40 from Tank 51. The blend of sludge in Tank 40 is also referred to as Macrobatch 9 (MB9). This report develops the list of reportable radionuclides and associated activities as a function of time. The DWPF will use this list and the activities as one of the inputs for the development of the Production Records that relate to

  7. Engineering test plan for field radionuclide migration experiments in climax granite

    SciTech Connect

    Isherwood, D.; Raber, E.; Stone, R.; Lord, D.; Rector, N.; Failor, R.

    1982-05-01

    This Engineering Test Plan (ETP) describes field studies of radionuclide migration in fractured rock designed for the Climax grainite at the Nevada Test Site. The purpose of the ETP is to provide a detailed written document of the method of accomplishing these studies. The ETP contains the experimental test plans, an instrumentation plan, system schematics, a description of the test facility, and a brief outline of the laboratory support studies needed to understand the chemistry of the rock/water/radionuclide interactions. Results of our initial hydrologic investigations are presented along with pretest predictions based on the hydrologic test results.

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

    SciTech Connect

    Mark Verdoorn; Tom Haney

    2012-06-01

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

  9. U.S. Department of Energy Report, 2005 LANL Radionuclide Air Emissions

    SciTech Connect

    Keith W. Jacobson, David P. Fuehne

    2006-09-01

    Amendments to the Clean Air Act, which added radionuclides to the National Emissions Standards for Hazardous Air Pollutants (NESHAP), went into effect in 1990. Specifically, a subpart (H) of 40 CFR 61 established an annual limit on the impact to the public attributable to emissions of radionuclides from U.S. Department of Energy facilities, such as the Los Alamos National Laboratory (LANL). As part of the new NESHAP regulations, LANL must submit an annual report to the U.S. Environmental Protection Agency headquarters and the regional office in Dallas by June 30. This report includes results of monitoring at LANL and the dose calculations for the calendar year 2006.

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

    SciTech Connect

    Verdoorn, Mark; Haney, Tom

    2013-06-01

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

  11. DETERMINATION OF REPORTABLE RADIONUCLIDES FOR DWPF SLUDGE BATCH 7B (MACROBATCH 9)

    SciTech Connect

    Crawford, C. L.; Diprete, D. P.

    2014-05-01

    The Waste Acceptance Product Specifications (WAPS) 1.2 require that “The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115”. As part of the strategy to comply with WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type, all radionuclides (with half-lives greater than 10 years) that have concentrations greater than 0.01 percent of the total inventory from time of production through the 1100 year period from 2015 through 3115. The initial listing of radionuclides to be included is based on the design-basis glass as identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report (WQR). However, it is required that this list be expanded if other radionuclides with half-lives greater than 10 years are identified that may meet the greater than 0.01% criterion for Curie content. Specification 1.6 of the WAPS, International Atomic Energy Agency (IAEA) Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, and Pu- 242. Therefore, the complete set of reportable radionuclides must also include this set of U and Pu isotopes. The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Sludge Batch 7a (SB7a) and Sludge Batch 7b (SB7b) that was transferred to Tank 40 from Tank 51. The blend of sludge in Tank 40 is also referred to as Macrobatch 9 (MB9). This report develops the list of reportable radionuclides and associated activities as a function of time. The DWPF will use this list and the activities as one of the inputs for the development of the Production Records that relate to

  12. Primary calibrations of radionuclide solutions and sources for the EML quality assessment program

    SciTech Connect

    Fisenne, I.M.

    1993-12-31

    The quality assurance procedures established for the operation of the U.S. Department of Energy`s Environmental Measurements Laboratory (DOE-EML`s) Quality Assessment Program (QAP) are essentially the same as those that are in effect for any EML program involving radiometric measurements. All these programs have at their core the use of radionuclide standards for their instrument calibration. This paper focuses on EML`s approach to the acquisition, calibration and application of a wide range of radionuclide sources that are required to meet its programmatic needs.

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

    SciTech Connect

    Verdoorn, Mark; Haney, Tom

    2014-06-01

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

  14. Radionuclide air emission report for the Hanford Site Calendar Year 1993

    SciTech Connect

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

    1994-08-01

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

  15. Analysis of natural radionuclides from uranium and thorium series in briney groundwaters

    SciTech Connect

    Laul, J.C.; Smith, M.R.; Thomas, C.W.; Jackson, P.O.; Hubbard, N.

