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Sample records for tritium extraction facility

  1. Commercial Light Water Reactor Tritium Extraction Facility

    SciTech Connect (OSTI)

    McHood, M D

    2000-10-12

    A geotechnical investigation program has been completed for the Commercial Light Water Reactor - Tritium Extraction Facility (CLWR-TEF) at the Savannah River Site (SRS). The program consisted of reviewing previous geotechnical and geologic data and reports, performing subsurface field exploration, field and laboratory testing, and geologic and engineering analyses. The purpose of this investigation was to characterize the subsurface conditions for the CLWR-TEF in terms of subsurface stratigraphy and engineering properties for design and to perform selected engineering analyses. The objectives of the evaluation were to establish site-specific geologic conditions, obtain representative engineering properties of the subsurface and potential fill materials, evaluate the lateral and vertical extent of any soft zones encountered, and perform engineering analyses for slope stability, bearing capacity and settlement, and liquefaction potential. In addition, provide general recommendations for construction and earthwork.

  2. Structural acceptance criteria Remote Handling Building Tritium Extraction Facility

    SciTech Connect (OSTI)

    Mertz, G.

    1999-12-16

    This structural acceptance criteria contains the requirements for the structural analysis and design of the Remote Handling Building (RHB) in the Tritium Extraction Facility (TEF). The purpose of this acceptance criteria is to identify the specific criteria and methods that will ensure a structurally robust building that will safely perform its intended function and comply with the applicable Department of Energy (DOE) structural requirements.

  3. Commercial Light Water Reactor Tritium Extraction Facility Geotechnical Summary Report

    SciTech Connect (OSTI)

    Lewis, M.R.

    2000-01-11

    A geotechnical investigation program has been completed for the Circulating Light Water Reactor - Tritium Extraction Facility (CLWR-TEF) at the Savannah River Site (SRS). The program consisted of reviewing previous geotechnical and geologic data and reports, performing subsurface field exploration, field and laboratory testing and geologic and engineering analyses. The purpose of this investigation was to characterize the subsurface conditions for the CLWR-TEF in terms of subsurface stratigraphy and engineering properties for design and to perform selected engineering analyses. The objectives of the evaluation were to establish site-specific geologic conditions, obtain representative engineering properties of the subsurface and potential fill materials, evaluate the lateral and vertical extent of any soft zones encountered, and perform engineering analyses for slope stability, bearing capacity and settlement, and liquefaction potential. In addition, provide general recommendations for construction and earthwork.

  4. Construction and Operation of a Tritium Extraction Facility at the Savannah Siver Site

    National Nuclear Security Administration (NNSA)

    N I T E D S T A T E S O F A M E R I C A D E P A R T M E NT O F E N E R G Y DOE/EIS-0271 Construction & Operation of a Tritium Extraction Facility at the Savannah River Site Department of Energy Savannah River Operations Office Aiken, South Carolina Final Environmental Impact Statement March 1999 DOE/EIS-0271 March 1999 Preface iii COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy (DOE) TITLE: Final Environmental Impact Statement: Construction and Operation of a Tritium Extraction

  5. STAR Facility Tritium Accountancy

    SciTech Connect (OSTI)

    R. J. Pawelko; J. P. Sharpe; B. J. Denny

    2007-09-01

    The Safety and Tritium Applied Research (STAR) facility has been established to provide a laboratory infrastructure for the fusion community to study tritium science associated with the development of safe fusion energy and other technologies. STAR is a radiological facility with an administrative total tritium inventory limit of 1.5g (14,429 Ci) [1]. Research studies with moderate tritium quantities and various radionuclides are performed in STAR. Successful operation of the STAR facility requires the ability to receive, inventory, store, dispense tritium to experiments, and to dispose of tritiated waste while accurately monitoring the tritium inventory in the facility. This paper describes tritium accountancy in the STAR facility. A primary accountancy instrument is the tritium Storage and Assay System (SAS): a system designed to receive, assay, store, and dispense tritium to experiments. Presented are the methods used to calibrate and operate the SAS. Accountancy processes utilizing the Tritium Cleanup System (TCS), and the Stack Tritium Monitoring System (STMS) are also discussed. Also presented are the equations used to quantify the amount of tritium being received into the facility, transferred to experiments, and removed from the facility. Finally, the STAR tritium accountability database is discussed.

  6. STAR facility tritium accountancy

    SciTech Connect (OSTI)

    Pawelko, R. J.; Sharpe, J. P.; Denny, B. J.

    2008-07-15

    The Safety and Tritium Applied Research (STAR) facility has been established to provide a laboratory infrastructure for the fusion community to study tritium science associated with the development of safe fusion energy and other technologies. STAR is a radiological facility with an administrative total tritium inventory limit of 1.5 g (14,429 Ci) [1]. Research studies with moderate tritium quantities and various radionuclides are performed in STAR. Successful operation of the STAR facility requires the ability to receive, inventory, store, dispense tritium to experiments, and to dispose of tritiated waste while accurately monitoring the tritium inventory in the facility. This paper describes tritium accountancy in the STAR facility. A primary accountancy instrument is the tritium Storage and Assay System (SAS): a system designed to receive, assay, store, and dispense tritium to experiments. Presented are the methods used to calibrate and operate the SAS. Accountancy processes utilizing the Tritium Cleanup System (TCS), and the Stack Tritium Monitoring System (STMS) are also discussed. Also presented are the equations used to quantify the amount of tritium being received into the facility, transferred to experiments, and removed from the facility. Finally, the STAR tritium accountability database is discussed. (authors)

  7. Type B Investigation Board Report on the April 2, 2002, Worker Fall from Shoring/Scaffolding Structure at the Savannah River Site Tritium Extraction Facility Construction Site

    Broader source: Energy.gov [DOE]

    On April 2, 2002, a carpenter helping to erect shoring/scaffolding fell about 52” and struck his head. He sustained head injuries requiring hospitalization that exceeded the threshold for a Type B investigation in accordance with Department of Energy (DOE) Order 225.1A, Accident Investigation. The accident occurred at the DOE’s Savannah River Site (SRS) at the Tritium Extraction Facility (TEF) construction site.

  8. An introduction to the National Tritium Labeling Facility

    SciTech Connect (OSTI)

    Dorsky, A.M.; Morimoto, H.; Saljoughian, M.; Williams, P.G.; Rapoport, H.

    1988-06-01

    The facilities and projects of the National Tritium Labeling Facility are described. 5 refs., 1 fig., 1 tab.

  9. Tritium extraction throughput at Hanford, 1949--1954

    SciTech Connect (OSTI)

    Gydesen, S.P.

    1994-02-24

    Two tritium extraction campaigns were conducted at the 108 B facility. Both glass and metal extraction lines were utilized during the first campaign which began in February 1949 and was completed in March 1952. Five glass lines were constructed and made available for use as needed. Operation of the metal extraction line was begun on May 3, 1951. It continued in production until completion of the first campaign in March 1952. The second campaign used only the metal line. It was initiated in December 1953 and fulfilled in August 1954. Tritium production and extraction throughput information from Hanford operations was recently declassified. This document presents tritium extraction throughput information excerpted from monthly production reports which remain classified SECRET-RESTRICTED DATA because they contain information on weapon part fabrication, shipments, tritium technology and unit costs. Individuals with the appropriate level of clearance and need-to-know may request access to these reports through the DOE or appropriate Hanford contractor, following established written procedures. This data was collected for use by the Source Term Task Leader of the hanford Environmental Dose Reconstruction Project, to develop a source term for tritium to meet a 1994 milestone. The extraction quantities for the two campaigns are presented.

  10. Radiological training for tritium facilities

    SciTech Connect (OSTI)

    1996-12-01

    This program management guide describes a recommended implementation standard for core training as outlined in the DOE Radiological Control Manual (RCM). The standard is to assist those individuals, both within DOE and Managing and Operating contractors, identified as having responsibility for implementing the core training recommended by the RCM. This training may also be given to radiological workers using tritium to assist in meeting their job specific training requirements of 10 CFR 835.

  11. Quantitative fire risk assessment for a proposed tritium technology facility

    SciTech Connect (OSTI)

    Zeng, Y. )

    1991-01-01

    A new Tritium Technology Facility has been proposed for the Chalk River Laboratories to support fusion research and the commercial use of tritium. One of the major safety and licensing issues for the new facility raised by the internal Safety Review Committee is the potential hazard fire poses to it. Fire could cause a large release from tritium from the facility's metal tritide storage beds, resulting in conversion of elemental tritium (HT) into oxide tritium (HTO). The radiological hazard of HTO is {approximately}10,000 times higher than that of HT. Because of the potential significance of fire in the tritium facility, a quantitative fire risk assessment has been conducted for the proposed new facility. The frequency of a large tritium release due to a fire in the Tritium Technology Facility was assessed as being on the order of 10{sup {minus}5} per year, which satisfies the safety goal requirement of the facility.

  12. The Safety and Tritium Applied Research (STAR) Facility: Status-2004

    SciTech Connect (OSTI)

    Anderl, R.A.; Longhurst, G.R.; Pawelko, R.J.; Sharpe, J.P.; Schuetz, S.T.; Petti, D.A.

    2005-07-15

    The Safety and Tritium Applied Research (STAR) Facility, a US DOE National User Facility at the Idaho National Engineering and Environmental Laboratory (INEEL), comprises capabilities and infrastructure to support both tritium and non-tritium research activities important to the development of safe and environmentally friendly fusion energy. Research thrusts include (1) interactions of tritium and deuterium with plasma-facing-component (PFC) materials, (2) fusion safety issues [PFC material chemical reactivity and dust/debris generation, activation product mobilization, tritium behavior in fusion systems], and (3) molten salts and fusion liquids for tritium breeder and coolant applications. This paper updates the status of STAR and the capabilities for ongoing research activities, with an emphasis on the development, testing and integration of the infrastructure to support tritium research activities. Key elements of this infrastructure include a tritium storage and assay system, a tritium cleanup system to process glovebox and experiment tritiated effluent gases, and facility tritium monitoring systems.

  13. TRITIUM 2013

    Office of Environmental Management (EM)

    www-fusion-magnetique.cea.fr/tritium2013/index.html 1. Containment, safety, and environmental impact 2. Decontamination and waste management 3. Water and air detritiation 4. Tritium processing (purification, isotopic separation,...) 5. Tritium facilities and operation 6. Biological effects 7. Interactions with materials 8. Tracer technics and isotopic effects 9. Measurement, monitoring and accountancy 10. Tritium supply, transport and storage 11. Tritium breeding and extraction 12. Ot

  14. Independent Oversight Review, Savannah River Site Tritium Facilities - June

    Office of Environmental Management (EM)

    2012 | Department of Energy June 2012 Independent Oversight Review, Savannah River Site Tritium Facilities - June 2012 June 2012 Review of the Savannah River Site Tritium Facilities Implementation Verification Review Processes This report documents the results of an independent review of the implementation verification review (IVR) processes at the Department of Energy's (DOE) Savannah River Site Tritium Facilities. The review was conducted April 16-19, 2012, by the DOE Office of Safety and

  15. Tritium Irrigation Facility & Automated Vadose Zone Monitoring System |

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

    Savannah River Ecology Laboratory Tritium Irrigation Facility and Automated Vadose Monitoring System The opportunity to study tritium movement in a natural system presents a rare opportunity for both physical and biological research. Researchers may take advantage of tritium's properties as a conservative tracer for modeling contaminant transport, as a radioactive tracer for examining biological processes involving water, or as an example of radionuclide contaminant behavior in natural

  16. Independent Oversight Review, Savannah River Site Tritium Facilities -

    Office of Environmental Management (EM)

    December 2012 | Department of Energy December 2012 Independent Oversight Review, Savannah River Site Tritium Facilities - December 2012 December 2012 Review of Site Preparedness for Severe Natural Phenomena Events at the Savannah River Site Tritium Facilities The Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted an independent review of preparedness for severe natural phenomena events (NPEs) at the National Nuclear

  17. Measurement and Control Systems of Tritium Facilities for Scientific Research

    SciTech Connect (OSTI)

    Vinogradov, Yu.I.; Kuryakin, A.V.; Yukhimchuk, A.A.

    2005-07-15

    The technical approach, equipment and software developed during the creation of measurement and control systems for two complexes are described. The first one is a complex that prepares the gas mixture and targets of the 'TRITON' facility. The 'TRITON' facility is designed for studying muon catalyzed fusion reactions in triple mixtures of H/D/T hydrogen isotopes over wide ranges of temperature and pressure. The second one is 'ACCULINNA' - the liquid tritium target designed to investigate the neutron overloaded hydrogen and helium nuclei. These neutron-overloaded nuclei are produced in reactions of tritium beams on a heavy hydrogen and tritium target.

  18. Operational Readiness Review: Savannah River Replacement Tritium Facility

    SciTech Connect (OSTI)

    Not Available

    1993-02-01

    The Operational Readiness Review (ORR) is one of several activities to be completed prior to introducing tritium into the Replacement Tritium Facility (RTF) at the Savannah River Site (SRS). The Secretary of Energy will rely in part on the results of this ORR in deciding whether the startup criteria for RTF have been met. The RTF is a new underground facility built to safely service the remaining nuclear weapons stockpile. At RTF, tritium will be unloaded from old components, purified and enriched, and loaded into new or reclaimed reservoirs. The RTF will replace an aging facility at SRS that has processed tritium for more than 35 years. RTF has completed construction and is undergoing facility startup testing. The final stages of this testing will require the introduction of limited amounts of tritium. The US Department of Energy (DOE) ORR was conducted January 19 to February 4, 1993, in accordance with an ORR review plan which was developed considering previous readiness reviews. The plan also considered the Defense Nuclear Facilities Safety Board (DNFSB) Recommendations 90-4 and 92-6, and the judgements of experienced senior experts. The review covered three major areas: (1) Plant and Equipment Readiness, (2) Personnel Readiness, and (3) Management Systems. The ORR Team was comprised of approximately 30 members consisting of a Team Leader, Senior Safety Experts, and Technical Experts. The ORR objectives and criteria were based on DOE Orders, industry standards, Institute of Nuclear Power Operations guidelines, recommendations of external oversight groups, and experience of the team members.

  19. Tritium research activities in Safety and Tritium Applied Research (STAR) facility, Idaho National Laboratory

    Broader source: Energy.gov [DOE]

    Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013.

  20. NPH Risk Assessment and Mitigation of a SRS Facility for the Safe Storage of Tritium

    SciTech Connect (OSTI)

    Joshi, J.R.; Griffin, M.J.; Bjorkman, G.S.

    1995-10-18

    Because of the reduction in the nation`s stockpile of weapon systems a large amount of tritium is being returned to the Savannah River Site in Aiken, SC. Due to the increased quantity of tritium returning to SRS, the SRS Tritium Facility was tasked to determine the most cost effective means to safely store the tritium gas in a short period of time. This paper presents results of the risk assessment developed to evaluate the safe storage of tritium at SRS, and highlights the structural design of the HIVES used as the cost-effective short term NPH mitigation solution.

  1. Report of Survey of the Los Alamos Tritium Systems Test Assembly Facility |

    Office of Environmental Management (EM)

    Department of Energy the Los Alamos Tritium Systems Test Assembly Facility Report of Survey of the Los Alamos Tritium Systems Test Assembly Facility The purpose of this document is to report the results of a survey conducted at the Los Alamos Tritium Systems Test Assembly (TSTA Facility). The survey was conducted during the week of 3/20/00. The primary purpose of the survey is to identify facility conditions and issues that need to be addressed to transfer responsibility for the facility

  2. Electrolytic Tritium Extraction in Molten Li-LiT

    Broader source: Energy.gov [DOE]

    Presentation from the 36th Tritium Focus Group Meeting held in Los Alamos, New Mexico, November 3-5, 2015.

  3. NNSA TRITIUM SUPPLY CHAIN

    SciTech Connect (OSTI)

    Wyrick, Steven; Cordaro, Joseph; Founds, Nanette; Chambellan, Curtis

    2013-08-21

    Savannah River Site plays a critical role in the Tritium Production Supply Chain for the National Nuclear Security Administration (NNSA). The entire process includes: Production of Tritium Producing Burnable Absorber Rods (TPBARs) at the Westinghouse WesDyne Nuclear Fuels Plant in Columbia, South Carolina Production of unobligated Low Enriched Uranium (LEU) at the United States Enrichment Corporation (USEC) in Portsmouth, Ohio Irradiation of TPBARs with the LEU at the Tennessee Valley Authority (TVA) Watts Bar Reactor Extraction of tritium from the irradiated TPBARs at the Tritium Extraction Facility (TEF) at Savannah River Site Processing the tritium at the Savannah River Site, which includes removal of nonhydrogen species and separation of the hydrogen isotopes of protium, deuterium and tritium.

  4. REPORT OF SURVEY OF THE LOS ALAMOS TRITIUM SYSTEMS TEST ASSEMBLY FACILITY

    Office of Environmental Management (EM)

    REPORT OF SURVEY OF THE LOS ALAMOS TRITIUM SYSTEMS TEST ASSEMBLY FACILITY U.S. Department of Energy Office of Environmental Management & Office of Science Report of Survey of the Los Alamos Tritium Systems Test Assembly Facility Rev. E (Final) October 3, 2000 Contents 1. Introduction 1.1 Purpose 1.2 Facility Description 1.3 Organization Representatives 1.4 Survey Participants 2. Summary, Conclusions & Recommendations 2.1 Comparison With LCAM Requirements 2.2 Transfer Considerations 2.3

  5. Tritium Permeation Activity at Safety and Tritium Applied Research...

    Office of Environmental Management (EM)

    Research (STAR) Facility More Documents & Publications Tritium Behavior in Lead Lithium Eutectic (LLE) at Low Tritium Partial Pressure Tritium Plasma Experiment and Its Role...

  6. Tritium research activities in Safety and Tritium Applied Research...

    Office of Environmental Management (EM)

    research activities in Safety and Tritium Applied Research (STAR) facility, Idaho National Laboratory Tritium research activities in Safety and Tritium Applied Research (STAR)...

  7. Tritium Permeation Activity at Safety and Tritium Applied Research (STAR)

    Office of Environmental Management (EM)

    Facility | Department of Energy Permeation Activity at Safety and Tritium Applied Research (STAR) Facility Tritium Permeation Activity at Safety and Tritium Applied Research (STAR) Facility Presentation from the 34th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014. PDF icon Tritium Permeation Activity at Safety and Tritium Applied Research (STAR) Facility More Documents & Publications Tritium Behavior in Lead Lithium Eutectic (LLE) at Low Tritium Partial

  8. Independent Oversight Review, Savannah River Site Tritium Facilities...

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

    Facilities - June 2012 More Documents & Publications Technical Qualification Program Self-Assessment Report - Savannah River Site Office - 2011 Independent Oversight Review,...

  9. Tritium monitoring in groundwater and evaluation of model predictions for the Hanford Site 200 Area Effluent Treatment Facility

    SciTech Connect (OSTI)

    Barnett, D.B.; Bergeron, M.P.; Cole, C.R.; Freshley, M.D.; Wurstner, S.K.

    1997-08-01

    The Effluent Treatment Facility (ETF) disposal site, also known as the State-Approved Land Disposal Site (SALDS), receives treated effluent containing tritium, which is allowed to infiltrate through the soil column to the water table. Tritium was first detected in groundwater monitoring wells around the facility in July 1996. The SALDS groundwater monitoring plan requires revision of a predictive groundwater model and reevaluation of the monitoring well network one year from the first detection of tritium in groundwater. This document is written primarily to satisfy these requirements and to report on analytical results for tritium in the SALDS groundwater monitoring network through April 1997. The document also recommends an approach to continued groundwater monitoring for tritium at the SALDS. Comparison of numerical groundwater models applied over the last several years indicate that earlier predictions, which show tritium from the SALDS approaching the Columbia River, were too simplified or overly robust in source assumptions. The most recent modeling indicates that concentrations of tritium above 500 pCi/L will extend, at most, no further than {approximately}1.5 km from the facility, using the most reasonable projections of ETF operation. This extent encompasses only the wells in the current SALDS tritium-tracking network.

  10. NNSA Breaks Ground on Tritium Facilities at SRS | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Breaks Ground on Tritium Facilities at SRS | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs

  11. Microsoft PowerPoint - Tritium Gas Stream Scrubbing using In-situ Reactive Materials.pptx

    Office of Environmental Management (EM)

    Stream Scrubbing using In-situ Reactive Materials Paul Korinko, Simona Murph, and George Larsen Tritium Focus Group Meeting LANL Nov 3-5, 2015 SRNL-STI-2015-00597 Tritium Production and Extraction * Tritium Producing Burnable Absorber Rods (TPBARs) * Built to strict materials specifications * Coatings, ceramics, metals, processes * Meet NQA-1 requirements * Irradiated in a commercial light water reactor * Extracted at SRS in the Tritium Extraction Facility * Waste disposed on-site Contamination

  12. Tritium Focus Group Meeting:

    Office of Environmental Management (EM)

    32 nd Tritium Focus Group Meeting: Tritium research activities in Safety and Tritium Applied Research (STAR) facility, Idaho National Laboratory Masashi Shimada Fusion Safety Program, Idaho National Laboratory April 25 th 2013, Germantown, MD STI #: INL/MIS-13-28975 Outlines 1. Motivation of tritium research activity in STAR facility 2. Unique capabilities in STAR facility 3. Research highlights from tritium retention in HFIR neutron- irradiated tungsten April 25th 2013 Germantown, MD STAR

  13. Tritium monitor

    DOE Patents [OSTI]

    Chastagner, Philippe (Augusta, GA)

    1994-01-01

    A system for continuously monitoring the concentration of tritium in an aqueous stream. The system pumps a sample of the stream to magnesium-filled combustion tube which reduces the sample to extract hydrogen gas. The hydrogen gas is then sent to an isotope separation device where it is separated into two groups of isotopes: a first group of isotopes containing concentrations of deuterium and tritium, and a second group of isotopes having substantially no deuterium and tritium. The first group of isotopes containing concentrations of deuterium and tritium is then passed through a tritium detector that produces an output proportional to the concentration of tritium detected. Preferably, the detection system also includes the necessary automation and data collection equipment and instrumentation for continuously monitoring an aqueous stream.

  14. Tritium monitor

    DOE Patents [OSTI]

    Chastagner, P.

    1994-06-14

    A system is described for continuously monitoring the concentration of tritium in an aqueous stream. The system pumps a sample of the stream to magnesium-filled combustion tube which reduces the sample to extract hydrogen gas. The hydrogen gas is then sent to an isotope separation device where it is separated into two groups of isotopes: a first group of isotopes containing concentrations of deuterium and tritium, and a second group of isotopes having substantially no deuterium and tritium. The first group of isotopes containing concentrations of deuterium and tritium is then passed through a tritium detector that produces an output proportional to the concentration of tritium detected. Preferably, the detection system also includes the necessary automation and data collection equipment and instrumentation for continuously monitoring an aqueous stream. 1 fig.

  15. Tritium Permeation Activity at Safety and Tritium Applied

    Office of Environmental Management (EM)

    facility Masashi Shimada and Bob Pawelko Fusion Safety Program Idaho National Laboratory ... application 3. Tritium permeation for fusion application M.Shimada | Tritium Focus ...

  16. An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

    SciTech Connect (OSTI)

    P. Calderoni; P. Sharpe; M. Shimada

    2009-09-01

    The Safety, Tritium and Applied Research facility at the Idaho National Laboratory is a US Department of Energy National User Facility engaged in various aspects of materials research for nuclear applications related to fusion and advanced fission systems. Research activities are mainly focused on the interaction of tritium with materials, in particular plasma facing components, liquid breeders, high temperature coolants, fuel cladding, cooling and blanket structures and heat exchangers. Other activities include validation and verification experiments in support of the Fusion Safety Program, such as beryllium dust reactivity and dust transport in vacuum vessels, and support of Advanced Test Reactor irradiation experiments. This paper presents an overview of the programs engaged in the activities, which include the US-Japan TITAN collaboration, the US ITER program, the Next Generation Power Plant program and the tritium production program, and a presentation of ongoing experiments as well as a summary of recent results with emphasis on fusion relevant materials.

  17. Tritium 2013 Presentation | Department of Energy

    Office of Environmental Management (EM)

    3 Presentation Tritium 2013 Presentation Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013. PDF icon Tritium 2013 Presentation More Documents & Publications Meeting Attendance - 32nd Tritium Focus Group Meeting Tritium Sessions At The 2012 ANS Meeting Tritium research activities in Safety and Tritium Applied Research (STAR) facility, Idaho National Laboratory

  18. Tritium Permeation Activity at Safety and Tritium Applied

    Office of Environmental Management (EM)

    Permeation Activity at Safety and Tritium Applied Research (STAR) facility Masashi Shimada and Bob Pawelko Fusion Safety Program Idaho National Laboratory Tritium Focus Group meeting September 23-25, 2014 at Idaho National Laboratory, Idaho Falls, ID Outline: 1. Motivation of low tritium partial pressure permeation 2. Tritium permeation for fission application 3. Tritium permeation for fusion application M.Shimada | Tritium Focus Group meeting | Idaho Falls, ID | September 23-25, 2014 2

  19. Tritium Technology at CNL

    Office of Environmental Management (EM)

    1- UNRESTRICTED/ ILLIMITÉ Chalk River Tritium Activities: Select Topics Presented by Hugh Boniface Tritium Focus Group Meeting, Princeton, NJ, 2015 May -2- UNRESTRICTED/ ILLIMITÉ * Canadian Nuclear Labs - former AECL * New Tritium Facility * Tritium-resistant e-cell materials * Beta-voltaics * Helium-3 recovery Topics -3- UNRESTRICTED/ ILLIMITÉ * Main campus of Canadian Nuclear Labs - former AECL * Established 1952 Crown Corporation * 3100 employees (500 advanced degrees) * 600 M$ in revenue

  20. Tritium Behavior in Lead Lithium Eutectic (LLE) at Low Tritium Partial

    Office of Environmental Management (EM)

    Pressure | Department of Energy Behavior in Lead Lithium Eutectic (LLE) at Low Tritium Partial Pressure Tritium Behavior in Lead Lithium Eutectic (LLE) at Low Tritium Partial Pressure Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Tritium Behavior in Lead Lithium Eutectic (LLE) at Low Tritium Partial Pressure More Documents & Publications Tritium Permeation Activity at Safety and Tritium Applied Research (STAR) Facility

  1. Facility effluent monitoring plan for the Plutonium Uranium Extraction Facility

    SciTech Connect (OSTI)

    Greager, E.M.

    1997-12-11

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan will ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, at a minimum, every 3 years.

  2. Facility effluent monitoring plan for the plutonium uranium extraction facility

    SciTech Connect (OSTI)

    Wiegand, D.L.

    1994-09-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

  3. Tritium Detection Methods and Limitations

    Office of Environmental Management (EM)

    Detection Methods and Limitations Tritium Focus Group Meeting, April 2014 Tom Voss, Northern New Mexico DOE-HDBK-1105-2002 RADIOLOGICAL TRAINING FOR TRITIUM FACILITIES U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1105-2002 Radiological Training for Tritium Facilities U.S. Department of Energy, Radiological Control Programs for Special Tritium Compounds, DOE-STD- draft, Washington, D.C.

  4. Tritium R&D at AECL Selected Topics

    Office of Environmental Management (EM)

    Tritium R&D at AECL Selected Topics Tritium Focus Group Meeting, Savannah River Site 2014 April 22-24 Hugh Boniface Chalk River Laboratories, Ontario, CANADA Outline of Presentation * Introduction & Background * Tritium Facilities: Laboratories, old and new * Tritium Separations: CECE process * Tritium Properties: Materials * Tritium Exploitation: Batteries, Helium-3 * Other work: Education, environment, biology, fusion, hydrogen UNRESTRICTED / ILLIMITÉ 2 Background UNRESTRICTED /

  5. Tritium Operation Improvements at the Idaho National Laboratory (INL)

    Office of Environmental Management (EM)

    Safety and Tritium Applied Research (STAR) facility | Department of Energy Operation Improvements at the Idaho National Laboratory (INL) Safety and Tritium Applied Research (STAR) facility Tritium Operation Improvements at the Idaho National Laboratory (INL) Safety and Tritium Applied Research (STAR) facility Presentation from the 35th Tritium Focus Group Meeting held in Princeton, New Jersey on May 05-07, 2015. PDF icon Tritium Operation Improvements at the INL STAR facility More Documents

  6. Corrosion within the Z-Bed Recovery Systems at the Savannah River Site’s Tritium Facilities

    Broader source: Energy.gov [DOE]

    Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013.

  7. Fermilab | Tritium at Fermilab | Tritium in Sanitary Sewers

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

    Tritium in Sanitary Sewers chart graphic As part of our environmental monitoring program, we routinely sample our sanitary sewer water that is discharged to wastewater treatment systems in the cities of Batavia and Warrenville. Samples taken from sanitary sewer water discharged to the Batavia Wastewater Treatment Facility show small but measurable levels of tritium. All tritium levels found on site are well below any federal health and environmental standards. No tritium has been detected in

  8. 34th Tritium Focus Group Meeting, Idaho National Laboratory,...

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

    Permeation Activity at Safety and Tritium Applied Research (STAR) Facility Validation of Hydrogen Exchange Methodology on Molecular Sieves for Tritium Removal from ...

  9. Demonstration of High Performance in Layered Deuterium-Tritium Capsule Implosions in Uranium Hohlraums at the National Ignition Facility

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

    Döppner, T.; Callahan, D. A.; Hurricane, O. A.; Hinkel, D. E.; Ma, T.; Park, H. -S.; Berzak Hopkins, L. F.; Casey, D. T.; Celliers, P. P.; Dewald, E. L.; et al

    2015-07-28

    We report on the first layered deuterium-tritium (DT) capsule implosions indirectly driven by a “highfoot” laser pulse that were fielded in depleted uranium hohlraums at the National Ignition Facility. Recently, high-foot implosions have demonstrated improved resistance to ablation-front Rayleigh-Taylor instability induced mixing of ablator material into the DT hot spot [Hurricane et al., Nature (London) 506, 343 (2014)]. Uranium hohlraums provide a higher albedo and thus an increased drive equivalent to an additional 25 TW laser power at the peak of the drive compared to standard gold hohlraums leading to higher implosion velocity. Additionally, we observe an improved hot-spot shapemore » closer to round which indicates enhanced drive from the waist. In contrast to findings in the National Ignition Campaign, now all of our highest performing experiments have been done in uranium hohlraums and achieved total yields approaching 1016 neutrons where more than 50% of the yield was due to additional heating of alpha particles stopping in the DT fuel.« less

  10. Demonstration of High Performance in Layered Deuterium-Tritium Capsule Implosions in Uranium Hohlraums at the National Ignition Facility

    SciTech Connect (OSTI)

    Döppner, T.; Callahan, D. A.; Hurricane, O. A.; Hinkel, D. E.; Ma, T.; Park, H. -S.; Berzak Hopkins, L. F.; Casey, D. T.; Celliers, P. P.; Dewald, E. L.; Dittrich, T. R.; Haan, S.; Kritcher, A. L.; MacPhee, A.; Le Pape, S.; Pak, A.; Patel, P. K.; Springer, P. T.; Salmonson, J. D.; Tommasini, R.; Benedetti, L. R.; Bond, E.; Bradley, D. K.; Caggiano, J.; Church, J.; Dixit, S.; Edgell, D.; Edwards, M. J.; Fittinghoff, D. N.; Frenje, J.; Gatu Johnson, M.; Grim, G.; Hatarik, R.; Havre, M.; Herrmann, H.; Izumi, N.; Khan, S. F.; Kline, J. L.; Knauer, J.; Kyrala, G. A.; Landen, O. L.; Merrill, F. E.; Moody, J.; Moore, A. S.; Nikroo, A.; Ralph, J. E.; Remington, B. A.; Robey, H.; Sayre, D.; Schneider, M.; Streckert, H.; Town, R.; Turnbull, D.; Volegov, P. L.; Wan, A.; Widmann, K.; Wilde, C. H.; Yeamans, C.

    2015-07-28

    We report on the first layered deuterium-tritium (DT) capsule implosions indirectly driven by a “highfoot” laser pulse that were fielded in depleted uranium hohlraums at the National Ignition Facility. Recently, high-foot implosions have demonstrated improved resistance to ablation-front Rayleigh-Taylor instability induced mixing of ablator material into the DT hot spot [Hurricane et al., Nature (London) 506, 343 (2014)]. Uranium hohlraums provide a higher albedo and thus an increased drive equivalent to an additional 25 TW laser power at the peak of the drive compared to standard gold hohlraums leading to higher implosion velocity. Additionally, we observe an improved hot-spot shape closer to round which indicates enhanced drive from the waist. In contrast to findings in the National Ignition Campaign, now all of our highest performing experiments have been done in uranium hohlraums and achieved total yields approaching 1016 neutrons where more than 50% of the yield was due to additional heating of alpha particles stopping in the DT fuel.

  11. Storage and Assay of Tritium in STAR

    SciTech Connect (OSTI)

    Longhurst, Glen R.; Anderl, Robert A.; Pawelko, Robert J.; Stoots, Carl J.

    2005-07-15

    The Safety and Tritium Applied Research (STAR) facility at the Idaho National Engineering and Environmental Laboratory (INEEL) is currently being commissioned to investigate tritium-related safety questions for fusion and other technologies. The tritium inventory for the STAR facility will be maintained below 1.5 g to avoid the need for STAR to be classified as a Category 3 nuclear facility. A key capability in successful operation of the STAR facility is the ability to receive, inventory, and dispense tritium to the various experiments underway there. The system central to that function is the Tritium Storage and Assay System (SAS).The SAS has four major functions: (1) receiving and holding tritium, (2) assaying, (3) dispensing, and (4) purifying hydrogen isotopes from non-hydrogen species.This paper describes the design and operation of the STAR SAS and the procedures used for tritium accountancy in the STAR facility.

  12. Independent Oversight Review, Savannah River Field Office Tritium

    Office of Environmental Management (EM)

    Facilities - November 2013 | Department of Energy Field Office Tritium Facilities - November 2013 Independent Oversight Review, Savannah River Field Office Tritium Facilities - November 2013 November 13, 2013 Review of Savannah River Field Office Tritium Facilities Radiological Controls Activity-Level Implementation This report documents the results of an independent oversight review of the radiological protection program at the Savannah River Site (SRS) tritium facilities implemented at the

  13. Tritium High Vacuum Pump Test Plan | Department of Energy

    Office of Environmental Management (EM)

    High Vacuum Pump Test Plan Tritium High Vacuum Pump Test Plan Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Tritium High Vacuum Pump Test Plan More Documents & Publications Normetex Pump Replacement Tritium Operation Improvements at the Idaho National Laboratory (INL) Safety and Tritium Applied Research (STAR) facility Fusion Nuclear Science and Technology Program - Status and Plans for Tritium Research

  14. Overview of tritium activity in Japan | Department of Energy

    Office of Environmental Management (EM)

    tritium activity in Japan Overview of tritium activity in Japan Presentation from the 34th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014. PDF icon Overview of tritium activity in Japan More Documents & Publications Tritium research activities in Safety and Tritium Applied Research (STAR) facility, Idaho National Laboratory Percolation behavior of tritiated water into a soil packed bed Technological Assessment of Plasma Facing Components for DEMO Reactors

  15. Material Control & Accountability for Department Of Energy (DOE) Tritium

    Energy Savers [EERE]

    Facilities | Department of Energy Material Control & Accountability for Department Of Energy (DOE) Tritium Facilities Material Control & Accountability for Department Of Energy (DOE) Tritium Facilities Presentation from the 35th Tritium Focus Group Meeting held in Princeton, New Jersey on May 05-07, 2015. PDF icon Material Control & Accountability for Department Of Energy (DOE) Tritium Facilities More Documents & Publications Managing Legacy Materials at WETF Inspection

  16. Tritium 2016

    Office of Environmental Management (EM)

    2016 11 TH International Conference on Tritium Science and Technology Robert Addis Director, Defense Programs Technology, SRNL Tritium Focus Group Meeting. Savannah River Site, Aiken, SC 29808 April 22, 2014 History of International Conference on Tritium Science and Technology Publication Pub Date * 1 st 1980 Dayton, USA * 2 nd 1985 Dayton, USA Fusion Tech 8, 2 (1985) * 3 rd 1988 Toronto, Canada Fusion Tech 14, 2 (1988) * 4 th 1991 Albuquerque, USA Fusion Tech 21, 2 (1992) * 5 th 1995 Belgirate,

  17. Tritium breeding materials

    SciTech Connect (OSTI)

    Hollenberg, G.W.; Johnson, C.E.; Abdou, M.

    1984-03-01

    Tritium breeding materials are essential to the operation of D-T fusion facilities. Both of the present options - solid ceramic breeding materials and liquid metal materials are reviewed with emphasis not only on their attractive features but also on critical materials issues which must be resolved.

  18. Evaluation of tritium release properties of advanced tritium breeders

    SciTech Connect (OSTI)

    Hoshino, T.; Ochiai, K.; Edao, Y.; Kawamura, Y.

    2015-03-15

    Demonstration power plant (DEMO) fusion reactors require advanced tritium breeders with high thermal stability. Lithium titanate (Li{sub 2}TiO{sub 3}) advanced tritium breeders with excess Li (Li{sub 2+x}TiO{sub 3+y}) are stable in a reducing atmosphere at high temperatures. Although the tritium release properties of tritium breeders are documented in databases for DEMO blanket design, no in situ examination under fusion neutron (DT neutron) irradiation has been performed. In this study, a preliminary examination of the tritium release properties of advanced tritium breeders was performed, and DT neutron irradiation experiments were performed at the fusion neutronics source (FNS) facility in JAEA. Considering the tritium release characteristics, the optimum grain size after sintering is <5 μm. From the results of the optimization of granulation conditions, prototype Li{sub 2+x}TiO{sub 3+y} pebbles with optimum grain size (<5 μm) were successfully fabricated. The Li{sub 2+x}TiO{sub 3+y} pebbles exhibited good tritium release properties similar to the Li{sub 2}TiO{sub 3} pebbles. In particular, the released amount of HT gas for easier tritium handling was higher than that of HTO water. (authors)

  19. Storage and Assay of Tritium in STAR

    SciTech Connect (OSTI)

    Glen R. Longhurst; Robert A. Anderl; Robert J. Pawelko

    2004-09-01

    The Safety and Tritium Applied Research (STAR) facility has recently been commissioned to investigate tritium-related safety questions for fusion and other technologies. The authorized inventory of tritium is 1.6 grams, the threshold quantity for nuclear facility classification. A key capability in successful operation of the STAR facility is the ability to receive, inventory, and dispense tritium to the various experiments underway there. The system central to that function is the Tritium Storage and Assay System (SAS). The SAS has four major functions: (1) receiving and holding tritium from shipping containers brought into the STAR facility, (2) assaying the amount of tritium in the SAS, (3) dispensing tritium to secondary beds or containers used for transferring it to the experimental systems in the STAR facility, and (4) purifying hydrogen isotopes from non-hydrogen species. To that may be added a fifth, optional function, isotopic separation of hydrogen isotopes using bed-to-bed transfer techniques. This paper documents the design and operation of the STAR SAS and the procedures used for tritium accountancy in the STAR facility.

  20. tritium1120

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

    SUMMARY REPORT ON INSPECTION OF ISSUES ASSOCIATED WITH THE DEPARTMENT OF ENERGY' S TRITIUM SOURCE SELECTION PROCESS NOVEMBER 1998 DOE/IG-0431 U.S. DEPARTMENT OF ENERGY OFFICE OF INSPECTOR GENERAL OFFICE OF INSPECTIONS INSPECTION REPORT November 23, 1999 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman /s/ Inspector General SUBJECT: INFORMATION: Summary Report on "Inspection of Issues Associated With the Department of Energy' s Tritium Source Selection Process" BACKGROUND The

  1. Tritium Instrument Demonstration Station (TIDS)

    Office of Environmental Management (EM)

    Cortés Concepción, Laura Tovo April 22, 2014 Tritium Focus Group Meeting SRNL-STI-2014-00172 What is the challenge? Tritium Facilities is critically reliant on dated analytical technologies Low-mass, high-resolution mass spectrometer issues: * Near end-of-life (30+ years old) * Spare parts not available from vendor * Vendor support is difficult or unavailable Need for alternative, accessible analytical technologies within DP for: * Complement current analytical methods * Greater ability to

  2. Use of system code to estimate equilibrium tritium inventory in fusion DT machines, such as ARIES-AT and components testing facilities

    SciTech Connect (OSTI)

    C.P.C. Wong; B. Merrill

    2014-10-01

    ITER is under construction and will begin operation in 2020. This is the first 500 MWfusion class DT device, and since it is not going to breed tritium, it will consume most of the limited supply of tritium resources in the world. Yet, in parallel, DT fusion nuclear component testing machines will be needed to provide technical data for the design of DEMO. It becomes necessary to estimate the tritium burn-up fraction and corresponding initial tritium inventory and the doubling time of these machines for the planning of future supply and utilization of tritium. With the use of a system code, tritium burn-up fraction and initial tritium inventory for steady state DT machines can be estimated. Estimated tritium burn-up fractions of FNSF-AT, CFETR-R and ARIES-AT are in the range of 12.8%. Corresponding total equilibrium tritium inventories of the plasma flow and tritium processing system, and with the DCLL blanket option are 7.6 kg, 6.1 kg, and 5.2 kg for ARIES-AT, CFETR-R and FNSF-AT, respectively.

  3. Independent Oversight Review, Savannah River Field Office Tritium...

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

    2013 Review of Savannah River Field Office Tritium Facilities Radiological Controls Activity-Level Implementation This report documents the results of an independent oversight...

  4. Disposal of tritium-exposed metal hydrides

    SciTech Connect (OSTI)

    Nobile, A.; Motyka, T.

    1991-01-01

    A plan has been established for disposal of tritium-exposed metal hydrides used in Savannah River Site (SRS) tritium production or Materials Test Facility (MTF) R D operations. The recommended plan assumes that the first tritium-exposed metal hydrides will be disposed of after startup of the Solid Waste Disposal Facility (SWDF) Expansion Project in 1992, and thus the plan is consistent with the new disposal requiremkents that will be in effect for the SWDF Expansion Project. Process beds containing tritium-exposed metal hydride powder will be disposed of without removal of the powder from the bed; however, disposal of tritium-exposed metal hydride powder that has been removed from its process vessel is also addressed.

  5. Disposal of tritium-exposed metal hydrides

    SciTech Connect (OSTI)

    Nobile, A.; Motyka, T.

    1991-12-31

    A plan has been established for disposal of tritium-exposed metal hydrides used in Savannah River Site (SRS) tritium production or Materials Test Facility (MTF) R&D operations. The recommended plan assumes that the first tritium-exposed metal hydrides will be disposed of after startup of the Solid Waste Disposal Facility (SWDF) Expansion Project in 1992, and thus the plan is consistent with the new disposal requiremkents that will be in effect for the SWDF Expansion Project. Process beds containing tritium-exposed metal hydride powder will be disposed of without removal of the powder from the bed; however, disposal of tritium-exposed metal hydride powder that has been removed from its process vessel is also addressed.

  6. Experiences with decontaminating tritium-handling apparatus

    SciTech Connect (OSTI)

    Maienschein, J.L.; Garcia, F.; Garza, R.G.; Kanna, R.L.; Mayhugh, S.R.; Taylor, D.T. )

    1992-03-01

    Tritium-handling apparatus has been decontaminated as part of the downsizing of the LLNL Tritium Facility. Two stainless-steel glove boxes that had been used to process lithium deuteride-tritide (LiDT) slat were decontaminated using the Portable Cleanup System so that they could be flushed with room air through the facility ventilation system. In this paper the details on the decontamination operation are provided. A series of metal (palladium and vanadium) hydride storage beds have been drained of tritium and flushed with deuterium, in order to remove as much tritium as possible. The bed draining and flushing procedure is described, and a calculational method is presented which allows estimation of the tritium remaining in a bed after it has been drained and flushed. Data on specific bed draining and flushing are given.

  7. Facility effluent monitoring plan for the plutonium-uranium extraction facility

    SciTech Connect (OSTI)

    Lohrasbi, J.; Johnson, D.L.; De Lorenzo, D.S.

    1993-12-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

  8. Tritium handling in vacuum systems

    SciTech Connect (OSTI)

    Gill, J.T. [Monsanto Research Corp., Miamisburg, OH (United States). Mound Facility; Coffin, D.O. [Los Alamos National Lab., NM (United States)

    1986-10-01

    This report provides a course in Tritium handling in vacuum systems. Topics presented are: Properties of Tritium; Tritium compatibility of materials; Tritium-compatible vacuum equipment; and Tritium waste treatment.

  9. TRITIUM SESSIONS AT THE

    Office of Environmental Management (EM)

    TRITIUM IN FISSION AND FUSION sponsored by IRD; cosponsored by BMD Session Organizer and Chair: Tom Voss (Cybermesa) Discussion of Tritium Safety in Fusion Reactors, Satoshi ...

  10. 1997 evaluation of tritium removal and mitigation technologies for Hanford Site wastewaters

    SciTech Connect (OSTI)

    Jeppson, D.W.; Biyani, R.K.; Duncan, J.B.; Flyckt, D.L.; Mohondro, P.C.; Sinton, G.L.

    1997-07-24

    This report contains results of a biennial assessment of tritium separation technology and tritium nitration techniques for control of tritium bearing wastewaters at the Hanford Site. Tritium in wastewaters at Hanford have resulted from plutonium production, fuel reprocessing, and waste handling operations since 1944. this assessment was conducted in response to the Hanford Federal Facility Agreement and Consent Order.

  11. EA-0874: Low-level Waste Drum Staging Building at Weapons Engineering Tritium Facility, TA-16 Los Alamos National Laboratory, Los Alamos, New Mexico

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of a proposal to place a 3 meter (m) by 4.5 m prefabricated storage building (transportainer) adjacent to the existing Weapons Engineering Tritium...

  12. Tritium glovebox stripper system seismic design evaluation

    SciTech Connect (OSTI)

    Grinnell, J. J.; Klein, J. E.

    2015-09-01

    The use of glovebox confinement at US Department of Energy (DOE) tritium facilities has been discussed in numerous publications. Glovebox confinement protects the workers from radioactive material (especially tritium oxide), provides an inert atmosphere for prevention of flammable gas mixtures and deflagrations, and allows recovery of tritium released from the process into the glovebox when a glovebox stripper system (GBSS) is part of the design. Tritium recovery from the glovebox atmosphere reduces emissions from the facility and the radiological dose to the public. Location of US DOE defense programs facilities away from public boundaries also aids in reducing radiological doses to the public. This is a study based upon design concepts to identify issues and considerations for design of a Seismic GBSS. Safety requirements and analysis should be considered preliminary. Safety requirements for design of GBSS should be developed and finalized as a part of the final design process.

  13. Continuous aqueous tritium monitor

    DOE Patents [OSTI]

    McManus, Gary J. (Idaho Falls, ID); Weesner, Forrest J. (Idaho Falls, ID)

    1989-05-30

    An apparatus for a selective on-line determination of aqueous tritium concentration is disclosed. A moist air stream of the liquid solution being analyzed is passed through a permeation dryer where the tritium and moisture and selectively removed to a purge air stream. The purge air stream is then analyzed for tritium concentration, humidity, and temperature, which allows computation of liquid tritium concentration.

  14. Tritium Behavior in Lead Lithium Eutectic (LLE) at Low Tritium...

    Office of Environmental Management (EM)

    Behavior in Lead Lithium Eutectic (LLE) at Low Tritium Partial Pressure Tritium Behavior in Lead Lithium Eutectic (LLE) at Low Tritium Partial Pressure Presentation from the 33rd...

  15. EXTRACTION OF FRACTURE-MECHANICS AND TRANSMISSION-ELECTRON-MICROSCOPY SAMPLES FROM TRITIUM-EXPOSED RESERVOIRS USING ELECTRIC-DISCHARGE MACHINING

    SciTech Connect (OSTI)

    Morgan, M; Ken Imrich, K; Michael Tosten, M

    2006-08-31

    The Enhanced Surveillance Campaign is funding a program to investigate tritium aging effects on the structural properties of tritium reservoir steels. The program is designed to investigate how the structural properties of reservoir steels change during tritium service and to examine the role of microstructure and reservoir manufacturing on tritium compatibility. New surveillance tests are also being developed that can better gauge the long-term effects of tritium and its radioactive decay product, helium-3, on the properties of reservoir steels. In order to conduct these investigations, three types of samples are needed from returned reservoirs: tensile, fracture mechanics, and transmission-electron microscopy (TEM). An earlier report demonstrated how the electric-discharge machining (EDM) technique can be used for cutting tensile samples from serial sections of a 3T reservoir and how yield strength, ultimate strength and elongation could be measured from those samples. In this report, EDM was used successfully to section sub-sized fracture-mechanics samples from the inner and outer walls of a 3T reservoir and TEM samples from serial sections of a 1M reservoir. This report fulfills the requirements for the FY06 Level 3 milestone, TSR 15.1 ''Cut Fracture-Mechanics Samples from Tritium-Exposed Reservoir'' and TSR 15.2 ''Cut Transmission-electron-microscopy foils from Tritium-Exposed Reservoir'' for the Enhance Surveillance Campaign (ESC). This was in support of ESC L2-1870 Milestone-''Provide aging and lifetime assessments of selected components and materials for multiple enduring stockpile systems''.

  16. Pf/Zeolite Catalyst for Tritium Stripping

    SciTech Connect (OSTI)

    Hsu, R.H.

    2001-03-26

    This report described promising hydrogen (protium and tritium) stripping results obtained with a Pd/zeolite catalyst at ambient temperature. Preliminary results show 90-99+ percent tritium stripping efficiency may be obtained, with even better performance expected as bed configuration and operating conditions are optimized. These results suggest that portable units with single beds of the Pd/zeolite catalyst may be utilized as ''catalytic absorbers'' to clean up both tritium gas and tritiated water. A cart-mounted prototype stripper utilizing this catalyst has been constructed for testing. This portable stripper has potential applications in maintenance-type jobs such as tritium line breaks. This catalyst can also potentially be utilized in an emergency stripper for the Replacement Tritium Facility.

  17. Radiological Training for Tritium Facilities

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

    Available to the public from the U.S. Department ... certification by the American Board of Health Physics andor ... Particles, Health Physics Journal, September (2001). ...

  18. Radiological Training for Tritium Facilities

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

    ... and Managing and Operating (M&O) contractors, identified as ... line management and their subordinates. The training function can be performed by a separate training organization, but ...

  19. Tritium handling experience at Atomic Energy of Canada Limited

    SciTech Connect (OSTI)

    Suppiah, S.; McCrimmon, K.; Lalonde, S.; Ryland, D.; Boniface, H.; Muirhead, C.; Castillo, I.

    2015-03-15

    Canada has been a leader in tritium handling technologies as a result of the successful CANDU reactor technology used for power production. Over the last 50 to 60 years, capabilities have been established in tritium handling and tritium management in CANDU stations, tritium removal processes for heavy and light water, tritium measurement and monitoring, and understanding the effects of tritium on the environment. This paper outlines details of tritium-related work currently being carried out at Atomic Energy of Canada Limited (AECL). It concerns the CECE (Combined Electrolysis and Catalytic Exchange) process for detritiation, tritium-compatible electrolysers, tritium permeation studies, and tritium powered batteries. It is worth noting that AECL offers a Tritium Safe-Handling Course to national and international participants, the course is a mixture of classroom sessions and hands-on practical exercises. The expertise and facilities available at AECL is ready to address technological needs of nuclear fusion and next-generation nuclear fission reactors related to tritium handling and related issues.

  20. Disposal of tritium residues at the Los Alamos National Laboratory. Audit repost

    SciTech Connect (OSTI)

    NONE

    1998-07-01

    The objective of this audit was to determine whether Los Alamos disposed of wastewater containing tritium residues in a safe and cost-effective manner subsequent to an October 1991 report reviewing tritium facility management practices.

  1. Tritium High Vacuum Pump Test Plan

    Office of Environmental Management (EM)

    High Vacuum Pump Test Plan Tritium Programs Engineering Louis Boone Joel Bennett M-TRT-H-00088 Rev 0 Date: 4/10/2014 Tritium Facilities Savannah River Nuclear Solutions, LLC Scope * Comparison of Normetex vs. Eumeca/ Air Squared/ Edwards/ Busch * Ultimate Vacuum * Develop Flow Curve * Provide basis for selecting the Normetex Pump Replacement Performance * Flow Rate - 9 cfm at 3 torr inlet pressure * Ultimate Vacuum Pressure - Acceptable: Less than 0.01 torr at discharge pressure of 30 torr -

  2. Tritium Focus Group

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

    matters related to tritium. Contacts Mike Rogers (505) 665-2513 Email Chandra Savage Marsden (505) 664-0183 Email The Tritium Focus Group consists of participants from member...

  3. Bulk Tritium Shipping Package

    Office of Energy Efficiency and Renewable Energy (EERE)

    Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013.

  4. TRITIUM SESSIONS AT THE

    Office of Environmental Management (EM)

    SESSIONS AT THE 2012 ANS MEETING James T (Tom) Voss April 24, 2013 Presented at the 2013 U. S. DOE Tritium Focus Group Meeting TRITIUM IN FISSION AND FUSION sponsored by IRD; cosponsored by BMD Session Organizer and Chair: Tom Voss (Cybermesa) Discussion of Tritium Safety in Fusion Reactors, Satoshi Fukada (Kyushu Univ) Commercial Light Water Production of Tritium: Update and Path Forward, Cheryl K. Thornhill (PNNL) Neutronics Experiments for the European ITER Test Blanket Modules, A. Klix -

  5. Fermilab | Tritium at Fermilab

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

    Feature photo Tritium is a weakly radioactive form of hydrogen. In nature, it's formed when cosmic particles hit Earth's atmosphere. Here at Fermilab, tritium is an expected byproduct of the operation of our particle accelerators. This website provides information on the monitoring and management of tritium at Fermilab. Small but detectable levels of tritium - well below regulatory limits - are found in some ponds on the Fermilab site, in Indian Creek as it leaves the laboratory and in some of

  6. Continuous aqueous tritium monitor

    DOE Patents [OSTI]

    McManus, G.J.; Weesner, F.J.

    1987-10-19

    An apparatus for a selective on-line determination of aqueous tritium concentration is disclosed. A moist air stream of the liquid solution being analyzed is passed through a permeation dryer where the tritium and moisture are selectively removed to a purge air stream. The purge air stream is then analyzed for tritium concentration, humidity, and temperature, which allows computation of liquid tritium concentration. 2 figs.

  7. Development of tritium technologies at KAERI

    SciTech Connect (OSTI)

    Chung, H.; Koo, D.; Lee, J.; Park, J.; Yim, S.P.; Yoon, C.; Lim, J.; Choi, W.; Ahn, H.; Kang, H.; Kim, I.; Paek, S.; Yunn, S.H.; Jung, K.J.

    2015-03-15

    Korea has been operating a CANDU nuclear power plant since 1983. Tritium generated in the heavy water of the plant is removed by the Wolsong TRF (Tritium Removal Facility) and measurement campaigns of tritium near the power plant have shown the efficiency of the TRF system. The HANARO reactor uses heavy water as both reflector and moderator. In HANARO the tritiated water removal system consists of compressors, condensers, and adsorption beds. A tritium behavior analysis code (TRIBAC) for a Very High Temperature Gas-Cooled Reactor (VHTR) is under development at KAERI. The TRIBAC computer software has been equipped with models for tritium production, purification, and leakage, as well as chemisorption and tritium behavior, in the hydrogen production system. Korea takes part into the ITER program and is responsible for the supply of an SDS (Tritium Storage and Delivery System). Within this program Korea has launched an experimental program to study the physico-chemical properties of metal and their hydrides in which hydrogen isotope gases can be stored and removed safely.

  8. Tritium 2016 11TH International Conference on Tritium Science and

    Office of Environmental Management (EM)

    Technology | Department of Energy 6 11TH International Conference on Tritium Science and Technology Tritium 2016 11TH International Conference on Tritium Science and Technology Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Tritium 2016 11TH International Conference on Tritium Science and Technology More Documents & Publications Advanced Polymers for Tritium Service A New Hydrogen Processing Demonstration System

  9. PDRD (SR13046) TRITIUM PRODUCTION FINAL REPORT

    SciTech Connect (OSTI)

    Smith, P.; Sheetz, S.

    2013-09-30

    Utilizing the results of Texas A&M University (TAMU) senior design projects on tritium production in four different small modular reactors (SMR), the Savannah River National Laboratory’s (SRNL) developed an optimization model evaluating tritium production versus uranium utilization under a FY2013 plant directed research development (PDRD) project. The model is a tool that can evaluate varying scenarios and various reactor designs to maximize the production of tritium per unit of unobligated United States (US) origin uranium that is in limited supply. The primary module in the model compares the consumption of uranium for various production reactors against the base case of Watts Bar I running a nominal load of 1,696 tritium producing burnable absorber rods (TPBARs) with an average refueling of 41,000 kg low enriched uranium (LEU) on an 18 month cycle. After inputting an initial year, starting inventory of unobligated uranium and tritium production forecast, the model will compare and contrast the depletion rate of the LEU between the entered alternatives. This is an annual tritium production rate of approximately 0.059 grams of tritium per kilogram of LEU (g-T/kg-LEU). To date, the Nuclear Regulatory Commission (NRC) license has not been amended to accept a full load of TPBARs so the nominal tritium production has not yet been achieved. The alternatives currently loaded into the model include the three light water SMRs evaluated in TAMU senior projects including, mPower, Holtec and NuScale designs. Initial evaluations of tritium production in light water reactor (LWR) based SMRs using optimized loads TPBARs is on the order 0.02-0.06 grams of tritium per kilogram of LEU used. The TAMU students also chose to model tritium production in the GE-Hitachi SPRISM, a pooltype sodium fast reactor (SFR) utilizing a modified TPBAR type target. The team was unable to complete their project so no data is available. In order to include results from a fast reactor, the SRNL Technical Advisory Committee (TAC) ran a Monte Carlo N-Particle (MCNP) model of a basic SFR for comparison. A 600MWth core surrounded by a lithium blanket produced approximately 1,000 grams of tritium annually with a 13% enriched, 6 year core. This is similar results to a mid-1990’s study where the Fast Flux Test Facility (FFTF), a 400 MWth reactor at the Idaho National Laboratory (INL), could produce about 1,000 grams with an external lithium target. Normalized to the LWRs values, comparative tritium production for an SFR could be approximately 0.31 g-T/kg LEU.

  10. Tritium Plasma Experiment and

    Office of Environmental Management (EM)

    Plasma Experiment and its role in PHENIX program Masashi Shimada, Chase Taylor Fusion Safety Program Idaho National Laboratory Rob Kolasinski Sandia National Laboratories, Livermore Tritium Focus Group meeting September 23-25, 2014 at Idaho National Laboratory, Idaho Falls, ID Outline: 1. Motivation 2. Tritium Plasma Experiment 3. INL/STAR's role on US-Japan collaboration 4. Role of TPE in PHENIX project 5. TPE modification and development of plasma-driven permeation M.Shimada | Tritium Focus

  11. Tritium Plasma Experiment and

    Office of Environmental Management (EM)

    Plasma Experiment and its role in PHENIX program Masashi Shimada, Chase Taylor Fusion ... in metal - Tritium behavior in the fusion nuclear environment is not fully ...

  12. Tritium 2016 11TH International Conference on Tritium Science...

    Office of Environmental Management (EM)

    Conference on Tritium Science and Technology More Documents & Publications Advanced Polymers for Tritium Service A New Hydrogen Processing Demonstration System Hydrogen Isotope...

  13. Microsoft PowerPoint - Tritium Design Practice.ppt

    Office of Environmental Management (EM)

    ASME B31.3 process piping code, ASME Boiler and Pressure Vessel Code Section VIII and Section II 3 SRS INTERNAL REFERENCES PB Moore, WSRC-RP-98-00009, "Tritium Facilities Design ...

  14. Experiences with decontaminating tritium-handling apparatus

    SciTech Connect (OSTI)

    Maienschein, J.L.; Garcia, F.; Garza, R.G.; Kanna, R.L.; Mayhugh, S.R.; Taylor, D.T.

    1991-07-01

    Tritium-handling apparatus has been decontaminated as part of the shutdown of the LLNL Tritium Facility. Two stainless-steel gloveboxes that had been used to process lithium deuteride-tritide (LiDT) salt were decontaminated using the Portable Cleanup System so that they could be flushed with room air through the facility ventilation system. Further surface decontamination was performed by scrubbing the interior with paper towels and ethyl alcohol or Swish{trademark}. The surface contamination, as shown by swipe surveys, was reduced from 4{times}10{sup 4}--10{sup 6} disintegrations per minute (dpm)/cm{sup 2} to 2{times}10{sup 2}--4{times}10{sup 4} dpm/cm{sup 2}. Details on the decontamination operation are provided. A series of metal (palladium and vanadium) hydride storage beds have been drained of tritium and flushed with deuterium in order to remove as much tritium as possible. The bed draining and flushing procedure is described, and a calculational method is presented which allows estimation of the tritium remaining in a bed after it has been drained and flushed. Data on specific bed draining and flushing are given.

  15. Methods for tritium labeling

    SciTech Connect (OSTI)

    Andres, Hendrik; Morimoto, Hiromi; Williams, Philip G.

    1993-01-01

    Reagents and processes for reductively introducing deuterium or tritium into organic molecules are described. The reagents are deuterium or tritium analogs of trialkyl boranes, borane or alkali metal aluminum hydrides. The process involves forming these reagents in situ from alkali metal tritides or deuterides.

  16. Oxidative Tritium Decontamination System

    DOE Patents [OSTI]

    Gentile, Charles A. (Plainsboro, NJ), Guttadora, Gregory L. (Highland Park, NJ), Parker, John J. (Medford, NJ)

    2006-02-07

    The Oxidative Tritium Decontamination System, OTDS, provides a method and apparatus for reduction of tritium surface contamination on various items. The OTDS employs ozone gas as oxidizing agent to convert elemental tritium to tritium oxide. Tritium oxide vapor and excess ozone gas is purged from the OTDS, for discharge to atmosphere or transport to further process. An effluent stream is subjected to a catalytic process for the decomposition of excess ozone to diatomic oxygen. One of two configurations of the OTDS is employed: dynamic apparatus equipped with agitation mechanism and large volumetric capacity for decontamination of light items, or static apparatus equipped with pressurization and evacuation capability for decontamination of heavier, delicate, and/or valuable items.

  17. Wet processing of palladium for use in the tritium facility at Westinghouse, Savannah River, SC. Preparation of palladium using the Mound Muddy Water process

    SciTech Connect (OSTI)

    Baldwin, D.P.; Zamzow, D.S.

    1998-11-10

    Palladium used at Savannah River for tritium storage is currently obtained from a commercial source. In order to better understand the processes involved in preparing this material, Savannah River is supporting investigations into the chemical reactions used to synthesize this material and into the conditions necessary to produce palladium powder that meets their specifications. This better understanding may help to guarantee a continued reliable source for this material in the future. As part of this evaluation, a work-for-others contract between Westinghouse Savannah River Company and the Ames Laboratory Metallurgy and Ceramics Program was initiated. During FY98, the process for producing palladium powder developed in 1986 by Dan Grove of Mound Applied Technologies (USDOE) was studied to understand the processing conditions that lead to changes in morphology in the final product. This report details the results of this study of the Mound Muddy Water process, along with the results of a round-robin analysis of well-characterized palladium samples that was performed by Savannah River and Ames Laboratory. The Mound Muddy Water process is comprised of three basic wet chemical processes, palladium dissolution, neutralization, and precipitation, with a number of filtration steps to remove unwanted impurity precipitates.

  18. Metabolism and dosimetry of tritium

    SciTech Connect (OSTI)

    Hill, R.L.; Johnson, J.R. )

    1993-12-01

    This document was prepared as a review of the current knowledge of tritium metabolism and dosimetry. The physical, chemical, and metabolic characteristics of various forms of tritium are presented as they pertain to performing dose assessments for occupational workers and for the general public. For occupational workers, the forms of tritium discussed include tritiated water, elemental tritium gas, skin absorption from elemental tritium gas-contaminated surfaces, organically bound tritium in pump oils, solvents and other organic compounds, metal tritides, and radioluminous paints. For the general public, age-dependent tritium metabolism is reviewed, as well as tritiated water, elemental tritium gas, organically bound tritium, organically bound tritium in food-stuffs, and tritiated methane. 106 refs.

  19. Tritium 2013 Presentation | Department of Energy

    Office of Environmental Management (EM)

    2013 Presentation More Documents & Publications Meeting Attendance - 32nd Tritium Focus Group Meeting Tritium Sessions At The 2012 ANS Meeting Overview of tritium activity in Japan...

  20. Tritium catalyzed deuterium tokamaks

    SciTech Connect (OSTI)

    Greenspan, E.; Miley, G.H.; Jung, J.; Gilligan, J.

    1984-04-01

    A preliminary assessment of the promise of the Tritium Catalyzed Deuterium (TCD) tokamak power reactors relative to that of deuterium-tritium (D-T) and catalyzed deuterium (Cat-D) tokamaks is undertaken. The TCD mode of operation is arrived at by converting the /sup 3/He from the D(D,n)/sup 3/He reaction into tritium, by neutron capture in the blanket; the tritium thus produced is fed into the plasma. There are three main parts to the assessment: blanket study, reactor design and economic analysis and an assessment of the prospects for improvements in the performance of TCD reactors (and in the promise of the TCD mode of operation, in general).

  1. Tritium waste package

    DOE Patents [OSTI]

    Rossmassler, R.; Ciebiera, L.; Tulipano, F.J.; Vinson, S.; Walters, R.T.

    1995-11-07

    A containment and waste package system for processing and shipping tritium oxide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within the outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen and oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB. 1 fig.

  2. Tritium waste package

    DOE Patents [OSTI]

    Rossmassler, Rich (Cranbury, NJ); Ciebiera, Lloyd (Titusville, NJ); Tulipano, Francis J. (Teaneck, NJ); Vinson, Sylvester (Ewing, NJ); Walters, R. Thomas (Lawrenceville, NJ)

    1995-01-01

    A containment and waste package system for processing and shipping tritium xide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen add oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB.

  3. Glovebox stripper system tritium capture efficiency-literature review

    SciTech Connect (OSTI)

    James, D. W.; Poore, A. S.

    2015-09-28

    Glovebox Stripper Systems (GBSS) are intended to minimize tritium emissions from glovebox confinement systems in Tritium facilities. A question was raised to determine if an assumed 99% stripping (decontamination) efficiency in the design of a GBBS was appropriate. A literature review showed the stated 99% tritium capture efficiency used for design of the GBSS is reasonable. Four scenarios were indicated for GBSSs. These include release with a single or dual stage setup which utilizes either single-pass or recirculation for stripping purposes. Examples of single-pass as well as recirculation stripper systems are presented and reviewed in this document.

  4. Facilities

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

    Facilities Facilities LANL's mission is to develop and apply science and technology to ensure the safety, security, and reliability of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. Contact Operator Los Alamos National Laboratory (505) 667-5061 Some LANL facilities are available to researchers at other laboratories, universities, and industry. Unique facilities foster experimental science, support LANL's security mission DARHT

  5. Facilities

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

    Secure and Sustainable Energy Future Mission/Facilities - FacilitiesTara Camacho-Lopez2015-10-27T01:52:50+00:00 National Solar Thermal Test Facility (NSTTF) facility_nsttf_slide NSTTF's primary goal is to provide experimental engineering data for the design, construction, and operation of unique components and systems in proposed solar thermal electrical plants, which have three generic system architectures: line-focus (trough and continuous linear Fresnel reflector systems), point-focus central

  6. Tritium Leak Detection: Strategies and Applications

    Office of Environmental Management (EM)

    Tritium Leak Detection: Strategies and Applications 2 *Radiological Protection *Elemental Tritium *Tritium Oxide *Locating the Point of Release *Real-time Measurement 3 The required radiological protection for tritium compounds is much higher than that for elemental tritium. 4 Elemental tritium will combine readily with oxygen to form tritium oxide and also will replace hydrogen atoms in compounds. 5 The presence of elemental tritium in the working environment is an indication of a

  7. Experience with Palladium Diffusers in Tritium Processing

    SciTech Connect (OSTI)

    Motyka, T.; Clark, E.A.; Dauchess, D.A.; Heung, L.K.; Rabum, R.L.

    1995-01-27

    Hydrogen isotopes are separated from other gases by permeation through palladium and palladium-silver alloy diffusers in the Tritium Facilities at the US Department of Energy Savannah River Site (SRS). Diffusers have provided effective service for almost forty years. This paper is an overview of the operational experience with the various diffuser types that have been employed at SRS. Alternative technologies being developed at SRS for purifying hydrogen isotopes are also discussed.

  8. Introduction to Airborne Tritium Tritides

    Office of Environmental Management (EM)

    ... Microscopic Metal Dust Tritium Tritides in airborne dust particles can be inhaled. 10CFR835 lists STCs (Special Tritium Compounds) with DAC factors that the are 2 to 5 times more ...

  9. Drum bubbler tritium processing system

    DOE Patents [OSTI]

    Rule, Keith (Hopewell, NJ); Gettelfinger, Geoff (Lexington, MA); Kivler, Paul (Hamilton Square, NJ)

    1999-01-01

    A method of separating tritium oxide from a gas stream containing tritium oxide. The gas stream containing tritium oxide is fed into a container of water having a head space above the water. Bubbling the gas stream containing tritium oxide through the container of water and removing gas from the container head space above the water. Thereafter, the gas from the head space is dried to remove water vapor from the gas, and the water vapor is recycled to the container of water.

  10. Tritium Effects on Reservoir Materials

    Broader source: Energy.gov [DOE]

    Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013.

  11. Advanced Polymers for Tritium Service

    Broader source: Energy.gov [DOE]

    Presentation from the 34th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014.

  12. Monitoring of tritium

    DOE Patents [OSTI]

    Corbett, James A.; Meacham, Sterling A.

    1981-01-01

    The fluid from a breeder nuclear reactor, which may be the sodium cooling fluid or the helium reactor-cover-gas, or the helium coolant of a gas-cooled reactor passes over the portion of the enclosure of a gaseous discharge device which is permeable to hydrogen and its isotopes. The tritium diffused into the discharge device is radioactive producing beta rays which ionize the gas (argon) in the discharge device. The tritium is monitored by measuring the ionization current produced when the sodium phase and the gas phase of the hydrogen isotopes within the enclosure are in equilibrium.

  13. Facilities

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

    Facilities - An example of a probablistic solar forecast produced with PRESCIENT. Permalink Gallery Sandia Develops Stochastic Production Cost Model Simulator for Electric Power Systems Analysis, Capabilities, Computational Modeling & Simulation, DETL, Distribution Grid Integration, Energy, Facilities, Grid Integration, Modeling, Modeling, Modeling & Analysis, Modeling & Analysis, News, News & Events, Photovoltaic, Renewable Energy, Research & Capabilities, Solar, Solar

  14. 2009 EVALUATION OF TRITIUM REMOVAL AND MITIGATION TECHNOLOGIES FOR WASTEWATER TREATMENT

    SciTech Connect (OSTI)

    LUECK KJ; GENESSE DJ; STEGEN GE

    2009-02-26

    Since 1995, a state-approved land disposal site (SALDS) has received tritium contaminated effluents from the Hanford Site Effluent Treatment Facility (ETF). Tritium in this effluent is mitigated by storage in slow moving groundwater to allow extended time for decay before the water reaches the site boundary. By this method, tritium in the SALDS is isolated from the general environment and human contact until it has decayed to acceptable levels. This report contains the 2009 update evaluation of alternative tritium mitigation techniques to control tritium in liquid effluents and groundwater at the Hanford site. A thorough literature review was completed and updated information is provided on state-of-the-art technologies for control of tritium in wastewaters. This report was prepared to satisfy the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-026-07B (Ecology, EPA, and DOE 2007). Tritium separation and isolation technologies are evaluated periodically to determine their feasibility for implementation to control Hanford site liquid effluents and groundwaters to meet the Us. Code of Federal Regulations (CFR), Title 40 CFR 141.16, drinking water maximum contaminant level (MCL) for tritium of 20,000 pOll and/or DOE Order 5400.5 as low as reasonably achievable (ALARA) policy. Since the 2004 evaluation, there have been a number of developments related to tritium separation and control with potential application in mitigating tritium contaminated wastewater. These are primarily focused in the areas of: (1) tritium recycling at a commercial facility in Cardiff, UK using integrated tritium separation technologies (water distillation, palladium membrane reactor, liquid phase catalytic exchange, thermal diffusion), (2) development and demonstration of Combined Electrolysis Catalytic Exchange (CECE) using hydrogen/water exchange to separate tritium from water, (3) evaporation of tritium contaminated water for dispersion in the atmosphere, and (4) use of barriers to minimize the transport of tritium in groundwater. Continuing development efforts for tritium separations processes are primarily to support the International Thermonuclear Experimental Reactor (ITER) program, the nuclear power industry, and the production of radiochemicals. While these applications are significantly different than the Hanford application, the technology could potentially be adapted for Hanford wastewater treatment. Separations based processes to reduce tritium levels below the drinking water MCL have not been demonstrated for the scale and conditions required for treating Hanford wastewater. In addition, available cost information indicates treatment costs for such processes will be substantially higher than for discharge to SALDS or other typical pump and treat projects at Hanford. Actual mitigation projects for groundwater with very low tritium contamination similar to that found at Hanford have focused mainly on controlling migration and on evaporation for dispersion in the atmosphere.

  15. Drum bubbler tritium processing system

    DOE Patents [OSTI]

    Rule, K.; Gettelfinger, G.; Kivler, P.

    1999-08-17

    A method is described for separating tritium oxide from a gas stream containing tritium oxide. The gas stream containing tritium oxide is fed into a container of water having a head space above the water. The tritium oxide is separated by bubbling the gas stream containing tritium oxide through the container of water and removing gas from the container head space above the water. Thereafter, the gas from the head space is dried to remove water vapor from the gas, and the water vapor is recycled to the container of water. 2 figs.

  16. Recent progress on tritium technology research and development for a fusion reactor in Japan Atomic Energy Agency

    SciTech Connect (OSTI)

    Hayashi, T.; Nakamura, H.; Kawamura, Y.; Iwai, Y.; Isobe, K.; Yamada, M.; Kurata, R.; Edao, Y.; Suzuki, T.; Oyaizu, M.; Yamanishi, T.

    2015-03-15

    JAEA (Japan Atomic Energy Agency) manages 2 tritium handling laboratories: Tritium Processing Laboratory (TPL) in Tokai and DEMO-RD building in Rokkasho. TPL has been accumulating a gram level tritium safety handling experiences without any accidental tritium release to the environment for more than 25 years. Recently, our activities have focused on 3 categories, as follows. First, the development of a detritiation system for ITER. This task is the demonstration test of a wet Scrubber Column (SC) as a pilot scale (a few hundreds m{sup 3}/h of processing capacity). Secondly, DEMO-RD tasks are focused on investigating the general issues required for DEMO-RD design, such as structural materials like RAFM (Reduced Activity Ferritic/Martensitic steels) and SiC/SiC, functional materials like tritium breeder and neutron multiplier, and tritium. For the last 4 years, we have spent a lot of time and means to the construction of the DEMO-RD facility and to its licensing, so we have just started the actual research program with tritium and other radioisotopes. This tritium task includes tritium accountancy, tritium basic safety research such as tritium interactions with various materials, which will be used for DEMO-RD and durability. The third category is the recovery work from the Great East Japan earthquake (2011 earthquake). It is worth noting that despite the high magnitude of the earthquake, TPL was able to confine tritium properly without any accidental tritium release.

  17. Design of a crystal extraction facility in the east utility straight

    SciTech Connect (OSTI)

    Dukes, E.C.; Murphy, C.T.; Parker, B.

    1993-09-01

    Parasitic extraction of a small fraction of the 20-TeV circulating beam of the Superconducting Super Collider can be done using a bent crystal situated in the halo of the orbiting beam. The authors present a design of a crystal extraction system that is compatible with current plans for momentum scraping in the east utility straight. The only modification to the collider tunnel is the addition of a 160-m-long alcove in the east utility straight to mate the extracted beam line microtunnel with the collider tunnel. No other changes to the east utility straight tunnel are needed.

  18. Tritium on Metal Surfaces | Department of Energy

    Office of Environmental Management (EM)

    on Metal Surfaces Tritium on Metal Surfaces Presentation from the 34th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014. PDF icon Tritium on Metal Surfaces More Documents & Publications Modeling Tritium on Metal Surfaces Tritium Plasma Experiment and Its Role in PHENIX Program Light Water Detritiation using the CECE Process

  19. Fermilab | Tritium at Fermilab | Tritium in Surface Water

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

    Surface Water Fermilab map Fermilab has conducted an environmental monitoring program on site for roughly 40 years. In November of 2005, for the first time, we detected low levels of tritium in Indian Creek, one of three creeks that travel through the Fermilab site. Low but measurable levels of tritium continue to be detected in Indian Creek. All tritium levels found on site are well below any federal health and environmental standards. The Department of Energy standard for surface water is

  20. Dismantling of the PETRA glove box: tritium contamination and inventory assessment

    SciTech Connect (OSTI)

    Wagner, R.

    2015-03-15

    The PETRA facility is the first installation in which experiments with tritium were carried out at the Tritium Laboratory Karlsruhe. After completion of two main experimental programs, the decommissioning of PETRA was initiated with the aim to reuse the glove box and its main still valuable components. A decommissioning plan was engaged to: -) identify the source of tritium release in the glove box, -) clarify the status of the main components, -) assess residual tritium inventories, and -) de-tritiate the components to be disposed of as waste. Several analytical techniques - calorimetry on small solid samples, wipe test followed by liquid scintillation counting for surface contamination assessment, gas chromatography on gaseous samples - were deployed and cross-checked to assess the remaining tritium inventories and initiate the decommissioning process. The methodology and the main outcomes of the numerous different tritium measurements are presented and discussed. (authors)

  1. Tritium monitor and collection system

    DOE Patents [OSTI]

    Bourne, G.L.; Meikrantz, D.H.; Ely, W.E.; Tuggle, D.G.; Grafwallner, E.G.; Wickham, K.L.; Maltrud, H.R.; Baker, J.D.

    1992-01-14

    This system measures tritium on-line and collects tritium from a flowing inert gas stream. It separates the tritium from other non-hydrogen isotope contaminating gases, whether radioactive or not. The collecting portion of the system is constructed of various zirconium alloys called getters. These alloys adsorb tritium in any of its forms at one temperature and at a higher temperature release it as a gas. The system consists of four on-line getters and heaters, two ion chamber detectors, two collection getters, and two guard getters. When the incoming gas stream is valved through the on-line getters, 99.9% of it is adsorbed and the remainder continues to the guard getter where traces of tritium not collected earlier are adsorbed. The inert gas stream then exits the system to the decay chamber. Once the on-line getter has collected tritium for a predetermined time, it is valved off and the next on-line getter is valved on. Simultaneously, the first getter is heated and a pure helium purge is employed to carry the tritium from the getter. The tritium loaded gas stream is then routed through an ion chamber which measures the tritium activity. The ion chamber effluent passes through a collection getter that readsorbs the tritium and is removable from the system once it is loaded and is then replaced with a clean getter. Prior to removal of the collection getter, the system switches to a parallel collection getter. The effluent from the collection getter passes through a guard getter to remove traces of tritium prior to exiting the system. The tritium loaded collection getter, once removed, is analyzed by liquid scintillation techniques. The entire sequence is under computer control except for the removal and analysis of the collection getter. 7 figs.

  2. Tritium monitor and collection system

    DOE Patents [OSTI]

    Bourne, Gary L. (Idaho Falls, ID); Meikrantz, David H. (Idaho Falls, ID); Ely, Walter E. (Los Alamos, NM); Tuggle, Dale G. (Los Alamos, NM); Grafwallner, Ervin G. (Arco, ID); Wickham, Keith L. (Idaho Falls, ID); Maltrud, Herman R. (Los Alamos, NM); Baker, John D. (Blackfoot, ID)

    1992-01-01

    This system measures tritium on-line and collects tritium from a flowing inert gas stream. It separates the tritium from other non-hydrogen isotope contaminating gases, whether radioactive or not. The collecting portion of the system is constructed of various zirconium alloys called getters. These alloys adsorb tritium in any of its forms at one temperature and at a higher temperature release it as a gas. The system consists of four on-line getters and heaters, two ion chamber detectors, two collection getters, and two guard getters. When the incoming gas stream is valved through the on-line getters, 99.9% of it is adsorbed and the remainder continues to the guard getter where traces of tritium not collected earlier are adsorbed. The inert gas stream then exits the system to the decay chamber. Once the on-line getter has collected tritium for a predetermined time, it is valved off and the next on-line getter is valved on. Simultaneously, the first getter is heated and a pure helium purge is employed to carry the tritium from the getter. The tritium loaded gas stream is then routed through an ion chamber which measures the tritium activity. The ion chamber effluent passes through a collection getter that readsorbs the tritium and is removable from the system once it is loaded and is then replaced with a clean getter. Prior to removal of the collection getter, the system switches to a parallel collection getter. The effluent from the collection getter passes through a guard getter to remove traces of tritium prior to exiting the system. The tritium loaded collection getter, once removed, is analyzed by liquid scintillation techniques. The entire sequence is under computer control except for the removal and analysis of the collection getter.

  3. Particulate Generation in Tritium Systems

    Office of Environmental Management (EM)

    Particulate Generation in a Tritium System Paul Cloessner, PhD Laboratory Fellow Tritium Focus Group February 22, 2014 Outline * Description of Events * Analysis of Material * Sources of material contamination * System Restoration/Modifications * Contaminant Minimization and Control * Lessons Learned 2 An Unpleasant Surprise * Let down filter on compressor became plugged after 10 years of operation. * Tritium processing interrupted when other filters (flow orifices) became plugged approximately

  4. Microsoft Word - Tritium Production and Environmental Impacts...

    National Nuclear Security Administration (NNSA)

    of tritium in the reactor's coolant water system. Since tritium is an isotope of the hydrogen atom, once the tritium is in the reactor's coolant water system, it can combine with...

  5. RESULTS OF THE EXTRACTION-SCRUB-STRIP TESTING USING AN IMPROVED SOLVENT FORMULATION AND SALT WASTE PROCESSING FACILITY SIMULATED WASTE

    SciTech Connect (OSTI)

    Peters, T.; Washington, A.; Fink, S.