    1985-06-01

    Analytical procedures for measuring various radionuclides in the /sup 238/U and /sup 232/Th chains in briney waters are described. Using methods such as mass spectrometry, and alpha, beta and gamma spectrometry, the desired measurement sensitivity required for each of the radionuclides is achieved. Uranium-233, /sup 230/Th, /sup 208/Po, /sup 212/Pb, and /sup 133/Ba are used as tracers for chemical yield recoveries. Typical precision of the results range from 5 to 20%. 14 refs., 6 figs., 3 tabs.

  16. Mathematical Deductions from Some Rules Concerning High-Energy Total Cross Sections

    DOE R&D Accomplishments

    Yang, C. N.

    1962-07-23

    Mathematical implications of the Pomeranchuk rule and the Pomeranchuk- Okun rule are discussed. (auth)

  17. Radionuclide distributions and migration mechanisms at shallow land burial sites. 1982 annual report of research investigations on the distribution, migration and containment of radionuclides at Maxey Flats, Kentucky

    SciTech Connect

    Kirby, L.J.

    1984-02-01

    Subsurface waters at Maxey Flats are anoxic, have a high alkalinity and contain high concentrations of ferrous, sulfide and ammonium ions and organic carbon. The trench leachates are extremely variable in composition. Prominent radionuclides include /sup 3/H, /sup 60/Co, /sup 90/Sr, /sup 137/Cs, /sup 238/ /sup 239/ /sup 240/Pu and /sup 241/Am. A wide spectrum of dissolved organic compounds is present in the leachates, including EDTA, polar organics and decomposition products from the waste forms. Cobalt-60 and plutonium are present as EDTA complexes and /sup 90/Sr and /sup 137/Cs are associated with carboxylic acid type compounds. The chemistry of these waters changes drastically as they become oxic and plutonium becomes less mobile under these new conditions. Water enters the trenches by infiltration through the trench caps, through subsidence areas, and through interfaces between new landfill and the original soil. Lateral flow is very complex and slow, and apparently occurs mainly by fracture flow. The plastic infiltration barrier installed in 1981 to 1982 has been effective in reducing soil moisture if cracks and leaks are eliminated. To date, no direct evidence of radionuclide transport to offsite locations by subsurface flow has been confirmed. The offsite distribution of radionuclides, except for tritium, is comparable to the ambient fallout from nuclear weapons testing. Tritium concentrations in water offsite are orders of magnitude below MPC levels. 24 figures, 31 tables.

  18. Calculation of External Gamma-Ray and Beta-Ray Doses from Accidental Atmospheric Releases of Radionuclides.

    Energy Science and Technology Software Center

    1981-02-25

    SUBDOSA-II calculates submersion doses from an acute release of radionuclides to the atmosphere, as did SUBDOSA. Doses are calculated as a function of distance from release point, atmospheric stability, and wind speed for a specified radionuclide inventory. Contributions from both beta and gamma radiation are included as a function of tissue depth.

  19. Montana Rule 36.25.1 Surface Management Rules | Open Energy Informatio...

    OpenEI (Open Energy Information) [EERE & EIA]

    36.25.1 Surface Management RulesLegal Abstract Montana regulation governing the administration of state surface land Published NA Year Signed or Took Effect 2014 Legal Citation...

  20. Enewetak radiological support project. Final report

    SciTech Connect

    Friesen, B.

    1982-09-01

    From 1972 through 1980, the Department of Energy acted in an advisory role to the Defense Nuclear Agency during planning for and execution of the cleanup of Enewetak Atoll. The Nevada Operations Office of the Department of Energy was responsible for the radiological characterization of the atoll and for certification of radiological condition of each island upon completion of the project. In-situ measurements of gamma rays emitted by americium-241 were utilized along with wet chemistry separation of plutonium from soil samples to identify and delineate surface areas requiring removal of soil. Military forces removed over 100,000 cubic yards of soil from the surface of five islands and deposited this material in a crater remaining from the nuclear testing period. Subsurface soil was excavated and removed from several locations where measurements indicated the presence of radionuclides above predetermined criteria. The methodologies of data acquisition, analysis and interpretation are described and detailed results are provided in text, figures and microfiche. The final radiological condition of each of 43 islets is reported.