    2012-01-09

    The Office of Waste Processing, within the Office of Technology Innovation and Development, is funding the development of an enhanced solvent - also known as the next generation solvent (NGS) - for deployment at the Savannah River Site to remove cesium from High Level Waste. The technical effort is a collaborative effort between Oak Ridge National Laboratory (ORNL) and Savannah River National Laboratory (SRNL). As part of the program, the Savannah River National Laboratory (SRNL) has performed a number of Extraction-Scrub-Strip (ESS) tests. These batch contact tests serve as first indicators of the cesium mass transfer solvent performance with actual or simulated waste. The test detailed in this report used simulated Tank 49H material, with the addition of extra potassium. The potassium was added at 1677 mg/L, the maximum projected (i.e., a worst case feed scenario) value for the Salt Waste Processing Facility (SWPF). The results of the test gave favorable results given that the potassium concentration was elevated (1677 mg/L compared to the current 513 mg/L). The cesium distribution value, DCs, for extraction was 57.1. As a comparison, a typical D{sub Cs} in an ESS test, using the baseline solvent formulation and the typical waste feed, is {approx}15. The Modular Caustic Side Solvent Extraction Unit (MCU) uses the Caustic-Side Solvent Extraction (CSSX) process to remove cesium (Cs) from alkaline waste. This process involves the use of an organic extractant, BoBCalixC6, in an organic matrix to selectively remove cesium from the caustic waste. The organic solvent mixture flows counter-current to the caustic aqueous waste stream within centrifugal contactors. After extracting the cesium, the loaded solvent is stripped of cesium by contact with dilute nitric acid and the cesium concentrate is transferred to the Defense Waste Processing Facility (DWPF), while the organic solvent is cleaned and recycled for further use. The Salt Waste Processing Facility (SWPF), under construction, will use the same process chemistry. The Office of Waste Processing (EM-31) expressed an interest in investigating the further optimization of the organic solvent by replacing the BoBCalixC6 extractant with a more efficient extractant. This replacement should yield dividends in improving cesium removal from the caustic waste stream, and in the rate at which the caustic waste can be processed. To that end, EM-31 provided funding for both the Savannah River National Laboratory (SRNL) and the Oak Ridge National Laboratory (ORNL). SRNL wrote a Task Technical Quality and Assurance Plan for this work. As part of the envisioned testing regime, it was decided to perform an ESS test using a simulated waste that simulated a typical envisioned SWPF feed, but with added potassium to make the waste more challenging. Potassium interferes in the cesium removal, and its concentration is limited in the feed to <1950 mg/L. The feed to MCU has typically contained <500 mg/L of potassium.

  6. Tritium Focus Group | Department of Energy

    Energy Savers [EERE]

    Tritium Focus Group Tritium Focus Group Tritium Focus Group The Tritium Focus Group (TFG), is a long standing DOE Working Group, whose purpose is to promote cost-effective improvements in tritium safety, handling, transportation, storage, and operations, and to enhance communication across the Department of Energy (DOE) (inclusive of the National Nuclear Security Administration (NNSA)) on all matters related to tritium. It was initially formed to develop corrective actions resulting from the

  7. Tritium accountancy in fusion systems

    SciTech Connect (OSTI)

    Klein, J.E.; Clark, E.A.; Harvel, C.D.; Farmer, D.A.; Tovo, L.L.; Poore, A.S.; Moore, M.L.

    2015-03-15

    The US Department of Energy (DOE) has clearly defined requirements for nuclear material control and accountability (MCA) of tritium whereas the International Atomic Energy Agency (IAEA) does not since tritium is not a fissile material. MCA requirements are expected for tritium fusion machines and will be dictated by the host country or regulatory body where the machine is operated. Material Balance Areas (MBA) are defined to aid in the tracking and reporting of nuclear material movements and inventories. Material sub-accounts (MSA) are established along with key measurement points (KMP) to further subdivide a MBA to localize and minimize uncertainties in the inventory difference (ID) calculations for tritium accountancy. Fusion systems try to minimize tritium inventory which may require continuous movement of material through the MSA. The ability of making meaningful measurements of these material transfers is described in terms of establishing the MSA structure to perform and reconcile ID calculations. For fusion machines, changes to the traditional ID equation will be discussed which includes breeding, burn-up, and retention of tritium in the fusion device. The concept of 'net' tritium quantities consumed or lost in fusion devices is described in terms of inventory taking strategies and how it is used to track the accumulation of tritium in components or fusion machines. (authors)

  8. TRITIUM ACCOUNTANCY IN FUSION SYSTEMS

    SciTech Connect (OSTI)

    Klein, J. E.; Farmer, D. A.; Moore, M. L.; Tovo, L. L.; Poore, A. S.; Clark, E. A.; Harvel, C. D.

    2014-03-06

    The US Department of Energy (DOE) has clearly defined requirements for nuclear material control and accountability (MC&A) of tritium whereas the International Atomic Energy Agency (IAEA) does not since tritium is not a fissile material. MC&A requirements are expected for tritium fusion machines and will be dictated by the host country or regulatory body where the machine is operated. Material Balance Areas (MBAs) are defined to aid in the tracking and reporting of nuclear material movements and inventories. Material subaccounts (MSAs) are established along with key measurement points (KMPs) to further subdivide a MBA to localize and minimize uncertainties in the inventory difference (ID) calculations for tritium accountancy. Fusion systems try to minimize tritium inventory which may require continuous movement of material through the MSAs. The ability of making meaningful measurements of these material transfers is described in terms of establishing the MSA structure to perform and reconcile ID calculations. For fusion machines, changes to the traditional ID equation will be discussed which includes breading, burn-up, and retention of tritium in the fusion device. The concept of net tritium quantities consumed or lost in fusion devices is described in terms of inventory taking strategies and how it is used to track the accumulation of tritium in components or fusion machines.

  9. Tritium Production from Palladium Alloys

    SciTech Connect (OSTI)

    Claytor, T.N.; Schwab, M.J.; Thoma, D.J.; Teter, D.F.; Tuggle, D.G.

    1998-04-19

    A number of palladium alloys have been loaded with deuterium or hydrogen under low energy bombardment in a system that allows the continuous measurement of tritium. Long run times (up to 200 h) result in an integration of the tritium and this, coupled with the high intrinsic sensitivity of the system ({approximately}0.1 nCi/l), enables the significance of the tritium measurement to be many sigma (>10). We will show the difference in tritium generation rates between batches of palladium alloys (Rh, Co, Cu, Cr, Ni, Be, B, Li, Hf, Hg and Fe) of various concentrations to illustrate that tritium generation rate is dependent on alloy type as well as within a specific alloy, dependent on concentration.

  10. Operating Experience Review of Tritium-in-Water Monitors

    SciTech Connect (OSTI)

    S. A. Bruyere; L. C. Cadwallader

    2011-09-01

    Monitoring tritium facility and fusion experiment effluent streams is an environmental safety requirement. This paper presents data on the operating experience of a solid scintillant monitor for tritium in effluent water. Operating experiences were used to calculate an average monitor failure rate of 4E-05/hour for failure to function. Maintenance experiences were examined to find the active repair time for this type of monitor, which varied from 22 minutes for filter replacement to 11 days of downtime while waiting for spare parts to arrive on site. These data support planning for monitor use; the number of monitors needed, allocating technician time for maintenance, inventories of spare parts, and other issues.

  11. Polymer Exposure and Testing Facilities at the Savannah River Site |

    Office of Environmental Management (EM)

    Department of Energy Polymer Exposure and Testing Facilities at the Savannah River Site Polymer Exposure and Testing Facilities at the Savannah River Site Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Polymer Exposure and Testing Facilities at the Savannah River Site More Documents & Publications Advanced Polymers for Tritium Service Meeting Attendance - 33rd Tritium Focus Group Meeting Postdoctoral Research Awards

  12. Tritium Focus Group - INEL | Department of Energy

    Office of Environmental Management (EM)

    Focus Group - INEL Tritium Focus Group - INEL Presentation from the 34th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014. PDF icon Tritium Focus Group - INEL More Documents & Publications Monitoring of Tritium release at PTC DOE-HDBK-1129-2007 DOE-HDBK-1129-2008

  13. Introduction Airborne Tritium Tritides | Department of Energy

    Office of Environmental Management (EM)

    Introduction Airborne Tritium Tritides Introduction Airborne Tritium Tritides Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Introduction Airborne Tritium Tritides More Documents & Publications DOE-HDBK-1129-2008 DOE-HDBK-1129-2007 DOE-HDBK-1129-99

  14. Polymer Exposure and Testing Facilities at the Savannah River...

    Office of Environmental Management (EM)

    15 * PDRD Program * Tritium Facilities * Elliot Clark * Steve Murphy * Pam Morgan * Dante Pilgrim * Carol Kestin * Lynn Bouknight * Greg Staack * Marie Kane * Jay Gaillard...

  15. Fermilab | Tritium at Fermilab | Frequently asked questions

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

    Frequently asked questions about tritium Answers to Frequently Asked Questions about Tritium at Fermilab. If you have any questions about tritium at Fermilab, please call the Office of Communication at 630-840-3351, or submit a question online. Q: What is tritium? A: Tritium is a form of hydrogen. It's a weakly radioactive isotope with a half-life of 12.3 years. When tritium decays into ordinary helium, it emits low-energy particles called beta particles. Although tritium can be found as a gas,

  16. Differential atmospheric tritium sampler

    DOE Patents [OSTI]

    Griesbach, Otto A. (Langhorne, PA); Stencel, Joseph R. (Skillman, NJ)

    1990-01-01

    An atmospheric tritium sampler is provided which uses a carrier gas comprised of hydrogen gas and a diluting gas, mixed in a nonexplosive concentration. Sample air and carrier gas are drawn into and mixed in a manifold. A regulator meters the carrier gas flow to the manifold. The air sample/carrier gas mixture is pulled through a first moisture trap which adsorbs water from the air sample. The mixture then passes through a combustion chamber where hydrogen gas in the form of H.sub.2 or HT is combusted into water. The manufactured water is transported by the air stream to a second moisture trap where it is adsorbed. The air is then discharged back into the atmosphere by means of a pump.

  17. Differential atmospheric tritium sampler

    DOE Patents [OSTI]

    Griesbach, O.A.; Stencel, J.R.

    1987-10-02

    An atmospheric tritium sampler is provided which uses a carrier gas comprised of hydrogen gas and a diluting gas, mixed in a nonexplosive concentration. Sample air and carrier gas are drawn into and mixed in a manifold. A regulator meters the carrier gas flow to the manifold. The air sample/carrier gas mixture is pulled through a first moisture trap which adsorbs water from the air sample. The moisture then passes through a combustion chamber where hydrogen gas in the form of H/sub 2/ or HT is combusted into water. The manufactured water is transported by the air stream to a second moisture trap where it is adsorbed. The air is then discharged back into the atmosphere by means of a pump.

  18. Normalized Tritium Quantification Approach (NoTQA) a Method for Quantifying Tritium Contaminated Trash and Debris at LLNL

    SciTech Connect (OSTI)

    Dominick, J L; Rasmussen, C L

    2008-07-23

    Several facilities and many projects at LLNL work exclusively with tritium. These operations have the potential to generate large quantities of Low-Level Radioactive Waste (LLW) with the same or similar radiological characteristics. A standardized documented approach to characterizing these waste materials for disposal as radioactive waste will enhance the ability of the Laboratory to manage them in an efficient and timely manner while ensuring compliance with all applicable regulatory requirements. This standardized characterization approach couples documented process knowledge with analytical verification and is very conservative, overestimating the radioactivity concentration of the waste. The characterization approach documented here is the Normalized Tritium Quantification Approach (NoTQA). This document will serve as a Technical Basis Document which can be referenced in radioactive waste characterization documentation packages such as the Information Gathering Document. In general, radiological characterization of waste consists of both developing an isotopic breakdown (distribution) of radionuclides contaminating the waste and using an appropriate method to quantify the radionuclides in the waste. Characterization approaches require varying degrees of rigor depending upon the radionuclides contaminating the waste and the concentration of the radionuclide contaminants as related to regulatory thresholds. Generally, as activity levels in the waste approach a regulatory or disposal facility threshold the degree of required precision and accuracy, and therefore the level of rigor, increases. In the case of tritium, thresholds of concern for control, contamination, transportation, and waste acceptance are relatively high. Due to the benign nature of tritium and the resulting higher regulatory thresholds, this less rigorous yet conservative characterization approach is appropriate. The scope of this document is to define an appropriate and acceptable characterization method for quantification of tritium contaminated trash and debris. The characterization technique is applicable to surface and subsurface tritium contaminated materials with surfaces amenable to swiping. Some limitations of this characterization technique are identified.

  19. Combined gettering and molten salt process for tritium recovery from lithium

    SciTech Connect (OSTI)

    Sze, D.K.; Finn, P.A.; Bartlit, J.; Tanaka, S.; Teria, T.; Yamawaki, M.

    1988-02-01

    A new tritium recovery concept from lithium has been developed as part of the US/Japan collaboration on Reversed-Field Pinch Reactor Design Studies. This concept combines the ..gamma..-gettering process as the front end to recover tritium from the coolant, and a molten salt recovery process to extract tritium for fuel processing. A secondary lithium is used to regenerate the tritium from the gettering bed and, in the process, increases the tritium concentration by a factor of about 20. That way, the required size of the molten salt process becomes very small. A potential problem is the possible poisoning of the gettering bed by the salt dissolved in lithium. 16 refs., 6 figs.

  20. Tritium Operation Improvements at the Idaho National Laboratory...

    Office of Environmental Management (EM)

    More Documents & Publications Fusion Nuclear Science and Technology Program - Status and Plans for Tritium Research Tritium Plasma Experiment and Its Role in PHENIX Program Tritium ...

  1. A study of tritium in municipal solid waste leachate and gas

    SciTech Connect (OSTI)

    Mutch Jr, R. D.; Mahony, J. D.

    2008-07-15

    It has become increasingly clear in the last few years that the vast majority of municipal solid waste landfills produce leachate that contains elevated levels of tritium. The authors recently conducted a study of landfills in New York and New Jersey and found that the mean concentration of tritium in the leachate from ten municipal solid waste (MSW) landfills was 33,800 pCi/L with a peak value of 192,000 pCi/L. A 2003 study in California reported a mean tritium concentration of 99,000 pCi/L with a peak value of 304,000 pCi/L. Studies in Pennsylvania and the UK produced similar results. The USEPA MCL for tritium is 20,000 pCi/L. Tritium is also manifesting itself as landfill gas and landfill gas condensate. Landfill gas condensate samples from landfills in the UK and California were found to have tritium concentrations as high as 54,400 and 513,000 pCi/L, respectively. The tritium found in MSW leachate is believed to derive principally from gaseous tritium lighting devices used in some emergency exit signs, compasses, watches, and even novelty items, such as 'glow stick' key chains. This study reports the findings of recent surveys of leachate from a number of municipal solid waste landfills, both open and closed, from throughout the United States and Europe. The study evaluates the human health and ecological risks posed by elevated tritium levels in municipal solid waste leachate and landfill gas and the implications to their safe management. We also assess the potential risks posed to solid waste management facility workers exposed to tritium-containing waste materials in transfer stations and other solid waste management facilities. (authors)

  2. Separation of Tritium from Wastewater

    SciTech Connect (OSTI)

    JEPPSON, D.W.

    2000-01-25

    A proprietary tritium loading bed developed by Molecular Separations, Inc (MSI) has been shown to selectively load tritiated water as waters of hydration at near ambient temperatures. Tests conducted with a 126 {micro}C{sub 1} tritium/liter water standard mixture showed reductions to 25 {micro}C{sub 1}/L utilizing two, 2-meter long columns in series. Demonstration tests with Hanford Site wastewater samples indicate an approximate tritium concentration reduction from 0.3 {micro}C{sub 1}/L to 0.07 {micro}C{sub 1}/L for a series of two, 2-meter long stationary column beds Further reduction to less than 0.02 {micro}C{sub 1}/L, the current drinking water maximum contaminant level (MCL), is projected with additional bed media in series. Tritium can be removed from the loaded beds with a modest temperature increase and the beds can be reused Results of initial tests are presented and a moving bed process for treating large quantities of wastewaters is proposed. The moving bed separation process appears promising to treat existing large quantities of wastewater at various US Department of Energy (DOE) sites. The enriched tritium stream can be grouted for waste disposition. The separations system has also been shown to reduce tritium concentrations in nuclear reactor cooling water to levels that allow reuse. Energy requirements to reconstitute the loading beds and waste disposal costs for this process appear modest.

  3. Production of highly tritiated water for tritium exposure studies

    SciTech Connect (OSTI)

    Muirhead, C.; Pilatzke, K.; Tripple, A.; Philippi, N.; McCrimmon, K.; Castillo, I.; Boniface, H.; Suppiah, S.

    2015-03-15

    Tritium Facility staff at Chalk River Laboratories (CRL) have successfully prepared highly tritiated water for use in radiation resistance of PEM (Proton Exchange Membrane-based)electrolyser membrane. The goal of System A was to convert a known amount of elemental tritium (HT) into tritiated water vapour using a copper(II) oxide bed, and to condense the tritiated water vapour into a known amount of chilled heavy water (D{sub 2}O). The conversion and capture of tritium using this system is close to 100%. The goal of System B was to transfer tritiated water from the containment vessel to an exposure vessel (experiment) in a controlled and safe manner. System B is based on the pushing of D{sub 2}0 with low-pressure argon carrier gas to a calibrated volume and then to the exposure vessel. A method for delivering a known and controlled amount of tritiated water has been successfully demonstrated at CRL. Using both systems Tritium Facility staff have made and distributed highly tritiated water in a safe and controlled manner. This paper focuses on how the tritiated water was produced and dispensed to the experiment.

  4. Primer on tritium safe handling practices

    SciTech Connect (OSTI)

    Not Available

    1994-12-01

    This Primer is designed for use by operations and maintenance personnel to improve their knowledge of tritium safe handling practices. It is applicable to many job classifications and can be used as a reference for classroom work or for self-study. It is presented in general terms for use throughout the DOE Complex. After reading it, one should be able to: describe methods of measuring airborne tritium concentration; list types of protective clothing effective against tritium uptake from surface and airborne contamination; name two methods of reducing the body dose after a tritium uptake; describe the most common method for determining amount of tritium uptake in the body; describe steps to take following an accidental release of airborne tritium; describe the damage to metals that results from absorption of tritium; explain how washing hands or showering in cold water helps reduce tritium uptake; and describe how tritium exchanges with normal hydrogen in water and hydrocarbons.

  5. Laser-assisted isotope separation of tritium

    DOE Patents [OSTI]

    Herman, Irving P. (Castro Valley, CA); Marling, Jack B. (Livermore, CA)

    1983-01-01

    Methods for laser-assisted isotope separation of tritium, using infrared multiple photon dissociation of tritium-bearing products in the gas phase. One such process involves the steps of (1) catalytic exchange of a deuterium-bearing molecule XYD with tritiated water DTO from sources such as a heavy water fission reactor, to produce the tritium-bearing working molecules XYT and (2) photoselective dissociation of XYT to form a tritium-rich product. By an analogous procedure, tritium is separated from tritium-bearing materials that contain predominately hydrogen such as a light water coolant from fission or fusion reactors.

  6. Modeling Tritium on Metal Surfaces | Department of Energy

    Office of Environmental Management (EM)

    Tritium on Metal Surfaces Modeling Tritium on Metal Surfaces Presentation from the 36th Tritium Focus Group Meeting held in Los Alamos, New Mexico, November 3-5, 2015. PDF icon Modeling Tritium on Metal Surfaces More Documents & Publications Tritium on Metal Surfaces DOE-HDBK-1079-94 Overview of tritium activity in Japan

  7. Tritium emissions from 200 East Area Double-Shell Tanks

    SciTech Connect (OSTI)

    Bachand, D.D.

    1994-11-28

    This document evaluates the need for tritium sampling of the emissions from the 200 East Area Double Shell Tanks based on the requirements of {open_quotes}National Emission Standards for Hazardous Air Pollutants{close_quotes} (NESHAP). The NESHAP requirements are specified in 40 Code of Federal Regulation (CFR), Part 61, Subpart H; {open_quotes}National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities{close_quotes}.

  8. A Plan for Modularization of Tritium Components

    Office of Environmental Management (EM)

    Tritium Components Randy Davis Davis Consultants M-TRT-H-00089 Savannah River Nuclear Solutions, LLC April 22, 2014 M-TRT-H-00089 Current Approach * All "tritium wetted components" ...

  9. Crediting Tritium Deposition in Accident Analysis

    SciTech Connect (OSTI)

    Murphy, C.E. Jr.

    2001-06-20

    This paper describes the major aspects of tritium dispersion phenomenology, summarizes deposition attributes of the computer models used in the DOE Complex for tritium dispersion, and recommends an approach to account for deposition in accident analysis.

  10. Overview of Recent Tritium Experiments in TPE

    SciTech Connect (OSTI)

    Masashi Shimada; T. Otsuka; R. J. Pawelko; P. Calderoni; J. P. Sharpe

    2010-10-01

    Tritium retention in plasma-facing components influences the design, operation, and lifetime of fusion devices such as ITER. Most of the retention studies were carried out with the use of either hydrogen or deuterium. Tritium Plasma Experiment is a unique linear plasma device that can handle radioactive fusion fuel of tritium, toxic material of beryllium, and neutron-irradiated material. A tritium depth profiling method up to mm range was developed using a tritium imaging plate and a diamond wire saw. A series of tritium experiments (T2/D2 ratio: 0.2 and 0.5 %) was performed to investigate tritium depth profiling in bulk tungsten, and the results shows that tritium is migrated into bulk tungsten up to mm range.

  11. Bulk Tritium Shipping Package Overview and Status

    Office of Energy Efficiency and Renewable Energy (EERE)

    Presentation from the 36th Tritium Focus Group Meeting held in Los Alamos, New Mexico, November 3-5, 2015.

  12. A Plan for Modularization of Tritium Components

    Broader source: Energy.gov [DOE]

    Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014.

  13. Design of the Target Fabrication Tritium Laboratory

    SciTech Connect (OSTI)

    Sherohman, J.W.; Roberts, D.H.; Levine, B.H.

    1982-05-05

    The design of the Target Fabrication Tritium Laboratory for deuterium-tritium fuel processing for laser fusion targets has been accomplished with the intent of providing redundant safeguard systems. The design of the tritium laboratory is based on a combination of tritium handling techniques that are currently used by experienced laboratories. A description of the laboratory in terms of its interrelated processing systems is presented to provide an understanding of the design features for safe operation.

  14. Secure Wireless Tritium Air Monitoring Cart Development

    Broader source: Energy.gov [DOE]

    Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014.

  15. Monitoring of Tritium release at PTC

    Broader source: Energy.gov [DOE]

    Presentation from the 34th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014.

  16. Chalk River Tritium Activities: Select Topics

    Broader source: Energy.gov [DOE]

    Presentation from the 35th Tritium Focus Group Meeting held in Princeton, New Jersey on May 05-07, 2015.

  17. Tritium Gas Processing for Magnetic Fusion

    Broader source: Energy.gov [DOE]

    Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014.

  18. Tritium Sessions At The 2012 ANS Meeting

    Broader source: Energy.gov [DOE]

    Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013.

  19. Fermilab | Tritium at Fermilab | Kress Creek Results

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

    Kress Creek Results chart This chart (click chart for larger version) shows the levels of tritium in Kress Creek since January 2006. To date, Fermilab has not detected tritium in Kress Creek. The detection limit is one picocurie per milliliter (see footnote). Increased monitoring began on Kress Creek following detection of low levels of tritium in Indian Creek in November 2005. The levels of tritium measured in the Fermilab cooling ponds and in Indian Creek are well below federal water standards

  20. TEST PROCEDURE VALIDATION TEST OF A DISCRIMINATING TRITIUM MONITOR FOR MEASURING TRITIUM OXIDE IN THE PRESENCE OF NOBLE GASES

    Office of Environmental Management (EM)

    Test Results For Physical Separation Of Tritium From Noble Gases And It's Implications For Sensitivity And Accuracy In Air And Stack Monitoring Robert Goldstein, Ivan Mitev, Dell Williamson WE FACE A CHALLENGE At many nuclear facilities, Air and Stack monitors are required to measure: Multiple radio-active materials Separately and simultaneously With great accuracy and high sensitivity EVEN WHEN High concentrations of one material are likely to mask the signals from the low concentration of

  1. Tritium Ground Water Issues | Department of Energy

    Office of Environmental Management (EM)

    Ground Water Issues Tritium Ground Water Issues Presentation from the 35th Tritium Focus Group Meeting held in Princeton, New Jersey on May 05-07, 2015. PDF icon Tritium Ground Water Issues More Documents & Publications Managing Uncertainty and Demonstrating Compliance EA-1356: Final Environmental Assessment SRS FTF Section 3116 Basis for Determination

  2. Tritium contamination and decontamination of sealing oil for vacuum pump

    SciTech Connect (OSTI)

    Takeishi, T.; Kotoh, K.; Kawabata, Y.; Tanaka, J.I.; Kawamura, S.; Iwata, M.

    2015-03-15

    The existence of tritium-contaminated oils from vacuum pumps used in tritium facilities, is becoming an important issue since there is no disposal way for tritiated waste oils. On recovery of tritiated water vapor in gas streams, it is well-known that the isotope exchange reaction between the gas phase and the liquid phase occurs effectively at room temperature. We have carried out experiments using bubbles to examine the tritium contamination and decontamination of a volume of rotary-vacuum-pump oil. The contamination of the pump oil was made by bubbling tritiated water vapor and tritiated hydrogen gas into the oil. Subsequently the decontamination was processed by bubbling pure water vapor and dry argon gas into the tritiated oil. Results show that the water vapor bubbling was more effective than dry argon gas. The experiment also shows that the water vapor bubbling in an oil bottle can remove and transfer tritium efficiently from the tritiated oil into another water-bubbling bottle.

  3. Characterization of LaNi{sub 4.25}Al{sub 0.75} tritide for use as a long term tritium storage medium

    SciTech Connect (OSTI)

    Wermer, J.R.

    1994-10-01

    Applications of metal hydride technology has offered numerous safety as well as operating advantages for tritium processing operations. The SRS Replacement Tritium Facility (RTF) utilizes this technology extensively. During design of the RTF systems, LaNi{sub 4.25}Al{sub 0.75} (LANA.75) was chosen as the primary tritium storage material. This material was selected largely because of the isotherm plateau pressure, which allows the tritium to be stored as a metal tritide at subatmospheric pressures while still being able to generate pressures of >1000 mm Hg needed for process applications. A benefit of this substitution is an increase in the stability of this material to tritium aging effects and to disproportionation. The LANA.75 material, like many metal tritides used for tritium processing, retains insoluble helium-3 which is born in the metal lattice through radiolytic decay of tritium. This causes changes in the thermodynamics of the metal-hydrogen system, decreasing the {alpha}-{beta} plateau pressure, increasing the plateau slope, and decreasing the reversible hydriding capacity. The latter also includes the growth of a tritium {open_quotes}heel{close_quotes} which cannot be removed under normal processing conditions. All of these factors affect the long-term performance of LANA.75-tritide in processing applications. Tritium aging studies have been underway on LANA.75 since 1987 in the SRTC Materials Test Facility. Material characterization of LANA.75-tritide has been completed on material exposed to tritium for 5.4 years at full stoichiometry.

  4. EFFECTS OF TRITIUM GAS EXPOSURE ON POLYMERS

    SciTech Connect (OSTI)

    Clark, E.; Fox, E.; Kane, M.; Staack, G.

    2011-01-07

    Effects of tritium gas exposure on various polymers have been studied over the last several years. Despite the deleterious effects of beta exposure on many material properties, structural polymers continued to be used in tritium systems. Improved understanding of the tritium effects will allow more resistant materials to be selected. Currently polymers find use mainly in tritium gas sealing applications (eg. valve stem tips, O-rings). Future uses being evaluated including polymeric based cracking of tritiated water, and polymer-based sensors of tritium.

  5. EVALUATION OF ALTERNATE STAINLESS STEEL SURFACE TREATMENTS FOR MASS SPECTROSCOPY AND OTHER TRITIUM SYSTEMS

    SciTech Connect (OSTI)

    Clark, E.; Mauldin, C.; Neikirk, K.

    2012-02-29

    There are specific components in the SRS Tritium Facilities that are required to introduce as few chemical impurities (such as protium and methane) as possible into the process gas. Two such components are the inlet systems for the mass spectroscopy facilities and hydrogen isotope mix standard containers. Two vendors now passivate stainless steel components for these systems, and both are relatively small businesses whose future viability can be questioned, which creates the need for new sources. Stainless steel containers were designed to evaluate alternate surface treatment vendors for tritium storage and handling for these high purity tritium systems. Five vendors applied their own 'best' surface treatments to two containers each - one was a current vendor, another was a chemical vapor deposited silicon coating, and the other three were electropolishing and chemical cleaning vendors. Pure tritium gas was introduced into all ten containers and the composition was monitored over time. The only observed impurities in the gas were some HT, less CT{sub 4}, and very small amounts of T{sub 2}O in all cases. The currently used vendor treated containers contained the least impurities. The chemical vapor deposited silicon treatment resulted in the highest impurity levels. Sampling one set of containers after about one month of tritium exposure revealed the impurity level to be nearly the same as that after more than a year of exposure - this result suggests that cleaning new stainless steel components by tritium gas contact for about a month may be a worthy operation.

  6. Tritium Handling and Safe Storage

    Energy Savers [EERE]

    NOT MEASUREMENT SENSITIVE DOE-STD-1129-2015 September 2015 DOE STANDARD TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS DOE-STD-1129-2015 ii TABLE OF CONTENTS FOREWORD ............................................................................................................................................. 1 ACRONYMS

  7. Tritium Waste Treatment System component failure data analysis from June 18, 1984--December 31, 1989

    SciTech Connect (OSTI)

    Cadwallader, L.C. ); Stolpe Gavett, M.A. )

    1990-09-01

    This document gives the failure rates for the major tritium-bearing components in the Tritium Waste Treatment System at the Tritium Systems Test Assembly, which is a fusion research and technology facility at the Los Alamos National Laboratory. The failure reports, component populations, and operating demands/hours are given in this report, and sample calculations for binomial demand failure rates and poisson hourly failure rates are given in the appendices. The failure rates for tritium-bearing components were on the order of the screening failure rate values suggested for fusion reliability and risk analyses. More effort should be directed toward collecting and analyzing fusion component failure data, since accurate failure rates are necessary to refine reliability and risk analyses. 15 refs., 4 figs., 4 tabs.

  8. Meeting Attendance - 36th Tritium Focus Group Meeting | Department of

    Office of Environmental Management (EM)

    Energy 6th Tritium Focus Group Meeting Meeting Attendance - 36th Tritium Focus Group Meeting Attendees to the 36th Tritium Focus Group Meeting held in Los Alamos, New Mexico, November 03-05, 2015. PDF icon Meeting Attendance - 36th Tritium Focus Group Meeting More Documents & Publications Meeting Attendance - 35th Tritium Focus Group Meeting Meeting Attendance - 34th Tritium Focus Group Meeting Tritium Aging Studies of LaNi4.15Al0.85 (LANA.85)

  9. Facility Floorplan

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

    Facility Floorplan

  10. In-vessel tritium retention and removal in ITER

    SciTech Connect (OSTI)

    Federici, G.; Anderl, R.A.; Andrew, P.

    1998-06-01

    The International Thermonuclear Experimental Reactor (ITER) is envisioned to be the next major step in the world`s fusion program from the present generation of tokamaks and is designed to study fusion plasmas with a reactor relevant range of plasma parameters. During normal operation, it is expected that a fraction of the unburned tritium, that is used to routinely fuel the discharge, will be retained together with deuterium on the surfaces and in the bulk of the plasma facing materials (PFMs) surrounding the core and divertor plasma. The understanding of he basic retention mechanisms (physical and chemical) involved and their dependence upon plasma parameters and other relevant operation conditions is necessary for the accurate prediction of the amount of tritium retained at any given time in the ITER torus. Accurate estimates are essential to assess the radiological hazards associated with routine operation and with potential accident scenarios which may lead to mobilization of tritium that is not tenaciously held. Estimates are needed to establish the detritiation requirements for coolant water, to determine the plasma fueling and tritium supply requirements, and to establish the needed frequency and the procedures for tritium recovery and clean-up. The organization of this paper is as follows. Section 2 provides an overview of the design and operating conditions of the main components which define the plasma boundary of ITER. Section 3 reviews the erosion database and the results of recent relevant experiments conducted both in laboratory facilities and in tokamaks. These data provide the experimental basis and serve as an important benchmark for both model development (discussed in Section 4) and calculations (discussed in Section 5) that are required to predict tritium inventory build-up in ITER. Section 6 emphasizes the need to develop and test methods to remove the tritium from the codeposited C-based films and reviews the status and the prospects of the most attractive techniques. Section 7 identifies the unresolved issues and provides some recommendations on potential R and D avenues for their resolution. Finally, a summary is provided in Section 8.

  11. Sorption of tritium and tritiated water on construction materials

    SciTech Connect (OSTI)

    Dickson, R.S.; Miller, J.M. . Chalk River Nuclear Labs.)

    1992-03-01

    In this paper, sorption and desorption of tritium (HT) and tritiated water (HTO) on materials to be used in the construction of fusion facilities are studied. In ca. 24-hour exposures in argon or room air, metal samples sorbed 8-200 {mu}Ci/m{sup 2} (1 Ci = 3.7 {times} 10{sup 10} Bq) of tritium form atmospheres of 5-9 Ci/m{sup 3} HT, and non-metallic samples sorbed 60-800 {mu}Ci/m{sup 2} from atmospheres of 14 Ci/m{sup 3} HT. Sorption of HTO varied much more widely than HT sorption for different samples, ranging from 4 {mu}Ci/m{sup 2} for glass to 1,300,000 {mu}Ci/m{sup 3} HTO in room air. Time dependence of desorption in dry air showed a rapid initial process and a slower secondary process.

  12. Titanium for long-term tritium storage

    SciTech Connect (OSTI)

    Heung, L.K.

    1994-12-01

    Due to the reduction of nuclear weapon stockpile, there will be an excess of tritium returned from the field. The excess tritium needs to be stored for future use, which might be several years away. A safe and cost effective means for long term storage of tritium is needed. Storing tritium in a solid metal tritide is preferred to storing tritium as a gas, because a metal tritide can store tritium in a compact form and the stored tritium will not be released until heat is applied to increase its temperature to several hundred degrees centigrade. Storing tritium as a tritide is safer and more cost effective than as a gas. Several candidate metal hydride materials have been evaluated for long term tritium storage. They include uranium, La-Ni-Al alloys, zirconium and titanium. The criteria used include material cost, radioactivity, stability to air, storage capacity, storage pressure, loading and unloading conditions, and helium retention. Titanium has the best combination of properties and is recommended for long term tritium storage.

  13. EFFECTS OF TRITIUM EXPOSURE ON UHMW-PE, PTFE, AND VESPEL

    SciTech Connect (OSTI)

    Clark, E; Kirk Shanahan, K

    2006-05-31

    Samples of three polymers, Ultra-High Molecular Weight Polyethylene (UHMW-PE), polytetrafluoroethylene (PTFE, also known as Teflon{reg_sign}), and Vespel{reg_sign} polyimide were exposed to 1 atmosphere of tritium gas at ambient temperature for varying times up to 2.3 years in closed containers. Sample mass and size measurements (to calculate density), spectra-colorimetry, dynamic mechanical analysis (DMA), and Fourier-transform infrared spectroscopy (FT-IR) were employed to characterize the effects of tritium exposure on these samples. Changes of the tritium exposure gas itself were characterized at the end of exposure by measuring total pressure and by mass spectroscopic analysis of the gas composition. None of the polymers exhibited significant changes of density. The color of initially white UHMW-PE and PTFE dramatically darkened to the eye and the color also significantly changed as measured by colorimetry. The bulk of UHMW-PE darkened just like the external surfaces, however the fracture surface of PTFE appeared white compared to the PTFE external surfaces. The white interior could have been formed while the sample was breaking or could reflect the extra tritium dose at the surface directly from the gas. The dynamic mechanical response of UHMW-PE was typical of radiation effects on polymers- an initial stiffening (increased storage modulus) and reduction of viscous behavior after three months exposure, followed by lowering of the storage modulus after one year exposure and longer. The storage modulus of PTFE increased through about nine months tritium exposure, then the samples became too weak to handle or test using DMA. Characterization of Vespel{reg_sign} using DMA was problematic--sample-to-sample variations were significant and no systematic change with tritium exposure could be discerned. Isotopic exchange and incorporation of tritium into UHMW-PE (exchanging for protium) and into PTFE (exchanging for fluorine) was observed by FT-IR using an attenuated total reflectance method. No significant change in the Vespel{reg_sign} infrared spectrum was observed after three months exposure. Protium significantly pressurized the UHMW-PE containers during exposure to about nine atmospheres (the initial pressure was one atmosphere of tritium). This is consistent with the well-known production of hydrogen by irradiation of polyethylene by ionizing radiation. The total pressure in the PTFE containers decreased, and a mass balance reveals that the observed decrease is consistent with the formation of small amounts of {sup 3}HF, which is condensed at ambient temperature. No significant change of pressure occurred in the Vespel{reg_sign} containers; however the composition of the gas became about 50% protium, showing that Vespel{reg_sign} interacted with the tritium gas atmosphere to some degree. The relative resistance to degradation from tritium exposure is least for PTFE, more for UHMW-PE, and the most for Vespel{reg_sign}, which is consistent with the known relative resistance of these polymers to gamma irradiation. This qualitatively agrees with the concept of equivalent effects for equivalent absorbed doses of radiation damage of polymers. Some of the changes of different polymers are qualitatively similar; however each polymer exhibited unique property changes when exposed to tritium. Information from this study that can be applied to a tritium facility is: (1) the relative resistance to tritium degradation of the three polymers studied is the same as the relative resistance to gamma irradiation in air (so relative rankings of polymer resistance to ionizing radiation can be used as a relative ranking for assessing tritium compatibility and polymer selection); and (2) all three polymers changed the gas atmosphere during tritium exposure--UHMW-PE and Vespel{reg_sign} exposed to tritium formed H{sub 2} gas (UHMW-PE much more so), and PTFE exposed to tritium formed {sup 3}HF. This observation of forming {sup 3}HF supports the general concept of minimizing chlorofluorocarbon polymers in tritium systems.

  14. Tritium Handling and Safe Storage

    Energy Savers [EERE]

    DOE-HDBK-1129-2008 December 2008 DOE HANDBOOK TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS DOE-HDBK-1129-2008 ii This page is intentionally blank. DOE-HDBK-1129-2008 iii TABLE OF CONTENTS SECTION PAGE FOREWORD................................................................................................................................ ix ACRONYMS

  15. Tritium Handling and Safe Storage

    Energy Savers [EERE]

    SENSITIVE DOE-HDBK-1129-2007 March 2007 ____________________ DOE HANDBOOK TRITIUM HANDLING AND SAFE STORAGE U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1129-2007 ii This page is intentionally blank. DOE-HDBK-1129-2007 iii TABLE OF CONTENTS SECTION PAGE FOREWORD............................................................................................................................... vii

  16. Introduction to Airborne Tritium Tritides

    Office of Environmental Management (EM)

    OVER 65 YEARS OF RADIATION DETECTION & MEASURMENT SOLUTIONS US NUCLEAR CORP INTRODUCTION AIRBORNE TRITIUM TRITIDES HYDRIDES - An Anion of Hydrogen Compounds containing hydrogen bonded to metals or metalloid may be referred to as hydrides A hydride is a compound formed by hydrogen and another, usually more electropositive, element or group. Almost all of the elements form binary compounds with hydrogen (exceptions being He, Ne, Ar, Kr, Pm, Os, Ir, Rn, Fr, and Ra). There are three main types

  17. DEPLOYMENT OF THE BULK TRITIUM SHIPPING PACKAGE

    SciTech Connect (OSTI)

    Blanton, P.

    2013-10-10

    A new Bulk Tritium Shipping Package (BTSP) was designed by the Savannah River National Laboratory to be a replacement for a package that has been used to ship tritium in a variety of content configurations and forms since the early 1970s. The BTSP was certified by the National Nuclear Safety Administration in 2011 for shipments of up to 150 grams of Tritium. Thirty packages were procured and are being delivered to various DOE sites for operational use. This paper summarizes the design features of the BTSP, as well as associated engineered material improvements. Fabrication challenges encountered during production are discussed as well as fielding requirements. Current approved tritium content forms (gas and tritium hydrides), are reviewed, as well as, a new content, tritium contaminated water on molecular sieves. Issues associated with gas generation will also be discussed.

  18. Is Tritium Over-Regulated, Part 2 Should The TFG Support Higher Tritium Threshold Values?

    Broader source: Energy.gov [DOE]

    Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014.

  19. CHARTER OF THE TRITIUM FOCUS GROUP (TFG)

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

    CHARTER OF THE TRITIUM FOCUS GROUP (TFG) APRIL 2013 PURPOSE - The purpose of the TFG, a Standing DOE Working Group, is to promote cost-effective improvements in tritium safety, handling, transportation, storage, and operations, and to enhance communication across the Department of Energy (DOE) (inclusive of the National Nuclear Security Administration (NNSA)) on all matters related to tritium. OBJECTIVES - The objectives of the TFG include: 1. Serving as an efficient forum for communication and

  20. Recovery of tritium from tritiated molecules

    DOE Patents [OSTI]

    Swansiger, W.A.

    1984-10-17

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

  1. TRITIUM IN-BED ACCOUNTABILITY FOR A PASSIVELY COOLED, ELECTRICALLY HEATED HYDRIDE BED

    SciTech Connect (OSTI)

    Klein, J.; Foster, P.

    2011-01-21

    A PAssively Cooled, Electrically heated hydride (PACE) Bed has been deployed into tritium service in the Savannah River Site (SRS) Tritium Facilities. The bed design, absorption and desorption performance, and cold (non-radioactive) in-bed accountability (IBA) results have been reported previously. Six PACE Beds were fitted with instrumentation to perform the steady-state, flowing gas calorimetric inventory method. An IBA inventory calibration curve, flowing gas temperature rise ({Delta}T) versus simulated or actual tritium loading, was generated for each bed. Results for non-radioactive ('cold') tests using the internal electric heaters and tritium calibration results are presented. Changes in vacuum jacket pressure significantly impact measured IBA {Delta}T values. Higher jacket pressures produce lower IBA {Delta}T values which underestimate bed tritium inventories. The exhaust pressure of the IBA gas flow through the bed's U-tube has little influence on measured IBA {Delta}T values, but larger gas flows reduce the time to reach steady-state conditions and produce smaller tritium measurement uncertainties.

  2. Tritium Gas Processing for Magnetic Fusion

    Office of Environmental Management (EM)

    ... Conceptual Design Process Flow Diagram RAMI Value Engineering 16 Design Approach 16 ... Cleanup Storage Trace Tritium Removal Molecular Sieve Train Catalytic Reactor Permeator ...

  3. A Plan for Modularization of Tritium Components

    Office of Environmental Management (EM)

    plan for Modularization of Tritium Components Randy Davis Davis Consultants M-TRT-H-00089 Savannah River Nuclear Solutions, LLC April 22, 2014 M-TRT-H-00089 Current Approach * All "tritium wetted components" are located inside a glovebox - Why * Explosion Prevention - Ar/N2 filled * Fire Prevention - Ar/N2 filled * Tritium Leak/Spill Mitigation * Tritium Leak/Spill Recapture - Strippers * Provides access to components for maintenance 2 M-TRT-H-00089 Current Approach 3 TEF 249H ATLAS

  4. Tritium High Vacuum Pump Test Plan

    Office of Environmental Management (EM)

    High Vacuum Pump Test Plan Tritium Programs Engineering Louis Boone Joel Bennett ... Shimming will have to be internal to the pump. Test System Measure ultimate vacuum with ...

  5. Reclassification of the Tritium Research Laboratory

    SciTech Connect (OSTI)

    Johnson, A.J.

    1997-01-01

    This document is a collection of the required actions that were taken to reclassify Building 968, the Tritium Research Laboratory, at Sandia National Laboratories/California.

  6. CHARTER OF THE TRITIUM FOCUS GROUP (TFG)

    Office of Environmental Management (EM)

    and coordination of tritium issues and activities across the DOE complex and beyond. 2. Promoting sharing and application of state-of-the-art design and engineering...

  7. Methods to Improve the Lower Limit of Detection for Tritium...

    Office of Environmental Management (EM)

    Tritium Surface Contamination 10,000 DPM100 cm 2 STCs are Special Tritium Compounds STCs as metal tritides MAY be the MOST dangerous of ALL tritium forms. One case of death due to ...

  8. Meeting Attendance - 32nd Tritium Focus Group Meeting | Department...

    Office of Environmental Management (EM)

    2nd Tritium Focus Group Meeting Meeting Attendance - 32nd Tritium Focus Group Meeting Attendees to the 32nd Tritium Focus Group Meeting held in Germantown, Maryland, April 23-25,...

  9. Meeting Attendance - 35th Tritium Focus Group Meeting | Department...

    Office of Environmental Management (EM)

    5th Tritium Focus Group Meeting Meeting Attendance - 35th Tritium Focus Group Meeting Attendees to the 35th Tritium Focus Group Meeting held in Princeton, NJ on May 5-7, 2015. PDF...

  10. Meeting Attendance - 33rd Tritium Focus Group Meeting | Department of

    Office of Environmental Management (EM)

    Energy 3rd Tritium Focus Group Meeting Meeting Attendance - 33rd Tritium Focus Group Meeting Attendees to the 33rd Tritium Focus Group Meeting, held in Aiken, South Carolina, April 22-24, 2014. PDF icon Meeting Attendance - 33rd Tritium Focus Group Meeting More Documents & Publications Meeting Attendance - 32nd Tritium Focus Group Meeting Tritium Instrument Demonstration Station (TIDS) Tritiated Water Challenge in Fukushima Daiichi

  11. Overview of AECL's Tritium Compatible Electrolyser Program | Department

    Office of Environmental Management (EM)

    of Energy AECL's Tritium Compatible Electrolyser Program Overview of AECL's Tritium Compatible Electrolyser Program Presentation from the 34th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014. PDF icon Overview of AECL's Tritium Compatible Electrolyser Program More Documents & Publications Tritium R&D at AECL Selected Topics Chalk River Tritium Activities: Select Topics Comparison of Water-Hydrogen Catalytic Exchange Processes Versus Water Distillation

  12. TRITIUM EFFECTS ON WELDMENT FRACTURE TOUGHNESS

    SciTech Connect (OSTI)

    Morgan, M; Michael Tosten, M; Scott West, S

    2006-07-17

    The effects of tritium on the fracture toughness properties of Type 304L stainless steel and its weldments were measured. Fracture toughness data are needed for assessing tritium reservoir structural integrity. This report provides data from J-Integral fracture toughness tests on unexposed and tritium-exposed weldments. The effect of tritium on weldment toughness has not been measured until now. The data include tests on tritium-exposed weldments after aging for up to three years to measure the effect of increasing decay helium concentration on toughness. The results indicate that Type 304L stainless steel weldments have high fracture toughness and are resistant to tritium aging effects on toughness. For unexposed alloys, weldment fracture toughness was higher than base metal toughness. Tritium-exposed-and-aged base metals and weldments had lower toughness values than unexposed ones but still retained good toughness properties. In both base metals and weldments there was an initial reduction in fracture toughness after tritium exposure but little change in fracture toughness values with increasing helium content in the range tested. Fracture modes occurred by the dimpled rupture process in unexposed and tritium-exposed steels and welds. This corroborates further the resistance of Type 304L steel to tritium embrittlement. This report fulfills the requirements for the FY06 Level 3 milestone, TSR15.3 ''Issue summary report for tritium reservoir material aging studies'' for the Enhanced Surveillance Campaign (ESC). The milestone was in support of ESC L2-1866 Milestone-''Complete an annual Enhanced Surveillance stockpile aging assessment report to support the annual assessment process''.

  13. The Princeton Tritium Observatory for Light, Early Universe,...

    Office of Environmental Management (EM)

    The Princeton Tritium Observatory for Light, Early Universe, Massive Neutrino Yield (PTOLEMY) The Princeton Tritium Observatory for Light, Early Universe, Massive Neutrino Yield...

  14. Methods for Post Irradiation Examination of Tritium Producing...

    Office of Environmental Management (EM)

    Methods for Post Irradiation Examination of Tritium Producing Burnable Absorber Rods Methods for Post Irradiation Examination of Tritium Producing Burnable Absorber Rods...

  15. In-Reactor Measurement of Tritium Permeation through Stainless...

    Office of Environmental Management (EM)

    In-Reactor Measurement of Tritium Permeation through Stainless Steel Cladding In-Reactor Measurement of Tritium Permeation through Stainless Steel Cladding Presentation from the...

  16. Fermilab | Tritium at Fermilab | Tritium released into the air and disposed

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

    of as solid waste Tritium released into the air and disposed of as solid waste Fermilab produces tritium as an expected byproduct of accelerator operations. The lab actively manages tritium, using and disposing of it in ways that pose no health or environmental threat. One of the ways that tritium is discharged from the Fermilab site is by releasing it into the air. This release occurs in various ways. Tritium in the form of water vapor is emitted into the air through ventilation systems

  17. Thermal Removal of Tritium from Concrete and Soil to Reduce Groundwater Impacts - 13197

    SciTech Connect (OSTI)

    Jackson, Dennis G.; Blount, Gerald C.; Wells, Leslie H.; Cardoso, Joao E.; Kmetz, Thomas F.; Reed, Misty L.

    2013-07-01

    Legacy heavy-water moderator operations at the Savannah River Site (SRS) have resulted in the contamination of equipment pads, building slabs, and surrounding soil with tritium. At the time of discovery the tritium had impacted the shallow (< 3-m) groundwater at the facility. While tritium was present in the groundwater, characterization efforts determined that a significant source remained in a concrete slab at the surface and within the associated vadose zone soils. To prevent continued long-term impacts to the shallow groundwater a CERCLA non-time critical removal action for these source materials was conducted to reduce the leaching of tritium from the vadose zone soils and concrete slabs. In order to minimize transportation and disposal costs, an on-site thermal treatment process was designed, tested, and implemented. The on-site treatment consisted of thermal detritiation of the concrete rubble and soil. During this process concrete rubble was heated to a temperature of 815 deg. C (1,500 deg. F) resulting in the dehydration and removal of water bound tritium. During heating, tritium contaminated soil was used to provide thermal insulation during which it's temperature exceeded 100 deg. C (212 deg. F), causing drying and removal of tritium. The thermal treatment process volatiles the water bound tritium and releases it to the atmosphere. The released tritium was considered insignificant based upon Clean Air Act Compliance Package (CAP88) analysis and did not exceed exposure thresholds. A treatability study evaluated the effectiveness of this thermal configuration and viability as a decontamination method for tritium in concrete and soil materials. Post treatment sampling confirmed the effectiveness at reducing tritium to acceptable waste site specific levels. With American Recovery and Reinvestment Act (ARRA) funding three additional treatment cells were assembled utilizing commercial heating equipment and common construction materials. This provided a total of four units to batch treat concrete rubble and soil. Post treatment sampling verified that the activity in the treated soil and concrete met the treatment standards for each medium which allowed the treated concrete rubble and soil to be disposed of on-site as backfill. During testing and operations a total of 1,261-m{sup 3} (1,650-yd{sup 3}) of contaminated concrete and soils were treated with an actual incurred cost of $3,980,000. This represents a unit treatment cost of $3,156/m{sup 3} ($2,412/yd{sup 3}). In 2011 the project was recognized with an e-Star Sustainability Award by DOE's Office of Environmental Management. (authors)

  18. Tritium research laboratory cleanup and transition project final report

    SciTech Connect (OSTI)

    Johnson, A.J.

    1997-02-01

    This Tritium Research Laboratory Cleanup and Transition Project Final Report provides a high-level summary of this project`s multidimensional accomplishments. Throughout this report references are provided for in-depth information concerning the various topical areas. Project related records also offer solutions to many of the technical and or administrative challenges that such a cleanup effort requires. These documents and the experience obtained during this effort are valuable resources to the DOE, which has more than 1200 other process contaminated facilities awaiting cleanup and reapplication or demolition.

  19. Charter of the Tritium Focus Group (TFG)

    Broader source: Energy.gov [DOE]

    The purpose of the TFG, a Standing DOE Working Group, is to promote cost-effective improvements in tritium safety, handling, transportation, storage, and operations, and to enhance communication across the Department of Energy (DOE) (inclusive of the National Nuclear Security Administration (NNSA)) on all matters related to tritium.

  20. Scale-Up of Palladium Powder Production Process for Use in the Tritium Facility at Westinghouse, Savannah River, SC/Summary of FY99-FY01 Results for the Preparation of Palladium Using the Sandia/LANL Process

    SciTech Connect (OSTI)

    David P. Baldwin; Daniel S. Zamzow; R. Dennis Vigil; Jesse T. Pikturna

    2001-08-24

    Palladium used at Savannah River (SR) for process tritium storage is currently obtained from a commercial source. In order to understand the processes involved in preparing this material, SR is supporting investigations into the chemical reactions used to synthesize this material. The material specifications are shown in Table 1. An improved understanding of the chemical processes should help to guarantee a continued reliable source of Pd in the future. As part of this evaluation, a work-for-others contract between Westinghouse Savannah River Company and Ames Laboratory (AL) was initiated. During FY98, the process for producing Pd powder developed in 1986 by Dan Grove of Mound Applied Technologies, USDOE (the Mound muddy water process) was studied to understand the processing conditions that lead to changes in morphology in the final product. During FY99 and FY00, the process for producing Pd powder that has been used previously at Sandia and Los Alamos National Laboratories (the Sandia/LANL process) was studied to understand the processing conditions that lead to changes in the morphology of the final Pd product. During FY01, scale-up of the process to batch sizes greater than 600 grams of Pd using a 20-gallon Pfaudler reactor was conducted by the Iowa State University (ISU) Chemical Engineering Department. This report summarizes the results of FY99-FY01 Pd processing work done at AL and ISU using the Sandia/LANL process. In the Sandia/LANL process, Pd is dissolved in a mixture of nitric and hydrochloric acids. A number of chemical processing steps are performed to yield an intermediate species, diamminedichloropalladium (Pd(NH{sub 3}){sub 2}Cl{sub 2}, or DADC-Pd), which is isolated. In the final step of the process, the Pd(NH{sub 3}){sub 2}Cl{sub 2} intermediate is subsequently redissolved, and Pd is precipitated by the addition of a reducing agent (RA) mixture of formic acid and sodium formate. It is at this point that the morphology of the Pd product is determined. During FY99 and FY00, a study of how the characteristics of the Pd are affected by changes in processing conditions including the RA/Pd molar ratio, Pd concentration, mole fraction of formic acid (mf-FA) in the RA solution, reaction temperature, and mixing was performed. These parameters all had significant effects on the resulting values of the tap density (TD), BET surface area (SA), and Microtrac particle size (PS) distribution for the Pd samples. These effects were statistically modeled and fit in order to determine ranges of predicted experimental conditions that resulted in material that meets the requirements for the Pd powder to be used at SR. Although not statistically modeled, the method and rate of addition of the RA and the method and duration of stirring were shown to be significant factors affecting the product morphology. Instead of producing an additional statistical fit and due to the likely changes anticipated during scale-up of this processing procedure, these latter conditions were incorporated into a reproducible practical method of synthesis. Palladium powder that met the SR specifications for TD, BET SA, and Microtrac PS was reliably produced at batch sizes ranging from 25-100 grams. In FY01, scale-up of the Sandia/LANL process was investigated by the ISU Chemical Engineering Department for the production of 600-gram batches of Pd. Palladium that meets the SR specifications for TD, BET SA, and Microtrac PS has been produced using the Pfaudler reactor, and additional processing batches will be done during the remainder of FY01 to investigate the range of conditions that can be used to produce Pd powder within specifications. Palladium product samples were analyzed at AL and SR to determine TD and at SR to determine BET SA, Microtrac PS distribution, and Pd nodule size and morphology by scanning electron microscopy (SEM).

  1. DOE handbook: Tritium handling and safe storage

    SciTech Connect (OSTI)

    1999-03-01

    The DOE Handbook was developed as an educational supplement and reference for operations and maintenance personnel. Most of the tritium publications are written from a radiological protection perspective. This handbook provides more extensive guidance and advice on the null range of tritium operations. This handbook can be used by personnel involved in the full range of tritium handling from receipt to ultimate disposal. Compliance issues are addressed at each stage of handling. This handbook can also be used as a reference for those individuals involved in real time determination of bounding doses resulting from inadvertent tritium releases. This handbook provides useful information for establishing processes and procedures for the receipt, storage, assay, handling, packaging, and shipping of tritium and tritiated wastes. It includes discussions and advice on compliance-based issues and adds insight to those areas that currently possess unclear DOE guidance.

  2. Thermal Release of 3He from Tritium Aged LaNi4.25Al0.75 Hydride

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

    Staack, Gregory C.; Crowder, Mark L.; Klein, James E.

    2015-02-01

    Recently, the demand for He-3 has increased dramatically due to widespread use in nuclear nonproliferation, cryogenic, and medical applications. Essentially all of the world’s supply of He-3 is created by the radiolytic decay of tritium. The Savannah River Site Tritium Facilities (SRS-TF) utilizes LANA.75 in the tritium process to store hydrogen isotopes. The vast majority of He-3 “born” from tritium stored in LANA.75 is trapped in the hydride metal matrix. The SRS-TF has multiple LANA.75 tritium storage beds that have been retired from service with significant quantities of He-3 trapped in the metal. To support He-3 recovery, the Savannah Rivermore » National Laboratory (SRNL) conducted thermogravimetric analysis coupled with mass spectrometry (TGA-MS) on a tritium aged LANA.75 sample. TGA-MS testing was performed in an argon environment. Prior to testing, the sample was isotopically exchanged with deuterium to reduce residual tritium and passivated with air to alleviate pyrophoric concerns associated with handling the material outside of an inert glovebox. Analyses indicated that gas release from this sample was bimodal, with peaks near 220 and 490°C. The first peak consisted of both He-3 and residual hydrogen isotopes, the second was primarily He-3. The bulk of the gas was released by 600 °C« less

  3. Tritium Design Practices: Part 2 | Department of Energy

    Office of Environmental Management (EM)

    Design Practices: Part 2 Tritium Design Practices: Part 2 Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013. PDF icon Tritium Design Practices: Part 2 More Documents & Publications Tritium on Metal Surfaces DOE-HDBK-1105-2002

  4. Tritium Instrument Demonstration Station (TIDS) | Department of Energy

    Office of Environmental Management (EM)

    3rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Tritium Instrument Demonstration Station (TIDS) More Documents & Publications Tritium Instrument Demonstration Station (TIDS) Tritium Instrument Demonstration Station (TIDS) Analysis of Waste Isolation Pilot Plant (WIPP) Samples by the Savannah River National Laboratory (SRNL)

  5. Particulate Generation in a Tritium System | Department of Energy

    Office of Environmental Management (EM)

    Particulate Generation in a Tritium System Particulate Generation in a Tritium System Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Particulate Generation in a Tritium System More Documents & Publications Fuel Injector Holes Fuel Injector Holes Fuel injector Holes (Fabrication of Micro-Orifices for Fuel Injectors)

  6. Tritium monitor with improved gamma-ray discrimination

    DOE Patents [OSTI]

    Cox, Samson A.; Bennett, Edgar F.; Yule, Thomas J.

    1985-01-01

    Apparatus and method for selective measurement of tritium oxide in an environment which may include other radioactive components and gamma radiation, the measurement including the selective separation of tritium oxide from a sample gas through a membrane into a counting gas, the generation of electrical pulses individually representative by rise times of tritium oxide and other radioactivity in the counting gas, separation of the pulses by rise times, and counting of those pulses representative of tritium oxide. The invention further includes the separate measurement of any tritium in the sample gas by oxidizing the tritium to tritium oxide and carrying out a second separation and analysis procedure as described above.

  7. Tritium monitor with improved gamma-ray discrimination

    DOE Patents [OSTI]

    Cox, S.A.; Bennett, E.F.; Yule, T.J.

    1982-10-21

    Apparatus and method are presented for selective measurement of tritium oxide in an environment which may include other radioactive components and gamma radiation, the measurement including the selective separation of tritium oxide from a sample gas through a membrane into a counting gas, the generation of electrical pulses individually representative by rise times of tritium oxide and other radioactivity in the counting gas, separation of the pulses by rise times, and counting of those pulses representative of tritium oxide. The invention further includes the separate measurement of any tritium in the sample gas by oxidizing the tritium to tritium oxide and carrying out a second separation and analysis procedure as described above.

  8. Facility Survey & Transfer | Department of Energy

    Energy Savers [EERE]

    Survey & Transfer Facility Survey & Transfer As DOE facilities become excess, many that are radioactively and/or chemically contaminated will become candidate for transfer to DOE-EM for deactivation and decommissioning. PDF icon Facility Survey & Transfer More Documents & Publications Decommissioning Handbook Post-Deactivation Surveillance and Maintenance Planning Report of Survey of the Los Alamos Tritium Systems Test Assembly Facility

  9. Is Tritium Over-regulated, Part 2: Should the TFG Support Higher Tritium Threshold Values?

    Office of Environmental Management (EM)

    U N C L A S S I F I E D Slide 1 Is Tritium Over-Regulated, Part 2 Should The TFG Support Higher Tritium Threshold Values? (LA-UR-14-22479) Mike Rogers W-7, Gas Transfer Systems April, 2014 Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA U N C L A S S I F I E D Slide 2 Category 3 threshold Category 2 threshold DOE-STD-027-92 1.6 grams (tritium) 30 grams (tritium) 8.4 grams (Pu-239) 900 grams (Pu-239) NA-1 SD-G 1027 0.87 grams (tritium) 62.4 grams (tritium)

  10. Microsoft Word - fact sheet Tritium 082814.docx

    National Nuclear Security Administration (NNSA)

    Tritium WHAT IS TRITIUM? Tritium is an isotope of hydrogen that occurs naturally in very small quantities. Hydrogen has three isotopes:  Protium Ordinary hydrogen with one proton and one electron in the atom. When two atoms of protium are combined with one atom of oxygen, water is created. Ordinary hydrogen comprises over 99.9 percent of all naturally occurring hydrogen.  Deuterium Sometimes called "heavy hydrogen," a non-radioactive isotope that has a neutron in the atom, in

  11. THERMAL ENHANCEMENT CARTRIDGE HEATER MODIFIED TECH MOD TRITIUM HYDRIDE BED DEVELOPMENT PART I DESIGN AND FABRICATION

    SciTech Connect (OSTI)

    Klein, J.; Estochen, E.

    2014-03-06

    The Savannah River Site (SRS) tritium facilities have used 1{sup st} generation (Gen1) LaNi{sub 4.25}Al{sub 0.75} (LANA0.75) metal hydride storage beds for tritium absorption, storage, and desorption. The Gen1 design utilizes hot and cold nitrogen supplies to thermally cycle these beds. Second and 3{sup rd} generation (Gen2 and Gen3) storage bed designs include heat conducting foam and divider plates to spatially fix the hydride within the bed. For thermal cycling, the Gen2 and Gen 3 beds utilize internal electric heaters and glovebox atmosphere flow over the bed inside the bed external jacket for cooling. The currently installed Gen1 beds require replacement due to tritium aging effects on the LANA0.75 material, and cannot be replaced with Gen2 or Gen3 beds due to different designs of these beds. At the end of service life, Gen1 bed desorption efficiencies are limited by the upper temperature of hot nitrogen supply. To increase end-of-life desorption efficiency, the Gen1 bed design was modified, and a Thermal Enhancement Cartridge Heater Modified (TECH Mod) bed was developed. Internal electric cartridge heaters in the new design to improve end-of-life desorption, and also permit in-bed tritium accountability (IBA) calibration measurements to be made without the use of process tritium. Additional enhancements implemented into the TECH Mod design are also discussed.

  12. Evaluation of selected ex-reactor accidents related to the tritium and medical isotope production mission at the FFTF

    SciTech Connect (OSTI)

    Himes, D.A.

    1997-11-17

    The Fast Flux Test Facility (FFTF) has been proposed as a production facility for tritium and medical isotopes. A range of postulated accidents related to ex-reactor irradiated fuel and target handling were identified and evaluated using new source terms for the higher fuel enrichment and for the tritium and medical isotope targets. In addition, two in-containment sodium spill accidents were re-evaluated to estimate effects of increased fuel enrichment and the presence of the Rapid Retrieval System. Radiological and toxicological consequences of the analyzed accidents were found to be well within applicable risk guidelines.

  13. Tritium Detection Methods and Limitations | Department of Energy

    Office of Environmental Management (EM)

    Detection Methods and Limitations Tritium Detection Methods and Limitations Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Tritium Detection Methods and Limitations More Documents & Publications Methods to Improve the Lower Limit of Detectionfor Tritium in the Air and on Surfaces Improved Monitor Design and Configuration for Reducing Reported Tritium Discharges from the Orphee Research Reactor

  14. Meeting Attendance - 34th Tritium Focus Group Meeting | Department of

    Office of Environmental Management (EM)

    Energy 4th Tritium Focus Group Meeting Meeting Attendance - 34th Tritium Focus Group Meeting Attendees to the 34th Tritium Focus Group Meeting held in Idaho Falls, ID on September 23-25, 2014. PDF icon Meeting Attendance - 34th Tritium Focus Group Meeting More Documents & Publications Technological Assessment of Plasma Facing Components for DEMO Reactors Overview of tritium activity in Japan H-Sensors and Fusion Work at SNL-CA

  15. Overview of the Tritium research activities at Lawrence Livermore National

    Office of Environmental Management (EM)

    Laboratory (LLNL) | Department of Energy the Tritium research activities at Lawrence Livermore National Laboratory (LLNL) Overview of the Tritium research activities at Lawrence Livermore National Laboratory (LLNL) Presentation from the 35th Tritium Focus Group Meeting held in Princeton, New Jersey on May 05-07, 2015. PDF icon Overview of the Tritium research activities at LLNL More Documents & Publications Overview of Tritium Activities at the Laboratory for Laser Energetics NIF

  16. DOE - Office of Legacy Management -- Rulsion Tritium Transport Model

    Office of Legacy Management (LM)

    Rulsion Tritium Transport Model Rulison, Colorado, Site Tritium Transport Model Tritium Transport at the Rulison Site, a Nuclear-Stimulated Low-Permeability Natural Gas Reservoir, September 2007 pdf_icon Tritium Transport Model Comments and Responses Colorado Oil and Gas Conservation Commission Colorado Department of Public Health and Environment Gateway Enterprises Addendum: Tritium Transport at the Rulison Site, a Nuclear-stimulated Low-permeability Natural Gas Reservoir, January 2009 pdf_icon

  17. Tritium Behavior in Lead Lithium Eutectic (LLE) at Low Tritium Partial Pressure

    Office of Environmental Management (EM)

    Behavior in Lead Lithium Eutectic (LLE) at Low Tritium Partial Pressure 33 rd Tritium Focus Group meeting, Savannah River National Laboratory, SC Masashi Shimada, Ph.D. Fusion Safety Program, Idaho National Laboratory, STIMS # INL/MS-14-31893| Savannah River National Laboratory, SC | April 25, 2014 Outlines 1. Motivation 2. Experimental apparatus 3. TMAP modeling 4. Experimental results 5. Modeling results 6. Future work M.Shimada | Tritium Focus Group meeting | SRNL, SC | April 25, 2014 2

  18. Tritium containing polymers having a polymer backbone substantially void of tritium

    DOE Patents [OSTI]

    Jensen, G.A.; Nelson, D.A.; Molton, P.M.

    1992-03-31

    A radioluminescent light source comprises a solid mixture of a phosphorescent substance and a tritiated polymer. The solid mixture forms a solid mass having length, width, and thickness dimensions, and is capable of self-support. In one aspect of the invention, the phosphorescent substance comprises solid phosphor particles supported or surrounded within a solid matrix by a tritium containing polymer. The tritium containing polymer comprises a polymer backbone which is essentially void of tritium. 2 figs.

  19. Tritium containing polymers having a polymer backbone substantially void of tritium

    DOE Patents [OSTI]

    Jensen, George A. (Richland, WA); Nelson, David A. (Richland, WA); Molton, Peter M. (Richland, WA)

    1992-01-01

    A radioluminescent light source comprises a solid mixture of a phosphorescent substance and a tritiated polymer. The solid mixture forms a solid mass having length, width, and thickness dimensions, and is capable of self-support. In one aspect of the invention, the phosphorescent substance comprises solid phosphor particles supported or surrounded within a solid matrix by a tritium containing polymer. The tritium containing polymer comprises a polymer backbone which is essentially void of tritium.

  20. Guide to user facilities at the Lawrence Berkeley Laboratory

    SciTech Connect (OSTI)

    Not Available

    1984-04-01

    Lawrence Berkeley Laboratories' user facilities are described. Specific facilities include: the National Center for Electron Microscopy; the Bevalac; the SuperHILAC; the Neutral Beam Engineering Test Facility; the National Tritium Labeling Facility; the 88 inch Cyclotron; the Heavy Charged-Particle Treatment Facility; the 2.5 MeV Van de Graaff; the Sky Simulator; the Center for Computational Seismology; and the Low Background Counting Facility. (GHT)

  1. Tritium Leak Detection: Strategies and Applications

    Office of Environmental Management (EM)

    Oxide *Locating the Point of Release *Real-time Measurement 3 The required radiological ... A tritium monitor configured as a "sniffer" to provide real-time indication of the T2 and ...

  2. EIS-0161: Tritium Supply and Recycling

    Broader source: Energy.gov [DOE]

    This PEIS evaluates the potential environmental impacts of technology and siting alternatives for the production of tritium for national security purposes as well as the impacts of constructing a...

  3. Fermilab | Tritium at Fermilab | Ferry Creek Results

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

    has been taken and analyzed. For samples in which a level of tritium above the limit of detection has been measured, the uncertainty of the measurement is indicated by an error...

  4. Secure Wireless Tritium Air Monitoring Cart Development

    Office of Environmental Management (EM)

    Wireless Tritium Air Monitoring Cart Development PDRD Projects #SR13020, SR14058 Davie Shull and Joe Cordaro Research and Development Engineering Tritium Focus Group Meeting April 24, 2014 Acknowledgements * SRNL Team - Software Development * Matt Folsom * Joel Jones - Engineering Design * David McFall * Monica Phillips * Chad Sweeney - Electrical Fabrication * Kevin Tietze * Don Varble * George Graham - Drafting / Designer * Larry Feutral * Ken Meeler - Procurement * Linda Gray * Jim Buchanan -

  5. Fermilab | Tritium at Fermilab | Indian Creek Results

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

    Indian Creek Results chart This chart (click chart for larger version) shows the levels of tritium in Indian Creek since November 2005, when our environmental monitoring program detected low levels of tritium in Indian Creek for the first time in its 35-year history, well below the federal water standards that Fermilab is required to meet. The detection limit is one picocurie per milliliter (see footnote below). Fermilab continues to monitor Indian Creek frequently and the results are displayed

  6. Vanadium hydride deuterium-tritium generator

    DOE Patents [OSTI]

    Christensen, L.D.

    1980-03-13

    A pressure controlled vanadium hydride gas generator was designed to provide deuterium-tritium gas in a series of pressure increments. A high pressure chamber filled with vanadium-deuterium-tritium hydride is surrounded by a heater which controls the hydride temperature. The heater is actuated by a power controller which responds to the difference signal between the actual pressure signal and a programmed pressure signal.

  7. Microsoft Word - PTC-Tritium-monitoring.docx

    Office of Environmental Management (EM)

    Monitoring of Tritium release at PTC. Scope of the project From more than 20 projects supported by Equipment Manufacturing Support group this is one of the simplest. What is nice about it is that elegant programming technique was used to obtain necessary reliability. Radioactive gas Tritium is used here at PTC for the manufacturing of Minitrons (nutron generators). Because of the personnel safety concerns and environmental regulation the release of the gas into environment should be monitored

  8. Tritium evolution from various morphologies of palladium

    SciTech Connect (OSTI)

    Tuggle, D.G.; Claytor, T.N.; Taylor, S.F. |

    1994-04-01

    The authors have been able to extend the tritium production techniques to various novel morphologies of palladium. These include small solid wires of various diameters and a type of pressed powder wire and a plasma cell. In most successful experiments, the amount of palladium required, for an equivalent tritium output, has been reduced by a factor of 100 over the older powder methods. In addition, they have observed rates of tritium production (>5 nCi/h) that far exceed most of the previous results. Unfortunately, the methods that they currently use to obtain the tritium are poorly understood and consequently there are numerous variables that need to be investigated before the new methods are as reliable and repeatable as the previous techniques. For instance, it seems that surface and/or bulk impurities play a major role in the successful generation of any tritium. In those samples with total impurity concentrations of >400 ppM essentially no tritium has been generated by the gas loading and electrical simulation methods.

  9. Recommended tritium surface contamination release guides

    SciTech Connect (OSTI)

    Johnson, J.R.; Draper, D.G.; Foulke, J.D.; Hafner, R.S.; Jalbert, R.A.; Kennedy, W.E.; Myers, D.S.; Strain, C.D. )

    1991-03-01

    This document was prepared to provide scientific basis for recommended changes in specific limits for tritium surface contamination in DOE Order 5480.11. A summary of the physical and biological characteristics of tritium has been provided that illustrate the unique nature of this radionuclide when compared to other pure beta emitters or to beta-gamma emitting radionuclides. This document is divided into nine sections. The introduction and the purpose and scope are addressed in Section 1.0 and Section 2.0, respectively. Section 3.0 contains recommended interpretation of terms used in this document. Section 4.0 addresses recommended methods for evaluating surface contamination. Biological and physical characteristics of tritium compounds are discussed in Section 5.0, as they relate to tritium radiotoxicity. Scenarios and dose calculations for selected, conservatively limiting cases of tritium intake are given and discussed in Section 6.0 and Section 7.0. Section 8.0 provides conclusions on the information given and recommendations for changes in the surface contamination limits for total tritium to 1 {times} 10{sup 6} dpm per 100 cm{sup 2}. 30 refs., 2 tabs.

  10. Method and apparatus for controlling accidental releases of tritium

    DOE Patents [OSTI]

    Galloway, Terry R. [Berkeley, CA

    1980-04-01

    An improvement in a tritium control system based on a catalytic oxidation reactor wherein accidental releases of tritium into room air are controlled by flooding the catalytic oxidation reactor with hydrogen when the tritium concentration in the room air exceeds a specified limit. The sudden flooding with hydrogen heats the catalyst to a high temperature within seconds, thereby greatly increasing the catalytic oxidation rate of tritium to tritiated water vapor. Thus, the catalyst is heated only when needed. In addition to the heating effect, the hydrogen flow also swamps the tritium and further reduces the tritium release.

  11. Method and apparatus for controlling accidental releases of tritium

    DOE Patents [OSTI]

    Galloway, T.R.

    1980-04-01

    An improvement is described in a tritium control system based on a catalytic oxidation reactor wherein accidental releases of tritium into room air are controlled by flooding the catalytic oxidation reactor with hydrogen when the tritium concentration in the room air exceeds a specified limit. The sudden flooding with hydrogen heats the catalyst to a high temperature within seconds, thereby greatly increasing the catalytic oxidation rate of tritium to tritiated water vapor. Thus, the catalyst is heated only when needed. In addition to the heating effect, the hydrogen flow also swamps the tritium and further reduces the tritium release. 1 fig.

  12. Independent Oversight Review, Savannah River Site Tritium Facilities...

    Energy Savers [EERE]

    Management Evaluations performed this review to evaluate the processes for identifying emergency response capabilities and maintaining them in a state of readiness in case of a...

  13. Advancement Of Tritium Powered Betavoltaic Battery Systems

    SciTech Connect (OSTI)

    Staack, G.; Gaillard, J.; Hitchcock, D.; Peters, B.; Colon-Mercado, H.; Teprovich, J.; Coughlin, J.; Neikirk, K.; Fisher, C.

    2015-10-14

    Due to their decades-long service life and reliable power output under extreme conditions, betavoltaic batteries offer distinct advantages over traditional chemical batteries, especially in applications where frequent battery replacement is hazardous, or cost prohibitive. Although many beta emitting isotopes exist, tritium is considered ideal in betavoltaic applications for several reasons: 1) it is a pure beta emitter, 2) the beta is not energetic enough to damage the semiconductor, 3) it has a moderately long half-life, and 4) it is readily available. Unfortunately, the widespread application of tritium powered betavoltaics is limited, in part, by their low power output. This research targets improving the power output of betavoltaics by increasing the flux of beta particles to the energy conversion device (the p-n junction) through the use of low Z nanostructured tritium trapping materials.

  14. Tritium Instrument Demonstration Station (TIDS) | Department of Energy

    Office of Environmental Management (EM)

    5th Tritium Focus Group Meeting held in Princeton, New Jersey on May 05-07, 2015

  15. Tritium Instrument Demonstration Station (TIDS) | Department of Energy

    Office of Environmental Management (EM)

    4th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014

  16. Tritium Leak Detection: Strategies and Applications | Department of Energy

    Office of Environmental Management (EM)

    Leak Detection: Strategies and Applications Tritium Leak Detection: Strategies and Applications Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Tritium Leak Detection: Strategies and Applications More Documents & Publications Test Results For Physical Separation Of Tritium From Noble Gases And It's Implications For Sensitivity And Accuracy In Air And Stack Monitoring Fusion Nuclear Science and Technology Program - Status and

  17. Tritium Plasma Experiment and Its Role in PHENIX Program

    Broader source: Energy.gov [DOE]

    Presentation from the 34th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014.

  18. Improved Monitor Design and Configuration for Reducing Reported Tritium

    Office of Environmental Management (EM)

    Discharges from the Orphee Research Reactor | Department of Energy Improved Monitor Design and Configuration for Reducing Reported Tritium Discharges from the Orphee Research Reactor Improved Monitor Design and Configuration for Reducing Reported Tritium Discharges from the Orphee Research Reactor Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Improved Monitor Design and Configuration for Reducing Reported Tritium

  19. Methods for Post Irradiation Examination of Tritium Producing Burnable

    Office of Environmental Management (EM)

    Absorber Rods | Department of Energy for Post Irradiation Examination of Tritium Producing Burnable Absorber Rods Methods for Post Irradiation Examination of Tritium Producing Burnable Absorber Rods Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013. PDF icon Methods for Post Irradiation Examination of Tritium Producing Burnable Absorber Rods More Documents & Publications Design and Fabrication of In-Reactor Experiment to Measure

  20. Commercial Light Water Production of Tritium: Update and Path Forward

    Broader source: Energy.gov [DOE]

    Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013.

  1. Overview of Tritium Betavoltaic Power for Micro Sensors

    Broader source: Energy.gov [DOE]

    Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013.

  2. Let's Compare Tritium Design Practices Across The DOE Complex

    Office of Energy Efficiency and Renewable Energy (EERE)

    Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013.

  3. Tritium Science and Technology at Atomic Weapons Establishment (AWE)

    Broader source: Energy.gov [DOE]

    Presentation from the 36th Tritium Focus Group Meeting held in Los Alamos, New Mexico, November 3-5, 2015.

  4. Overview of Tritium Activities at the Laboratory for Laser Energetics

    Broader source: Energy.gov [DOE]

    Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013.

  5. Tritium Transport within the TMIST-3 In-Reactor Experiment

    Broader source: Energy.gov [DOE]

    Presentation from the 35th Tritium Focus Group Meeting held in Princeton, New Jersey on May 05-07, 2015.

  6. Tritium Separation at Cernavoda Nuclear - Romania | Department of Energy

    Office of Environmental Management (EM)

    Separation at Cernavoda Nuclear - Romania Tritium Separation at Cernavoda Nuclear - Romania Presentation from the 35th Tritium Focus Group Meeting held in Princeton New Jersey on May 05-07, 2015. PDF icon Tritium Separation at Cernavoda Nuclear - Romania More Documents & Publications Management of Spent Desiccant from Vapour Recovery Dryers Flexible Assembly Solar Technology USABC LEESS and PHEV Programs

  7. Tritium Aging Effects in Palladium on Kieselguhr

    SciTech Connect (OSTI)

    Shanahan, K.L.; Holder, J.S.; Wermer, J.R.

    1998-10-01

    50 weight % Pd on kieselguhr (Pd/k) is used in hydrogen isotope separation processes at the Savannah River Site. Long term aging studies on this material were undertaken in June, 1992. P-c-T data showing the aging effect of tritium loading for long periods will be presented and discussed covering from June, 1992 to March, 1997. Lowering of plateau pressures and increasing indications of in homogeneities have been observed in both tritium and deuterium absorption isotherms at 0 C, and desorption isotherms at 80 and 120 C.

  8. EIS-0288-S1: Production of Tritium in a Commercial Light Water Reactor (CLWR) Tritium Readiness Supplemental Environmental Impact Statement

    Broader source: Energy.gov [DOE]

    This Supplemental EIS updates the environmental analyses in DOE’s 1999 EIS for the Production of Tritium in a Commercial Light Water Reactor (CLWR EIS). The CLWR EIS addressed the production of tritium in Tennessee Valley Authority reactors in Tennessee using tritium-producing burnable absorber rods.

  9. Commercial Light Water Production of Tritium Update and Path Forward

    Office of Environmental Management (EM)

    Light Water Production of Tritium: Update and Path Forward Dave Senor April 23, 2013 Tritium Focus Group 1 PNNL-SA-94431 Background United States defense maintains a stockpile of nuclear weapons as a "deterrent" to military actions by others Tritium is required for all U.S. nuclear weapons to function as designed: 6 Li + 1 n → 3 T + 4 He With a 12.2 year half-life, tritium must be replaced. Department of Energy (DOE) stopped production of tritium at Savannah River Site (SRS) in 1988.

  10. Microsoft PowerPoint - Tritium Design Practice.ppt

    Office of Environmental Management (EM)

    LET'S COMPARE TRITIUM DESIGN PRACTICES ACROSS THE DOE COMPLEX X Steve Xiao 2 GENERAL REFERENCES DOE-HDBK-1129-2008, "DOE Handbook Tritium Handling and Safe Storage", 2008 William W Weaver et al, DOE/EH-0417, Technical Notice Issue No 94-01, "Guidelines for Valves in Tritium Service", 1994 F Mannone, Springer, Editor, "Safety in Tritium Handling Technology", Kluwer Academic Publishers, 1993 International Atomic Energy Agency, "Safe Handling of Tritium: Review of

  11. Small system for tritium accelerator mass spectrometry

    DOE Patents [OSTI]

    Roberts, M.L.; Davis, J.C.

    1993-02-23

    Apparatus for ionizing and accelerating a sample containing isotopes of hydrogen and detecting the ratios of hydrogen isotopes contained in the sample is disclosed. An ion source generates a substantially linear ion beam including ions of tritium from the sample. A radio-frequency quadrupole accelerator is directly coupled to and axially aligned with the source at an angle of substantially zero degrees. The accelerator accelerates species of the sample having different mass to different energy levels along the same axis as the ion beam. A spectrometer is used to detect the concentration of tritium ions in the sample. In one form of the invention, an energy loss spectrometer is used which includes a foil to block the passage of hydrogen, deuterium and [sup 3]He ions, and a surface barrier or scintillation detector to detect the concentration of tritium ions. In another form of the invention, a combined momentum/energy loss spectrometer is used which includes a magnet to separate the ion beams, with Faraday cups to measure the hydrogen and deuterium and a surface barrier or scintillation detector for the tritium ions.

  12. DEVELOPMENT OF THE BULK TRITIUM SHIPPING PACKAGING

    SciTech Connect (OSTI)

    Blanton, P.; Eberl, K.

    2008-09-14

    A new radioactive shipping packaging for transporting bulk quantities of tritium, the Bulk Tritium Shipping Package (BTSP), has been designed for the Department of Energy (DOE) as a replacement for a package designed in the early 1970s. This paper summarizes significant design features and describes how the design satisfies the regulatory safety requirements of the Code of Federal Regulations and the International Atomic Energy Agency. The BTSP design incorporates many improvements over its predecessor by implementing improved testing, handling, and maintenance capabilities, while improving manufacturability and incorporating new engineered materials. This paper also discusses the results from testing of the BTSP to 10 CFR 71 Normal Conditions of Transport and Hypothetical Accident Condition events. The programmatic need of the Department of Energy (DOE) to ship bulk quantities of tritium has been satisfied since the late 1970s by the UC-609 shipping package. The current Certificate of Conformance for the UC-609, USA/9932/B(U) (DOE), will expire in late 2011. Since the UC-609 was not designed to meet current regulatory requirements, it will not be recertified and thereby necessitates a replacement Type B shipping package for continued DOE tritium shipments in the future. A replacement tritium packaging called the Bulk Tritium Shipping Package (BTSP) is currently being designed and tested by Savannah River National Laboratory (SRNL). The BTSP consists of two primary assemblies, an outer Drum Assembly and an inner Containment Vessel Assembly (CV), both designed to mitigate damage and to protect the tritium contents from leaking during the regulatory Hypothetical Accident Condition (HAC) events and during Normal Conditions of Transport (NCT). During transport, the CV rests on a silicone pad within the Drum Liner and is covered with a thermal insulating disk within the insulated Drum Assembly. The BTSP packaging weighs approximately 500 lbs without contents and is 50-1/2 inches high by 24-1/2 inches in outside diameter. With contents the gross weight of the BTSP is 650 lbs. The BTSP is designed for the safe shipment of 150 grams of tritium in a solid or gaseous state. To comply with the federal regulations that govern Type B shipping packages, the BTSP is designed so that it will not lose tritium at a rate greater than the limits stated in 10CFR 71.51 of 10{sup -6} A2 per hour for the 'Normal Conditions of Transport' (NCT) and an A2 in 1 week under 'Hypothetical Accident Conditions' (HAC). Additionally, since the BTSP design incorporates a valve as part of the tritium containment boundary, secondary containment features are incorporated in the CV Lid to protect against gas leakage past the valve as required by 10CFR71.43(e). This secondary containment boundary is designed to provide the same level of containment as the primary containment boundary when subjected to the HAC and NCT criteria.

  13. In-bed measurement of tritium loading in process metal hydride beds

    SciTech Connect (OSTI)

    Nobile, A.

    1988-01-01

    The Replacement Tritium Facility at Savannah River Plant will make extensive use of metal hydride technology for the storage, pumping, isotopic separation, and compression of hydrogen isotopes. Two options were considered for routine accountability of tritium stored in metal hydride beds. One option was to use standard P-V-T-mass spectrometry techniques after desorption of storage beds to tanks of known volume. The second option was to develop a technique for direct measurement of bed loading. It was thought that such a technique would be more rapid and would account for heel, although some accuracy would be lost.The static nitrogen and flowing nitrogen methods were considered for this option. The flowing nitrogen method was eventually selected because it was insensitive to bed physical properties and isotopic gas composition, as well as being more accurate and easier to automate.

  14. Apparatus to recover tritium from tritiated molecules

    DOE Patents [OSTI]

    Swansiger, William A. (Livermore, CA)

    1988-01-01

    An apparatus for recovering tritium from tritiated compounds is provided, including a preheater for heating tritiated water and other co-injected tritiated compounds to temperatures of about 600.degree. C. and a reactor charged with a mixture of uranium and uranium dioxide for receiving the preheated mixture. The reactor vessel is preferably stainless steel of sufficient mass so as to function as a heat sink preventing the reactor side walls from approaching high temperatures. A disposable copper liner extends between the reaction chamber and stainless steel outer vessel to prevent alloying of the uranium with the outer vessel. The uranium dioxide functions as an insulating material and heat sink preventing the reactor side walls from attaining reaction temperatures to thereby minimize tritium permeation rates. The uranium dioxide also functions as a diluent to allow for volumetric expansion of the uranium as it is converted to uranium dioxide.

  15. Recovery of tritium from tritiated molecules

    DOE Patents [OSTI]

    Swansiger, William A. (Livermore, CA)

    1987-01-01

    A method of recovering tritium from tritiated compounds comprises the steps of heating tritiated water and other co-injected tritiated compounds in a preheater to temperatures of about 600.degree. C. The mixture is injected into a reactor charged with a mixture of uranium and uranium dioxide. The injected mixture undergoes highly exothermic reactions with the uranium causing reaction temperatures to occur in excess of the melting point of uranium, and complete decomposition of the tritiated compounds to remove tritium therefrom. The uranium dioxide functions as an insulating material and heat sink preventing the reactor side walls from attaining reaction temperatures to thereby minimize tritium permeation rates. The uranium dioxide also functions as a diluent to allow for volumetric expansion of the uranium as it is converted to uranium dioxide. The reactor vessel is preferably stainless steel of sufficient mass so as to function as a heat sink preventing the reactor side walls from approaching high temperatures. A disposable copper liner extends between the reaction chamber and stainless steel outer vessel to prevent alloying of the uranium with the outer vessel. Apparatus used to carry out the method of the invention is also disclosed.

  16. Microsoft PowerPoint - Electrolytic T Extraction in Molten Li-LiT_2.pptx

    Office of Environmental Management (EM)

    Electrolytic Tritium Extraction in Molten Li-LiT Luke Olson Brenda L. García-Díaz Hector Colon-Mercado Joe Teprovich Dave Babineau Savannah River National Laboratory Fall 2015 Tritium Focus Group Meeting November 3-5, 2015 SRNL-STI-2015-00605 This presentation does not contain any proprietary, confidential, or otherwise restricted information LiT Electrolysis Options LiT Electrolysis Maroni Process (Baseline Option) Improve Liquid-Liquid Extraction & Electrolysis Process Intensification

  17. Tritium Related Material Research -Irradiation Effect on Isotropic...

    Office of Environmental Management (EM)

    Related Material Research -Irradiation Effect on Isotropic Graphite Utilizing Heavy Ion-Irradiation- Tritium Related Material Research -Irradiation Effect on Isotropic Graphite...

  18. Test Results For Physical Separation Of Tritium From Noble Gases...

    Office of Environmental Management (EM)

    Test Results For Physical Separation Of Tritium From Noble Gases And It's Implications For Sensitivity And Accuracy In Air And Stack Monitoring Test Results For Physical Separation ...

  19. Overview of the Tritium research activities at Lawrence Livermore...

    Office of Environmental Management (EM)

    activities at LLNL More Documents & Publications Overview of Tritium Activities at the Laboratory for Laser Energetics NIF Presentation by Ed Moses EIS-0236-S1: Record of Decision...

  20. Tritium Formation and Mitigation in High-Temperature Reactor Systems

    SciTech Connect (OSTI)

    Piyush Sabharwall; Carl Stoots; Hans A. Schmutz

    2013-03-01

    Tritium is a radiologically active isotope of hydrogen. It is formed in nuclear reactors by neutron absorption and ternary fission events and can subsequently escape into the environment. To prevent the tritium contamination of proposed reactor buildings and surrounding sites, this study examines the root causes and potential mitigation strategies for permeation of tritium (such as: materials selection, inert gas sparging, etc...). A model is presented that can be used to predict permeation rates of hydrogen through metallic alloys at temperatures from 450750 degrees C. Results of the diffusion model are presented for a steady production of tritium

  1. Tritium Formation and Mitigation in High-Temperature Reactors

    SciTech Connect (OSTI)

    Piyush Sabharwall; Carl Stoots

    2012-10-01

    Tritium is a radiologically active isotope of hydrogen. It is formed in nuclear reactors by neutron absorption and ternary fission events and can subsequently escape into the environment. To prevent the tritium contamination of proposed reactor buildings and surrounding sites, this study examines the root causes and potential mitigation strategies for permeation of tritium (such as: materials selection, inert gas sparging, etc...). A model is presented that can be used to predict permeation rates of hydrogen through metallic alloys at temperatures from 450750 degrees C. Results of the diffusion model are presented for a steady production of tritium

  2. Behavior of tritium permeation induced by water corrosion of...

    Office of Scientific and Technical Information (OSTI)

    induced by water corrosion of alpha iron around room temperature Citation Details In-Document Search Title: Behavior of tritium permeation induced by water corrosion of ...

  3. EFFECTS OF TRITIUM GAS EXPOSURE ON EPDM ELASTOMER

    SciTech Connect (OSTI)

    Clark, E.

    2009-12-11

    Samples of four formulations of ethylene-propylene diene monomer (EPDM) elastomer were exposed to initially pure tritium gas at one atmosphere and ambient temperature for various times up to about 420 days in closed containers. Two formulations were carbon-black-filled commercial formulations, and two were the equivalent formulations without filler synthesized for this work. Tritium effects on the samples were characterized by measuring the sample volume, mass, flexibility, and dynamic mechanical properties and by noting changes in appearance. The glass transition temperature was determined by analysis of the dynamic mechanical properties. The glass transition temperature increased significantly with tritium exposure, and the unfilled formulations ceased to behave as elastomers after the longest tritium exposure. The filled formulations were more resistant to tritium exposure. Tritium exposure made all samples significantly stiffer and therefore much less able to form a reliable seal when employed as O-rings. No consistent change of volume or density was observed; there was a systematic lowering of sample mass with tritium exposure. In addition, the significant radiolytic production of gas, mainly protium (H{sub 2}) and HT, by the samples when exposed to tritium was characterized by measuring total pressure in the container at the end of each exposure and by mass spectroscopy of a gas sample at the end of each exposure. The total pressure in the containers more than doubled after {approx}420 days tritium exposure.

  4. 2012 ACCOMPLISHMENTS - TRITIUM AGING STUDIES ON STAINLESS STEELS

    SciTech Connect (OSTI)

    Morgan, M.

    2013-01-31

    This report summarizes the research and development accomplishments during FY12 for the tritium effects on materials program. The tritium effects on materials program is designed to measure the long-term effects of tritium and its radioactive decay product, helium-3, on the structural properties of forged stainless steels which are used as the materials of construction for tritium reservoirs. The FY12 R&D accomplishments include: (1) Fabricated and Thermally-Charged 150 Forged Stainless Steel Samples with Tritium for Future Aging Studies; (2) Developed an Experimental Plan for Measuring Cracking Thresholds of Tritium-Charged-and-Aged Steels in High Pressure Hydrogen Gas; (3) Calculated Sample Tritium Contents For Laboratory Inventory Requirements and Environmental Release Estimates; (4) Published report on Cracking Thresholds and Fracture Toughness Properties of Tritium-Charged-and-Aged Stainless Steels; and, (5) Published report on The Effects of Hydrogen, Tritium, and Heat Treatment on the Deformation and Fracture Toughness Properties of Stainless Steels. These accomplishments are highlighted here and references given to additional reports for more detailed information.

  5. Preliminary safety assessment for an IFE target fabrication facility

    SciTech Connect (OSTI)

    Latkowski, J F; Reyes, S; Besenbruch, G E; Goodin, D T

    2000-10-13

    We estimate possible ranges of tritium inventories for an inertial fusion energy (IFE) target fabrication facility producing various types of targets and using various production technologies. Target fill is the key subtask in determining the overall tritium inventory for the plant. By segmenting the inventory into multiple, parallel production lines--each with its own fill canister--and including an expansion tank to limit releases, we are able to ensure that a target fabrication facility would meet the accident dose goals of 10 mSv (1 rem) set forth in the Department of Energy's Fusion Safety Standards. For indirect-drive targets, we calculate release fractions for elements from lithium to bismuth and show that nearly all elements meet the dose goal. Our work suggests directions for future R&D that will help reduce total tritium inventories and increase the flexibility of target fabrication facilities.

  6. EIS-0288-S1: Production of Tritium in a Commercial Light Water Reactor

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

    (CLWR) Tritium Readiness Supplemental Environmental Impact Statement | Department of Energy 288-S1: Production of Tritium in a Commercial Light Water Reactor (CLWR) Tritium Readiness Supplemental Environmental Impact Statement EIS-0288-S1: Production of Tritium in a Commercial Light Water Reactor (CLWR) Tritium Readiness Supplemental Environmental Impact Statement Summary This Supplemental EIS updates the environmental analyses in DOE's 1999 EIS for the Production of Tritium in a Commercial

  7. Is Tritium over-regulated by DOE? Should the TFG support NA-1 SD G 1027

    Office of Environmental Management (EM)

    tritium values? | Department of Energy over-regulated by DOE? Should the TFG support NA-1 SD G 1027 tritium values? Is Tritium over-regulated by DOE? Should the TFG support NA-1 SD G 1027 tritium values? Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013. PDF icon Is Tritium over-regulated by DOE? Should the TFG support NA-1 SD G 1027 tritium values? More Documents & Publications Is Tritium Over-Regulated, Part 2 Should The TFG

  8. Laser Facilities

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

    Laser Facilities Current Schedule of Experiments Operation Schedule Janus Titan Europa COMET Facility Floorplan

  9. Microsoft Word - Cooper_Tritium.final.doc

    Office of Legacy Management (LM)

    PROCEEDINGS, TOUGH Symposium 2006 Lawrence Berkeley National Laboratory, Berkeley, California, May 15-17, 2006 - 1 - TRITIUM TRANSPORT THROUGH A LOW-PERMEABILITY NATURAL GAS RESERVOIR Clay A. Cooper 1 , Ming Ye 2 , and Jenny Chapman 2 Desert Research Institute 1 2215 Raggio Pkwy Reno, Nevada, 89512, USA E-mail: clay@dri.edu 2 755 E. Flamingo Road Las Vegas, NV 89119, USA ABSTRACT The U.S. Department of Energy and its predecessor agencies conducted a program in the 1960s and 1970s to evaluate

  10. Radiological Control Programs for Special Tritium Compounds

    Energy Savers [EERE]

    84-2004 SEPTEMBER 2004 CHANGE NOTICE NO. 1 Date June 2006 DOE HANDBOOK RADIOLOGICAL CONTROL PROGRAMS FOR SPECIAL TRITIUM COMPOUNDS U.S. Department of Energy AREA OCSH Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE ii Table of Changes Page Change 67 (near bottom) In row 1, column 2 of the table titled "dosimetric properties" 6 mrem was changed to 6 x 10 -2 mrem Available on the Department of Energy

  11. Radiological Control Programs for Special Tritium Compounds

    Energy Savers [EERE]

    DOE.F 1325.8 (08-93) United States Government Department of Energy memorandum DATE: May 11, 2006 REPLY TO EH-52:JRabovsky:3-2 135 ATTN OF: APPROVAL OF CHANGE NOTICE 1 TO DEPARTMENT OF ENERGY (DOE) SUBJECT. HANDBOOK 1184-2004, RADIOLOGICAL CONTROL PROGRAMS FOR SPECIAL TRITIUM COMPOUNDS TO: Dennis Kubicki, EH-24 Technical Standards Manager This memorandum forwards the subject Change Notice 1 to DOE Handbook, DOE- HDBK- 1184-2004, which has approved for publication and distribution. The change to

  12. Nuclear Facilities Production Facilities

    National Nuclear Security Administration (NNSA)

    Facilities Production Facilities Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. Sand 2011-4582P. ENERGY U.S. DEPARTMENT OF Gamma Irradiation Facility (GIF) The GIF provides test cells for the irradiation of experiments with high-intensity gamma ray sources. The main features

  13. Organically bound tritium analysis in environmental samples

    SciTech Connect (OSTI)

    Baglan, N.; Cossonnet, C.; Fournier, M.; Momoshima, N.; Ansoborlo, E.

    2015-03-15

    Organically bound tritium (OBT) has become of increased interest within the last decade, with a focus on its behaviour and also its analysis, which are important to assess tritium distribution in the environment. In contrast, there are no certified reference materials and no standard analytical method through the international organization related to OBT. In order to resolve this issue, an OBT international working group was created in May 2012. Over 20 labs from around the world participated and submitted their results for the first intercomparison exercise results on potato (Sep 2013). The samples, specially-prepared potatoes, were provided in March 2013 to each participant. Technical information and results from this first exercise are discussed here for all the labs which have realised the five replicates necessary to allow a reliable statistical treatment. The results are encouraging as the increased number of participating labs did not degrade the observed dispersion of the results for a similar activity level. Therefore, the results do not seem to depend on the analytical procedure used. From this work an optimised procedure can start to be developed to deal with OBT analysis and will guide subsequent planned OBT trials by the international group.

  14. Derivation of dose conversion factors for tritium

    SciTech Connect (OSTI)

    Killough, G. G.

    1982-03-01

    For a given intake mode (ingestion, inhalation, absorption through the skin), a dose conversion factor (DCF) is the committed dose equivalent to a specified organ of an individual per unit intake of a radionuclide. One also may consider the effective dose commitment per unit intake, which is a weighted average of organ-specific DCFs, with weights proportional to risks associated with stochastic radiation-induced fatal health effects, as defined by Publication 26 of the International Commission on Radiological Protection (ICRP). This report derives and tabulates organ-specific dose conversion factors and the effective dose commitment per unit intake of tritium. These factors are based on a steady-state model of hydrogen in the tissues of ICRP's Reference Man (ICRP Publication 23) and equilibrium of specific activities between body water and other tissues. The results differ by 27 to 33% from the estimate on which ICRP Publication 30 recommendations are based. The report also examines a dynamic model of tritium retention in body water, mineral bone, and two compartments representing organically-bound hydrogen. This model is compared with data from human subjects who were observed for extended periods. The manner of combining the dose conversion factors with measured or model-predicted levels of contamination in man's exposure media (air, drinking water, soil moisture) to estimate dose rate to an individual is briefly discussed.

  15. Facility Environmental Vulnerability Assessment

    SciTech Connect (OSTI)

    Van Hoesen, S.D.

    2001-07-09

    From mid-April through the end of June 2001, a Facility Environmental Vulnerability Assessment (FEVA) was performed at Oak Ridge National Laboratory (ORNL). The primary goal of this FEVA was to establish an environmental vulnerability baseline at ORNL that could be used to support the Laboratory planning process and place environmental vulnerabilities in perspective. The information developed during the FEVA was intended to provide the basis for management to initiate immediate, near-term, and long-term actions to respond to the identified vulnerabilities. It was expected that further evaluation of the vulnerabilities identified during the FEVA could be carried out to support a more quantitative characterization of the sources, evaluation of contaminant pathways, and definition of risks. The FEVA was modeled after the Battelle-supported response to the problems identified at the High Flux Beam Reactor at Brookhaven National Laboratory. This FEVA report satisfies Corrective Action 3A1 contained in the Corrective Action Plan in Response to Independent Review of the High Flux Isotope Reactor Tritium Leak at the Oak Ridge National Laboratory, submitted to the Department of Energy (DOE) ORNL Site Office Manager on April 16, 2001. This assessment successfully achieved its primary goal as defined by Laboratory management. The assessment team was able to develop information about sources and pathway analyses although the following factors impacted the team's ability to provide additional quantitative information: the complexity and scope of the facilities, infrastructure, and programs; the significantly degraded physical condition of the facilities and infrastructure; the large number of known environmental vulnerabilities; the scope of legacy contamination issues [not currently addressed in the Environmental Management (EM) Program]; the lack of facility process and environmental pathway analysis performed by the accountable line management or facility owner; and poor facility and infrastructure drawings. The assessment team believes that the information, experience, and insight gained through FEVA will help in the planning and prioritization of ongoing efforts to resolve environmental vulnerabilities at UT-Battelle--managed ORNL facilities.

  16. Tritium and neutron measurements from deuterated Pd-Si

    SciTech Connect (OSTI)

    Claytor, T.N.; Tuggle, D.G.; Menlove, H.O.; Seeger, P.A.; Doty, W.R.; Rohwer, R.K. (Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States))

    1991-05-10

    Evidence has been found for tritium and neutron production in palladium and silicon stacks when pulsed with a high electric current. These palladium-silicon stacks consist of alternating layers of pressed palladium and silicon powder. A pulsed high electric current is thought to promote non-equilibrium conditions important for tritium and neutron production. More than 2000 hours of neutron counting time has been accumulated in a underground, low background, environment with high efficiency counters (21%). Neutron emission has occurred as infrequent bursts or as low level emission lasting for up to 20 hours. In eight of 30 cells, excess tritium greater than 3 sigma has been observed. In each of these measurements, with the powder system, the ratio of tritium detected to total integrated total neutrons inferred has been anomalously high. Recent cells have shown reproducible tritium generation at a level of about 0.5 nCi/hr. Several hydrogen and air control cells have been run with no anomalous excess tritium or neutron emission above background. A singificant amount of the total palladium inventory (18%) has been checked for tritium contamination by three independent means.

  17. Tritium and neutron measurements from deuterated Pd-Si

    SciTech Connect (OSTI)

    Claytor, T.N.; Tuggle, D.G.; Menlove, H.O.; Seeger, P.A.; Doty, W.R.; Rohwer, R.K.

    1990-01-01

    Evidence has been found for tritium and neutron production in palladium and silicon stacks when pulsed with a high electric current. These palladium-silicon stacks consist of alternating layers of pressed palladium and silicon powder. A pulsed high electric current is thought to promote non equilibrium conditions important for tritium and neutron production. More than 2000 hours of neutron counting time has been accumulated in a underground, low background, environment with high efficiency counters (21%). Neutron emission has occurred as infrequent burst or as low level emission lasting for up to 20 hours. In eight of 30 cells, excess tritium greater than 3 sigma has been observed. In each of these measurements, with the powder system, the ratio of tritium detected to total integrated total neutrons inferred has been anomalously high. Recent cells have shown reproducible tritium generation at a level of about 0.5 nCi/hr. Several hydrogen and air control cells have been run with no anomalous excess tritium or neutron emission above background. A significant amount of the total palladium inventory (18%) has been checked for tritium contamination by three independent means. 12 refs., 6 figs., 2 tabs.

  18. MEASUREMENT OF TRITIUM DURING VOLOXIDATION OF ZIRCALOY-2 FUEL HULLS

    SciTech Connect (OSTI)

    Crowder, M.; Laurinat, J.; Stillman, J.

    2010-10-14

    A straightforward method to evaluate the tritium content of Zircaloy-2 cladding hulls via oxidation of the hull and capture of the volatilized tritium in liquids has been demonstrated. Hull samples were heated in air inside a thermogravimetric analyzer (TGA). The TGA was rapidly heated to 1000 C to oxidize the hulls and release absorbed tritium. To capture tritium, the TGA off-gas was bubbled through a series of liquid traps. The concentrations of tritium in bubbler solutions indicated that tritiated water vapor was captured nearly quantitatively. The average tritium content measured in the hulls was 19% of the amount of tritium produced by the fuel, according to ORIGEN2 isotope generation and depletion calculations. Published experimental data show that Zircaloy-2 oxidation follows an Arrhenius model, and that an initial, nonlinear oxidation rate is followed by a faster, linear rate after 'breakaway' of the oxide film. This study demonstrates that the linear oxidation rate of Zircaloy samples at 974 C is faster than predicted by the extrapolation of data from lower temperatures.

  19. Apparatus for monitoring tritium in tritium-contaminating environments using a modified Kanne chamber

    DOE Patents [OSTI]

    Anderson, D.F.

    1981-01-27

    A conventional Kanne tritium monitor has been redesigned to reduce its sensitivity to such contaminants as tritiated water vapor and tritiated oil. The high voltage electrode has been replaced by a wire cylinder and the collector electrode has been reduced in diameter. The area sensitive to contamination has thereby been reduced by about a factor of forty while the overall apparatus sensitivity and operation has not been affected. The design allows for in situ decontamination of the chambers, if necessary.

  20. Apparatus for monitoring tritium in tritium contaminating environments using a modified Kanne chamber

    DOE Patents [OSTI]

    Anderson, David F. (Los Alamos, NM)

    1984-01-01

    A conventional Kanne tritium monitor has been redesigned to reduce its sensitivity to such contaminants as tritiated water vapor and tritiated oil. The high voltage electrode has been replaced by a wire cylinder and the collector electrode has been reduced in diameter. The area sensitive to contamination has thereby been reduced by about a factor of forty while the overall apparatus sensitivity and operation has not been affected. The design allows for in situ decontamination of the chambers, if necessary.

  1. Utilization of Kinetic Isotope Effects for the Concentration of Tritium

    SciTech Connect (OSTI)

    Brown, Gilbert M.; Meyer, Thomas j.; Moyer, Bruce A.

    1999-06-01

    The objective of this research program is to develop methods for concentrating tritium in water based on large primary isotope effects in catalytic redox processes. Basic research is being conducted to develop the chemistry of a complete cyclic process. Because tritium (generally present as HTO) is in a rapidly established equilibrium with protio-water, it moves with groundwater and separation from water cannot be achieved by the usual pump-and-treat methods using sorbants. The general methodology developed in this work will be applicable to a number of DOE waste streams, and as a consequence of the process tritium will be incorporated into an organic compound that will not readily exchange the tritium with groundwater. The process to be developed will remove tritium from H2O by concentrating it with respect to protio-water. This research involves developing chemical cycles that produce high concentration factors for HTO and T2O based on the discrimination of C-H and C-T bonds in oxidation reactions. Several steps are required in a cyclic process for the concentration of tritium in water. In the first step the tritium is incorporated in an organic compound. H-T discrimination occurs as the tritium containing compound is oxidized in a step involving a Ru(IV) oxo complex. Strong primary kinetic isotope effects lead to the oxidation of C-H bonds in preference to C-T bonds, and this reaction leads to concentration of tritium in the organic compound. The reduced form of the ruthenium compound can be reoxidized so that the oxidation step can be made catalytic.

  2. Scientific and engineering services for the LANCE/ER accelerator production of tritium (APT) project

    SciTech Connect (OSTI)

    1994-12-05

    The APT project office is conducting a preconceptual design study for an accelerator driven concept to produce tritium. The facility will require new technology in many areas, since the scale of this accelerator is significantly larger then any in operation to date. The facility is composed of four subsystems: accelerator, target & blanket, balance of plant, and tritium purification system (TPS). New physics realms will be entered in order for the concept to be feasible; for example, extremely high energy levels of the entering protons that induce (multiplicative) spallation of the neutrons from the high Z target will occur. These are complex and require advance codes (MCNP) to predict the physics interactions and as well as deleterious material effects in the surrounding structures. Other issues include component cooling and complex thermal-hydraulics effects within the blanket and the beam {open_quotes}window.{close_quotes} In order to support a DOE mandated fast ROD schedule, Los Alamos APT staff will be provided with senior, engineering technical support staff with direct APT technology experience and whom are {open_quotes}on site{close_quotes}. This report contains resumes of the staff.

  3. Tritium Formation and Mitigation in High Temperature Reactors

    SciTech Connect (OSTI)

    Piyush Sabharwall; Carl Stoots

    2012-08-01

    Tritium is a radiologically active isotope of hydrogen. It is formed in nuclear reactors by neutron absorption and ternary fission events and can subsequently escape into the environment. In order to prevent the tritium contamination of proposed reactor buildings and surrounding sites, this paper examines the root causes and potential solutions for the production of this radionuclide, including materials selection and inert gas sparging. A model is presented that can be used to predict permeation rates of hydrogen through metallic alloys at temperatures from 450750C. Results of the diffusion model are presented for one steadystate value of tritium production in the reactor.

  4. On-line tritium production monitor

    DOE Patents [OSTI]

    Mihalczo, John T. (Oak Ridge, TN)

    1993-01-01

    A scintillation optical fiber system for the on-line monitoring of nuclear reactions in an event-by-event manner is described. In the measurement of tritium production one or more optical fibers are coated with enriched .sup.6 Li and connected to standard scintillation counter circuitry. A neutron generated .sup.6 Li(n )T reaction occurs in the coated surface of .sup.6 Li-coated fiber to produce energetic alpha and triton particles one of which enters the optical fiber and scintillates light through the fiber to the counting circuit. The coated optical fibers can be provided with position sensitivity by placing a mirror at the free end of the fibers or by using pulse counting circuits at both ends of the fibers.

  5. Tritium Migration Analysis Program Version 4

    Energy Science and Technology Software Center (OSTI)

    1991-06-12

    TMAP4 was developed as a safety analysis code, mainly to analyze tritium retention and loss in fusion reactor structures and systems during normal operational and accident conditions. It incorporates one-dimensional thermal and mass-diffusive transport and trapping calculations through structures and zero dimensional fluid transport between enclosures and across the interface between enclosures and structures. Diffusion structures may be linked together with other structures, and multiple structures may interact with an enclosure. A key feature ismore » the ability to input problem definition parameters as constants, interpolation tables, or FORTRAN equations. The code is specifically intended for use under a DOS operating system on PC type minicomputers, but it has also been run successfully on workstations and mainframe computer systems. Use of the equation-input feature requires access to a FORTRAN-77 compiler, and a linker program is required.« less

  6. On-line tritium production monitor

    DOE Patents [OSTI]

    Mihalczo, J.T.

    1993-11-23

    A scintillation optical fiber system for the on-line monitoring of nuclear reactions in an event-by-event manner is described. In the measurement of tritium production one or more optical fibers are coated with enriched {sup 6}Li and connected to standard scintillation counter circuitry. A neutron generated {sup 6}Li(n)T reaction occurs in the coated surface of {sup 6}Li-coated fiber to produce energetic alpha and triton particles one of which enters the optical fiber and scintillates light through the fiber to the counting circuit. The coated optical fibers can be provided with position sensitivity by placing a mirror at the free end of the fibers or by using pulse counting circuits at both ends of the fibers. 5 figures.

  7. Ignition of deuterium-tritium fuel targets

    DOE Patents [OSTI]

    Musinski, D.L.; Mruzek, M.T.

    1991-08-27

    Disclosed is a method of igniting a deuterium-tritium ICF fuel target to obtain fuel burn in which the fuel target initially includes a hollow spherical shell having a frozen layer of DT material at substantially uniform thickness and cryogenic temperature around the interior surface of the shell. The target is permitted to free-fall through a target chamber having walls heated by successive target ignitions, so that the target is uniformly heated during free-fall to at least partially melt the frozen fuel layer and form a liquid single-phase layer or a mixed liquid/solid bi-phase layer of substantially uniform thickness around the interior shell surface. The falling target is then illuminated from exteriorly of the chamber while the fuel layer is at substantially uniformly single or bi-phase so as to ignite the fuel layer and release energy therefrom. 5 figures.

  8. Recommendations for Tritium Science and Technology Research and Development in Support of the Tritium Readiness Campaign, TTP-7-084

    SciTech Connect (OSTI)

    Senor, David J.

    2013-10-30

    Between 2006 and 2012 the Tritium Readiness Campaign Development and Testing Program produced significant advances in the understanding of in-reactor TPBAR performance. Incorporating these data into existing TPBAR performance models has improved permeation predictions, and the discrepancy between predicted and observed tritium permeation in the WBN1 coolant has been decreased by about 30%. However, important differences between predicted and observed permeation still remain, and there are significant knowledge gaps that hinder the ability to reliably predict other aspects of TPBAR performance such as tritium distribution, component integrity, and performance margins. Based on recommendations from recent Tritium Readiness Campaign workshops and reviews coupled with technical and programmatic priorities, high-priority activities were identified to address knowledge gaps in the near- (3-5 year), middle- (5-10 year), and long-term (10+ year) time horizons. It is important to note that there are many aspects to a well-integrated research and development program. The intent is not to focus exclusively on one aspect or another, but to approach the program in a holistic fashion. Thus, in addition to small-scale tritium science studies, ex-reactor tritium technology experiments such as TMED, and large-scale in-reactor tritium technology experiments such as TMIST, a well-rounded research and development program must also include continued analysis of WBN1 performance data and post-irradiation examination of TPBARs and lead use assemblies to evaluate model improvements and compare separate-effects and integral component behavior.

  9. Tritium R&D at AECL Selected Topics | Department of Energy

    Office of Environmental Management (EM)

    R&D at AECL Selected Topics Tritium R&D at AECL Selected Topics Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Tritium R&D at AECL Selected Topics More Documents & Publications Chalk River Tritium Activities: Select Topics Overview of AECL's Tritium Compatible Electrolyser Program Light Water Detritiation using the CECE Process

  10. 34th Tritium Focus Group Meeting, Idaho National Laboratory, Idaho Falls,

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

    September 23-25, 2014 | Department of Energy 4th Tritium Focus Group Meeting, Idaho National Laboratory, Idaho Falls, September 23-25, 2014 34th Tritium Focus Group Meeting, Idaho National Laboratory, Idaho Falls, September 23-25, 2014 34th Tritium Focus Group Meeting, Idaho National Laboratory, Idaho Falls, September 23-25, 2014 The Tritium Focus Group (TFG), is a long standing DOE Working Group, whose purpose is to promote cost-effective improvements in tritium safety, handling,

  11. ARM - SGP Central Facility

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

    Central Facility SGP Related Links Virtual Tour Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration...

  12. Microsoft Word - Tritium Fact Sheet Oct 17 2011

    National Nuclear Security Administration (NNSA)

    ... Tritium is also used in medical and biological research for tracer studies. It may also be used in the production of electricity by fusion, which is currently in the experimental ...

  13. Fermilab | Tritium at Fermilab | Steps taken to reduce the amount...

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

    levels of tritium in a stream leaving the Fermilab site, and in the sanitary sewers that pump water to the Batavia Wastewater Treatment Plant. The levels detected were far lower...

  14. Tritium removal from tritiated water by organic functionalized SBA-15

    SciTech Connect (OSTI)

    Taguchi, A.; Kato, Y.; Akai, R.; Torikai, Y.; Matsuyama, M.

    2015-03-15

    The recovery of tritium from tritiated water is important for reducing tritium emissions to the environment and for recycling tritium. Meso-porous silicas (SBA-15) were modified by -COOH, -SO{sub 3}H and -NH{sub 2} groups and their tritium adsorption ability from tritiated water under solid-liquid sorption was investigated. The adsorption abilities and separation factor of organic functionalized SBAs were comparable to those of bare SBA. The desorption of water from bare SBA and -COOH functionalized SBA were studied by Fourier transform infra-red spectroscopy using D{sub 2}O as a probe molecule. An interaction was observed for D{sub 2}O with -COOH group where the hydrogen bonds became weaker than D{sub 2}O with bare SBA. (authors)

  15. Pre-operational safety appraisal Tritiated Scrap Recovery Facility, Mound facility

    SciTech Connect (OSTI)

    Dauby, J.J.; Flanagan, T.M.; Metcalf, L.W.; Rhinehammer, T.B.

    1996-07-01

    The purpose of this report is to identify, assess, and document the hazards which are associated with the proposed operation of the Tritiated Scrap Recovery Facility at Mound Facility. A Pre-operational Safety Appraisal is a requirement as stated in Department of Energy Order 5481.1, Safety Analysis and Review System. The operations to be conducted in the new Tritiated Scrap Waste Recovery Facility are not new, but a continuation of a prime mission of Mound`s i.e. recovery of tritium from waste produced throughout the DOE complex. The new facility is a replacement of an existing process started in the early 1960`s and incorporates numerous design changes to enhance personnel and environmental safety. This report also documents the safety of a one time operation involving the recovery of tritium from material obtained by the Department of Energy from the State of Arizona. This project will involve the processing of 240,000 curies of tritium contained in glass ampoules that were to be used in items such as luminous dial watches. These were manufactured by the now defunct American Atomics Corporation, Tucson, Arizona.

  16. Utilization of Kinetic Isotope Effects for the Concentration of Tritium

    SciTech Connect (OSTI)

    Brown, Gilbert M.; Meyer, Thomas J.; Moyer, Bruce A.

    2000-06-01

    Work is in progress to develop methods for concentrating tritium in water based on large primary isotope effects in catalytic redox processes. Basic research is being conducted to develop the chemistry of a complete cyclic process. The process will remove tritium from H2O by concentrating it with respect to protio-water. This research involves developing chemical cycles that produce high concentration factors for HTO based on the discrimination of CH and C-T bonds in oxidation reactions. Several steps are required in a cyclic process for the concentration of tritium in water. In the first step, the tritium is incorporated in an organic compound. H-T discrimination occurs as the tritium containing compound is oxidized in a step involving a Ru(IV) oxo complex. Strong primary kinetic isotope effects lead to the oxidation of C-H bonds in preference to C-T bonds, and this reaction leads to concentration of tritium in the organic compound. The reduced form of the ruthenium compound can be reoxidized so that the oxidation step can be made catalytic.

  17. Wheelabrator Sherman Energy Facility Biomass Facility | Open...

    Open Energy Info (EERE)

    Sherman Energy Facility Biomass Facility Jump to: navigation, search Name Wheelabrator Sherman Energy Facility Biomass Facility Facility Wheelabrator Sherman Energy Facility Sector...

  18. Huntington Resource Recovery Facility Biomass Facility | Open...

    Open Energy Info (EERE)

    Resource Recovery Facility Biomass Facility Jump to: navigation, search Name Huntington Resource Recovery Facility Biomass Facility Facility Huntington Resource Recovery Facility...

  19. Key technologies for tritium storage bed development

    SciTech Connect (OSTI)

    Yu, S.H.; Chang, M.H.; Kang, H.G.; Chung, D.Y.; Oh, Y.H.; Jung, K.J.; Chung, H.; Koo, D.; Sohn, S.H.; Song, K.M.

    2015-03-15

    ITER Storage and Delivery System (SDS) is a complex system involving tens of storage beds. The most important SDS getter bed will be used for the absorption and desorption of hydrogen isotopes in accordance with the fusion fuel cycle scenario. In this paper the current status concerning research/development activities for the optimal approach to the final SDS design is introduced. A thermal analysis is performed and discussed on the aspect of heat losses considering whether the reflector and/or the feed-through is present or not. A thermal hydraulic simulation shows that the presence of 3 or 4 reflectors minimize the heat loss. Another important point is to introduce the real-time gas analysis in the He{sup 3} collection system. In this study 2 independent strength methods based on gas chromatography and quadruple mass spectrometer for one and on a modified self-assaying quadruple mass spectrometer for the second are applied to separate the hydrogen isotopes in helium gas. Another issue is the possibility of using depleted uranium getter material for the storage of hydrogen isotopes, especially of tritium.

  20. Low-energy beta spectroscopy using pin diodes to monitor tritium surface contamination

    SciTech Connect (OSTI)

    Wampler, W.R.; Doyle, B.L.

    1994-06-01

    We show that tritium betas emitted from a surface can be counted using a pin photodiode as a solid state charged particle detector. Furthermore, we show that the range of tritium betas through air is sufficient to allow measurement of tritium on samples in air by this method. These two findings make possible a new method to survey tritium surface contamination which has advantages over existing methods. We have built and tested several prototype instruments which use this method to measure tritium surface contamination, including a compact portable unit. The design of these instruments and results from tests and calibrations are described. Potential applications of this new method to monitor tritium are discussed.

  1. Three tritium systems test assembly (TSTA) off-loop experiments

    SciTech Connect (OSTI)

    Talcott, C.L.; Anderson, J.L.; Carlson, R.V.; Coffin, D.O.; Walthers, C.R.; Hamerdinger, D.; Binning, K.; Trujillo, R.D.; Moya, J.S.; Hayashi, T.; Okuno, K.; Yamanishi, T.

    1993-11-01

    This report contains the results from three different experiments. Experiment one was initiated to establish the possibility of using a soft elastomer in ITER (International Thermonuclear Experimental Reactor) applications. Used in this application, the sealing material is anticipated to be in tritium at pressures in the range of 1 {times} 10{sup {minus}3} torr for many years. Here two O-ring valve seals each of Viton-A, Buna-N, and EDPM were exposed to 1, 40, or 400 torr of tritium while being cycled open and closed approximately 11,500 times in 192 days. EDPM is the least susceptible to damage from the tritium. Both Buna-N and Viton-A showed deterioration following the first cycling at 400 torr. Using commercially available materials, the Tritium Systems Test Assembly (TSTA) designed and built a Portable Water Removal (PWR) Unit to reduce tritium oxide emissions during glovebox breaches. The PWR removes 99.9% of all tritium and saves between 0.7 and 3.5 curies of tritium oxide from being stacked during each of the five tests. Finally, a series of tests are done to determine whether the presence of SF{sub 6} changes the ability of palladium and platinum to catalyze the T{sub 2}-O{sub 2} reaction to form T{sub 2}O. No deterioration of the catalytic activity is observed. This is important because the Tokamak Fusion Test Reactor (TFTR) requires information about the effect of SF{sub 6}, an electrical insulator, on the catalytic behavior of Pt and Pd in a T{sub 2} environment. This information is necessary for the accident analysis in the Safety Analysis Report for TFTR. This study is done using an apparatus supplied to TSTA by TFTR.

  2. Byron Extended Facility

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

    Byron Extended Facility Map

  3. Ashton Extended Facility

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

    Ashton Extended Facility Map

  4. User Facilities

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

    User Facilities User Facilities User facility agreements allow Los Alamos partners and other entities to conduct research at our unique facilities. In 2011, LANL hosted more than 1,200 users at CINT, LANSCE, and NHMFL. Users came from across the DOE complex, from international academia, and from industrial companies from 45 states across the U.S. Unique world-class user facilities foster rich research opportunities Through its technology transfer efforts, LANL can implement user facility

  5. Mobile Facility

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

    2009-2010 Shouxian, China, 2008 Black Forest, Germany, 2007 Niamey, Niger, 2006 Point Reyes, California, 2005 Mobile Facilities Pictured here in Gan, the second mobile facility...

  6. Tritium production from a plasma discharge on palladium

    SciTech Connect (OSTI)

    Claytor, T.N.; Tuggle, D.G.; Jackson, D.D.

    1995-12-01

    Over the past year we have been able to demonstrate that a plasma loading method produces an exciting and unexpected amount of tritium. In contrast to electrochemical hydrogen or deuterium loading of palladium, this method yields a reproducible tritium generation rate when various electrical and physical conditions are met. We will show tritium generation rates for deuterium-palladium foreground runs that are up to 25 times larger than hydrogen-palladium control experiments using materials from the same batch. The reproducibility of the technique and the large signal to noise over background has allowed us to vary parameters that have been difficult to investigate with previous methods. We intend to illustrate the difference between batches of annealed palladium and as received palladium from several batches to demonstrate that the tritium generation rate can vary by a factor of 40 from batch to batch. The effect of other metals, wire and plate thicknesses on the tritium generation rate will be shown. We plan to discuss these new procedures, present typical results, and speculate concerning the implications for further work.

  7. Evaluation of In-Situ Tritium Transport Parameters for Type 316...

    Office of Environmental Management (EM)

    Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Evaluation of In-Situ Tritium Transport Parameters for Type 316 Stainless Steel during...

  8. Evaluation of Tritium Content and Release from Pressurized Water Reactor Fuel Cladding

    SciTech Connect (OSTI)

    Robinson, Sharon M.; Chattin, Marc Rhea; Giaquinto, Joseph; Jubin, Robert Thomas

    2015-09-01

    It is expected that tritium pretreatment will be required in future reprocessing plants to prevent the release of tritium to the environment (except for long-cooled fuels). To design and operate future reprocessing plants in a safe and environmentally compliant manner, the amount and form of tritium in the used nuclear fuel (UNF) must be understood and quantified. Tritium in light water reactor (LWR) fuel is dispersed between the fuel matrix and the fuel cladding, and some tritium may be in the plenum, probably as tritium labelled water (THO) or T2O. In a standard processing flowsheet, tritium management would be accomplished by treatment of liquid streams within the plant. Pretreating the fuel prior to dissolution to release the tritium into a single off-gas stream could simplify tritium management, so the removal of tritium in the liquid streams throughout the plant may not be required. The fraction of tritium remaining in the cladding may be reduced as a result of tritium pretreatment. Since Zircaloy cladding makes up roughly 25% by mass of UNF in the United States, processes are being considered to reduce the volume of reprocessing waste for Zircaloy clad fuel by recovering the zirconium from the cladding for reuse. These recycle processes could release the tritium in the cladding. For Zircaloy-clad fuels from light water reactors, the tritium produced from ternary fission and other sources is expected to be divided between the fuel, where it is generated, and the cladding. It has been previously documented that a fraction of the tritium produced in uranium oxide fuel from LWRs can migrate and become trapped in the cladding. Estimates of the percentage of tritium in the cladding typically range from 096%. There is relatively limited data on how the tritium content of the cladding varies with burnup and fuel history (temperature, power, etc.) and how pretreatment impacts its release. To gain a better understanding of how tritium in cladding will behave during processing, scoping tests are being performed to determine the tritium content in the cladding pre- and post-tritium pretreatment. Samples of Surry-2 and H.B. Robinson pressurized water reactor cladding were heated to 11001200C to oxidize the zirconium and release all of the tritium in the cladding sample. Cladding samples were also heated within the temperature range of 480600C expected for standard air tritium pretreatment systems, and to a slightly higher temperature (700C) to determine the impact of tritium pretreatment on tritium release from the cladding. The tritium content of the Surry-2 and H.B. Robinson cladding was measured to be ~234 and ~500 Ci/g, respectively. Heating the Surry-2 cladding at 500C for 24 h removed ~0.2% of the tritium from the cladding, and heating at 700C for 24 h removed ~9%. Heating the H.B. Robinson cladding at 700C for 24 h removed ~11% of the tritium. When samples of the Surry-2 and H.B. Robinson claddings were heated at 700C for 96 h, essentially all of the tritium in the cladding was removed. However, only ~3% of the tritium was removed when a sample of Surry-2 cladding was heated at 600C for 96 h. These data indicate that the amount of tritium released from tritium pretreatment systems will be dependent on both the operating temperature and length of time in the system. Under certain conditions, a significant fraction of the tritium could remain bound in the cladding and would need to be considered in operations involving cladding recycle.

  9. Is Tritium Over-Regulated, Part 2 Should The TFG Support Higher...

    Office of Environmental Management (EM)

    Threshold Values? Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Is Tritium Over-Regulated, Part 2...

  10. EIS-0288: Production of Tritium in a Commercial Light Water Reactor

    Broader source: Energy.gov [DOE]

    This Environmental Impact Statement for the Production of Tritium in a Commercial Light Water Reactor (CLWR EIS) evaluates the environmental impacts associated with producing tritium at one or more...

  11. Continuous production of tritium in an isotope-production reactor with a separate circulation system

    DOE Patents [OSTI]

    Cawley, W.E.; Omberg, R.P.

    1982-08-19

    A method is described for producing tritium in a fast breeder reactor cooled with liquid metal. Lithium is allowed to flow through the reactor in separate loops in order to facilitate the production and removal of tritium.

  12. Alternate Tritium Production Methods Using A Liquid Lithium Target

    SciTech Connect (OSTI)

    Wilson, J.

    2015-10-08

    For over 60 years, the Savannah River Site’s primary mission has been the production of tritium. From the beginning, the Savannah River National Laboratory (SRNL) has provided the technical foundation to ensure the successful execution of this critical defense mission. SRNL has developed most of the processes used in the tritium mission and provides the research and development necessary to supply this critical component. This project was executed by first developing reactor models that could be used as a neutron source. In parallel to this development calculations were carried out testing the feasibility of accelerator technologies that could also be used for tritium production. Targets were designed with internal moderating material and optimized target was calculated to be capable of 3000 grams using a 1400 MWt sodium fast reactor, 850 grams using a 400 MWt sodium fast reactor, and 100 grams using a 62 MWt reactor, annually.

  13. TRITIUM EFFECTS ON DYNAMIC MECHANICAL PROPERTIES OF POLYMERIC MATERIALS

    SciTech Connect (OSTI)

    Clark, E

    2008-11-12

    Dynamic mechanical analysis has been used to characterize the effects of tritium gas (initially 1 atm. pressure, ambient temperature) exposure over times up to 2.3 years on several thermoplastics-ultrahigh molecular weight polyethylene (UHMW-PE), polytetrafluoroethylene (PTFE), and Vespel{reg_sign} polyimide, and on several formulations of elastomers based on ethylene propylene diene monomer (EPDM). Tritium exposure stiffened the elastic modulus of UHMW-PE up to about 1 year and then softened it, and reduced the viscous response monotonically with time. PTFE initially stiffened, however the samples became too weak to handle after nine months exposure. The dynamic properties of Vespel{reg_sign} were not affected. The glass transition temperature of the EPDM formulations increased approximately 4 C. following three months tritium exposure.

  14. Thermal Removal of Tritium from Concrete and Soil to Reduce Groundwater

    Office of Environmental Management (EM)

    Impacts | Department of Energy Thermal Removal of Tritium from Concrete and Soil to Reduce Groundwater Impacts Thermal Removal of Tritium from Concrete and Soil to Reduce Groundwater Impacts Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Thermal Removal of Tritium from Concrete and Soil to Reduce Groundwater Impacts More Documents & Publications Long-Term Surveillance and Maintenance Requirements for Remediated FUSRAP

  15. Detection Limit of H and D for Tritium Process R&D

    Broader source: Energy.gov [DOE]

    Presentation from the 35th Tritium Focus Group Meeting held in Princeton, New Jersey on May 05-07, 2015.

  16. Memorandum for Tritium Focus Group Members from Bill Weaver | Department of

    Office of Environmental Management (EM)

    Energy Memorandum for Tritium Focus Group Members from Bill Weaver Memorandum for Tritium Focus Group Members from Bill Weaver Official Position of the Tritium Focus Group on Hazard Category 2 and 3 Threshold Values for Tritium. PDF icon Memorandum from Bill Weaver More Documents & Publications Draft STD-1027 Supplemental Directive (Alternate Hazard Categorization) Methodology DOE-HDBK-1129-99 DOE-HDBK-1129-2007

  17. Evaluation of In-Situ Tritium Transport Parameters for Type 316 Stainless

    Office of Environmental Management (EM)

    Steel during Irradiation | Department of Energy In-Situ Tritium Transport Parameters for Type 316 Stainless Steel during Irradiation Evaluation of In-Situ Tritium Transport Parameters for Type 316 Stainless Steel during Irradiation Presentation from the 33rd Tritium Focus Group Meeting held in Aiken, South Carolina on April 22-24, 2014. PDF icon Evaluation of In-Situ Tritium Transport Parameters for Type 316 Stainless Steel during Irradiation More Documents & Publications In-Reactor

  18. Fusion Nuclear Science and Technology Program- Status and plans for tritium research

    Broader source: Energy.gov [DOE]

    Presentation from the 35th Tritium Focus Group Meeting held in Princeton, New Jersey on May 05-07, 2015.

  19. The Princeton Tritium Observatory for Light, Early Universe, Massive Neutrino Yield (PTOLEMY)

    Broader source: Energy.gov [DOE]

    Presentation from the 34th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014.

  20. Thermal Removal of Tritium from Concrete and Soil to Reduce Groundwater Impacts

    Office of Environmental Management (EM)

    at the Tritium Focus Group Meeting April 22 - 24, 2014 Aiken, South Carolina Thermal Removal of Tritium from Concrete and Soil to Reduce Groundwater Impacts Dennis Jackson P.E. - Savannah River National Laboratory Gerald Blount, Leslie Wells, Joao Cardoso & Thomas Kmetz - Savannah River Nuclear Solutions SP01 Savannah River Site & D-Area Heavy Water Processing Moderator Processing Subunit & Impacts to Groundwater Tritium (pCi/ml) > 200 20 - 200 1Q2006 Synopsis of Tritium at

  1. In-Reactor Measurement of Tritium Permeation through Stainless Steel Cladding

    Broader source: Energy.gov [DOE]

    Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013.

  2. Validation of Hydrogen Exchange Methodology on Molecular Sieves for Tritium Removal from Contaminated Water

    Broader source: Energy.gov [DOE]

    Presentation from the 34th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014.

  3. Tritium on Z: The challenges and possibilities for MagLIF

    Broader source: Energy.gov [DOE]

    Presentation from the 36th Tritium Focus Group Meeting held in Los Alamos, New Mexico, November 3-5, 2015.

  4. Tritium Related Material Research-Irradiation Effect on Isotropic Graphite Utilizing Heavy Ion-Irradiation-

    Broader source: Energy.gov [DOE]

    Presentation from the 34th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014.

  5. Methods to Improve the Lower Limit of Detectionfor Tritium in the Air and on Surfaces

    Broader source: Energy.gov [DOE]

    Presentation from the 36th Tritium Focus Group Meeting held in Los Alamos, New Mexico, November 3-5, 2015.

  6. Facility Representatives

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

    2011-03-01

    This standard, DOE-STD-1063, Facility Representatives, defines the duties, responsibilities and qualifications for Department of Energy (DOE) Facility Representatives, based on facility hazard classification; risks to workers, the public, and the environment; and the operational activity level. This standard provides the guidance necessary to ensure that DOEs hazardous nuclear and non-nuclear facilities have sufficient staffing of technically qualified facility representatives (FRs) to provide day-to-day oversight of contractor operations.

  7. User Facilities

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

    User Facilities /collaboration/_assets/images/icon-collaboration.jpg User Facilities A new research frontier awaits! Our door is open and we thrive on mutually beneficial partnerships, collaborations that drive innovations and new technologies. Unique world-class user facilities foster rich research opportunities Through its technology transfer efforts, LANL can implement user facility agreements that allow its partners and other entities to conduct research at many of its unique facilities.

  8. Tritium Permeability of Incoloy 800H and Inconel 617

    SciTech Connect (OSTI)

    Philip Winston; Pattrick Calderoni; Paul Humrickhouse

    2011-09-01

    Design of the Next Generation Nuclear Plant (NGNP) reactor and its high-temperature components requires information regarding the permeation of fission generated tritium and hydrogen product through candidate heat exchanger alloys. Release of fission-generated tritium to the environment and the potential contamination of the helium coolant by permeation of product hydrogen into the coolant system represent safety basis and product contamination issues. Of the three potential candidates for high-temperature components of the NGNP reactor design, only permeability for Incoloy 800H has been well documented. Hydrogen permeability data have been published for Inconel 617, but only in two literature reports and for partial pressures of hydrogen greater than one atmosphere, far higher than anticipated in the NGNP reactor. To support engineering design of the NGNP reactor components, the tritium permeability of Inconel 617 and Incoloy 800H was determined using a measurement system designed and fabricated at Idaho National Laboratory. The tritium permeability of Incoloy 800H and Inconel 617, was measured in the temperature range 650 to 950 C and at primary concentrations of 1.5 to 6 parts per million volume tritium in helium. (partial pressures of 10-6 atm) - three orders of magnitude lower partial pressures than used in the hydrogen permeation testing. The measured tritium permeability of Incoloy 800H and Inconel 617 deviated substantially from the values measured for hydrogen. This may be due to instrument offset, system absorption, presence of competing quantities of hydrogen, surface oxides, or other phenomena. Due to the challenge of determining the chemical composition of a mixture with such a low hydrogen isotope concentration, no categorical explanation of this offset has been developed.

  9. Tritium Permeability of Incoloy 800H and Inconel 617

    SciTech Connect (OSTI)

    Philip Winston; Pattrick Calderoni; Paul Humrickhouse

    2012-07-01

    Design of the Next Generation Nuclear Plant (NGNP) reactor and its high-temperature components requires information regarding the permeation of fission generated tritium and hydrogen product through candidate heat exchanger alloys. Release of fission-generated tritium to the environment and the potential contamination of the helium coolant by permeation of product hydrogen into the coolant system represent safety basis and product contamination issues. Of the three potential candidates for high-temperature components of the NGNP reactor design, only permeability for Incoloy 800H has been well documented. Hydrogen permeability data have been published for Inconel 617, but only in two literature reports and for partial pressures of hydrogen greater than one atmosphere, far higher than anticipated in the NGNP reactor. To support engineering design of the NGNP reactor components, the tritium permeability of Inconel 617 and Incoloy 800H was determined using a measurement system designed and fabricated at Idaho National Laboratory. The tritium permeability of Incoloy 800H and Inconel 617, was measured in the temperature range 650 to 950C and at primary concentrations of 1.5 to 6 parts per million volume tritium in helium. (partial pressures of 10-6 atm)three orders of magnitude lower partial pressures than used in the hydrogen permeation testing. The measured tritium permeability of Incoloy 800H and Inconel 617 deviated substantially from the values measured for hydrogen. This may be due to instrument offset, system absorption, presence of competing quantities of hydrogen, surface oxides, or other phenomena. Due to the challenge of determining the chemical composition of a mixture with such a low hydrogen isotope concentration, no categorical explanation of this offset has been developed.

  10. 36th Tritium Focus Group Meeting, Los Alamos, New Mexico, November 03-05, 2015

    Broader source: Energy.gov [DOE]

    The Tritium Focus Group (TFG), is a long standing DOE Working Group, whose purpose is to promote cost-effective improvements in tritium safety, handling, transportation, storage, and operations, and to enhance communication across the Department of Energy (DOE) (inclusive of the National Nuclear Security Administration (NNSA)) on all matters related to tritium.

  11. 35th Tritium Focus Group Meeting, Princeton, New Jersey, May 05-07, 2015

    Broader source: Energy.gov [DOE]

    The Tritium Focus Group (TFG), is a long standing DOE Working Group, whose purpose is to promote cost-effective improvements in tritium safety, handling, transportation, storage, and operations, and to enhance communication across the Department of Energy (DOE) (inclusive of the National Nuclear Security Administration (NNSA)) on all matters related to tritium.

  12. Uncertainty assessment and analysis of ITER in-VV tritium inventory determination

    SciTech Connect (OSTI)

    Cristescu, I. R.; Cristescu, I.; Glugla, M.; Murdoch, D.; Ciattaglia, S.

    2008-07-15

    Tracking of tritium inventories on ITER will be essential to ensure that the safety limits established for the mobilizable tritium inventory in the vacuum vessel are not violated. Tritium will be delivered to the ITER site from outside suppliers. Staring with the tritium imports the value of tritium inventory at ITER site will be known with a certain error that will propagate in time. During plasma operation, shot by shot measurements of the tritium delivered to the Torus and recovered will allow the amount of tritium trapped in the Torus to be computed at the end of the day. A case study for different measuring techniques and several measuring points for the tritium recovered from Torus have been done. An alternative method is to measure overnight the variation in the inventory of the storage and delivery system and the associated error when this method will be employed are presented. In order to reduce the errors on the tritium trapped in-vessel, at certain time intervals a method of global tritium inventory will be performed. The method envisages the transfer of all the mobilizable tritium from the plant and measurement of this inventory in the self-assay beds from the storage and delivery system. Evaluation of the most important sources of error for the tritium trapped in-vessel and means of minimization are eventually presented. (authors)

  13. Savannah River Nuclear Solutions S A V A N N A H R I V E R S

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

    nuclear materials. Support facilities, including two chemical separations plants, a heavy water extraction plant, a nuclear fuel and target fabrication facility, a tritium...

  14. 32nd Tritium Focus Group Meeting, Cloverleaf Building, Germantown MD, April

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

    23-25, 2013 | Department of Energy 2nd Tritium Focus Group Meeting, Cloverleaf Building, Germantown MD, April 23-25, 2013 32nd Tritium Focus Group Meeting, Cloverleaf Building, Germantown MD, April 23-25, 2013 32nd Tritium Focus Group Meeting, Cloverleaf Building, Germantown MD, April 23-25, 2013 The Tritium Focus Group (TFG), is a long standing DOE Working Group, whose purpose is to promote cost-effective improvements in tritium safety, handling, transportation, storage, and operations, and

  15. 33rd Tritium Focus Group Meeting, Aiken, South Carolina, April 22-24, 2014

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

    | Department of Energy 3rd Tritium Focus Group Meeting, Aiken, South Carolina, April 22-24, 2014 33rd Tritium Focus Group Meeting, Aiken, South Carolina, April 22-24, 2014 33rd Tritium Focus Group Meeting, Aiken, South Carolina, April 22-24, 2014 The Tritium Focus Group (TFG), is a long standing DOE Working Group, whose purpose is to promote cost-effective improvements in tritium safety, handling, transportation, storage, and operations, and to enhance communication across the Department of

  16. Evaluation of In-Situ Tritium Transport Parameters for Type 316 Stainless Steel during Irradiation

    Office of Environmental Management (EM)

    In-Situ Tritium Transport Parameters for Type 316 Stainless Steel during Irradiation D.J. Senor, W.G. Luscher K.K. Clayton, G.R. Longhurst Tritium Focus Group Meeting Savannah River National Laboratory Aiken, SC 23 April 2014 PNNL-SA-102143 Motivation and Scope TMIST-2 Experiment Measured in-reactor steady state tritium permeation through Type 316 stainless steel as a function of tritium partial pressure and temperature Tritium permeation irradiation enhancement of ~3X was observed relative to

  17. Preparation and characterization of tritium targets. [Titanium tritide

    SciTech Connect (OSTI)

    Ramey, D.W.; Adair, H.L.

    1982-01-01

    The Isotope Research Materials Laboratory (IRML) of the Oak Ridge National Laboratory (ORNL) prepares tritium targets that are used to produce an intense beam of 14.5 MeV neutrons by the /sup 3/H(/sup 2/H,/sup 1/n)/sup 4/He reaction. The intense beams of 14.5 MeV neutrons are used in programs involving cancer research, materials evaluation, and materials identification. The tritium targets required by researchers have ranged in size from 1-cm diam to 50-cm diam and have contained from 3.7 x 10/sup 4/ MBq to 2.2 x 10/sup 8/ MBq of tritium. Important parameters in the performance of tritium targets, when bombarded with deuterons, include target lifetime and neutron output. These parameters are heavily dependent on the host metal layer used to form the tritide compound and the gas-to-metal loading of the host material. Fabrication procedures used in preparing titanium tritide targets with subsequent gas-to-metal determinations are described.

  18. Solubility of hydrogen, deuterium, and tritium in palladium metal

    SciTech Connect (OSTI)

    Powell, G.L.; Laesser, R.

    1988-12-20

    The solubility of hydrogen, deuterium, and tritium in palladium has been measured, described analytically over a wide temperature range (296 to 1460 K), and used to calculate enthalpies of reaction, isotope separation factors, and phase boundaries. 44 refs., 11 figs., 5 tabs.

  19. Facility Safety

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

    1996-10-24

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

  20. Facility Safety

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

    1995-11-16

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

  1. ORISE: Facilities

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

    ORISE Facilities Unique laboratories and training centers among the assets managed on behalf of the U.S. Department of Energy The Oak Ridge Institute for Science and Education (ORISE) is home to a number of on- and off-site facilities that support the U.S. Department of Energy's (DOE) science education and research mission. From on-site medical laboratories to radiation emergency medicine training facilities, ORISE facilities are helping to address national needs in the following areas:

  2. Science Facilities

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

    Facilities /science-innovation/_assets/images/icon-science.jpg Science Facilities The focal point for basic and applied R&D programs with a primary focus on energy but also encompassing medical, biotechnology, high-energy physics, and advanced scientific computing programs. Center for Integrated Nanotechnologies» Dual Axis Radiographic Hydrodynamic Test Facility (DARHT)» Electron Microscopy Lab» Ion Beam Materials Lab» Isotope Production Facility» Los Alamos Neutron Science Center»

  3. Comparison of the recently proposed super-Marx generator approach to thermonuclear ignition with the deuterium-tritium laser fusion-fission hybrid concept by the Lawrence Livermore National Laboratory

    SciTech Connect (OSTI)

    Winterberg, F.

    2009-01-01

    The recently proposed super-Marx generator pure deuterium microdetonation ignition concept is compared to the Lawrence Livermore National Ignition Facility (NIF) Laser deuterium-tritium fusion-fission hybrid concept (LIFE). In a super-Marx generator, a large number of ordinary Marx generators charge up a much larger second stage ultrahigh voltage Marx generator from which for the ignition of a pure deuterium microexplosion an intense GeV ion beam can be extracted. Typical examples of the LIFE concept are a fusion gain of 30 and a fission gain of 10, making up a total gain of 300, with about ten times more energy released into fission as compared to fusion. This means the substantial release of fission products, as in fissionless pure fission reactors. In the super-Marx approach for the ignition of pure deuterium microdetonation, a gain of the same magnitude can, in theory, be reached. If feasible, the super-Marx generator deuterium ignition approach would make lasers obsolete as a means for the ignition of thermonuclear microexplosions.

  4. Comparison of the recently proposed super-Marx generator approach to thermonuclear ignition with the deuterium-tritium laser fusion-fission hybrid concept by the Lawrence Livermore National Laboratory

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

    Winterberg, F.

    2009-01-01

    The recently proposed super-Marx generator pure deuterium microdetonation ignition concept is compared to the Lawrence Livermore National Ignition Facility (NIF) Laser deuterium-tritium fusion-fission hybrid concept (LIFE). In a super-Marx generator, a large number of ordinary Marx generators charge up a much larger second stage ultrahigh voltage Marx generator from which for the ignition of a pure deuterium microexplosion an intense GeV ion beam can be extracted. Typical examples of the LIFE concept are a fusion gain of 30 and a fission gain of 10, making up a total gain of 300, with about ten times more energy released into fissionmore » as compared to fusion. This means the substantial release of fission products, as in fissionless pure fission reactors. In the super-Marx approach for the ignition of pure deuterium microdetonation, a gain of the same magnitude can, in theory, be reached. If feasible, the super-Marx generator deuterium ignition approach would make lasers obsolete as a means for the ignition of thermonuclear microexplosions.« less

  5. Wheelabrator Millbury Facility Biomass Facility | Open Energy...

    Open Energy Info (EERE)

    Facility Facility Wheelabrator Millbury Facility Sector Biomass Facility Type Municipal Solid Waste Location Worcester County, Massachusetts Coordinates 42.4096528, -71.8571331...

  6. ARM - Facility News Article

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

    November 8, 2008 [Facility News] See ARM Data in a New Light Bookmark and Share Two new visualization tools are now available from the ARM Data Archive to help you plot and package data orders, and preview climate-scale data collections. Implemented this summer, an enhanced version of the NCVweb offers many powerful features such as producing detailed tables of NetCDF file contents, data extraction, generating statistics, and plotting one variable against another. Using NCVweb, users can plot

  7. ARM - Facility News Article

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

    July 15, 2008 [Facility News] Extract This! Enhanced Visualization Tool Available at the Data Archive Bookmark and Share Custom 2-day plot of downwelling shortwave and longwave radiation made using the enhanced NCVweb feature. Like many scientific organizations, the ARM Data Archive stores and distributes atmospheric data from the ARM sites in Network common data form, or NetCDF. This file format applies names or attributes to the various layers of data for efficient identification and

  8. Retention and release of tritium in aluminum clad, Al-Li alloys

    SciTech Connect (OSTI)

    Louthan, M.R. Jr.

    1991-12-31

    Tritium retention in and release from aluminum clad, aluminum-lithium alloys is modeled from experimental and operational data developed during the thirty plus years of tritium production at the Savannah River Site. The model assumes that tritium atoms, formed by the {sup 6}Li(n,{alpha}){sup 3}He reaction, are produced in solid solution in the Al-Li alloy. Because of the low solubility of hydrogen isotopes in aluminum alloys, the irradiated Al-Li rapidly becomes supersaturated in tritium. Newly produced tritium atoms are trapped by lithium atoms to form a lithium tritide. The effective tritium pressure required for trap or tritide stability is the equilibrium decomposition pressure of tritium over a lithium tritide-aluminum mixture. The temperature dependence of tritium release is determined by the permeability of the cladding to tritium and the local equilibrium at the trap sites. This model is used to calculate tritium release from aluminum clad, aluminum-lithium alloys. 9 refs., 3 figs.

  9. Retention and release of tritium in aluminum clad, Al-Li alloys

    SciTech Connect (OSTI)

    Louthan, M.R. Jr.

    1991-01-01

    Tritium retention in and release from aluminum clad, aluminum-lithium alloys is modeled from experimental and operational data developed during the thirty plus years of tritium production at the Savannah River Site. The model assumes that tritium atoms, formed by the {sup 6}Li(n,{alpha}){sup 3}He reaction, are produced in solid solution in the Al-Li alloy. Because of the low solubility of hydrogen isotopes in aluminum alloys, the irradiated Al-Li rapidly becomes supersaturated in tritium. Newly produced tritium atoms are trapped by lithium atoms to form a lithium tritide. The effective tritium pressure required for trap or tritide stability is the equilibrium decomposition pressure of tritium over a lithium tritide-aluminum mixture. The temperature dependence of tritium release is determined by the permeability of the cladding to tritium and the local equilibrium at the trap sites. This model is used to calculate tritium release from aluminum clad, aluminum-lithium alloys. 9 refs., 3 figs.

  10. Scoping Analyses on Tritium Permeation to VHTR Integarted Industrial Application Systems

    SciTech Connect (OSTI)

    Chang H. Oh; Eung S. Kim

    2011-03-01

    Tritium permeation is a very important current issue in the very high temperature reactor (VHTR) because tritium is easily permeated through high temperature metallic surfaces. Tritium permeations in the VHTR-integrated systems were investigated in this study using the tritium permeation analysis code (TPAC) that was developed by Idaho National Laboratory (INL). The INL TPAC is a numerical tool that is based on the mass balance equations of tritium containing species and hydrogen (i.e. HT, H2, HTO, HTSO4, TI) coupled with a variety of tritium sources, sink, and permeation models. In the TPAC, ternary fission and thermal neutron caption reactions with 6Li, 7Li 10B, 3He were taken into considerations as tritium sources. Purification and leakage models were implemented as main tritium sinks. Permeation of tritium and H2 through pipes, vessels, and heat exchangers were considered as main tritium transport paths. In addition, electroyzer and isotope exchange models were developed for analyzing hydrogen production systems including high temperature electrolysis (HTSE) and sulfur-iodine processes.

  11. 3HE RECOVERY FROM A TRITIUM-AGED LANA75 SAMPLE

    SciTech Connect (OSTI)

    Shanahan, K.

    2010-12-01

    {sup 3}He recovery is a topic of recent interest. One potential recovery source is from metal hydride materials once used to store tritium, as the decay product, {sup 3}He, is primarily trapped in the metal lattice, usually in bubbles, with such materials. In 2001, a Tritium Exposure Program (TEP) sample known as LANA75-SP1 was retired and the material was removed from the test cell and stored. Subsequently scoping temperature programmed desorption (TPD) experiments were conducted on that material to see what it might take to drive out He and residual H isotopes (the heel). Two experiments consisted of heating the sample in the presence of an excess of tin (the so-called Sn fusion experiment), and one was a simple TPD with no additives. Prior data on the so-called '21-month bed' material in the 1980's had produced {approx}21 cc of gas per gram of a LANA30 material (LaNi4.7Al0.3), with approximately 67% of that being {sup 3}He and the rest being D{sub 2} (Fig.3). However, the material had to be heated in excess of 850 C to obtain that level. Heating to less produced approximately half that amount of gas. The data also showed that {sup 3}He was released at different temperatures than the residual hydrogen isotopes. Unfortunately this implies full {sup 3}He recovery will be a difficult process. Therefore, it seemed advisable to attempt to extract as much information from the 3 scoping experiments from 2001-2 as possible.

  12. Beamlines & Facilities

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

    Imaging Group: Beamlines The X-ray Micrscopy and Imaging Group operates several beamlines and facilities. The bending magnet beamline (2-BM) entertaines 2 general user programs in...

  13. DEVELOPMENT AND USE OF A BULK TRITIUM SHIPPING PACKAGE

    SciTech Connect (OSTI)

    Blanton, P.

    2010-09-30

    A shipping package for transporting tritium has been developed for use by the National Nuclear Safety Administration as a replacement for the DOE Model UC-609, a tritium package developed and used by the DOE and NRC since the early 1970s. This paper presents the major design features and highlights the improvements made over its predecessor by incorporating new engineered materials and implementing improved testing, handling, and maintenance capabilities, while improving manufacturability. A discussion will be provided demonstrating how the BTSP complies with the regulatory safety requirements of the Nuclear Regulatory Commission. The paper further summarizes the results of testing to 10 CFR 71 Normal Conditions of Transport and Hypothetical Accident Conditions events. Planned and possible future missions for this packaging will be addressed.

  14. FINITE ELEMENT ANALYSIS OF BULK TRITIUM SHIPPING PACKAGE

    SciTech Connect (OSTI)

    Jordan, J.

    2010-06-02

    The Bulk Tritium Shipping Package was designed by Savannah River National Laboratory. This package will be used to transport tritium. As part of the requirements for certification, the package must be shown to meet the scenarios of the Hypothetical Accident Conditions (HAC) defined in Code of Federal Regulations Title 10 Part 71 (10CFR71). The conditions include a sequential 30-foot drop event, 30-foot dynamic crush event, and a 40-inch puncture event. Finite Element analyses were performed to support and expand upon prototype testing. Cases similar to the tests were evaluated. Additional temperatures and orientations were also examined to determine their impact on the results. The peak stress on the package was shown to be acceptable. In addition, the strain on the outer drum as well as the inner containment boundary was shown to be acceptable. In conjunction with the prototype tests, the package was shown to meet its confinement requirements.

  15. Elastic Electron Scattering from Tritium and Helium-3

    DOE R&D Accomplishments [OSTI]

    Collard, H.; Hofstadter, R.; Hughes, E. B.; Johansson, A.; Yearian, M. R.; Day, R. B.; Wagner, R. T.

    1964-10-01

    The mirror nuclei of tritium and helium-3 have been studied by the method of elastic electron scattering. Absolute cross sections have been measured for incident electron energies in the range 110 - 690 MeV at scattering angles lying between 40 degrees and 135 degrees in this energy range. The data have been interpreted in a straightforward manner and form factors are given for the distributions of charge and magnetic moment in the two nuclei over a range of four-momentum transfer squared 1.0 - 8.0 F{sup -2}. Model-independent radii of the charge and magnetic moment distributions are given and an attempt is made to deduce form factors describing the spatial distribution of the protons in tritium and helium-3.

  16. IN-LINE CHEMICAL SENSOR DEPLOYMENT IN A TRITIUM PLANT

    SciTech Connect (OSTI)

    Tovo, L.; Wright, J.; Torres, R.; Peters, B.

    2013-10-02

    The Savannah River Tritium Plant (TP) relies on well understood but aging sensor technology for process gas analysis. Though new sensor technologies have been brought to various readiness levels, the TP has been reluctant to install technologies that have not been tested in tritium service. This gap between sensor technology development and incorporating new technologies into practical applications demonstrates fundamental challenges that exist when transitioning from status quo to state-of-the-art in an extreme environment such as a tritium plant. These challenges stem from three root obstacles: 1) The need for a comprehensive assessment of process sensing needs and requirements; 2) The lack of a pick-list of process-compatible sensor technologies; and 3) The need to test technologies in a tritium-contaminated process environment without risking production. At Savannah River, these issues are being addressed in a two phase project. In the first phase, TP sensing requirements were determined by a team of process experts. Meanwhile, Savannah River National Laboratory sensor experts identified candidate technologies and related them to the TP processing requirements. The resulting roadmap links the candidate technologies to actual plant needs. To provide accurate assessments of how a candidate sensor technology would perform in a contaminated process environment, an instrument demonstration station was established within a TP glove box. This station was fabricated to TP process requirements and designed to handle high activity samples. The combination of roadmap and demonstration station provides the following assets: ? Creates a partnership between the process engineers and researchers for sensor selection, maturation, and insertion, ? Selects the right sensors for process conditions ? Provides a means for safely inserting new sensor technology into the process without risking production, and ? Provides a means to evaluate off normal occurrences where and when they occur. This paper discusses the process to identify and demonstrate new sensor technologies for the Savannah River TP.

  17. Electron Proton Hydrogen Deuterium Tritium Neutron Fusion Basics

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

    Proton Hydrogen Deuterium Tritium Neutron Fusion Basics Throughout history, the way in which the sun and stars produce their energy remained a mystery. During the 20th century, scientists discovered that the energy is produced through the fusion of light atoms. Albert Einstein's familiar formula, E=mc 2 , provided the basis for understanding that mass can be converted into energy. With fission, heavy atoms - such as uranium - can be split to release the internal energy that holds them together.

  18. Luis Alvarez, the Hydrogen Bubble Chamber, Tritium, and Dinosaurs

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

    Luis Alvarez, the Hydrogen Bubble Chamber, Tritium, and Dinosaurs Resources with Additional Information * Patents Luis Alvarez Courtesy Lawrence Berkeley National Laboratory 'Luis W. Alvarez was an adventurer physicist. The two terms may seem an odd combination until one considers Alvarez's career. A member of the National Inventor's Hall of Fame, Alvarez developed the proton linear accelerator, patented three types of radar still used today, designed an instrument that for 15 years served as

  19. Savannah River Tritium Enterprise exceeds productivity savings goals for

    National Nuclear Security Administration (NNSA)

    FY13 | National Nuclear Security Administration Tritium Enterprise exceeds productivity savings goals for FY13 | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact

  20. Microsoft Word - Tritium Production and Environmental Impacts Oct 17 2011

    National Nuclear Security Administration (NNSA)

    Production and Environmental Impacts The production of tritium in a commercial light water reactor (CLWR) is technically straightforward. Most existing CLWRs utilize 12-foot-long rods containing an isotope of boron (boron-10) in ceramic form. These rods are generally referred to as burnable absorber rods. The rods are inserted in the reactor fuel assemblies to absorb excess neutrons produced by the uranium fuel in the fission process for the purpose of controlling power at the beginning of an

  1. Measurement of uptake and release of tritium by tungsten

    SciTech Connect (OSTI)

    Nakayama, M.; Torikai, Y.; Saito, M.; Penzhorn, R.D.; Isobe, K.; Yamanishi, T.; Kurishita, H.

    2015-03-15

    Tungsten is currently contemplated as plasma facing material for the divertor of future fusion machines. In this paper the uptake of tritium by tungsten and its release behavior have been investigated. Tungsten samples have been annealed at various temperatures and loaded at also different temperatures with deuterium containing 7.2 % tritium at a pressure of 1.2 kPa. A specific system was designed to assess the release of tritiated water and molecular tritium by the samples. Due to the rather low solubility of hydrogen isotopes in tungsten it is particularly important to be aware of the presence of hydrogen traps or thin oxide films. As shown in this work, traps or oxide films may affect the retention capability of tungsten and lead to significantly modified release properties. It became clear that there were capture sites that had different thermal stability and different capture intensity in tungsten after polishing, or oxide films that were grown on the surface of tungsten and had barrier effects.

  2. Tritium and neutron measurements of a solid state cell

    SciTech Connect (OSTI)

    Claytor, T.N.; Seeger, P.A.; Rohwer, R.K.; Tuggle, D.G.; Doty, W.R.

    1989-01-01

    A solid state cold fusion'' cell was constructed to test for non-equilibrium fusion in a solid. The stimulus for the design was the hypothesis that the electrochemical surface layer in the Pons- Fleischmann cell could be replaced with a metal-insulator- semiconductor (MIS) barrier. Cells were constructed of alternating layers of palladium and silicon powders pressed into a ceramic form and exposed to deuterium gas at 110 psia resulting in a D/Pd ratio of 0.7. Pulses of current were passed through the cells to populate non-equilibrium states at the MIS barriers. One cell showed neutron activity and was found to have a large amount of tritium, other cells have produced tritium at a low rate consistent with neutron emission below the threshold of observability. The branching ratio for n/p has been about 1 {times} 10{sup {minus}9} in all the experiments where a substantial amount of tritium has been found. 11 refs., 9 figs., 2 tabs.

  3. Tritium permeation experiments using reduced activation ferritic/martensitic steel tube and erbium oxide coating

    SciTech Connect (OSTI)

    Takumi Chikada; Masashi Shimada; Robert Pawelko; Takayuki Terai; Takeo Muroga

    2013-09-01

    Low concentration tritium permeation experiments have been performed on uncoated F82H and Er2O3-coated tubular samples in the framework of the Japan-US TITAN collaborative program. Tritium permeability of the uncoated sample with 1.2 ppm tritium showed one order of magnitude lower than that with 100% deuterium. The permeability of the sample with 40 ppm tritium was more than twice higher than that of 1.2 ppm, indicating a surface contribution at the lower tritium concentration. The Er2O3-coated sample showed two orders of magnitude lower permeability than the uncoated sample, and lower permeability than that of the coated plate sample with 100% deuterium. It was also indicated that the memory effect of ion chambers in the primary and secondary circuits was caused by absorption of tritiated water vapor that was generated by isotope exchange reactions between tritium and surface water on the coating.

  4. In-bed accountability of tritium in production scale metal hydride storage beds

    SciTech Connect (OSTI)

    Klein, J.E.

    1995-10-01

    An `in-bed accountability` (IBA) flowing gas calorimetric measurement method has been developed and implemented to eliminate the need to remove tritium from production scale metal hydride storage beds for inventory measurement purposes. Six-point tritium IBA calibration curves have been completed for two, 390 gram tritium metal hydride storage beds. The calibration curves for the two tritium beds are similar to those obtained from the `cold` test program. Tritium inventory errors at the 95 percent confidence level ranged from {+-} 7.3 to 8.6 grams for the cold test results compared to {+-} 4.2 to 7.5 grams obtained for the two tritium calibrated beds. 5 refs., 4 figs., 1 tab.

  5. Tritium permeation characterization of materials for fusion and generation IV very high temperature reactors

    SciTech Connect (OSTI)

    Thomson, S.; Pilatzke, K.; McCrimmon, K.; Castillo, I.; Suppiah, S.

    2015-03-15

    The objective of this work is to establish the tritium-permeation properties of structural alloys considered for Fusion systems and very high temperature reactors (VHTR). A description of the work performed to set up an apparatus to measure permeation rates of hydrogen and tritium in 304L stainless steel is presented. Following successful commissioning with hydrogen, the test apparatus was commissioned with tritium. Commissioning tests with tritium suggest the need for a reduction step that is capable of removing the oxide layer from the test sample surfaces before accurate tritium-permeation data can be obtained. Work is also on-going to clearly establish the temperature profile of the sample to correctly estimate the tritium-permeability data.

  6. Facility Safety

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

    2005-12-22

    This Order establishes facility and programmatic safety requirements for Department of Energy facilities, which includes nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards mitigation, and the System Engineer Program. Cancels DOE O 420.1A. DOE O 420.1B Chg 1 issued 4-19-10.

  7. Tritium Gas Stream Scrubbing using In-situ Reactive Materials | Department

    Office of Environmental Management (EM)

    of Energy Stream Scrubbing using In-situ Reactive Materials Tritium Gas Stream Scrubbing using In-situ Reactive Materials Presentation from the 36th Tritium Focus Group Meeting held in Los Alamos, New Mexico, November 3-5, 2015. PDF icon Tritium Gas Stream Scrubbing using In-situ Reactive Materials More Documents & Publications Effect of Various Impurities on the Hydrogen Absorption on SAES ST198 AVTA: Oil Bypass Filter Specifications and Test Procedures Vehicle Technologies Office Merit

  8. Report on the evaluation of the tritium producing burnable absorber rod lead test assembly. Revision 1

    SciTech Connect (OSTI)

    1997-03-01

    This report describes the design and fabrication requirements for a tritium-producing burnable absorber rod lead test assembly and evaluates the safety issues associated with tritium-producing burnable absorber rod irradiation on the operation of a commercial light water reactor. The report provides an evaluation of the tritium-producing burnable absorber rod design and concludes that irradiation can be performed within U.S. Nuclear Regulatory Commission regulations applicable to a commercial pressurized light water reactor.

  9. Behavior of tritium permeation induced by water corrosion of alpha iron

    Office of Scientific and Technical Information (OSTI)

    around room temperature (Journal Article) | SciTech Connect Behavior of tritium permeation induced by water corrosion of alpha iron around room temperature Citation Details In-Document Search Title: Behavior of tritium permeation induced by water corrosion of alpha iron around room temperature Tritium (T) permeation leakage to surroundings is a great safety concern in fission and fusion reactor systems. T permeation potentially occurs from T contaminated water through cooling tubes or

  10. Radioluminescent light sources, tritium containing polymers, and methods for producing the same

    DOE Patents [OSTI]

    Jensen, G.A.; Nelson, D.A.; Molton, P.M.

    1989-12-26

    A radioluminescent light source comprises a solid mixture of a phosphorescent substance and a tritiated polymer. The solid mixture forms a solid mass having length, width, and thickness dimensions, and is capable of self-support. In one aspect of the invention, the phosphorescent substance comprises solid phosphor particles supported or surrounded within a solid matrix by a tritium containing polymer. The tritium containing polymer comprises a polymer backbone which is essentially void of tritium. 2 figs.

  11. Radioluminescent light sources, tritium containing polymers, and methods for producing the same

    DOE Patents [OSTI]

    Jensen, George A. (Richland, WA); Nelson, David A. (Richland, WA); Molton, Peter M. (Richland, WA)

    1989-01-01

    A radioluminescent light source comprises a solid mixture of a phosphorescent substance and a tritiated polymer. The solid mixture forms a solid mass having length, width, and thickness dimensions, and is capable of self-support. In one aspect of the invention, the phosphorescent substance comprises solid phosphor particles supported or surrounded within a solid matix by a tritium containing polymer. The tritium containing polymer comprises a polymer backbone which is essentially void of tritium.

  12. Concentration and removal of tritium and/or deuterium from water contaminated with tritium and/or deuterium

    DOE Patents [OSTI]

    Meyer, Thomas J. (Chapel Hill, NC); Narula, Poonam M. (Carrboro, NC)

    2001-01-01

    Concentration of tritium and/or deuterium that is a contaminant in H.sub.2 O, followed by separation of the concentrate from the H.sub.2 O. Employed are certain metal oxo complexes, preferably with a metal from Group VIII. For instance, [Ru.sup.IV (2,2',6',2"-terpyridine)(2,2'-bipyridine)(O)](ClO.sub.4).sub.2 is very suitable.

  13. Thermal Removal of Tritium from Concrete and Soil to Reduce Groundwate...

    Office of Environmental Management (EM)

    Thermal Removal of Tritium from Concrete and Soil to Reduce Groundwater Impacts Dennis Jackson P.E. - Savannah River National Laboratory Gerald Blount, Leslie Wells, Joao...

  14. Methods to Improve the Lower Limit of Detection for Tritium in the Air and on Surfaces

    Office of Environmental Management (EM)

    Group LANL Nov. 3 - 5, 2015 Methods to Improve the Lower Limit of Detection for Tritium in the Air and on Surfaces James T. (Tom) Voss, LANL LA-UR-15-28465 Present methods for the detection of tritium are adequate for most applications. However, the technology is becoming antiquated and in need of improvement, especially to address methods to achieve a lower limit of detection for Tritium in the air and on surfaces. The present methods to detect tritium in air are with the use of ion chamber

  15. The Tritium Under-flow Study at the Savannah River Site

    SciTech Connect (OSTI)

    Hiergesell, Robert A.

    2008-01-15

    An issue of concern at the Savannah River Site (SRS) over the past 20 years is whether tritiated groundwater originating at SRS might be the cause of low levels of tritium measured in certain domestic wells in Georgia. Tritium activity levels in several domestic wells have been observed to occur at levels comparable to what is measured in rainfall in areas surrounding SRS. Since 1988, there has been speculation that tritiated groundwater from SRS could flow under the river and find its way into Georgia wells. A considerable effort was directed at assessing the likelihood of trans-river flow, and 44 wells have been drilled by the USGS and the Georgia Department of Natural Resources. Also, as part of the data collection and analysis, the USGS developed a numerical model during 1997-98 to assess the possibility for such trans-river flow to occur. The model represented the regional groundwater flow system surrounding the Savannah River Site (SRS) in seven layers corresponding to the underlying hydrostratigraphic units, which was regarded as sufficiently detailed to evaluate whether groundwater originating at SRS could possibly flow beneath the Savannah River into Georgia. The model was calibrated against a large database of water-level measurements obtained from wells on both sides of the Savannah River and screened in each of the hydrostratigraphic units represented within the model. The model results verified that the groundwater movement in all hydrostratigraphic units proceeds laterally toward the Savannah River from both South Carolina and Georgia, and discharges into the river. Once the model was calibrated, a particle-track analysis was conducted to delineate areas of potential trans-river flow. Trans-river flow can occur in either an eastward or westward direction. The model indicated that all locations of trans-river flow are restricted to the Savannah River's flood plain, where groundwater passes immediately prior to discharging into the river. Whether the trans-river flow is eastward or westward depends primarily on the position of the Savannah River as it meanders back and forth within the flood plain and is limited to narrow sections of land adjacent to the river. With respect to the only location of westward trans-river flow that has a recharge area within the SRS, the new evaluations of hypothetical pumping scenarios indicated that only a very slight impact is incurred, even under the most extreme groundwater extraction scenario. The updated model did not result in a significant change in the location of the recharge areas at SRS and the only impact was measured in slight changes in the travel times associated with the travel path. The median groundwater travel times for particles released under each of the 4 groundwater extraction scenarios ranged from 366 to 507 years while. Under the most extreme scenario, that under which SRS groundwater extraction is discontinued, the shortest travel time was reduced from 90 to 79 years. It should be emphasized that the groundwater transit times do not include the time required for groundwater to migrate vertically downward across the uppermost aquifer (i.e. at the recharge area), thus the actual groundwater travel times could be up to several decades longer than what was calculated in the model. The exhaustive evaluations that have been conducted indicates that it is highly unlikely that tritiated groundwater originating at the SRS could migrate into Georgia and explain the low tritium activity levels that were originally observed in certain domestic water supply wells. Considering that those wells were located at some distance (several km) from the Savannah River, a far more likely explanation is that tritiated rainfall infiltrated the subsurface and recharged the shallow aquifer within which the well was finished.

  16. Total Energy Facilities Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    Energy Facilities Biomass Facility Jump to: navigation, search Name Total Energy Facilities Biomass Facility Facility Total Energy Facilities Sector Biomass Facility Type...

  17. Gas Utilization Facility Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    Gas Utilization Facility Biomass Facility Jump to: navigation, search Name Gas Utilization Facility Biomass Facility Facility Gas Utilization Facility Sector Biomass Facility Type...

  18. Facility Safety

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

    2002-05-20

    To establish facility safety requirements for the Department of Energy, including National Nuclear Security Administration. Cancels DOE O 420.1. Canceled by DOE O 420.1B.

  19. Research Facility,

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

    and Delivering the Data As a general condition for use of the ARM Climate Research Facility, users are required to include their data in the ARM Data Archive. All data acquired...

  20. Evaluation of Technologies to Complement/Replace Mass Spectrometers in the Tritium Facilities

    SciTech Connect (OSTI)

    Tovo, L. L.; Lascola, R. J.; Spencer, W. A.; McWhorter, C. S.; Zeigler, K. E.

    2005-08-30

    The primary goal of this work is to determine the suitability of the Infraran sensor for use in the Palladium Membrane Reactor. This application presents a challenge for the sensor, since the process temperature exceeds its designed operating range. We have demonstrated that large baseline offsets, comparable to the sensor response to the analyte, are obtained if cool air is blown across the sensor. We have also shown that there is a strong environmental component to the noise. However, the current arrangement does not utilize a reference detector. The strong correlation between the CO and H{sub 2}O sensor responses to environmental changes indicate that a reference detector can greatly reduce the environmental sensitivity. In fact, incorporation of a reference detector is essential for the sensor to work in this application. We have also shown that the two sensor responses are adequately independent. Still, there are several small corrections which must to be made to the sensor response to accommodate chemical and physical effects. Interactions between the two analytes will alter the relationship between number density and pressure. Temperature and pressure broadening will alter the relationship between absorbance and number density. The individual effects are small--on the order of a few percent or less--but cumulatively significant. Still, corrections may be made if temperature and total pressure are independently measured and incorporated into a post-analysis routine. Such corrections are easily programmed and automated and do not represent a significant burden for installation. The measurements and simulations described above indicate that with appropriate corrections, the Infraran sensor can approach the 1-1.5% measurement accuracy required for effective PMR process control. It is also worth noting that the Infraran may be suitable for other gas sensing applications, especially those that do not need to be made in a high-temperature environment. Any gas with an infrared absorption (methane, ammonia, etc.) may be detected so long as an appropriate bandpass filter can be manufactured. Note that homonuclear diatomic molecules (hydrogen and its isotopes, nitrogen, oxygen) do not have infrared absorptions. We have shown that the sensor response may be adequately predicted using commercially available software. Measurement of trace concentrations is limited by the broad spectral bandpass, since the total signal includes non-absorbed frequencies. However, cells with longer pathlengths can be designed to address this problem.

  1. Radiological Training for Tritium Facilities DOE-HDBK-1105-2002

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

    Available to the public from the U.S. Department ... certification by the American Board of Health Physics andor ... Particles, Health Physics Journal, September (2001). ...

  2. Facility Safety

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

    2013-06-21

    DOE-STD-1104 contains the Department's method and criteria for reviewing and approving nuclear facility's documented safety analysis (DSA). This review and approval formally document the basis for DOE, concluding that a facility can be operated safely in a manner that adequately protects workers, the public, and the environment. Therefore, it is appropriate to formally require implementation of the review methodology and criteria contained in DOE-STD-1104.

  3. Facility Safety

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

    2000-11-20

    The objective of this Order is to establish facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. The Order has Change 1 dated 11-16-95, Change 2 dated 10-24-96, and the latest Change 3 dated 11-22-00 incorporated. The latest change satisfies a commitment made to the Defense Nuclear Facilities Safety Board (DNFSB) in response to DNFSB recommendation 97-2, Criticality Safety.

  4. Facility Safety

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

    2005-12-22

    The order establishes facility and programmatic safety requirements for nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and the System Engineer Program.Chg 1 incorporates the use of DOE-STD-1189-2008, Integration of Safety into the Design Process, mandatory for Hazard Category 1, 2 and 3 nuclear facilities. Cancels DOE O 420.1A.

  5. Working with SRNL - Our Facilities - Glovebox Facilities

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

    SRNL Our Facilities - Glovebox Facilities Govebox Facilities are sealed, protectively-lined compartments with attached gloves, allowing workers to safely handle dangerous materials...

  6. Sandia National Laboratories: Facilities

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

    Facilities Bioscience Computing and Information Science Electromagnetics Facilities Electromagnetic Environments Simulator (EMES) Mode Stirred Chamber Lightning Facility...

  7. Method and apparatus for extracting tritium and preparing radioactive waste for disposal

    DOE Patents [OSTI]

    Heung, Leung K. (Aiken, SC)

    1994-01-01

    Apparatus for heating an object such as a nuclear target bundle to release and recover hydrogen and contain the disposable residue for disposal. The apparatus comprises an inverted furnace, a sleeve/crucible assembly for holding and enclosing the bundle, conveying equipment for placing the sleeve onto the crucible and loading the bundle into the sleeve/crucible, a lift for raising the enclosed bundle into the furnace, and hydrogen recovery equipment including a trap and strippers, all housed in a containment having negative internal pressure. The crucible/sleeve assembly has an internal volume that is sufficient to enclose and hold the bundle before heating; the crucible's internal volume is sufficient by itself to hold and enclose the bundle's volume after heating. The crucible can then be covered and disposed of; the sleeve, on the other hand, can be reused.

  8. Method and apparatus for extracting tritium and preparing radioactive waste for disposal

    DOE Patents [OSTI]

    Heung, L.K.

    1994-03-29

    Apparatus is described for heating an object such as a nuclear target bundle to release and recover hydrogen and contain the disposable residue for disposal. The apparatus comprises an inverted furnace, a sleeve/crucible assembly for holding and enclosing the bundle, conveying equipment for placing the sleeve onto the crucible and loading the bundle into the sleeve/crucible, a lift for raising the enclosed bundle into the furnace, and hydrogen recovery equipment including a trap and strippers, all housed in a containment having negative internal pressure. The crucible/sleeve assembly has an internal volume that is sufficient to enclose and hold the bundle before heating; the crucible's internal volume is sufficient by itself to hold and enclose the bundle's volume after heating. The crucible can then be covered and disposed of; the sleeve, on the other hand, can be reused. 4 figures.

  9. SLAC Accelerator Test Facilities

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

    FACET & TF Careers & Education Archived FACET User Facility Quick Launch About FACET & Test Facilities Expand About FACET & Test Facilities FACET & Test Facilities User Portal...

  10. Field Deployable Tritium Assay System Host Graphical User Interface Software

    Energy Science and Technology Software Center (OSTI)

    1998-05-12

    The FDTASHOST software is a Graphical User Interface for the Field Deployable Tritium Assay System (FDTAS - Invention Disclosure SRS-96-09-091 has been submitted). The program runs on the Host computer which is located in the Laboratory and connected to the FDTAS remote field system via a modem over a phone line. The operator receives status information and messages from the Remote system. The operator can enter in commands to be executed by the remote systemmore » using the mouse and a pull down menu.« less

  11. Microsoft Word - Tritium Fact Sheet Oct 17 2011

    National Nuclear Security Administration (NNSA)

    Tritium is an isotope of hydrogen that occurs naturally in very small quantities. Hydrogen has three isotopes:  Protium Ordinary hydrogen with one proton and one electron in the atom. When two atoms of protium are combined with one atom of oxygen, water is created.  Deuterium Sometimes called "heavy hydrogen," a non-radioactive isotope that has a neutron in the atom, in addition to the proton and electron. Water made with this isotope is called "heavy water." 

  12. Prospects for Relic Neutrino Detection at PTOLEMY: Princeton Tritium Observatory for Light, Early-Universe, Massive-Neutrino Yield

    Broader source: Energy.gov [DOE]

    Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013.

  13. Tritium recovery from tritiated water with a two-stage palladium membrane reactor

    SciTech Connect (OSTI)

    Birdsell, S.A.; Willms, R.S.

    1997-04-01

    A process to recover tritium from tritiated water has been successfully demonstrated at TSTA. The 2-stage palladium membrane reactor (PMR) is capable of recovering tritium from water without generating additional waste. This device can be used to recover tritium from the substantial amount of tritiated water that is expected to be generated in the International Thermonuclear Experimental Reactor both from torus exhaust and auxiliary operations. A large quantity of tritiated waste water exists world wide because the predominant method of cleaning up tritiated streams is to oxidize tritium to tritiated water. The latter can be collected with high efficiency for subsequent disposal. The PMR is a combined catalytic reactor/permeator. Cold (non-tritium) water processing experiments were run in preparation for the tritiated water processing tests. Tritium was recovered from a container of molecular sieve loaded with 2,050 g (2,550 std. L) of water and 4.5 g of tritium. During this experiment, 27% (694 std. L) of the water was processed resulting in recovery of 1.2 g of tritium. The maximum water processing rate for the PMR system used was determined to be 0.5 slpm. This correlates well with the maximum processing rate determined from the smaller PMR system on the cold test bench and has resulted in valuable scale-up and design information.

  14. Lithium aluminate/zirconium material useful in the production of tritium

    DOE Patents [OSTI]

    Cawley, W.E.; Trapp, T.J.

    1984-10-09

    A composition is described useful in the production of tritium in a nuclear reactor. Lithium aluminate particles are dispersed in a matrix of zirconium. Tritium produced by the reactor of neutrons with the lithium are absorbed by the zirconium, thereby decreasing gas pressure within capsules carrying the material.

  15. NaNi sub 3 Mn sub 2 alloy as a tritium storage material

    SciTech Connect (OSTI)

    Ide, T.; Okuno, K.; Konishi, S.; Sakai, F.; Fukui, H.; Enoeda, M.; Naruse, Y.; Anderson, J.L.; Bartlit, J.R.; Los Alamos National Lab., NM )

    1989-01-01

    An all metal apparatus has been constructed and installed in the main cell of the Tritium System Assembly (TSTA) at Los Alamos National Laboratory, as a separate experiment, to handle about 2600 Ci of tritium for study of metal tritides of potential application for storing tritium in fusion fuel processing. The apparatus is similar to that used for protium/deuterium gas but some modifications were made to assure safe handling of tritium. The pressure-composition isotherms for the LaNi{sub 3}Mn{sub 2}-protium (H), deuterium (D) and tritium (T) system were measured to study isotopic effects in the temperature range of 60 {degree}C to 250 {degree}C, the pressure range below 120 kPa. 2 refs., 10 figs.

  16. Tritium stripping in a nitrogen glove box using palladium/zeolite and SAES St 198{trademark}

    SciTech Connect (OSTI)

    Klien, J.E.; Wermer, J.R.

    1995-01-01

    Glove box clean-up experiments were conducted in a nitrogen glove box using palladium deposited on zeolite (Pd/z) and a SAES St 198{trademark} getter as tritium stripping materials. Protium/deuterium samples spiked with tritium were released into a 620 liter glove box to simulate tritium releases in a 10,500 liter glove box. The Pd/z and the SAES St 198{trademark} stripper beds produced a reduction in tritium activity of approximately two to three orders of magnitude and glove box clean-up was limited by a persistent background tritium activity level. Attempts to significantly reduce the glove box activity to lower levels without purging were unsuccessful.

  17. Tritium stripping in a nitrogen glove box using palladium/zeolite and SAES St 198

    SciTech Connect (OSTI)

    Klein, J.E.; Wermer, J.R.

    1995-10-01

    Glove box clean-up experiments were conducted in a nitrogen glove box using palladium deposited on zeolite (Pd/z) and a SAES St 198 getter as tritium stripping materials. Protium/deuterium samples spiked with tritium were released into a 620 liter glove box to simulate tritium releases in a 10,500 liter glove box. The Pd/z and the SAES St 198 stripper beds produced a reduction in tritium activity of approximately two to three orders of magnitude and glove box clean-up was limited by a persistent background tritium activity level. Attempts to significantly reduce the glove box activity to lower levels without purging were unsuccessful. 3 refs., 6 figs., 1 tab.

  18. Fast Flux Test Facility (FFTF) Briefing Book 1 Summary

    SciTech Connect (OSTI)

    WJ Apley

    1997-12-01

    This report documents the results of evaluations preformed during 1997 to determine what, if an, future role the Fast Flux Test Facility (FFTF) might have in support of the Department of Energys tritium productions strategy. An evaluation was also conducted to assess the potential for the FFTF to produce medical isotopes. No safety, environmental, or technical issues associated with producing 1.5 kilograms of tritium per year in the FFTF have been identified that would change the previous evaluations by the Department of Energy, the JASON panel, or Putnam, Hayes & Bartlett. The FFTF can be refitted and restated by July 2002 for a total expenditure of $371 million, with an additional $64 million of startup expense necessary to incorporate the production of medical isotopes. Therapeutic and diagnostic applications of reactor-generated medical isotopes will increase dramatically over the next decade. Essential medical isotopes can be produced in the FFTF simultaneously with tritium production, and while a stand-alone medical isotope mission for the facility cannot be economically justified given current marker conditions, conservative estimates based on a report by Frost &Sullivan indicate that 60% of the annual operational costs (reactor and fuel supply) could be offset by revenues from medical isotope production within 10 yeas of restart. The recommendation of the report is for the Department of Energy to continue to maintain the FFTF in standby and proceed with preparation of appropriate Nations Environmental Policy Act documentation in full consultation with the public to consider the FFTF as an interim tritium production option (1.5 kilograms/year) with a secondary mission of producing medical isotopes.

  19. Fluid extraction

    DOE Patents [OSTI]

    Wai, Chien M.; Laintz, Kenneth E.

    1999-01-01

    A method of extracting metalloid and metal species from a solid or liquid material by exposing the material to a supercritical fluid solvent containing a chelating agent is described. The chelating agent forms chelates that are soluble in the supercritical fluid to allow removal of the species from the material. In preferred embodiments, the extraction solvent is supercritical carbon dioxide and the chelating agent is a fluorinated .beta.-diketone. In especially preferred embodiments the extraction solvent is supercritical carbon dioxide, and the chelating agent comprises a fluorinated .beta.-diketone and a trialkyl phosphate, or a fluorinated .beta.-diketone and a trialkylphosphine oxide. Although a trialkyl phosphate can extract lanthanides and actinides from acidic solutions, a binary mixture comprising a fluorinated .beta.-diketone and a trialkyl phosphate or a trialkylphosphine oxide tends to enhance the extraction efficiencies for actinides and lanthanides. The method provides an environmentally benign process for removing contaminants from industrial waste without using acids or biologically harmful solvents. The method is particularly useful for extracting actinides and lanthanides from acidic solutions. The chelate and supercritical fluid can be regenerated, and the contaminant species recovered, to provide an economic, efficient process.

  20. Mass Spectrometer Facility | Photosynthetic Antenna Research Center

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

    Mass Spectrometer Facility Mass Spectrometer Facility The PARC Mass Spectrometer Facility uses customized instrumentation to directly measure the individual polypeptide mass of different light-harvesting complexes to do assignment to specific gene products and investigate protein processing. Newly developed techniques are also applied to measure the mass of native protein complexes. Structural information of complexes is extracted by combining protein chemical modification and H/D exchange

  1. Tritium Specific Adsorption Simulation Utilizing the OSPREY Model

    SciTech Connect (OSTI)

    Veronica Rutledge; Lawrence Tavlarides; Ronghong Lin; Austin Ladshaw

    2013-09-01

    During the processing of used nuclear fuel, volatile radionuclides will be discharged to the atmosphere if no recovery processes are in place to limit their release. The volatile radionuclides of concern are 3H, 14C, 85Kr, and 129I. Methods are being developed, via adsorption and absorption unit operations, to capture these radionuclides. It is necessary to model these unit operations to aid in the evaluation of technologies and in the future development of an advanced used nuclear fuel processing plant. A collaboration between Fuel Cycle Research and Development Offgas Sigma Team member INL and a NEUP grant including ORNL, Syracuse University, and Georgia Institute of Technology has been formed to develop off gas models and support off gas research. This report is discusses the development of a tritium specific adsorption model. Using the OSPREY model and integrating it with a fundamental level isotherm model developed under and experimental data provided by the NEUP grant, the tritium specific adsorption model was developed.

  2. Tritium-compatible high-vacuum pumping system

    SciTech Connect (OSTI)

    Coffin, D.O.

    1982-04-01

    Large magnetic-fusion power reactors will require vacuum pumps with greater speeds and capacities for hydrogen and helium isotopes than any now available. Present fusion engineering efforts concentrate on DT-burning tokamaks, so pumps for these systems must perform reliably during prolonged exposure to radioactive tritium gas. A mechanical pumping train that exposes only tritium-compatible metals to the vacuum medium has been assembled. The system comprises a reciprocating metal-bellows compressor, a bellows-sealed, spiral-cavity, positive-displacement blower, and a canned-motor, magnetic-bearing turbopump. These pumps feature hermetic drives, and their pumping chambers contain no liquid metals, plastics, elastomers, or lubricants. The pumping system achieves vacuums as low as 1 mPa without cryogenics, and its pumping speed increases from 5 L/s at atmospheric pressure to 500 L/s below 100 mPa. Systems with ultimate pumping speeds of 5000 L/s can be assembled using larger pumps of the same design as those tested.

  3. Weldability of tritium-charged 304L stainless steel

    SciTech Connect (OSTI)

    Kanne, W R; Angerman, C L; Eberhard, B J

    1987-02-01

    Attempts to repair the wall of C-Reactor Tank at the Savannah River Plant were halted when Gas Tungsten Arc (GTA) welds joining patches to the wall developed toe cracks in the heat affected zone (HAZ). The cause of the toe cracks was investigated by welding on 304L samples that were tritium charged and aged to produce helium. Helium embrittlement was shown to be the likely cause of weld toe cracking in C-Reactor Tank. GTA welds made on helium impregnated 304L produced toe cracks identical to those that caused leaking patches during C-Reactor Tank repair. Heating of a sample to remove deuterium and tritium without removing helium did not reduce cracking susceptibility. Low heat input and spot GTA welds also produced cracks, indicating possible problems using these techniques for reactor repair. However, cracks were not produced by solid state resistance welds, or by a very low heat GTA pass that did not produce melting. This indicates that non-melting or low tensile stress techniques could be used for repair.

  4. SHINE Tritium Nozzle Design: Activity 6, Task 1 Report

    SciTech Connect (OSTI)

    Okhuysen, Brett S.; Pulliam, Elias Noel

    2015-11-05

    In FY14, we studied the qualitative and quantitative behavior of a SHINE/PNL tritium nozzle under varying operating conditions. The result is an understanding of the nozzles performance in terms of important flow features that manifest themselves under different parametric profiles. In FY15, we will consider nozzle design with a focus on nozzle geometry and integration. From FY14 work, we will understand how the SHINE/PNL nozzle behaves under different operating scenarios. The first task for FY15 is to evaluate the FY14 model as a predictor of the actual flow. Considering different geometries is more time-intensive than parameter studies, therefore we recommend considering any relevant flow features that were not included in the FY14 model. In the absence of experimental data, it is particularly important to consider any sources of heat in the domain or boundary conditions that may affect the flow and incorporate these into the simulation if they are significant. Additionally, any geometric features of the beamline segment should be added to the model such as the orifice plate. The FY14 model works with hydrogen. An improvement that can be made for FY15 is to develop CFD properties for tritium and incorporate those properties into the new models.

  5. Hydrogen, Deuterium and Tritium in Palladium: An Elastic Constants Study

    SciTech Connect (OSTI)

    Bach, H.T.; Schwarz, R.B.; Tuggle, D.G.

    2005-07-15

    We have used resonant ultrasound spectroscopy to measure the three independent elastic constants of Pd-H, Pd-D, and Pd-T single crystal at 300K as a function of hydrogen, deuterium, and tritium concentration, respectively. The addition of interstitial H (D, or T) atoms, located at (0,1/2,0) in the fcc Pd lattice, affects all three elastic constants C', C{sub 44}, and B. In the mixed ({alpha}+{beta}) phase, and with increasing H isotope, the shear modulus C' shows an abnormal softening whereas C{sub 44} and B do not. This is explained in terms of Zener-type an elastic relaxations affecting the shape of the hydride phases in the coherent({alpha}+{beta}) two-phase mixture In the single {beta}-phase, C' shows a strong isotope dependence whereas C{sub 44} and B show none. This behavior is explained in terms of differences in the excitation of optical phonons. In Pd-T, {sup 3}He is produced by the radioactive decay of tritium. We have measured in situ the swelling and the change in the elastic constants in Pd-T as a function of aging time. Aging ({sup 3}He formation) affects all three elastic constants. These measurements are being used to understand the early stages of {sup 3}H-{sup 3}He cluster formation in aged Pd-T crystal.

  6. Hydrogen, deuterium and tritium in palladium: An eleastic constants study

    SciTech Connect (OSTI)

    Bach, H. T.; Schwarz, R. B.; Tuggle, D. G.

    2004-01-01

    We have used resonant ultrasound spectroscopy to measure the three independent elastic constants of Pd-H, Pd-D, and Pd-T single crystal at 300K as a junction of hydrogen, deuterium, and tritium concentration, respectively. The addition of interstitial H (D, or T) atoms, located at (0, 1/2, 0) in the fcc Pd lattice, affects all three elastic constants C, C{sub 44}, and B. In the mixed (a+{beta}) phase, and with increasing H isotope, the shear modulus C' shows an abnormal softening whereas C{sub 44} and B do not. This is explained in terms of Zener-type anelastic relaxations affecting the shape of the hydride phases in the coherent ({alpha}+{beta}) two-phase mixture In the single {beta}-phase, C' shows a strong isotope dependence whereas C{sub 44} and B show none. This behavior is explained in terms of differences in the excitation of optical phonons. In Pd-T, {sup 3}He is produced by the radioactive decay of tritium. We have measured in situ the swelling and the change in the elastic constants in Pd-T as a function of aging time. Aging ({sup 3}He formation) affects all three elastic constants. These measurements are being used to understand the early stages of {sup 3}H-{sup 3}He clusterformation in aged Pd-T crystal.

  7. Facility Safety

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

    1995-10-13

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. Cancels DOE 5480.7A, DOE 5480.24, DOE 5480.28 and Division 13 of DOE 6430.1A. Canceled by DOE O 420.1A.

  8. Facility Safety

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

    2012-12-04

    The Order establishes facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and System Engineer Program. Cancels DOE O 420.1B, DOE G 420.1-2 and DOE G 420.1-3.

  9. Metro Methane Recovery Facility Biomass Facility | Open Energy...

    Open Energy Info (EERE)

    Methane Recovery Facility Biomass Facility Jump to: navigation, search Name Metro Methane Recovery Facility Biomass Facility Facility Metro Methane Recovery Facility Sector Biomass...

  10. Development and Verification of Tritium Analyses Code for a Very High Temperature Reactor

    SciTech Connect (OSTI)

    Chang H. Oh; Eung S. Kim

    2009-09-01

    A tritium permeation analyses code (TPAC) has been developed by Idaho National Laboratory for the purpose of analyzing tritium distributions in the VHTR systems including integrated hydrogen production systems. A MATLAB SIMULINK software package was used for development of the code. The TPAC is based on the mass balance equations of tritium-containing species and a various form of hydrogen (i.e., HT, H2, HTO, HTSO4, and TI) coupled with a variety of tritium source, sink, and permeation models. In the TPAC, ternary fission and neutron reactions with 6Li, 7Li 10B, 3He were taken into considerations as tritium sources. Purification and leakage models were implemented as main tritium sinks. Permeation of HT and H2 through pipes, vessels, and heat exchangers were importantly considered as main tritium transport paths. In addition, electroyzer and isotope exchange models were developed for analyzing hydrogen production systems including both high-temperature electrolysis and sulfur-iodine process. The TPAC has unlimited flexibility for the system configurations, and provides easy drag-and-drops for making models by adopting a graphical user interface. Verification of the code has been performed by comparisons with the analytical solutions and the experimental data based on the Peach Bottom reactor design. The preliminary results calculated with a former tritium analyses code, THYTAN which was developed in Japan and adopted by Japan Atomic Energy Agency were also compared with the TPAC solutions. This report contains descriptions of the basic tritium pathways, theory, simple user guide, verifications, sensitivity studies, sample cases, and code tutorials. Tritium behaviors in a very high temperature reactor/high temperature steam electrolysis system have been analyzed by the TPAC based on the reference indirect parallel configuration proposed by Oh et al. (2007). This analysis showed that only 0.4% of tritium released from the core is transferred to the product hydrogen. The amount of tritium in the product hydrogen was estimated to be approximately an order less than the gaseous effluent limit for tritium.

  11. ARM - SGP Intermediate Facility

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

    Intermediate Facility SGP Related Links Virtual Tour Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site SGP Fact Sheet Images Information for Guest Scientists Contacts SGP Intermediate Facility For over 20 years, 3 intermediate facilities, within 6.2 miles (10 km) of the Central Facility, provided a

  12. ARM - Guest Instrument Facility

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

    PlainsGuest Instrument Facility SGP Related Links Virtual Tour Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site SGP Fact Sheet Images Information for Guest Scientists Contacts Guest Instrument Facility ARM's Guest Instrument Facility at the SGP site near Lamont, Oklahoma. ARM's Guest Instrument Facility at

  13. Milestone report - M4FT-14OR0302102b - Evaluation of Tritium Content and Release from Surry-2 Fuel Cladding

    SciTech Connect (OSTI)

    Robinson, Sharon M.; Chattin, Marc Rhea; Giaquinto, Joseph M.; Jubin, Robert Thomas

    2014-09-01

    To design and operate future reprocessing plants in a safe and environmentally compliant manner, the amount and form of tritium in the used nuclear fuel (UNF) must be understood and quantified.To gain a better understanding of how tritium in cladding will behave during processing, scoping tests are being performed to determine the tritium content in the cladding pre- and post-tritium pretreatment. A sample of Surry-2 pressurized water reactor (PWR) cladding was heated to 11001200C to oxidize the zirconium and release all of the tritium in the cladding sample. The tritium content was measured to be ~240 Ci/g. Cladding samples were heated to 500C, which is within the temperature range (480 - 600C) expected for standard air tritium pretreatment systems, and to a slightly higher temperature (700C) to determine the impact of tritium pretreatment on tritium release from the cladding. Heating at 500C for 24 hr removes ~0.2% of the tritium from the cladding, and heating at 700C for 24 hr removes ~9%. Thus, a significant fraction of the tritium remains bound in the cladding and must be considered in operations involving cladding recycle.

  14. Extractant composition

    DOE Patents [OSTI]

    Smith, Barbara F.; Jarvinen, Gordon D.; Ryan, Robert R.

    1990-01-01

    An organic extracting solution useful for separating elements of the actinide series of the periodic table from elements of the lanthanide series, where both are in trivalent form. The extracting solution consists of a primary ligand and a secondary ligand, preferably in an organic solvent. The primary ligand is a substituted monothio-1,3-dicarbonyl, which includes a substituted 4-acyl-2-pyrazolin-5-thione, such as 4-benzoyl-2,4-dihydro-5-methyl-2-phenyl-3H-pyrazol-3-thione (BMPPT). The secondary ligand is a substituted phosphine oxide, such as trioctylphosphine oxide (TOPO).

  15. Facility Type!

    Office of Legacy Management (LM)

    ITY: --&L~ ----------- srct-r~ -----------~------~------- if yee, date contacted ------------- cl Facility Type! i I 0 Theoretical Studies Cl Sample 84 Analysis ] Production 1 Diepasal/Storage 'YPE OF CONTRACT .--------------- 1 Prime J Subcontract&- 1 Purchase Order rl i '1 ! Other information (i.e., ---------~---~--~-------- :ontrait/Pirchaee Order # , I C -qXlJ- --~-------~~-------~~~~~~ I I ~~~---~~~~~~~T~~~ FONTRACTING PERIODi IWNERSHIP: ,I 1 AECIMED AECMED GOVT GOUT &NTtiAC+OR

  16. Tritium-target performance at RTNS-II

    SciTech Connect (OSTI)

    Heikkinen, D.W.; Logan, C.M.

    1982-01-01

    The Rotating Target Neutron Source (RTNS-II) uses a 360-keV deuteron beam and the /sup 3/He(d,n)/sup 4/He reaction to generate 14-MeV neutrons. The neutrons are used for fusion materials damage studies. The tritium target consists of a band of titanium tritide on copper alloy substrates of 23- or 50-cm diameter. During operation, the substrates are internally cooled and rotated at approx. 4000 rpm to withstand beam intensities in excess of 100 mA. Neutron production data have been accumulated for fifty-eight 23-cm and five 50-cm targets. From these data, using a non-linear least-squares fitting procedure, target performance parameters have been obtained which permit a quantitative comparison of individual targets. Average parameters are obtained for the 23- and 50-cm targets.

  17. Field Deployable Tritium Assay System Remote Control Software

    Energy Science and Technology Software Center (OSTI)

    1998-05-12

    The FDTASREM software is a command control based application for the Field Deployable Tritium Assay System (FDTAS-Invention Disclosure SRS-96-091 has been submitted). The program runs on the Remote computer which is located at the field site with the FDTAS sampling and analysis components. The application executes commands received over the connected phone line from the operator via the FDTAS Host GUI running in the laboratory some distance away. The FDTASREM controls interface with the FDTASmore » auto sampler and the analysis systems. It tells the sampler to take a sample from a specified location and send it to the analyzer. Once the sample is sent to the analyzer, FDTASREM sequences the internal valves and pumps to deliver the sample and cocktail to the counting chamber. Once the analysis is complete, the program can execute the clean command and prepare the system for the next sample.« less

  18. Field Deployable Tritium Assay System Remote Control Software

    SciTech Connect (OSTI)

    1998-05-12

    The FDTASREM software is a command control based application for the Field Deployable Tritium Assay System (FDTAS-Invention Disclosure SRS-96-091 has been submitted). The program runs on the Remote computer which is located at the field site with the FDTAS sampling and analysis components. The application executes commands received over the connected phone line from the operator via the FDTAS Host GUI running in the laboratory some distance away. The FDTASREM controls interface with the FDTAS auto sampler and the analysis systems. It tells the sampler to take a sample from a specified location and send it to the analyzer. Once the sample is sent to the analyzer, FDTASREM sequences the internal valves and pumps to deliver the sample and cocktail to the counting chamber. Once the analysis is complete, the program can execute the clean command and prepare the system for the next sample.

  19. SGP Central Facility

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

    Central Facility SGP Related Links Virtual Tour Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site SGP Fact Sheet Images Information for Guest Scientists Contacts SGP Central Facility The ARM Climate Research Facility deploys specialized remote sensing instruments in a fixed location at the site to gather

  20. ARM - SGP Extended Facility

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

    Extended Facility SGP Related Links Virtual Tour Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site SGP Fact Sheet Images Information for Guest Scientists Contacts SGP Extended Facility For over 20 years, 23 extended facilities were distributed evenly throughout a 55,000-square-mile domain and at the corners of

  1. Savannah River Site | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Locations / Savannah River Site Savannah River Site NNSA operates facilities at the Savannah River Site (SRS) to supply and process tritium, a radioactive form of hydrogen that is a vital component of nuclear weapons. SRS loads tritium and non-tritium reservoirs; including reclamation of previously used tritium reservoirs, receipt, packing and shipping of reservoirs; recycling, extraction, and enrichment of tritium gas and laboratory operations. SRS also plays a critical role in NNSA's

  2. Projects & Facilities - Hanford Site

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

    Facilities About Us Projects & Facilities Email Email Page | Print Print Page |Text Increase Font Size Decrease Font Size Projects & Facilities 100 Area 118-K-1 Burial Ground 200...

  3. Facility Representatives

    Office of Environmental Management (EM)

    DOE-STD-1063-2006 April 2006 Superseding DOE-STD-1063-2000 March 2000 DOE STANDARD FACILITY REPRESENTATIVES U.S. Department of Energy AREA MGMT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-1063-2006 ii Available on the Department of Energy Technical Standards Program web site at http://www.eh.doe.gov/techstds/ DOE-STD-1063-2006 iii FOREWORD 1. This Department of Energy standard is approved for use by

  4. Facility Representatives

    Office of Environmental Management (EM)

    063-2011 February 2011 Superseding DOE-STD-1063-2006 April 2006 DOE STANDARD FACILITY REPRESENTATIVES U.S. Department of Energy AREA MGMT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-1063-2011 ii Available on the Department of Energy Technical Standards Program Web site at http://www.hss.doe.gov/nuclearsafety/ns/techstds/ DOE-STD-1063-2011 iii FOREWORD 1. This Department of Energy (DOE) standard is

  5. Harrisburg Facility Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    2006 Database Retrieved from "http:en.openei.orgwindex.php?titleHarrisburgFacilityBiomassFacility&oldid397545" Feedback Contact needs updating Image needs updating...

  6. Brookhaven Facility Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    2006 Database Retrieved from "http:en.openei.orgwindex.php?titleBrookhavenFacilityBiomassFacility&oldid397235" Feedback Contact needs updating Image needs updating...

  7. Radiation Effects Facility - Facilities - Cyclotron Institute

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

    Radiation Effects Facility Typical DUT(device under test) set-up at the end of the Radiation Effects beamline. The Radiation Effects Facility is available for commercial,...

  8. Finding of No Significant Impact for the Storage of Tritium-Producing...

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

    for the Storage of Tritium-Producing Burnable Absorber Rods in K-Area Transfer Bay at the Savannah River Site Agency: U.S. Department of Energy (DOE) Action: Finding of No...

  9. Is Tritium Over-regulated, Part 2: Should the TFG Support Higher...

    Office of Environmental Management (EM)

    Should The TFG Support Higher Tritium Threshold Values? (LA-UR-14-22479) Mike Rogers W-7, Gas Transfer Systems April, 2014 Operated by Los Alamos National Security, LLC for the...

  10. Recovery of tritium dissolved in sodium at the steam generator of fast breeder reactor

    SciTech Connect (OSTI)

    Oya, Y.; Oda, T.; Tanaka, S.; Okuno, K.

    2008-07-15

    The tritium recovery technique in steam generators for fast breeder reactors using the double pipe concept was proposed. The experimental system for developing an effective tritium recovery technique was developed and tritium recovery experiments using Ar gas or Ar gas with 10-10000 ppm oxygen gas were performed using D{sub 2} gas instead of tritium gas. It was found that deuterium permeation through two membranes decreased by installing the double pipe concept with Ar gas. By introducing Ar gas with 10000 ppm oxygen gas, the concentration of deuterium permeation through two membranes decreased by more than 1/200, compared with the one pipe concept, indicating that most of the deuterium was scavenged by Ar gas or reacted with oxygen to form a hydroxide. However, most of the hydroxide was trapped at the surface of the membranes because of the short duration of the experiment. (authors)

  11. Design and Fabrication of In-Reactor Experiment to Measure Tritium...

    Office of Environmental Management (EM)

    Design and Fabrication of In-Reactor Experiment to Measure Tritium Release and Speciation from LiAlO2 and LiAlO2Zr Cermets Design and Fabrication of In-Reactor Experiment to...

  12. Target designs for Accelerator Production of Tritium (APT) utilizing lithium-aluminum

    SciTech Connect (OSTI)

    Todosow, M.; Van Tuyle, G.J.

    1996-03-01

    A number of accelerator-driven spallation neutron-source target/blanket systems have been developed for production of tritium under the APT Program. The two systems described in this paper employ a proton linear accelerator, and a target which contains a heavy-metal(s) for the production of neutrons via spallation, and solid lithium-aluminum for the production of tritium via neutron capture. lie lithium-aluminum technology is based on that employed at Savannah River for tritium production since the 1950`s. In the APT concept tritium is produced without the presence of fissionable materials; therefore, no high-level waste is produced, and the ES&H concerns are significantly reduced compared to reactor systems.

  13. Celebrating the 20th anniversary of the tritium shot heard around...

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

    were so good and so thorough that the tritium shots were successful early on in the D-T campaign." The preparations mobilized physicists, engineers and staffers throughout the...

  14. A Fusion Development Facility on the Critical Path to Fusion Energy

    SciTech Connect (OSTI)

    Chan, V. S.; Stambaugh, R

    2011-01-01

    A fusion development facility (FDF) based on the tokamak approach with normal conducting magnetic field coils is presented. FDF is envisioned as a facility with the dual objective of carrying forward advanced tokamak (AT) physics and enabling the development of fusion energy applications. AT physics enables the design of a compact steady-state machine of moderate gain that can provide the neutron fluence required for FDF's nuclear science development objective. A compact device offers a uniquely viable path for research and development in closing the fusion fuel cycle because of the demand to consume only a moderate quantity of the limited supply of tritium fuel before the technology is in hand for breeding tritium.

  15. A fusion development facility on the critical path to fusion energy

    SciTech Connect (OSTI)

    Chan, Dr. Vincent; Canik, John; Peng, Yueng Kay Martin

    2011-01-01

    A fusion development facility (FDF) based on the tokamak approach with normal conducting magnetic field coils is presented. FDF is envisioned as a facility with the dual objective of carrying forward advanced tokamak (AT) physics and enabling the development of fusion energy applications. AT physics enables the design of a compact steady-state machine of moderate gain that can provide the neutron fluence required for FDF s nuclear science development objective. A compact device offers a uniquely viable path for research and development in closing the fusion fuel cycle because of the demand to consume only a moderate quantity of the limited supply of tritium fuel before the technology is in hand for breeding tritium.

  16. TRITIUM PERMEATION AND TRANSPORT IN THE GASOLINE PRODUCTION SYSTEM COUPLED WITH HIGH TEMPERATURE GAS-COOLED REACTORS (HTGRS)

    SciTech Connect (OSTI)

    Chang H. Oh; Eung S. Kim; Mike Patterson

    2011-05-01

    This paper describes scoping analyses on tritium behaviors in the HTGR-integrated gasoline production system, which is based on a methanol-to-gasoline (MTG) plant. In this system, the HTGR transfers heat and electricity to the MTG system. This system was analyzed using the TPAC code, which was recently developed by Idaho National Laboratory. The global sensitivity analyses were performed to understand and characterize tritium behaviors in the coupled HTGR/MTG system. This Monte Carlo based random sampling method was used to evaluate maximum 17,408 numbers of samples with different input values. According to the analyses, the average tritium concentration in the product gasoline is about 3.0510-3 Bq/cm3, and 62 % cases are within the tritium effluent limit (= 3.7x10-3 Bq/cm3[STP]). About 0.19% of released tritium is finally transported from the core to the gasoline product through permeations. This study also identified that the following four parameters are important concerning tritium behaviors in the HTGR/MTG system: (1) tritium source, (2) wall thickness of process heat exchanger, (3) operating temperature, and (4) tritium permeation coefficient of process heat exchanger. These four parameters contribute about 95 % of the total output uncertainties. This study strongly recommends focusing our future research on these four parameters to improve modeling accuracy and to mitigate tritium permeation into the gasol ine product. If the permeation barrier is included in the future study, the tritium concentration will be significantly reduced.

  17. Polymer Exposure and Testing Facilities at the Savannah River Site

    Office of Environmental Management (EM)

    Polymer Exposure and Testing Facilities at the Savannah River Site Elise B. Fox, Ph.D. Tritium Focus Group April 22, 2014 SRNL-MS-2014-00050 Outline * How we expose our materials * Available characterization methods * Previous and current work 2 Sample Exposure * Design rating for 500 psig and 260°C * Typically loaded with six samples or the same material - ½" * 2" * Load with 1 atm T * Partial pressures have also been loaded * Gas composition confirmed by GC at loading * Record

  18. The Princeton Tritium Observatory for Light, Early Universe, Massive Neutrino Yield (PTOLEMY) Prototype

    Office of Environmental Management (EM)

    Princeton Tritium Observatory for Light, Early Universe, Massive Neutrino Yield (PTOLEMY) Tritium Focus Group Meeting Sept 24, 2014 C.A. Gentile and P.G. Efthimion on behalf of the PTOLEMY team Motivation * Big bang relic neutrinos are predicted to be amongst the oldest and smallest particles in the universe. Information on their mass and density would significantly enhance our understanding of elementary particles, the ways in which mass is distributed, and the formation of the universe. *

  19. Kent County Waste to Energy Facility Biomass Facility | Open...

    Open Energy Info (EERE)

    County Waste to Energy Facility Biomass Facility Jump to: navigation, search Name Kent County Waste to Energy Facility Biomass Facility Facility Kent County Waste to Energy...

  20. Stockton Regional Water Control Facility Biomass Facility | Open...

    Open Energy Info (EERE)

    Stockton Regional Water Control Facility Biomass Facility Jump to: navigation, search Name Stockton Regional Water Control Facility Biomass Facility Facility Stockton Regional...

  1. Evolution of tritium from deuterided palladium subject to high electrical currents

    SciTech Connect (OSTI)

    Claytor, T.N.; Tuggle, D.G.; Taylor, S.F.

    1992-12-31

    An increase in the tritium level was detected in deuterium when various configurations of palladium foil or powder and silicon wafers or powder were subject to a high pulsed current. The deuterium, at one atmosphere pressure, and was circulated in a sealed loop containing the cell and an ionization chamber to measure the tritium increase as a function of time. Over 4800 hours of data, spanning 10 cells (including deuterium and hydrogen controls), were collected with this system. Average tritium production has varied from 0.02 to 0.2 nCi/h. Due to experimental constraints we have not been able to measure neutron output with these cells while simultaneously measuring the tritium increase. The question of tritium contamination in the palladium has been primarily resolved by the development of techniques that allow the palladium powder or foil to be reused. Various methods for increasing the tritium production, such as, increased current density, surface modifiers, and higher deuterium loading, will be discussed. 8 refs, 5 figs.

  2. Evolution of tritium from deuterided palladium subject to high electrical currents

    SciTech Connect (OSTI)

    Claytor, T.N.; Tuggle, D.G.; Taylor, S.F.

    1992-01-01

    An increase in the tritium level was detected in deuterium when various configurations of palladium foil or powder and silicon wafers or powder were subject to a high pulsed current. The deuterium, at one atmosphere pressure, and was circulated in a sealed loop containing the cell and an ionization chamber to measure the tritium increase as a function of time. Over 4800 hours of data, spanning 10 cells (including deuterium and hydrogen controls), were collected with this system. Average tritium production has varied from 0.02 to 0.2 nCi/h. Due to experimental constraints we have not been able to measure neutron output with these cells while simultaneously measuring the tritium increase. The question of tritium contamination in the palladium has been primarily resolved by the development of techniques that allow the palladium powder or foil to be reused. Various methods for increasing the tritium production, such as, increased current density, surface modifiers, and higher deuterium loading, will be discussed. 8 refs, 5 figs.

  3. Quantification of tritium ``heels`` and isotope exchange mechanisms in La-Ni-Al tritides

    SciTech Connect (OSTI)

    Wermer, J.R.

    1992-07-27

    Formation of tritium heels in LANA (LaNi{sub 5-x}Al{sub x}) 0.30 (x=0.30) and 0.75 tritides was quantified; size of the heel is dependent on storage and processing conditions. Absorption-desorption cycling of the tritide beds mitigates formation of the tritium heel and can reduce its size. The higher pressure material LANA 0.30 showed slower heel formation than LANA 0.75; this allows more tritium to be removed at the maximum processing temperature. In plant application, LANA 0.30 beds are used as compressors; except during compressor operation, their aging will be very slow. Tritium heel removal by D exchange was demonstrated. Absorption-desorption cycling during an exchange cycle does not improve the exchange efficiency. Residual tritium can be removed to very low levels. For a tritide bed scheduled for removal from the process, a final tritium level can be estimated based on the number of D exchange cycles. 13 refs, 8 figs, 6 tabs.

  4. Tritium trapping in silicon carbide in contact with solid breeder under high flux isotope reactor irradiation

    SciTech Connect (OSTI)

    H. Katsui; Y. Katoh; A. Hasegawa; M. Shimada; Y. Hatano; T. Hinoki; S. Nogami; T. Tanaka; S. Nagata; T. Shikama

    2013-11-01

    The trapping of tritium in silicon carbide (SiC) injected from ceramic breeding materials was examined via tritium measurements using imaging plate (IP) techniques. Monolithic SiC in contact with ternary lithium oxide (lithium titanate and lithium aluminate) as a ceramic breeder was irradiated in the High Flux Isotope Reactor (HFIR) in Oak Ridge, Tennessee, USA. The distribution of photo-stimulated luminescence (PSL) of tritium in SiC was successfully obtained, which separated the contribution of 14C -rays to the PSL. The tritium incident from ceramic breeders was retained in the vicinity of the SiC surface even after irradiation at 1073 K over the duration of ~3000 h, while trapping of tritium was not observed in the bulk region. The PSL intensity near the SiC surface in contact with lithium titanate was higher than that obtained with lithium aluminate. The amount of the incident tritium and/or the formation of a Li2SiO3 phase on SiC due to the reaction with lithium aluminate under irradiation likely were responsible for this observation.

  5. ARM - Facility News Article

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

    December 4, 2010 [Facility News] Request for Proposals Now Open Bookmark and Share The ARM Climate Research Facility is now accepting applications for use of the ARM mobile facilities, aerial facility, and fixed sites. Proposals are welcome from all members of the scientific community for conducting field campaigns and scientific research using the ARM Facility. Facility availability is as follows: ARM Mobile Facility 2 (AMF2) available FY2013 ARM Mobile Facility 1 (AMF1) available March 2015

  6. EIS-0271: Final Environmental Impact Statement | Department of Energy

    Office of Environmental Management (EM)

    Final Environmental Impact Statement EIS-0271: Final Environmental Impact Statement Construction and Operation of a Tritium Extraction Facility at the Savannah Siver Site DOE proposes to construct and operate a Tritium Extraction Facility (TEF) at H Area on the Savannah River Site (SRS) to provide the capability to extract tritium from commercial light water reactor (CLWR) targets and from targets of similar design. The proposed action is also DOE's preferred alternative. An action alternative

  7. Hydrodynamic instability growth and mix experiments at the National Ignition Facility

    SciTech Connect (OSTI)

    Smalyuk, V. A.; Barrios, M.; Caggiano, J. A.; Casey, D. T.; Cerjan, C. J.; Clark, D. S.; Edwards, M. J.; Haan, S. W.; Hammel, B. A.; Hamza, A.; Hsing, W. W.; Hurricane, O.; Kroll, J.; Landen, O. L.; Lindl, J. D.; Ma, T.; McNaney, J. M.; Mintz, M.; Parham, T.; Peterson, J. L.; and others

    2014-05-15

    Hydrodynamic instability growth and its effects on implosion performance were studied at the National Ignition Facility [G. H. Miller, E. I. Moses, and C. R. Wuest, Opt. Eng. 443, 2841 (2004)]. Implosion performance and mix have been measured at peak compression using plastic shells filled with tritium gas and containing embedded localized carbon-deuterium diagnostic layers in various locations in the ablator. Neutron yield and ion temperature of the deuterium-tritium fusion reactions were used as a measure of shell-gas mix, while neutron yield of the tritium-tritium fusion reaction was used as a measure of implosion performance. The results have indicated that the low-mode hydrodynamic instabilities due to surface roughness were the primary culprits for yield degradation, with atomic ablator-gas mix playing a secondary role. In addition, spherical shells with pre-imposed 2D modulations were used to measure instability growth in the acceleration phase of the implosions. The capsules were imploded using ignition-relevant laser pulses, and ablation-front modulation growth was measured using x-ray radiography for a shell convergence ratio of ?2. The measured growth was in good agreement with that predicted, thus validating simulations for the fastest growing modulations with mode numbers up to 90 in the acceleration phase. Future experiments will be focused on measurements at higher convergence, higher-mode number modulations, and growth occurring during the deceleration phase.

  8. Toroidal Alfvn Eigenmodes in TFTR Deuterium-Tritium Plasmas

    SciTech Connect (OSTI)

    G.Y. Fu; H. Berk; R. Nazikian; S.H. Batha; Z. Chang; et al

    1998-01-01

    Purely alpha-particle-driven Toroidal Alfvn Eigenmodes (TAEs) with toroidal mode numbers n=1-6 have been observed in Deuterium-Tritium (D-T) plasmas on the Tokamak Fusion Test Reactor [D.J. Grove and D.M. Meade, Nucl. Fusion 25, 1167 (1985)]. The appearance of mode activity following termination of neutral beam injection in plasmas with q(0)>1 is generally consistent with theoretical predictions of TAE stability [G.Y. Fu et al., Phys. Plasmas 3, 4036 (1996]. Internal reflectometer measurements of TAE activity is compared with theoretical calculations of the radial mode structure. Core localization of the modes to the region of reduced central magnetic shear is confirmed, however the mode structure can deviate significantly from theoretical estimates. The peak measured TAE amplitude of delta n/n~10(superscript -4) at r/a~0.3-0.4 corresponds to delta B/B~10-5, while dB/B~10(superscript -8) is measured at the plasma edge. Enhanced alpha particle loss associated with TAE activity has not been observed.

  9. A Summary of Tritium In-Bed Accountability for 1500 Liter La-Ni-Al Storage Beds

    SciTech Connect (OSTI)

    Klein, J.E.

    2001-07-31

    This paper summarizes the in-bed accountability (IBA) calibration results for all the RF LaNi4.25Al0.75 tritium storage beds.

  10. Secondary Startup Neutron Sources as a Source of Tritium in a Pressurized Water Reactor (PWR) Reactor Coolant System (RCS)

    SciTech Connect (OSTI)

    Shaver, Mark W.; Lanning, Donald D.

    2010-02-01

    The hypothesis of this paper is that the Zircaloy clad fuel source is minimal and that secondary startup neutron sources are the significant contributors of the tritium in the RCS that was previously assigned to release from fuel. Currently there are large uncertainties in the attribution of tritium in a Pressurized Water Reactor (PWR) Reactor Coolant System (RCS). The measured amount of tritium in the coolant cannot be separated out empirically into its individual sources. Therefore, to quantify individual contributors, all sources of tritium in the RCS of a PWR must be understood theoretically and verified by the sum of the individual components equaling the measured values.

  11. Cyclotron Institute TAMU - Radiation Effects Testing Facility

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

    TAMU - Radiation Effects Testing Facility CONTROL SOFTWARE DOWNLOAD PAGE (Updated on January 12, 2016) INSTALLATION INSTRUCTIONS: The latest (2016) version of the the control software for the Cyclotron Institute TAMU Radiation Effects Testing Facility (SEUSS) is included in the ZIP archive that can be downloaded from http://cyclotron.tamu.edu/vladimir/SeussW.zip (12,351 kb). After downloading the archive, please extract the files it contains into an EMPTY folder of your choice. The files can be

  12. NREL: Wind Research - Facilities

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

    Facilities Our facilities are designed to meet the wind industry's critical research needs with state-of-the-art design and testing facilities. NREL's unique and highly versatile facilities at the National Wind Technology Center offer research and analysis of wind turbine components and prototypes rated from 400 watts to 3 megawatts. Satellite facilities support the growth of wind energy development across the United States. National Wind Technology Center Facilities Our facilities are contained

  13. Compression of a spherically symmetric deuterium-tritium plasma liner onto a magnetized deuterium-tritium target

    SciTech Connect (OSTI)

    Santarius, J. F.

    2012-07-15

    Converging plasma jets may be able to reach the regime of high energy density plasmas (HEDP). The successful application of plasma jets to magneto-inertial fusion (MIF) would heat the plasma by fusion products and should increase the plasma energy density. This paper reports the results of using the University of Wisconsin's 1-D Lagrangian, radiation-hydrodynamics, fusion code BUCKY to investigate two MIF converging plasma jet test cases originally analyzed by Samulyak et al.[Physics of Plasmas 17, 092702 (2010)]. In these cases, 15 cm or 5 cm radially thick deuterium-tritium (DT) plasma jets merge at 60 cm from the origin and converge radially onto a DT target magnetized to 2 T and of radius 5 cm. The BUCKY calculations reported here model these cases, starting from the time of initial contact of the jets and target. Compared to the one-temperature Samulyak et al. calculations, the one-temperature BUCKY results show similar behavior, except that the plasma radius remains about twice as long near maximum compression. One-temperature and two-temperature BUCKY results differ, reflecting the sensitivity of the calculations to timing and plasma parameter details, with the two-temperature case giving a more sustained compression.

  14. Tritium production from a low voltage deuterium discharge on palladium and other metals

    SciTech Connect (OSTI)

    Claytor, T.N.; Jackson, D.D.; Tuggle, D.G.

    1995-09-01

    Over the past year the authors have been able to demonstrate that a plasma loading method produces an exciting and unexpected amount of tritium from small palladium wires. In contrast to electrochemical hydrogen or deuterium loading of palladium, this method yields a reproducible tritium generation rate when various electrical and physical conditions are met. Small diameter wires (100--250 microns) have been used with gas pressures above 200 torr at voltages and currents of about 2,000 V at 3--5 A. By carefully controlling the sputtering rate of the wire, runs have been extended to hundreds of hours allowing a significant amount (> 10`s nCi) of tritium to accumulate. they show tritium generation rates for deuterium-palladium foreground runs that are up to 25 times larger than hydrogen-palladium control experiments using materials from the same batch. They illustrate the difference between batches of annealed palladium and as received palladium from several batches as well as the effect of other metals (Pt, Ni, Nb, Zr, V, W, Hf) to demonstrate that the tritium generation rate can vary greatly from batch to batch.

  15. Export Control Requirements for Tritium Processing Design and R&D

    SciTech Connect (OSTI)

    Hollis, William Kirk; Maynard, Sarah-Jane Wadsworth

    2015-10-30

    This document will address requirements of export control associated with tritium plant design and processes. Los Alamos National Laboratory has been working in the area of tritium plant system design and research and development (R&D) since the early 1970s at the Tritium Systems Test Assembly (TSTA). This work has continued to the current date with projects associated with the ITER project and other Office of Science Fusion Energy Science (OS-FES) funded programs. ITER is currently the highest funding area for the DOE OS-FES. Although export control issues have been integrated into these projects in the past a general guidance document has not been available for reference in this area. To address concerns with currently funded tritium plant programs and assist future projects for FES, this document will identify the key reference documents and specific sections within related to tritium research. Guidance as to the application of these sections will be discussed with specific detail to publications and work with foreign nationals.

  16. THE EFFECT OF 3HE ON LOW PRESSURE HYDRIDE ABSORPTION MEASUREMENTS WITH TRITIUM

    SciTech Connect (OSTI)

    Staack, G.; Klein, J.

    2011-01-20

    Absorption isotherm data exists for a wide variety of hydrogen-metal systems. When working with high purity gases, appropriately sized equipment, and hydrides with equilibrium pressures above several hundred Pa, data collection is relatively straightforward. Special consideration must be given to experiments involving low equilibrium pressure hydrides, as even sub-ppm levels of gas impurities can generate partial pressures many times greater than the equilibrium pressures to be measured. Tritium absorption experiments are further complicated by the continuous generation of helium-3. The time required to transfer and absorb a known quantity of tritium onto a sample ultimately limits the minimum pressure range that can be studied using the standard technique. Equations are presented which show the pressure of helium-3 in a sample cell based on the amount of tritium to be absorbed, the sample cell volume and temperature, and the decay time of tritium. Sample calculations for zirconium show that at 300 C, the estimated helium-3 pressure in the cell will be equal to the hydrogen absorption pressure after only milliseconds of tritium decay. An alternate method is presented that permits the collection of equilibrium data at pressures orders of magnitude lower than possible using a direct approach.

  17. Tritons and tritides as the solute and diffusing species in ceramic tritium breeders

    SciTech Connect (OSTI)

    Fischer, A.K.; Johnson, C.E.

    1988-06-01

    Intragranular diffusion of tritium is one component of the overall process for tritium release from lithium-containing ceramics that may be used to breed tritium in a fusion reactor. The nature of this transport is reviewed in terms of the understanding established for the mechanism of hydrogen migration in other oxides. In this mechanism, the diffusing species is the proton, which moves from oxide ion to oxide ion, thereby giving rise to apparent hydroxide migration. Analogously, at high oxygen activity, the tritio, transiently bonded to successive oxides and forming successive tritoxides, is taken to be the dominant migrating species in ceramic breeders. In addition, tritide is a significant participant in tritium release at low oxygen activity. The relationship of tritons and tritides as the migration species to the observed release of both reduced and oxidized forms of tritium can be understood in terms of the thermodynamic conditions that prevail. Mechanisms are proposed to rationalize the participation of these species. 29 refs., 3 figs.

  18. ARM - Facility News Article

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

    February 16, 2005 Facility News Mobile Facility Arrives Safe and Sound in Point Reyes Bookmark and Share Image - The ARM Mobile Facility in Point Reyes, California Safe and sound...

  19. ARM - Facility News Article

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

    20, 2010 Facility News ARM Mobile Facility Blogs from Steamboat Springs Bookmark and Share This month, team members for the second ARM Mobile Facility (AMF2) are in Steamboat...

  20. McKay Bay Facility Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    Biomass Facility Facility McKay Bay Facility Sector Biomass Facility Type Municipal Solid Waste Location Hillsborough County, Florida Coordinates 27.9903597, -82.3017728...

  1. Facilities | Argonne National Laboratory

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

    Facilities Some of the nation's most powerful and sophisticated facilities for energy research Argonne National Laboratory is home to some of the nation's most powerful and sophisticated research facilities. As a U.S. Department of Energy national laboratory, Argonne offers access to the facilities listed below through a variety of arrangements. Advanced Powertrain Research Facility Center for Transportation Research Materials Engineering Research Facility Distributed Energy Research Center

  2. National User Facilities

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

    National User Facilities Our Vision National User Facilities Research Areas In Focus Global Solutions ⇒ Navigate Section Our Vision National User Facilities Research Areas In Focus Global Solutions Berkeley Lab's User Facilities-Engines of Discovery Berkeley Lab's User Facilities provide state-of-the-art resources for scientists across the nation and around the world. About 10,000 researchers a year use these facilities, representing nearly one third of the total for all Department of Energy

  3. EFFECTS OF TRITIUM GAS EXPOSURE ON THE DYNAMIC MECHANICAL PROPERTIES OF EPDM ELASTOMER

    SciTech Connect (OSTI)

    Clark, E; Gregory Staack, G

    2007-08-13

    Samples of ethylene propylene diene monomer (EPDM) elastomer were exposed to tritium gas in closed containers initially at 101 kPa (1 atmosphere) pressure and ambient temperature for about one week. Tritium exposure effects on the samples were characterized by dynamic mechanical analysis (DMA) and radiolysis products were characterized by measuring the total final pressure and composition in the exposure containers at the end of exposure period. There was no effect of one week tritium exposure on the glass transition temperature, Tg, of the samples tested. Impurity gases produced in the closed containers included HT and lesser amounts of H{sub 2}, DTO, and CT{sub 4}. The total pressure remained the same during exposure.

  4. Tritons and tritides as the solute and diffusing species in ceramic tritium breeders

    SciTech Connect (OSTI)

    Fischer, A.K.; Johnson, C.E.

    1987-01-01

    Intragranular diffusion of tritium is an inherent participant in the process of releasing tritium from lithium-containing ceramics that are used to breed tritium in a fusion reactor. The nature of this transport is reviewed in terms of the understanding established for the mechanism of hydrogen migration in other oxides, namely, that the diffusing species is the proton and that it moves from oxide ion to oxide ion, thereby giving rise to apparent hydroxide migration. Analogously, the triton, transiently bonded to successive oxides and forming successive tritoxides, is taken to be the dominant migrating species in ceramic breeders. In addition, tritide becomes a significant participant at low oxygen activity. The relationship of tritons and tritides as the migrating species to the observed release of both reduced and oxidized forms can be understood in terms of the thermodynamic conditions that prevail. Mechanisms exist that can be proposed to rationalize the participation of these species.

  5. Recent palladium membrane reactor development at the tritium systems test assembly

    SciTech Connect (OSTI)

    Scott, W.R.; Birdsell, S.A.; Wilhelm, R.C. [Los Alamos National Lab., NM (United States)

    1995-10-01

    The palladium membrane reactor (PMR) is being investigated as a means for recovering hydrogen isotopes (including tritium) from compounds such as water and methane. Previous work with protiated water and methane showed that this device can be used to obtain high hydrogen recovery efficiencies using a single processing pass and with essentially no waste production. With these successful proof-of-principle results completed, recent work has focused on PMR development. This included studies of various geometries and testing with tritium. The results, which are reported here, have led to a better understanding of the PMR and will lead to the ultimate goal of building a production PMR and putting it into practical tritium processing service. 3 refs., 5 figs., 1 tab.

  6. ARM - NSA Barrow Facility

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

    Barrow Facility NSA Related Links Facilities and Instruments Barrow Atqasuk Oliktok Point (AMF3) ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site NSA...

  7. NSA Barrow Facility

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

    Barrow Facility NSA Related Links Facilities and Instruments Barrow Atqasuk Oliktok Point (AMF3) ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site NSA...

  8. NREL: Biomass Research - Facilities

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

    Facilities At NREL's state-of-the-art biomass research facilities, researchers design and optimize processes to convert renewable biomass feedstocks into transportation fuels and...

  9. ARM - Facility News Article

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

    facility use by total visitor days and facility to track actual visitors and active user research computer accounts. Historical data show an apparent relationship between the...

  10. Central Receiver Test Facility

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

    Receiver Test Facility - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us ... Applications National Solar Thermal Test Facility Nuclear Energy Systems ...

  11. ARM - Facility News Article

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

    (BERAC) published findings and recommendations from their assessment of the effectiveness of ARM Climate Research Facility as a national scientific user facility. Based on...

  12. ARM - Facility News Article

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

    years, DOE Office of Science user facilities undergo a review to evaluate their effectiveness in contributing to their respective science areas. The latest ARM Facility review...

  13. ARM - Facility News Article

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

    30, 2009 Facility News ARM Aerial Facility Leads International Discussions on Aircraft Research Bookmark and Share Five research aircraft participated in the VAMOS...

  14. Research Facilities | NREL

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

    and systems, ensuring integration with the U.S. electric grid. Learn more Integrated Biorefinery Research Facility (IBRF) Integrated Biorefinery Research Facility (IBRF) Work with...

  15. ARM - Facility News Article

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

    to our new ARM News Center. The RSS feed will alert readers to the latest ARM science and ARM Climate Research Facility news, events, feature stories, facility updates,...

  16. ARM - Facility News Article

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

    of instruments collecting data for the ARM Mobile Facility field campaign at Point Reyes National Seashore. Since March 2005, the ARM Mobile Facility (AMF) has been at Point...

  17. ARM - Facility News Article

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

    the SGP site, and will begin in March for the ARM Mobile Facility deployment in Point Reyes, California. Launches for the ARM Climate Research Facility Tropical Western Pacific...

  18. ARM - Facility News Article

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

    a number of other guest instruments at the ARM Mobile Facility deployment site at Point Reyes National Seashore in California. The ARM Mobile Facility's (AMF's) inaugural field...

  19. ARM - Facility News Article

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

    May 15, 2008 Facility News National User Facility Organization Meets to Discuss Progress and Ideas Bookmark and Share In late April, the ARM Technical Director attended an annual...

  20. ARM - Facility News Article

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

    30, 2007 Facility News Interferometers Compared for ARM Mobile Facility Deployment in China Bookmark and Share During the 2-week instrument comparison, the AERI planned for Linze...

  1. ARM - Facility News Article

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

    Announcements, Facility News Data Available from ARM Mobile Facility Deployment in China Bookmark and Share The Study of Aerosol Indirect Effects in China was anchored by the...

  2. ARM - Facility News Article

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

    5, 2008 Facility News Mobile Facility Anchors Multi-site Aerosol Study in China Bookmark and Share The AMF installation in Shouxian includes the primary shelters and operations...

  3. ARM - Facility News Article

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

    15, 2005 Facility News Aging, Overworked Computer Network at SGP Gets Overhauled Bookmark and Share This aerial map of instruments deployed at the SGP Central Facility provides...

  4. ARM - Facility News Article

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

    January 15, 2008 Facility News ARM Mobile Facility Completes Field Campaign in Germany Bookmark and Share Researchers will study severe precipitation events that occurred in...

  5. ARM - Facility News Article

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

    News ARM Mobile Facility Completes Extended Campaign in the Azores; Next Stop-India Bookmark and Share The ARM Mobile Facility obtained data on Graciosa Island in the...

  6. Design and Fabrication of In-Reactor Experiment to Measure Tritium Release and Speciation from LiAlO2 and LiAlO2/Zr Cermets

    Broader source: Energy.gov [DOE]

    Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013.

  7. Test Results For Physical Separation Of Tritium From Noble Gases And It’s Implications For Sensitivity And Accuracy In Air And Stack Monitoring

    Broader source: Energy.gov [DOE]

    Presentation from the 32nd Tritium Focus Group Meeting held in Germantown, Maryland on April 23-25, 2013.

  8. ARM - SGP Radiometric Calibration Facility

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

    Radiometric Calibration Facility SGP Related Links Virtual Tour Facilities and Instruments Central Facility Boundary Facility Extended Facility Intermediate Facility Radiometric Calibration Facility Geographic Information ES&H Guidance Statement Operations Science Field Campaigns Visiting the Site SGP Fact Sheet Images Information for Guest Scientists Contacts SGP Radiometric Calibration Facility The Radiometric Calibration Facility (RCF) provides shortwave radiometer calibrations traceable

  9. Lithium Ceramic Blankets for Russian Fusion Reactors and Influence of Breeding Operation Mode on Parameters of Reactor Tritium Systems

    SciTech Connect (OSTI)

    Kapyshev, Victor K.; Chernetsov, Mikhail Yu.; Zhevotov, Sergej I.; Kersnovskij, Alexandr Yu.; Kolbasov, Boris N.; Kovalenko, Victor G.; Paltusov, Nikolaj P.; Sernyaev, Georgeij A.; Sterebkov, Juri S.; Zyryanov, Alexej P.

    2005-07-15

    Russian controlled fusion program supposes development of a DEMO reactor design and participation in ITER Project. A solid breeder blanket of DEMO contains a ceramic lithium orthosilicate breeder and a beryllium multiplier. Test modules of the blanket are developed within the scope of ITER activities. Experimental models of module tritium breeding zones (TBZ), materials and fabrication technology of the TBZ, tritium reactor systems to analyse and process gas released from lithium ceramics are being developed. Two models of tritium breeding and neutron multiplying elements of the TBZ have been designed, manufactured and tested in IVV-2M nuclear reactor. Initial results of the in-pile experiments and outcome of lithium ceramics irradiation in a water-graphite nuclear reactor are considered to be a data base for development of the test modules and initial requirements for DEMO tritium system design. Influence of the tritium release parameters and hydrogen concentration in a purge gas on parameters of reactor system are discussed.

  10. Guide to research facilities

    SciTech Connect (OSTI)

    Not Available

    1993-06-01

    This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

  11. Overview of Japanese activities on tritium research for fusion reactors and Research activities at The University of Tokyo and Shizuoka University

    Office of Environmental Management (EM)

    tritium activity in Japan Yasuhisa Oya Graduate School of Science, Shizuoka University Tritium Focus Group Meeting @INL 2014.9.23 Research Subjects and Institutes for Tritium Issues Research Subjects - Fusion (Processing, Blanket, First Wall, Safety, Licensing) - Fission Reactor (Heavy Water Reactor) - Waste Management - Environmental Behavior - Biological Effects - Fundamental Science Institutes - Universities - Japan Atomic Energy Agency - National Institute for Fusion Science (NIFS) -

  12. Investigation of non-magnetic alloys for the suppression of tritium permeation

    SciTech Connect (OSTI)

    1980-07-01

    The present work was aimed at identification of alloys which might combine low tritium permeation with other properties desired in fusion reactor vessels, heat exchangers, lithium-handling plumbing and other components likely to contain tritium. These properties include low radiation damage, low magnetic permeability, high temperature strength, and compatibility with potential heat transfer and blanket materials. The work consisted of two tasks: problem definition, and literature search and analysis. Task I was complicated by the incomplete status of fusion reactor development, particularly with respect to selection of coolant and blanket materials and temperatures. The approach taken was to establish a probable range of requirements.

  13. Tritium in the World Trade Center September 11, 2001 Terrorist Attack: It's Possible Sources and Fate

    SciTech Connect (OSTI)

    Parekh, P; Semkow, T; Husain, L; Haines, D; Woznial, G; Williams, P; Hafner, R; Rabun, R

    2002-05-03

    Traces of tritiated water (HTO) were determined at World Trade Center (WTC) ground zero after the 9/11/01 terrorist attack. A method of ultralow-background liquid scintillation counting was used after distilling HTO from the samples. A water sample from the WTC sewer, collected on 9/13/01, contained 0.174{plus_minus}0.074 (2{sigma}) nCi/L of HTO. A split water sample, collected on 9/21/01 from the basement of WTC Building 6, contained 3.53{plus_minus}0.17 and 2.83{plus_minus}0.15 nCi/L, respectively. Several water and vegetation samples were analyzed from areas outside the ground zero, located in Manhattan, Brooklyn, Queens, and Kensico Reservoir. No HTO above the background was found in those samples. All these results are well below the levels of concern to human exposure. Several tritium radioluminescent (RL) devices were investigated as possible sources of the traces of tritium at ground zero. Tritium is used in self-luminescent emergency EXIT signs. No such signs were present inside the WTC buildings. However, it was determined that Boeing 767-222 aircraft operated by the United Airlines that hit WTC Tower 2 as well as Boeing 767-223ER operated by the American Airlines, that hit WTC Tower 1, had a combined 34.3 Ci of tritium at the time of impact. Other possible sources of tritium include dials and lights of fire and emergency equipment, sights and scopes in weaponry, as well as time devices equipped with tritium dials. It was determined that emergency equipment was not a likely source. However, WTC hosted several law-enforcement agencies such as ATF, CIA, US Secret Service and US Customs. The ATF office had two weapon vaults in WTC Building 6. Also 63 Police Officers, possibly carrying handguns with tritium sights, died in the attack. The weaponry containing tritium was therefore a likely and significant source of tritium. It is possible that some of the 2830 victims carried tritium watches, however this source appears to be less significant that the other two. The fate of tritium in the attack depended on its chemistry. Any tritium present in the vicinity of jet-fuel explosion or fire would convert to HTO. The molecular tritium is also known to quickly exchange with water adsorbed on surfaces at ambient temperatures. Therefore, the end product of reacted tritium was HTO. A part of it would disperse into the atmosphere and a part would remain on site. The dynamic aspect of HTO removal was investigated taking into a consideration water flow at ground zero. Most of ground zero is encircled by the Slurry Wall, 70 ft deep underground, called a Bathtub. Approximately three million gallons of water were hosed on site in the fire-fighting efforts, and 1 million gallons fell as rainwater, between 9/11 and 9/21 (the day of the reported measurement). The combined water percolated through the debris down to the bottom of the Bathtub dissolving and removing HTO with it. That water would meet and combine with the estimated 26 million gallons of water that leaked from the Hudson River as well as broken mains, during the same period of 10 days after the attack. The combined water was collecting in the PATH train tunnel and continuously being pumped out to prevent flooding. A %Box model of water flow was developed to describe the above scenario. Considering the uncertainty in the amount of tritium present from sources other than the aircraft, as well as the dynamic character of tritium removal from the site, it is feasible to provide only a qualitative picture of the fate and behavior of tritium at WTC with the limited experimental data available. If the time history of tritium concentration at WTC had been measured, this study could have been a tracer study of water flow at WTC possibly useful to civil engineering.

  14. Apparatus for hydrocarbon extraction

    DOE Patents [OSTI]

    Bohnert, George W.; Verhulst, Galen G.

    2013-03-19

    Systems and methods for hydrocarbon extraction from hydrocarbon-containing material. Such systems and methods relate to extracting hydrocarbon from hydrocarbon-containing material employing a non-aqueous extractant. Additionally, such systems and methods relate to recovering and reusing non-aqueous extractant employed for extracting hydrocarbon from hydrocarbon-containing material.

  15. Proceedings of the tenth annual DOE low-level waste management conference: Session 3: Disposal technology and facility development

    SciTech Connect (OSTI)

    Not Available

    1988-12-01

    This document contains ten papers on various aspects of low-level radioactive waste management. Topics include: design and construction of a facility; alternatives to shallow land burial; the fate of tritium and carbon 14 released to the environment; defense waste management; engineered sorbent barriers; remedial action status report; and the disposal of mixed waste in Texas. Individual papers were processed separately for the data base. (TEM)

  16. K150 - Facilities - Cyclotron Institute

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

    K150 Cyclotron K150 (88 The K150 Cyclotron, commissioned in 1967, supplied variable energy light and heavy ions for experimental use for almost 20 years before it was decommissioned in 1985 when construction of the K500 Cyclotron began. Following twenty years of being off line, the K150 cyclotron is once again operational. The first beams after re-commissioning were accelerated and extracted in October of 2007. The K150 will be an integral part of the new facility upgrade, making the Cyclotron

  17. NREL: Energy Systems Integration Facility - Facility Design

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

    Facility Design Throughout the Energy Systems Integration Facility design process, the National Renewable Energy Laboratory hosted workshops in which stakeholders from across the country provided feedback on the proposed design and functionality. The resulting capabilities, both human and equipment, provide high-value assets that might otherwise be cost-prohibitive for private-sector organizations to build, maintain, and operate on their own. Planning for the research facility and its innovative

  18. ARM - Facility News Article

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

    22, 2011 [Facility News] Request for Proposals Now Open Bookmark and Share The ARM Climate Research Facility is now accepting applications for use of an ARM mobile facility (AMF), the ARM aerial facility (AAF), and fixed sites. Proposals are welcome from all members of the scientific community for conducting field campaigns and scientific research using the ARM Facility, with availability as follows: AMF2 available December 2013 AMF1 available March 2015 AAF available between June and October

  19. ARM - Facility News Article

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

    10, 2016 [Facility News] Opportunity for Cloud Properties Retrieval Algorithm Development: Request for Interest Opened Bookmark and Share The ARM Facility is seeking a scientific consultant to develop an operational cloud property algorithm, using data from ARM facilities and instruments like these scanning cloud radars. The ARM Facility is seeking a scientific consultant to develop an operational cloud property algorithm, using data from ARM facilities and instruments like these scanning cloud

  20. NREL: Research Facilities - Test and User Facilities

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

    Test and User Facilities NREL has test and user facilities available to industry and other organizations for researching, developing, and evaluating renewable energy and energy efficiency technologies. Here you'll find an alphabetical listing and brief descriptions of NREL's test and user facilities. A | B | C | D | E | F | G | H | I | J | K | L | M | N | O | P | Q | R | S | T | U | V | W | X | Y | Z A Advanced Research Turbines At our wind testing facilities, we have turbines available to test